Notice of Availability of Model Application Concerning Technical Specification Task Force (TSTF) Traveler To Provide Actions for One Steam Supply to Turbine Driven AFW/EFW Pump Inoperable Using the Consolidated Line Item Improvement Process, 39089-39094 [E7-13845]
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Federal Register / Vol. 72, No. 136 / Tuesday, July 17, 2007 / Notices
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated June 29, 2007.
No significant hazards consideration
comments received: No.
Dated at Rockville, Maryland, this sixth
day of July 2007.
For the Nuclear Regulatory Commission.
Catherine Haney,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. E7–13537 Filed 7–16–07; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Background
Notice of Availability of Model
Application Concerning Technical
Specification Task Force (TSTF)
Traveler To Provide Actions for One
Steam Supply to Turbine Driven AFW/
EFW Pump Inoperable Using the
Consolidated Line Item Improvement
Process
Nuclear Regulatory
Commission.
ACTION: Notice of availability.
sroberts on PROD1PC70 with NOTICES
AGENCY:
SUMMARY: Notice is hereby given that
the staff of the Nuclear Regulatory
Commission (NRC) has prepared a
model license amendment request
(LAR), model safety evaluation (SE), and
model proposed no significant hazards
consideration (NSHC) determination
related to changes to Actions in the
Standard Technical Specifications (STS)
relating to One Steam Supply to Turbine
Driven Auxiliary Feedwater/Emergency
Feedwater (AFW/EFW) Pump
Inoperable. This change establishes a
Completion Time in the Standard
Technical Specifications for the
Condition where one steam supply to
the turbine driven AFW/EFW pump is
inoperable concurrent with an
inoperable motor driven AFW/EFW
train.
The purpose of these models is to
permit the NRC to efficiently process
amendments that propose to adopt the
associated changes into plant-specific
technical specifications (TS). Licensees
of nuclear power reactors to which the
models apply can request amendments
confirming the applicability of the SE
and NSHC determination to their
reactors.
DATES: The NRC staff issued a Federal
Register Notice (72 FR 12845, March 19,
2007) which provided a model LAR,
model SE, and model NSHC related to
one steam supply to turbine driven
auxiliary feedwater/emergency
feedwater pump inoperable; similarly
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17:40 Jul 16, 2007
the NRC staff herein provides the model
LAR, a revised model SE, and the model
NSHC. The NRC staff can most
efficiently consider applications based
upon the model LAR, which references
the model SE, if the application is
submitted within one year of this
Federal Register Notice.
FOR FURTHER INFORMATION CONTACT:
Trent L. Wertz, Technical Specifications
Branch, Division of Inspection and
Regional Support, Office of Nuclear
Reactor Regulation, Mail Stop O–12H2,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001, telephone
301–415–1568.
SUPPLEMENTARY INFORMATION:
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Regulatory Issue Summary 2000–06,
‘‘Consolidated Line Item Improvement
Process for Adopting Standard
Technical Specification Changes for
Power Reactors,’’ was issued on March
20, 2000. The consolidated line item
improvement process (CLIIP) is
intended to improve the efficiency and
transparency of NRC licensing
processes. This is accomplished by
processing proposed changes to the
Standard Technical Specifications (STS)
(NUREGs 1430—1434) in a manner that
supports subsequent license amendment
applications. The CLIIP includes an
opportunity for the public to comment
on proposed changes to the STS
following a preliminary assessment by
the NRC staff and finding that the
change will likely be offered for
adoption by licensees. The CLIIP directs
the NRC staff to evaluate any comments
received for a proposed change to the
STS and to either reconsider the change
or proceed with announcing the
availability of the change to licensees.
Those licensees opting to apply for the
subject change to TS are responsible for
reviewing the NRC staff’s evaluation,
referencing the applicable technical
justifications, and providing any
necessary plant specific information.
Each amendment application submitted
in response to the notice of availability
would be processed and noticed in
accordance with applicable rules and
NRC procedures.
This notice involves establishing a
Completion Time in the Limiting
Condition for Operation (LCO) 3.7.5 of
the STS for the Condition where one
steam supply to the turbine driven
AFW/EFW pump is inoperable
concurrent with an inoperable motor
driven AFW/EFW train. This notice also
involves two additional changes to the
STS that establish specific Conditions
and Action requirements: (1) For when
two motor driven AFW/EFW trains are
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Sfmt 4703
39089
inoperable at the same time and; (2) for
when the turbine driven AFW/EFW
train is inoperable either (a) due solely
to one inoperable steam supply, or (b)
due to reasons other than one
inoperable steam supply. The changes
were proposed by the Technical
Specification Task Force (TSTF) in
TSTF Traveler TSTF–412, Revision 3,
which is accessible electronically from
the Agencywide Documents Access and
Management System (ADAMS) Public
Electronic Reading Room on the Internet
at the NRC Web site https://www.nrc.gov/
reading-rm/adams.html (Accession No.
ML070100363). Persons who do not
have access to ADAMS or who
encounter problems in accessing the
documents located in ADAMS, should
contact the NRC Public Document Room
Reference staff by telephone at 1–800–
397–4209, 301–415–4737, or by e-mail
to pdr@nrc.gov.
Applicability
This change is applicable to all
pressurized water reactors (PWRs)
designed by Babcock and Wilcox
(B&W), Westinghouse, and Combustion
Engineering (CE). To efficiently process
the incoming license amendment
applications, the NRC staff requests that
each licensee applying for the changes
use the CLIIP to submit a License
Amendment Request (LAR) that
conforms to the enclosed Model
Application (Enclosure 1). Any
deviations from the Model Application
should be explained in the licensee’s
submittal. Significant deviations from
the approach, or inclusion of additional
changes to the license, will result in
staff rejection of the submittal. Instead,
licensees desiring significant variations
and/or additional changes should
submit a LAR that does not claim to
adopt TSTF–412. Variations from the
approach recommended in this notice
may require additional review by the
NRC staff and may increase the time and
resources needed for the review.
Public Notices
The staff issued a Federal Register
Notice (72 FR 12845, March 19, 2007)
that requested public comment on the
NRC’s pending action to establish a
Completion Time in the Limiting
Condition for Operation (LCO) 3.7.5 of
the STS for the Condition where one
steam supply to the turbine driven
AFW/EFW pump is inoperable
concurrent with an inoperable motor
driven AFW/EFW train. This notice also
involves two additional changes to the
STS that establish specific Conditions
and Action requirements: (1) For when
two motor driven AFW/EFW trains are
inoperable at the same time and; (2) for
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39090
Federal Register / Vol. 72, No. 136 / Tuesday, July 17, 2007 / Notices
when the turbine driven AFW/EFW
train is inoperable either (a) due solely
to one inoperable steam supply, or (b)
due to reasons other than one
inoperable steam supply. In particular,
following an assessment and draft safety
evaluation by the NRC staff, the staff
sought public comment on proposed
changes to the STS, designated TSTF–
412 Revision 3.
In response to the notice soliciting
comments from the interested members
of the public about NRC’s pending
action to establish a Completion Time in
the Standard Technical Specifications
for the Condition where one steam
supply to the turbine driven AFW/EFW
pump is inoperable concurrent with an
inoperable motor driven AFW/EFW
train, the staff received one comment
(from a licensee). The comment on the
model SE is summarized and discussed
below:
1. COMMENT: The first sentence in
the third paragraph under ‘‘STS 3.7.5,
Condition C (as Proposed),’’ in Section
3.0 of the Proposed Model Safety
Evaluation states the following:
‘‘The STS typically allows a 72 hour
Completion Time for Conditions where
the remaining operable equipment is
able to mitigate postulated accidents
without assuming a concurrent single
active failure.’’ Since there are several
TSs in the STS that allow a longer
Completion time than 72 hours for
conditions where the remaining
operable equipment is able to mitigate
postulated accidents without assuming
a concurrent single active failure (such
as seven days in TS 3.5.2, 3.6.6, and
3.7.10 in NUREG–1432), it is
recommended that the sentence be
changed to the following: ‘‘The STS
typically allows a 72 hour or longer
Completion Time for Conditions where
the remaining operable equipment is
able to mitigate postulated accidents
without assuming a concurrent single
active failure.’’
Response: The NRC staff agrees with
the comment and has modified the
model SE.
sroberts on PROD1PC70 with NOTICES
Dated at Rockville, Maryland, this 11th day
of July, 2007.
For the Nuclear Regulatory Commission.
Timothy J. Kobetz,
Chief Technical Specifications Branch,
Division of Inspection and Regional Support,
Office of Nuclear Reactor Regulation.
The following example of a license
amendment request (LAR) was prepared
by the NRC staff to facilitate the
adoption of Technical Specifications
Task Force (TSTF) Traveler TSTF–412,
Revision 3 ‘‘Provide Actions for One
Steam Supply to Turbine Driven AFW/
EFW Pump Inoperable.’’ The model
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17:40 Jul 16, 2007
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provides the expected level of detail and
content for a LAR to adopt TSTF–412,
Revision 3. Licensees remain
responsible for ensuring that their plantspecific LAR fulfills their administrative
requirements as well as NRC
regulations.
llllllllllllllllll
l
PROPOSED MODEL LICENSE
AMENDMENT REQUEST
U.S. Nuclear Regulatory Commission,
Document Control Desk,
Washington, DC 20555.
SUBJECT: PLANT NAME
DOCKET NO. 50–
APPLICATION FOR TECHNICAL
SPECIFICATION IMPROVEMENT TO
REVISE ACTIONS FOR ONE STEAM
SUPPLY TO TURBINE DRIVEN
AUXILIARY FEEDWATER /
EMERGENCY FEEDWATER PUMP
INOPERABLE USING THE
CONSOLIDATED LINE ITEM
IMPROVEMENT PROCESS
Gentlemen: In accordance with the
provisions of 10 CFR 50.90 of Title 10
of the Code of Federal Regulations (10
CFR), [LICENSEE] is submitting a
request for an amendment to the
technical specifications (TS) for [PLANT
NAME, UNIT NOS.].
The proposed amendment establishes
Conditions, Required Actions, and
Completion Times in the Standard
Technical Specifications (STS) for the
Condition where one steam supply to
the turbine driven Auxiliary Feedwater/
Emergency Feedwater (AFW/EFW)
pump is inoperable concurrent with an
inoperable motor driven AFW/EFW
train. In addition, this amendment
establishes changes to the STS that
establish specific Actions: (1) For when
two motor driven AFW/EFW trains are
inoperable at the same time and; (2) for
when the turbine driven AFW/EFW
train is inoperable either (a) due solely
to one inoperable steam supply, or (b)
due to reasons other than one
inoperable steam supply. The change is
consistent with NRC-approved
Technical Specification Task Force
(TSTF) Traveler, TSTF–412, Revision 3,
‘‘Provide Actions for One Steam Supply
to Turbine Driven AFW/EFW Pump
Inoperable.’’ The availability of this
technical specification improvement
was announced in the Federal Register
on [DATE OF NOTICE OF
AVAILABILITY] as part of the
consolidated line item improvement
process (CLIIP).
Enclosure 1 provides a description of
the proposed change and confirmation
of applicability. Enclosure 2 provides
the existing TS pages marked-up to
show the proposed change. Enclosure 3
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provides the existing TS Bases pages
marked-up to reflect the proposed
change. There are no new regulatory
commitments associated with this
proposed change.
[LICENSEE] requests approval of the
proposed license amendment by
[DATE], with the amendment being
implemented [BY DATE OR WITHIN X
DAYS].
In accordance with 10 CFR 50.91, a
copy of this application, with
enclosures, is being provided to the
designated [STATE] Official.
I declare under penalty of perjury
under the laws of the United States of
America that I am authorized by
[LICENSEE] to make this request and
that the foregoing is true and correct.
[Note that request may be notarized in
lieu of using this oath or affirmation
statement].
If you should have any questions
regarding this submittal, please contact
[ ].
Sincerely,
Name, Title
Enclosures: 1. Description and
Assessment
2. Proposed Technical Specification
Changes
3. Proposed Technical Specification
Bases Changes
cc: NRR Project Manager
Regional Office
Resident Inspector
State Contact
llllllllllllllllll
l
Enclosure 1 to Model License
Amendment Request Description and
Assessment
1.0 DESCRIPTION
The proposed License amendment
establish a new Completion Time in
Standard Technical Specifications
Section [3.7.5] where one steam supply
to the turbine driven AFW/EFW pump
is inoperable concurrent with an
inoperable motor driven AFW/EFW
train. This amendment also establishes
specific Conditions and Action
requirements: (1) For when two motor
driven AFW/EFW trains are inoperable
at the same time and; (2) for when the
turbine driven AFW/EFW train is
inoperable either (a) due solely to one
inoperable steam supply, or (b) due to
reasons other than one inoperable steam
supply.
The changes are consistent with NRC
approved Industry/Technical
Specification Task Force (TSTF)
Standard Technical Specification
Change Traveler, TSTF–412, Revision 3,
‘‘Provide Actions for One Steam Supply
to Turbine Driven AFW/EFW Pump
Inoperable.’’ The availability of this
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Federal Register / Vol. 72, No. 136 / Tuesday, July 17, 2007 / Notices
technical specification improvement
was announced in the Federal Register
on [DATE ] ([xx FR xxxxx]) as part of
the consolidated line item improvement
process (CLIIP).
2.0
ASSESSMENT
2.1 Applicability of Published Safety
Evaluation
[LICENSEE] has reviewed the safety
evaluation published on [DATE ] ([xx
FR xxxxx]) as part of the CLIIP. This
verification included a review of the
NRC staff’s evaluation as well as the
supporting information provided to
support TSTF–412, Revision 3.
[LICENSEE] has concluded that the
justifications presented in the TSTF
proposal and the safety evaluation
prepared by the NRC staff are applicable
to [PLANT, UNIT NOS.] and justify this
amendment for the incorporation of the
changes to the [PLANT] Technical
Specifications.
2.2 Optional Changes and Variations
[LICENSEE] is not proposing any
variations or deviations from the
technical specification changes
described in TSTF–412, Revision 3, or
the NRC staff’s model safety evaluation
published in the Federal Register on
[DATE ] ([xx FR xxxxx]).
3.0 REGULATORY ANALYSIS
A description of the proposed change
and its relationship to applicable
regulatory requirements and guidance
was provided in the Notice of
Availability published on [DATE] ([xx
FR xxxxx]). [Pre-General Design
Criteria plants need to include
applicable plant specific regulatory
requirements].
3.1 No Significant Hazards
Determination
[LICENSEE] has reviewed the
proposed no significant hazards
consideration determination published
on [DATE] as part of the CLIIP.
[LICENSEE] has concluded that the
proposed determination presented in
the notice is applicable to [PLANT] and
the determination is hereby
incorporated by reference to satisfy the
requirements of 10 CFR 50.91(a).
sroberts on PROD1PC70 with NOTICES
3.2 Verification and Commitments
There are no new regulatory
commitments associated with this
proposed change.
4.0 ENVIRONMENTAL
EVALUATION
[LICENSEE] has reviewed the
environmental evaluation included in
the model safety evaluation published
in the Federal Register on [DATE ] ([xx
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17:40 Jul 16, 2007
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39091
Specifications (TS). Pursuant to 10 CFR
50.36(c), TS are required to include
items in the following categories: (1)
Safety limits, limiting safety system
settings, and limiting control settings;
(2) limiting conditions for operation
(LCOs); (3) surveillance requirements
(SRs); (4) design features; and (5)
administrative controls. The rule does
Enclosure 2 to Model License
not specify the particular requirements
Amendment Request: PROPOSED
to be included in a plant’s TS.
TECHNICAL SPECIFICATION
Also, in 10 CFR 50 Appendix A the
CHANGES
Commission established regulatory
llllllllllllllllll
l requirements related to Auxiliary
Feedwater Systems. General Design
Enclosure 3 to Model License
Criteria 34 and 44 state that the AFW
Amendment Request: CHANGES TO TS
system is required to assure (1) the
BASES PAGES
capability to transfer heat loads from the
llllllllllllllllll
l reactor system to a heat sink under both
normal operating and accident
PROPOSED MODEL SAFETY
conditions; (2) the redundancy of
EVALUATION
components for performance of the
U.S. Nuclear Regulatory Commission
safety function under accident
Office of Nuclear Reactor Regulation
conditions, assuming a single active
Consolidated Line Item Improvement
component failure; and (3) the
Technical Specification Task Force
capability to isolate components,
Traveler TSTF–412, Revision 3, Provide subsystems, or piping if required to
Actions for One Steam Supply to the
maintain system safety function.
Turbine Driven AFW/EFW Pump
3.0 TECHNICAL EVALUATION
Inoperable
TS 3.7.5, Auxiliary Feedwater (AFW)/
1.0 INTRODUCTION
Emergency Feedwater (EFW) System
By application dated [DATE],
The AFW/EFW System is designed to
[LICENSEE NAME] (the licensee),
automatically supply sufficient water to
submitted a request for changes to the
the steam generator(s) to remove decay
[PLANT NAME], Technical
heat upon the loss of normal feedwater
Specifications (TS) (Agencywide
supply with steam generator pressure at
Documents Access and Management
the set point of the Main Steam Safety
System (ADAMS) Accession No.
[MLxxxxxxxxx]). The requested changes Valves (MSSVs). Subsequently, the
AFW/EFW System supplies sufficient
adopt TSTF–412, Revision 3, ‘‘Provide
water to cool the unit to Residual Heat
Actions for One Steam Supply to the
Removal (RHR) System entry
Turbine Driven AFW/EFW Pump
conditions, with steam being released
Inoperable.’’ NRC approval of these
through the Atmospheric Dump Valves
changes was announced in the Federal
(ADVs).
Register on [DATE] [xx FR xxxxx]. The
AFW/EFW Systems typically consist
requested change would establish a
of two motor driven AFW/EFW pumps
Completion Time for the Condition
and one steam turbine driven pump
where one steam supply to the turbine
configured into three trains. The
driven AFW/EFW pump is inoperable
capacity of the motor driven and steam
concurrent with an inoperable motor
driven AFW/EFW pumps can vary by
driven AFW/EFW train and establish
plant. Motor driven pumps typically
specific Conditions and Required
provide 50% or 100% of the required
Actions: (1) When two motor driven
AFW/EFW flow capacity as assumed in
AFW/EFW trains are inoperable at the
the accident analysis. Motor driven
same time and; (2) when the turbine
AFW/EFW pumps are typically
driven AFW/EFW train is inoperable
powered from an independent Class 1E
either (a) due solely to one inoperable
steam supply, or (b) due to reasons other power supply and each pump train
typically feeds half of the steam
than one inoperable steam supply.
generators, although each pump has the
These changes were described in a
capability to be realigned from the
Notice of Availability published in the
control room to feed other steam
Federal Register on [DATE ] ([xx FR
generators. The steam turbine driven
xxxxx]).
AFW/EFW pump provides either 100%
2.0 REGULATORY EVALUATION
or 200% of the required capacity to all
steam generators. The steam turbine
In 10 CFR 50.36, the Commission
driven pump receives steam from two
established its regulatory requirements
main steam lines upstream of the main
related to the content of Technical
FR xxxxx]) as part of the CLIIP.
[LICENSEE] has concluded that the NRC
staff’s findings presented in that
evaluation are applicable to [PLANT]
and the evaluation is hereby
incorporated by reference for this
application.
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Federal Register / Vol. 72, No. 136 / Tuesday, July 17, 2007 / Notices
steam isolation valves. Each of the
steam feed lines will supply 100% of
the requirements of the turbine driven
AFW/EFW pump.
sroberts on PROD1PC70 with NOTICES
LCO 3.7.5 Condition A (as proposed)
Condition A is modified to refer to the
inoperability of a turbine driven AFW/
EFW train due to an inoperable steam
supply, instead of referring to the
inoperability of a turbine driven AFW/
EFW pump. This change is being
proposed in order to make Condition A
train oriented instead of component
oriented, consistent with the other
Conditions that are included in STS
3.7.5. The train oriented approach is
consistent with the preferred approach
that is generally reflected in the STS,
and therefore the proposed change is
considered to be acceptable.
STS 3.7.5, Condition C (as proposed)
A new Condition C with two possible
Required Actions (C.1 OR C.2) is
proposed for the turbine driven AFW/
EFW train being inoperable due to one
inoperable steam supply and one motor
driven AFW/EFW train being inoperable
at the same time. Required Action C.1
requires restoration of the affected steam
supply to operable status within either
24 or 48 hours, depending on the
capability of the motor driven AFW/
EFW train that remains operable.
Alternatively, Required Action C.2
requires restoration of the inoperable
motor driven AFW/EFW train within
either 24 or 48 hours, again depending
on the capability of the motor driven
AFW/EFW train that remains operable.
New Condition C provides two
proposed Completion Times that are
dependent upon the capacity of the
remaining operable motor driven AFW/
EFW train to provide AFW/EFW to the
steam generators.
A proposed 24 hour Completion Time
is applicable to plants that may provide
insufficient flow to the steam generators
(SGs) in accordance with accident
analyses assumptions if a main steam
line break (MSLB) or feedwater line
break (FLB) were to occur that renders
the remaining steam supply to the
turbine driven AFW/EFW pump
inoperable (a concurrent single failure is
not assumed). Insufficient feedwater
flow could result, for example, if a
single motor driven AFW/EFW train
does not have sufficient capacity to
satisfy accident analyses assumptions,
or if the operable pump is feeding the
faulted SG (i.e. the SG that is aligned to
the operable steam supply for the
turbine driven AFW/EFW pump). øThis
would typically apply to plants with
each AFW/EFW motor driven pump
having less than 100% of the required
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17:40 Jul 16, 2007
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flow.¿ A proposed 48 hour Completion
Time is applicable when the remaining
operable motor driven AFW/EFW train
is capable of providing sufficient
feedwater flow in accordance with
accident analyses assumptions. øThis
would typically apply to plants with
each AFW/EFW motor driven pump
having greater than or equal to 100% of
the required flow.¿
The STS typically allows a 72 hour or
longer Completion Time for Conditions
where the remaining operable
equipment is able to mitigate postulated
accidents without assuming a
concurrent single active failure. In this
particular case, a 24 hour Completion
Time is proposed for the situation
where the AFW/EFW system would be
able to perform its function for most
postulated events, and would only be
challenged by a MSLB or FLB that
renders the remaining operable steam
supply to the turbine driven AFW/EFW
pump inoperable. Additionally,
depending on the capacity of the
operable motor driven AFW/EFW
pump, it may be able to mitigate MSLB
and FLB accidents during those
instances when it is not aligned to the
faulted SG. The selection of 24 hours for
the Completion Time is based on the
remaining operable steam supply to the
turbine driven AFW/EFW pump and the
continued functionality of the turbine
driven AFW/EFW train, the remaining
operable motor driven AFW/EFW train,
and the low likelihood of an event
occurring during this 24 hour period
that would challenge the capability of
the AFW/EFW system to provide
feedwater to the SGs. The proposed
Completion Time for this particular
situation is consistent with what was
approved for Waterford 3 by License
Amendment 173 for a similar Condition
(ADAMS Accession No. ML012840538),
and it is consistent with the STS in that
the proposed Completion Time is much
less than the 72 hours that is allowed for
the situation where accident mitigation
capability is maintained. Therefore, the
NRC staff agrees that the proposed 24
hour Completion Time is acceptable for
this particular situation.
A 48 hour Completion Time is
proposed for the situation where the
remaining operable motor driven AFW/
EFW train is able to mitigate postulated
accidents in accordance with accident
analyses assumptions without assuming
a concurrent single active failure. The
selection of 48 hours is based on the
continued capability of the AFW/EFW
system to perform its function, while at
the same time recognizing that this
Condition represents a higher level of
degradation than one inoperable AFW/
EFW train which is currently allowed
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Sfmt 4703
for up to 72 hours by STS 3.7.5. The
proposed 48 hour Completion Time
represents an appropriate balance
between the more severe 24 hour
situation discussed in the previous
paragraph and the less severe Condition
that is afforded a 72 hour Completion
Time by the current STS. Therefore, the
NRC staff agrees that the proposed 48
hour Completion Time is acceptable for
this particular situation.
STS 3.7.5, Condition D (as proposed)
The current Condition C is renamed
as Condition D. This Condition has been
modified to incorporate changes brought
on by the addition of new Condition C.
The first of the two listed Conditions
under Condition D has been modified
and now applies to the situation where
the Required Action and associated
Completion Time of Condition A, B, or
C are not met. This section of Condition
D is modified to also apply to the new
Condition C when the Completion Time
that is specified for new Condition C is
not met. The NRC staff considers this to
be appropriate and consistent with
existing STS 3.7.5 requirements to place
the plant in a mode where the Condition
does not apply when the Required
Actions are not met.
The second listed Condition under
Condition D (following the first ‘‘OR’’)
is modified from ‘‘Two AFW/EFW
trains inoperable in MODE 1, 2, or 3’’
to ‘‘Two AFW/EFW trains inoperable in
MODE 1, 2, or 3 for reasons other than
Condition C.’’ This change is necessary
to recognize the situation specified by
Condition C (as proposed) where one
motor driven AFW/EFW train is
allowed to be inoperable at the same
time that the turbine driven AFW/EFW
train is inoperable due to an inoperable
steam supply to the pump turbine.
Therefore, the NRC staff considers the
proposed change to be acceptable.
The Required Actions associated with
this Condition were renamed from C.1
AND C.2 to D.1 AND D.2 but not
otherwise changed. Required Action D.1
requires the plant to be in Mode 3 in 6
hours, and Required Action D.2 requires
the plant to be in Mode 4 in 18 hours.
This change is purely editorial as no
other changes are involved. Therefore,
this proposed change is acceptable.
STS 3.7.5, Condition E (as proposed)
Because current Condition C is
renamed as Condition D, current
Condition D is renamed as Condition E.
This change is purely editorial as no
other changes are involved. Therefore,
the proposed change is acceptable.
E:\FR\FM\17JYN1.SGM
17JYN1
Federal Register / Vol. 72, No. 136 / Tuesday, July 17, 2007 / Notices
STS 3.7.5, Condition F (as proposed)
Because current Condition D is
renamed as Condition E, current
Condition E is renamed as Condition F.
This change is purely editorial as no
other changes are involved. Therefore,
the proposed change is acceptable.
4.0
STATE CONSULTATION
In accordance with the Commission’s
regulations, the [STATE] State official
was notified of the proposed issuance of
the amendments. The State official had
[(1) no comments or (2) the following
comments—with subsequent
disposition by the NRC staff].
5.0 ENVIRONMENTAL
CONSIDERATION
The amendment changes a
requirement with respect to the
installation or use of a facility
component located within the restricted
area as defined in 10 CFR Part 20 and
changes surveillance requirements. The
NRC staff has determined that the
amendment involves no significant
increase in the amounts and no
significant change in the types of any
effluents that may be released offsite,
and that there is no significant increase
in individual or cumulative
occupational radiation exposure. The
Commission has previously issued a
proposed finding that the amendment
involves no significant hazards
consideration, and there has been [(1)
no public comment on such finding (2)
the following comments with
subsequent disposition by the NRC staff
([xx FR xxxxx, DATE]). Accordingly, the
amendment meets the eligibility criteria
for categorical exclusion set forth in 10
CFR 51.22(c)(9). Pursuant to 10 CFR
51.22(b) no environmental impact
statement or environmental assessment
need be prepared in connection with the
issuance of the amendment.
sroberts on PROD1PC70 with NOTICES
6.0
CONCLUSION
The Commission has concluded,
based on the considerations discussed
above, that (1) there is reasonable
assurance that the health and safety of
the public will not be endangered by
operation in the proposed manner, (2)
such activities will be conducted in
compliance with the Commission’s
regulations, and (3) the issuance of the
amendments will not be inimical to the
common defense and security or to the
health and safety of the public.
The proposed changes are consistent
with NRC practices and policies as
generally reflected in the STS and as
reflected by applicable precedents that
have been approved. Therefore, the NRC
staff has determined that the proposed
VerDate Aug<31>2005
17:40 Jul 16, 2007
Jkt 211001
changes to STS 3.7.5 should be
approved.
MODEL NO SIGNIFICANT HAZARDS
CONSIDERATION DETERMINATION
Description of amendment request:
The requested change, applicable to all
pressurized water reactors (PWRs)
designed by Babcock and Wilcox
(B&W), Westinghouse, and Combustion
Engineering (CE), would provide
changes to the Actions in the Standard
Technical Specifications (STS) relating
to One Steam Supply to Turbine Driven
Auxiliary Feedwater / Emergency
Feedwater (AFW/EFW) Pump
Inoperable. The proposed change is
described in Technical Specification
Task Force (TSTF) Standard TS Change
Traveler TSTF–412, Revision 3, and was
described in the Notice of Availability
published in the Federal Register on
[DATE] ([xx FR xxxxx]).
Basis for proposed no significant
hazards consideration determination: As
required by 10 CFR 50.91(a), an analysis
of the issue of no significant hazards
consideration is presented below:
1. Does the proposed change involve
a significant increase in the probability
or consequences of any accident
previously evaluated?
Response: No
The Auxiliary/Emergency Feedwater
(AFW/EFW) System is not an initiator of
any design basis accident or event, and
therefore the proposed changes do not
increase the probability of any accident
previously evaluated. The proposed
changes to address the condition of one
or two motor driven AFW/EFW trains
inoperable and the turbine driven AFW/
EFW train inoperable due to one steam
supply inoperable do not change the
response of the plant to any accidents.
The proposed changes do not
adversely affect accident initiators or
precursors nor alter the design
assumptions, conditions, and
configuration of the facility or the
manner in which the plant is operated
and maintained. The proposed changes
do not adversely affect the ability of
structures, systems, and components
(SSCs) to perform their intended safety
function to mitigate the consequences of
an initiating event within the assumed
acceptance limits. The proposed
changes do not affect the source term,
containment isolation, or radiological
release assumptions used in evaluating
the radiological consequences of any
accident previously evaluated. Further,
the proposed changes do not increase
the types and amounts of radioactive
effluent that may be released offsite, nor
significantly increase individual or
cumulative occupational/public
radiation exposures.
PO 00000
Frm 00052
Fmt 4703
Sfmt 4703
39093
Therefore, the changes do not involve
a significant increase in the probability
or consequences of any accident
previously evaluated.
2. Does the proposed change create
the possibility of a new or different kind
of accident from any accident
previously evaluated?
Response: No
The proposed changes do not result in
a change in the manner in which the
AFW/EFW System provides plant
protection. The AFW/EFW System will
continue to supply water to the steam
generators to remove decay heat and
other residual heat by delivering at least
the minimum required flow rate to the
steam generators. There are no design
changes associated with the proposed
changes. The changes to the Conditions
and Required Actions do not change any
existing accident scenarios, nor create
any new or different accident scenarios.
The changes do not involve a physical
alteration of the plant (i.e., no new or
different type of equipment will be
installed) or a change in the methods
governing normal plant operation. In
addition, the changes do not impose any
new or different requirements or
eliminate any existing requirements.
The changes do not alter assumptions
made in the safety analysis. The
proposed changes are consistent with
the safety analysis assumptions and
current plant operating practice.
Therefore, the changes do not create
the possibility of a new or different kind
of accident from any accident
previously evaluated.
3. Does the proposed change involve
a significant reduction in a margin of
safety?
Response: No
The proposed changes do not alter the
manner in which safety limits, limiting
safety system settings or limiting
conditions for operation are determined.
The safety analysis acceptance criteria
are not impacted by these changes. The
proposed changes will not result in
plant operation in a configuration
outside the design basis.
Therefore, it is concluded that the
proposed change does not involve a
significant reduction in a margin of
safety.
Based on the above, the proposed
change involves no significant hazards
consideration under the standards set
forth in 10 CFR 50.92(c), and
accordingly, a finding of no significant
hazards consideration is justified.
Dated at Rockville, Maryland, this
th
day of
, 2007.
For the Nuclear Regulatory Commission.
Project Manager
Plant Licensing Branch [ ]
E:\FR\FM\17JYN1.SGM
17JYN1
39094
Federal Register / Vol. 72, No. 136 / Tuesday, July 17, 2007 / Notices
Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation
[FR Doc. E7–13845 Filed 7–16–07; 8:45 am]
BILLING CODE 7590–01–P
OFFICE OF PERSONNEL
MANAGEMENT
Proposed Collection; Comment
Request for Review of a Revised
Information Collection; Federal
Employees Health Benefits (FEHB)
Open Season Express; Interactive
Voice Response (IVR) System
Office of Personnel
Management.
ACTION: Notice.
sroberts on PROD1PC70 with NOTICES
AGENCY:
SUMMARY: In accordance with the
Paperwork Reduction Act of 1995 (Pub.
L. 104–13, May 22, 1995), this notice
announces that the Office of Personnel
Management (OPM) intends to submit to
the Office of Management and Budget
(OMB) a request for review of a revised
information collection. The Federal
Employees Health Benefits (FEHB)
Open Season Express Interactive Voice
Response (IVR) System and the Open
Season Web site, Open Season Online,
are used by retirees and survivors. They
collect information for changing FEHB
enrollments, collecting dependent and
other insurance information for self and
family enrollments, requesting plan
brochures, requesting a change of
address, requesting cancellation or
suspension of FEHB benefits, asking to
make payment to the Office of Personnel
Management when the FEHB payment
is greater than the monthly annuity
amount, or for requesting FEHB plan
accreditation and Customer Satisfaction
Survey information.
Comments are particularly invited on:
Whether this information is necessary
for the proper performance of functions
of the Office of Personnel Management
and whether it will have practical
utility; whether our estimate of the
public burden of this collection of
information is accurate and based on
valid assumptions and methodology;
and ways in which we can minimize the
burden of the collection of information
on those who are to respond, through
the use of appropriate technological
collection techniques or other forms of
information technology.
We receive approximately 215,000
responses per year to the IVR system
and the online Web. Each response
takes approximately 10 minutes to
complete. The annual burden is 35,833
hours.
For copies of this proposal, contact
Mary Beth Smith-Toomey on (202) 606–
VerDate Aug<31>2005
17:40 Jul 16, 2007
Jkt 211001
8358, FAX (202) 418–3251 or via e-mail
to: MaryBeth.Smith-Toomey@opm.gov.
Please include a mailing address with
your request.
DATES: Comments on this proposal
should be received within 60 calendar
days from the date of this publication.
ADDRESSES: Send or deliver comments
to—
Ed Foelster, Chief, Methods and
Procedures Branch, Operations Support
Group, Center for Retirement and
Insurance Services, U.S. Office of
Personnel Management, 1900 E Street,
NW., Room 3349, Washington, DC
20415–3540.
For Information Regarding
Administrative Coordination—
Contact: Cyrus S. Benson, Team
Leader, Publications Team, RIS Support
Services/Support Group, (202) 606–
0623.
OFFICE OF PERSONNEL
MANAGEMENT
on those who are to respond, through
the use of appropriate technological
collection techniques or other forms of
information technology.
Approximately 500 OPM Form 1530
will be completed annually. We
estimate it takes approximately 90
minutes to complete the form. The
annual burden is 750 hours.
For copies of this proposal, contact
Mary Beth Smith-Toomey on (202) 606–
8358, FAX (202) 418–3251 or via e-mail
to: MaryBeth.Smith-Toomey@opm.gov.
Please include a mailing address with
your request.
DATES: Comments on this proposal
should be received within 60 calendar
days from the date of this publication.
ADDRESSES: Send or deliver comments
to—
Pamela S. Israel, Chief, Operations
Support Group, Center for Retirement
and Insurance Services, U.S. Office of
Personnel Management, 1900 E Street,
NW., Room 3349, Washington, DC
20415–3540.
For Information Regarding
Administrative Coordination—
Contact: Cyrus S. Benson, Team
Leader, Publications Team, RIS Support
Services/Support Group, (202) 606–
0623.
Proposed Collection; Comment
Request for Extension of a Currently
Approved Information Collection: OPM
1530
U.S. Office of Personnel Management.
Tricia Hollis,
Chief of Staff.
[FR Doc. E7–13761 Filed 7–16–07; 8:45 am]
U.S. Office of Personnel Management.
Tricia Hollis,
Chief of Staff.
[FR Doc. E7–13760 Filed 7–16–07; 8:45 am]
BILLING CODE 6325–38–P
BILLING CODE 6325–38–P
Office of Personnel
Management.
ACTION: Notice.
AGENCY:
SUMMARY: In accordance with the
Paperwork Reduction Act of 1995 (Pub.
L. 104–13, May 22, 1995), this notice
announces that the Office of Personnel
Management (OPM) intends to submit to
the Office of Management and Budget
(OMB) a request for extension of a
currently approved information
collection. OPM Form 1530, Report of
Medical Examination of Person Electing
Survivor Benefit Under the Civil Service
Retirement System, is used to collect
information regarding an annuitant’s
health so that OPM can determine
whether the insurable interest survivor
benefit election can be allowed.
Comments are particularly invited on:
Whether this information is necessary
for the proper performance of functions
of the Office of Personnel Management,
and whether it will have practical
utility; whether our estimate of the
public burden of this collection of
information is accurate, and based on
valid assumptions and methodology;
and ways in which we can minimize the
burden of the collection of information
PO 00000
Frm 00053
Fmt 4703
Sfmt 4703
SECURITIES AND EXCHANGE
COMMISSION
Submission for OMB Review;
Comment Request
Upon Written Request, Copies Available
From: Securities and Exchange
Commission, Office of Filings and
Information Services, Washington, DC
20549.
Extension:
Rule 19h–1; SEC File No. 270–247; OMB
Control No. 3235–0259.
Notice is hereby given that pursuant
to the Paperwork Reduction Act of 1995
(44 U.S.C. 3501 et seq.) the Securities
and Exchange Commission
(‘‘Commission’’) has submitted to the
Office of Management and Budget a
request for extension of the previously
approved collection of information
discussed below.
• Rule 19h–1 (17 CFR 240.19h–1):
SRO notification of admission and/or
continuance despite statutory
disqualification.
Rule 19h–1 (‘‘Rule’’) under the
Securities Exchange Act of 1934 (15
E:\FR\FM\17JYN1.SGM
17JYN1
]]>Agencies
[Federal Register Volume 72, Number 136 (Tuesday, July 17, 2007)]
[Notices]
[Pages 39089-39094]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-13845]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
Notice of Availability of Model Application Concerning Technical
Specification Task Force (TSTF) Traveler To Provide Actions for One
Steam Supply to Turbine Driven AFW/EFW Pump Inoperable Using the
Consolidated Line Item Improvement Process
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of availability.
-----------------------------------------------------------------------
SUMMARY: Notice is hereby given that the staff of the Nuclear
Regulatory Commission (NRC) has prepared a model license amendment
request (LAR), model safety evaluation (SE), and model proposed no
significant hazards consideration (NSHC) determination related to
changes to Actions in the Standard Technical Specifications (STS)
relating to One Steam Supply to Turbine Driven Auxiliary Feedwater/
Emergency Feedwater (AFW/EFW) Pump Inoperable. This change establishes
a Completion Time in the Standard Technical Specifications for the
Condition where one steam supply to the turbine driven AFW/EFW pump is
inoperable concurrent with an inoperable motor driven AFW/EFW train.
The purpose of these models is to permit the NRC to efficiently
process amendments that propose to adopt the associated changes into
plant-specific technical specifications (TS). Licensees of nuclear
power reactors to which the models apply can request amendments
confirming the applicability of the SE and NSHC determination to their
reactors.
DATES: The NRC staff issued a Federal Register Notice (72 FR 12845,
March 19, 2007) which provided a model LAR, model SE, and model NSHC
related to one steam supply to turbine driven auxiliary feedwater/
emergency feedwater pump inoperable; similarly the NRC staff herein
provides the model LAR, a revised model SE, and the model NSHC. The NRC
staff can most efficiently consider applications based upon the model
LAR, which references the model SE, if the application is submitted
within one year of this Federal Register Notice.
FOR FURTHER INFORMATION CONTACT: Trent L. Wertz, Technical
Specifications Branch, Division of Inspection and Regional Support,
Office of Nuclear Reactor Regulation, Mail Stop O-12H2, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone 301-415-
1568.
SUPPLEMENTARY INFORMATION:
Background
Regulatory Issue Summary 2000-06, ``Consolidated Line Item
Improvement Process for Adopting Standard Technical Specification
Changes for Power Reactors,'' was issued on March 20, 2000. The
consolidated line item improvement process (CLIIP) is intended to
improve the efficiency and transparency of NRC licensing processes.
This is accomplished by processing proposed changes to the Standard
Technical Specifications (STS) (NUREGs 1430--1434) in a manner that
supports subsequent license amendment applications. The CLIIP includes
an opportunity for the public to comment on proposed changes to the STS
following a preliminary assessment by the NRC staff and finding that
the change will likely be offered for adoption by licensees. The CLIIP
directs the NRC staff to evaluate any comments received for a proposed
change to the STS and to either reconsider the change or proceed with
announcing the availability of the change to licensees. Those licensees
opting to apply for the subject change to TS are responsible for
reviewing the NRC staff's evaluation, referencing the applicable
technical justifications, and providing any necessary plant specific
information. Each amendment application submitted in response to the
notice of availability would be processed and noticed in accordance
with applicable rules and NRC procedures.
This notice involves establishing a Completion Time in the Limiting
Condition for Operation (LCO) 3.7.5 of the STS for the Condition where
one steam supply to the turbine driven AFW/EFW pump is inoperable
concurrent with an inoperable motor driven AFW/EFW train. This notice
also involves two additional changes to the STS that establish specific
Conditions and Action requirements: (1) For when two motor driven AFW/
EFW trains are inoperable at the same time and; (2) for when the
turbine driven AFW/EFW train is inoperable either (a) due solely to one
inoperable steam supply, or (b) due to reasons other than one
inoperable steam supply. The changes were proposed by the Technical
Specification Task Force (TSTF) in TSTF Traveler TSTF-412, Revision 3,
which is accessible electronically from the Agencywide Documents Access
and Management System (ADAMS) Public Electronic Reading Room on the
Internet at the NRC Web site https://www.nrc.gov/reading-rm/adams.html
(Accession No. ML070100363). Persons who do not have access to ADAMS or
who encounter problems in accessing the documents located in ADAMS,
should contact the NRC Public Document Room Reference staff by
telephone at 1-800-397-4209, 301-415-4737, or by e-mail to pdr@nrc.gov.
Applicability
This change is applicable to all pressurized water reactors (PWRs)
designed by Babcock and Wilcox (B&W), Westinghouse, and Combustion
Engineering (CE). To efficiently process the incoming license amendment
applications, the NRC staff requests that each licensee applying for
the changes use the CLIIP to submit a License Amendment Request (LAR)
that conforms to the enclosed Model Application (Enclosure 1). Any
deviations from the Model Application should be explained in the
licensee's submittal. Significant deviations from the approach, or
inclusion of additional changes to the license, will result in staff
rejection of the submittal. Instead, licensees desiring significant
variations and/or additional changes should submit a LAR that does not
claim to adopt TSTF-412. Variations from the approach recommended in
this notice may require additional review by the NRC staff and may
increase the time and resources needed for the review.
Public Notices
The staff issued a Federal Register Notice (72 FR 12845, March 19,
2007) that requested public comment on the NRC's pending action to
establish a Completion Time in the Limiting Condition for Operation
(LCO) 3.7.5 of the STS for the Condition where one steam supply to the
turbine driven AFW/EFW pump is inoperable concurrent with an inoperable
motor driven AFW/EFW train. This notice also involves two additional
changes to the STS that establish specific Conditions and Action
requirements: (1) For when two motor driven AFW/EFW trains are
inoperable at the same time and; (2) for
[[Page 39090]]
when the turbine driven AFW/EFW train is inoperable either (a) due
solely to one inoperable steam supply, or (b) due to reasons other than
one inoperable steam supply. In particular, following an assessment and
draft safety evaluation by the NRC staff, the staff sought public
comment on proposed changes to the STS, designated TSTF-412 Revision 3.
In response to the notice soliciting comments from the interested
members of the public about NRC's pending action to establish a
Completion Time in the Standard Technical Specifications for the
Condition where one steam supply to the turbine driven AFW/EFW pump is
inoperable concurrent with an inoperable motor driven AFW/EFW train,
the staff received one comment (from a licensee). The comment on the
model SE is summarized and discussed below:
1. COMMENT: The first sentence in the third paragraph under ``STS
3.7.5, Condition C (as Proposed),'' in Section 3.0 of the Proposed
Model Safety Evaluation states the following:
``The STS typically allows a 72 hour Completion Time for Conditions
where the remaining operable equipment is able to mitigate postulated
accidents without assuming a concurrent single active failure.'' Since
there are several TSs in the STS that allow a longer Completion time
than 72 hours for conditions where the remaining operable equipment is
able to mitigate postulated accidents without assuming a concurrent
single active failure (such as seven days in TS 3.5.2, 3.6.6, and
3.7.10 in NUREG-1432), it is recommended that the sentence be changed
to the following: ``The STS typically allows a 72 hour or longer
Completion Time for Conditions where the remaining operable equipment
is able to mitigate postulated accidents without assuming a concurrent
single active failure.''
Response: The NRC staff agrees with the comment and has modified
the model SE.
Dated at Rockville, Maryland, this 11th day of July, 2007.
For the Nuclear Regulatory Commission.
Timothy J. Kobetz,
Chief Technical Specifications Branch, Division of Inspection and
Regional Support, Office of Nuclear Reactor Regulation.
The following example of a license amendment request (LAR) was
prepared by the NRC staff to facilitate the adoption of Technical
Specifications Task Force (TSTF) Traveler TSTF-412, Revision 3
``Provide Actions for One Steam Supply to Turbine Driven AFW/EFW Pump
Inoperable.'' The model provides the expected level of detail and
content for a LAR to adopt TSTF-412, Revision 3. Licensees remain
responsible for ensuring that their plant-specific LAR fulfills their
administrative requirements as well as NRC regulations.
-----------------------------------------------------------------------
PROPOSED MODEL LICENSE AMENDMENT REQUEST
U.S. Nuclear Regulatory Commission, Document Control Desk, Washington,
DC 20555.
SUBJECT: PLANT NAME
DOCKET NO. 50-
APPLICATION FOR TECHNICAL SPECIFICATION IMPROVEMENT TO REVISE ACTIONS
FOR ONE STEAM SUPPLY TO TURBINE DRIVEN AUXILIARY FEEDWATER / EMERGENCY
FEEDWATER PUMP INOPERABLE USING THE CONSOLIDATED LINE ITEM IMPROVEMENT
PROCESS
Gentlemen: In accordance with the provisions of 10 CFR 50.90 of
Title 10 of the Code of Federal Regulations (10 CFR), [LICENSEE] is
submitting a request for an amendment to the technical specifications
(TS) for [PLANT NAME, UNIT NOS.].
The proposed amendment establishes Conditions, Required Actions,
and Completion Times in the Standard Technical Specifications (STS) for
the Condition where one steam supply to the turbine driven Auxiliary
Feedwater/Emergency Feedwater (AFW/EFW) pump is inoperable concurrent
with an inoperable motor driven AFW/EFW train. In addition, this
amendment establishes changes to the STS that establish specific
Actions: (1) For when two motor driven AFW/EFW trains are inoperable at
the same time and; (2) for when the turbine driven AFW/EFW train is
inoperable either (a) due solely to one inoperable steam supply, or (b)
due to reasons other than one inoperable steam supply. The change is
consistent with NRC-approved Technical Specification Task Force (TSTF)
Traveler, TSTF-412, Revision 3, ``Provide Actions for One Steam Supply
to Turbine Driven AFW/EFW Pump Inoperable.'' The availability of this
technical specification improvement was announced in the Federal
Register on [DATE OF NOTICE OF AVAILABILITY] as part of the
consolidated line item improvement process (CLIIP).
Enclosure 1 provides a description of the proposed change and
confirmation of applicability. Enclosure 2 provides the existing TS
pages marked-up to show the proposed change. Enclosure 3 provides the
existing TS Bases pages marked-up to reflect the proposed change. There
are no new regulatory commitments associated with this proposed change.
[LICENSEE] requests approval of the proposed license amendment by
[DATE], with the amendment being implemented [BY DATE OR WITHIN X
DAYS].
In accordance with 10 CFR 50.91, a copy of this application, with
enclosures, is being provided to the designated [STATE] Official.
I declare under penalty of perjury under the laws of the United
States of America that I am authorized by [LICENSEE] to make this
request and that the foregoing is true and correct. [Note that request
may be notarized in lieu of using this oath or affirmation statement].
If you should have any questions regarding this submittal, please
contact [ ].
Sincerely,
Name, Title
Enclosures: 1. Description and Assessment
2. Proposed Technical Specification Changes
3. Proposed Technical Specification Bases Changes
cc: NRR Project Manager
Regional Office
Resident Inspector
State Contact
-----------------------------------------------------------------------
Enclosure 1 to Model License Amendment Request Description and
Assessment
1.0 DESCRIPTION
The proposed License amendment establish a new Completion Time in
Standard Technical Specifications Section [3.7.5] where one steam
supply to the turbine driven AFW/EFW pump is inoperable concurrent with
an inoperable motor driven AFW/EFW train. This amendment also
establishes specific Conditions and Action requirements: (1) For when
two motor driven AFW/EFW trains are inoperable at the same time and;
(2) for when the turbine driven AFW/EFW train is inoperable either (a)
due solely to one inoperable steam supply, or (b) due to reasons other
than one inoperable steam supply.
The changes are consistent with NRC approved Industry/Technical
Specification Task Force (TSTF) Standard Technical Specification Change
Traveler, TSTF-412, Revision 3, ``Provide Actions for One Steam Supply
to Turbine Driven AFW/EFW Pump Inoperable.'' The availability of this
[[Page 39091]]
technical specification improvement was announced in the Federal
Register on [DATE ] ([xx FR xxxxx]) as part of the consolidated line
item improvement process (CLIIP).
2.0 ASSESSMENT
2.1 Applicability of Published Safety Evaluation
[LICENSEE] has reviewed the safety evaluation published on [DATE ]
([xx FR xxxxx]) as part of the CLIIP. This verification included a
review of the NRC staff's evaluation as well as the supporting
information provided to support TSTF-412, Revision 3. [LICENSEE] has
concluded that the justifications presented in the TSTF proposal and
the safety evaluation prepared by the NRC staff are applicable to
[PLANT, UNIT NOS.] and justify this amendment for the incorporation of
the changes to the [PLANT] Technical Specifications.
2.2 Optional Changes and Variations
[LICENSEE] is not proposing any variations or deviations from the
technical specification changes described in TSTF-412, Revision 3, or
the NRC staff's model safety evaluation published in the Federal
Register on [DATE ] ([xx FR xxxxx]).
3.0 REGULATORY ANALYSIS
A description of the proposed change and its relationship to
applicable regulatory requirements and guidance was provided in the
Notice of Availability published on [DATE] ([xx FR xxxxx]). [Pre-
General Design Criteria plants need to include applicable plant
specific regulatory requirements].
3.1 No Significant Hazards Determination
[LICENSEE] has reviewed the proposed no significant hazards
consideration determination published on [DATE] as part of the CLIIP.
[LICENSEE] has concluded that the proposed determination presented in
the notice is applicable to [PLANT] and the determination is hereby
incorporated by reference to satisfy the requirements of 10 CFR
50.91(a).
3.2 Verification and Commitments
There are no new regulatory commitments associated with this
proposed change.
4.0 ENVIRONMENTAL EVALUATION
[LICENSEE] has reviewed the environmental evaluation included in
the model safety evaluation published in the Federal Register on [DATE
] ([xx FR xxxxx]) as part of the CLIIP. [LICENSEE] has concluded that
the NRC staff's findings presented in that evaluation are applicable to
[PLANT] and the evaluation is hereby incorporated by reference for this
application.
-----------------------------------------------------------------------
Enclosure 2 to Model License Amendment Request: PROPOSED TECHNICAL
SPECIFICATION CHANGES
-----------------------------------------------------------------------
Enclosure 3 to Model License Amendment Request: CHANGES TO TS BASES
PAGES
-----------------------------------------------------------------------
PROPOSED MODEL SAFETY EVALUATION
U.S. Nuclear Regulatory Commission
Office of Nuclear Reactor Regulation
Consolidated Line Item Improvement
Technical Specification Task Force Traveler TSTF-412, Revision 3,
Provide Actions for One Steam Supply to the Turbine Driven AFW/EFW Pump
Inoperable
1.0 INTRODUCTION
By application dated [DATE], [LICENSEE NAME] (the licensee),
submitted a request for changes to the [PLANT NAME], Technical
Specifications (TS) (Agencywide Documents Access and Management System
(ADAMS) Accession No. [MLxxxxxxxxx]). The requested changes adopt TSTF-
412, Revision 3, ``Provide Actions for One Steam Supply to the Turbine
Driven AFW/EFW Pump Inoperable.'' NRC approval of these changes was
announced in the Federal Register on [DATE] [xx FR xxxxx]. The
requested change would establish a Completion Time for the Condition
where one steam supply to the turbine driven AFW/EFW pump is inoperable
concurrent with an inoperable motor driven AFW/EFW train and establish
specific Conditions and Required Actions: (1) When two motor driven
AFW/EFW trains are inoperable at the same time and; (2) when the
turbine driven AFW/EFW train is inoperable either (a) due solely to one
inoperable steam supply, or (b) due to reasons other than one
inoperable steam supply.
These changes were described in a Notice of Availability published
in the Federal Register on [DATE ] ([xx FR xxxxx]).
2.0 REGULATORY EVALUATION
In 10 CFR 50.36, the Commission established its regulatory
requirements related to the content of Technical Specifications (TS).
Pursuant to 10 CFR 50.36(c), TS are required to include items in the
following categories: (1) Safety limits, limiting safety system
settings, and limiting control settings; (2) limiting conditions for
operation (LCOs); (3) surveillance requirements (SRs); (4) design
features; and (5) administrative controls. The rule does not specify
the particular requirements to be included in a plant's TS.
Also, in 10 CFR 50 Appendix A the Commission established regulatory
requirements related to Auxiliary Feedwater Systems. General Design
Criteria 34 and 44 state that the AFW system is required to assure (1)
the capability to transfer heat loads from the reactor system to a heat
sink under both normal operating and accident conditions; (2) the
redundancy of components for performance of the safety function under
accident conditions, assuming a single active component failure; and
(3) the capability to isolate components, subsystems, or piping if
required to maintain system safety function.
3.0 TECHNICAL EVALUATION
TS 3.7.5, Auxiliary Feedwater (AFW)/Emergency Feedwater (EFW) System
The AFW/EFW System is designed to automatically supply sufficient
water to the steam generator(s) to remove decay heat upon the loss of
normal feedwater supply with steam generator pressure at the set point
of the Main Steam Safety Valves (MSSVs). Subsequently, the AFW/EFW
System supplies sufficient water to cool the unit to Residual Heat
Removal (RHR) System entry conditions, with steam being released
through the Atmospheric Dump Valves (ADVs).
AFW/EFW Systems typically consist of two motor driven AFW/EFW pumps
and one steam turbine driven pump configured into three trains. The
capacity of the motor driven and steam driven AFW/EFW pumps can vary by
plant. Motor driven pumps typically provide 50% or 100% of the required
AFW/EFW flow capacity as assumed in the accident analysis. Motor driven
AFW/EFW pumps are typically powered from an independent Class 1E power
supply and each pump train typically feeds half of the steam
generators, although each pump has the capability to be realigned from
the control room to feed other steam generators. The steam turbine
driven AFW/EFW pump provides either 100% or 200% of the required
capacity to all steam generators. The steam turbine driven pump
receives steam from two main steam lines upstream of the main
[[Page 39092]]
steam isolation valves. Each of the steam feed lines will supply 100%
of the requirements of the turbine driven AFW/EFW pump.
LCO 3.7.5 Condition A (as proposed)
Condition A is modified to refer to the inoperability of a turbine
driven AFW/EFW train due to an inoperable steam supply, instead of
referring to the inoperability of a turbine driven AFW/EFW pump. This
change is being proposed in order to make Condition A train oriented
instead of component oriented, consistent with the other Conditions
that are included in STS 3.7.5. The train oriented approach is
consistent with the preferred approach that is generally reflected in
the STS, and therefore the proposed change is considered to be
acceptable.
STS 3.7.5, Condition C (as proposed)
A new Condition C with two possible Required Actions (C.1 OR C.2)
is proposed for the turbine driven AFW/EFW train being inoperable due
to one inoperable steam supply and one motor driven AFW/EFW train being
inoperable at the same time. Required Action C.1 requires restoration
of the affected steam supply to operable status within either 24 or 48
hours, depending on the capability of the motor driven AFW/EFW train
that remains operable. Alternatively, Required Action C.2 requires
restoration of the inoperable motor driven AFW/EFW train within either
24 or 48 hours, again depending on the capability of the motor driven
AFW/EFW train that remains operable. New Condition C provides two
proposed Completion Times that are dependent upon the capacity of the
remaining operable motor driven AFW/EFW train to provide AFW/EFW to the
steam generators.
A proposed 24 hour Completion Time is applicable to plants that may
provide insufficient flow to the steam generators (SGs) in accordance
with accident analyses assumptions if a main steam line break (MSLB) or
feedwater line break (FLB) were to occur that renders the remaining
steam supply to the turbine driven AFW/EFW pump inoperable (a
concurrent single failure is not assumed). Insufficient feedwater flow
could result, for example, if a single motor driven AFW/EFW train does
not have sufficient capacity to satisfy accident analyses assumptions,
or if the operable pump is feeding the faulted SG (i.e. the SG that is
aligned to the operable steam supply for the turbine driven AFW/EFW
pump). [lsqbb]This would typically apply to plants with each AFW/EFW
motor driven pump having less than 100% of the required flow.[rsqbb] A
proposed 48 hour Completion Time is applicable when the remaining
operable motor driven AFW/EFW train is capable of providing sufficient
feedwater flow in accordance with accident analyses assumptions.
[lsqbb]This would typically apply to plants with each AFW/EFW motor
driven pump having greater than or equal to 100% of the required
flow.[rsqbb]
The STS typically allows a 72 hour or longer Completion Time for
Conditions where the remaining operable equipment is able to mitigate
postulated accidents without assuming a concurrent single active
failure. In this particular case, a 24 hour Completion Time is proposed
for the situation where the AFW/EFW system would be able to perform its
function for most postulated events, and would only be challenged by a
MSLB or FLB that renders the remaining operable steam supply to the
turbine driven AFW/EFW pump inoperable. Additionally, depending on the
capacity of the operable motor driven AFW/EFW pump, it may be able to
mitigate MSLB and FLB accidents during those instances when it is not
aligned to the faulted SG. The selection of 24 hours for the Completion
Time is based on the remaining operable steam supply to the turbine
driven AFW/EFW pump and the continued functionality of the turbine
driven AFW/EFW train, the remaining operable motor driven AFW/EFW
train, and the low likelihood of an event occurring during this 24 hour
period that would challenge the capability of the AFW/EFW system to
provide feedwater to the SGs. The proposed Completion Time for this
particular situation is consistent with what was approved for Waterford
3 by License Amendment 173 for a similar Condition (ADAMS Accession No.
ML012840538), and it is consistent with the STS in that the proposed
Completion Time is much less than the 72 hours that is allowed for the
situation where accident mitigation capability is maintained.
Therefore, the NRC staff agrees that the proposed 24 hour Completion
Time is acceptable for this particular situation.
A 48 hour Completion Time is proposed for the situation where the
remaining operable motor driven AFW/EFW train is able to mitigate
postulated accidents in accordance with accident analyses assumptions
without assuming a concurrent single active failure. The selection of
48 hours is based on the continued capability of the AFW/EFW system to
perform its function, while at the same time recognizing that this
Condition represents a higher level of degradation than one inoperable
AFW/EFW train which is currently allowed for up to 72 hours by STS
3.7.5. The proposed 48 hour Completion Time represents an appropriate
balance between the more severe 24 hour situation discussed in the
previous paragraph and the less severe Condition that is afforded a 72
hour Completion Time by the current STS. Therefore, the NRC staff
agrees that the proposed 48 hour Completion Time is acceptable for this
particular situation.
STS 3.7.5, Condition D (as proposed)
The current Condition C is renamed as Condition D. This Condition
has been modified to incorporate changes brought on by the addition of
new Condition C. The first of the two listed Conditions under Condition
D has been modified and now applies to the situation where the Required
Action and associated Completion Time of Condition A, B, or C are not
met. This section of Condition D is modified to also apply to the new
Condition C when the Completion Time that is specified for new
Condition C is not met. The NRC staff considers this to be appropriate
and consistent with existing STS 3.7.5 requirements to place the plant
in a mode where the Condition does not apply when the Required Actions
are not met.
The second listed Condition under Condition D (following the first
``OR'') is modified from ``Two AFW/EFW trains inoperable in MODE 1, 2,
or 3'' to ``Two AFW/EFW trains inoperable in MODE 1, 2, or 3 for
reasons other than Condition C.'' This change is necessary to recognize
the situation specified by Condition C (as proposed) where one motor
driven AFW/EFW train is allowed to be inoperable at the same time that
the turbine driven AFW/EFW train is inoperable due to an inoperable
steam supply to the pump turbine. Therefore, the NRC staff considers
the proposed change to be acceptable.
The Required Actions associated with this Condition were renamed
from C.1 AND C.2 to D.1 AND D.2 but not otherwise changed. Required
Action D.1 requires the plant to be in Mode 3 in 6 hours, and Required
Action D.2 requires the plant to be in Mode 4 in 18 hours. This change
is purely editorial as no other changes are involved. Therefore, this
proposed change is acceptable.
STS 3.7.5, Condition E (as proposed)
Because current Condition C is renamed as Condition D, current
Condition D is renamed as Condition E. This change is purely editorial
as no other changes are involved. Therefore, the proposed change is
acceptable.
[[Page 39093]]
STS 3.7.5, Condition F (as proposed)
Because current Condition D is renamed as Condition E, current
Condition E is renamed as Condition F. This change is purely editorial
as no other changes are involved. Therefore, the proposed change is
acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the [STATE] State
official was notified of the proposed issuance of the amendments. The
State official had [(1) no comments or (2) the following comments--with
subsequent disposition by the NRC staff].
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the
installation or use of a facility component located within the
restricted area as defined in 10 CFR Part 20 and changes surveillance
requirements. The NRC staff has determined that the amendment involves
no significant increase in the amounts and no significant change in the
types of any effluents that may be released offsite, and that there is
no significant increase in individual or cumulative occupational
radiation exposure. The Commission has previously issued a proposed
finding that the amendment involves no significant hazards
consideration, and there has been [(1) no public comment on such
finding (2) the following comments with subsequent disposition by the
NRC staff ([xx FR xxxxx, DATE]). Accordingly, the amendment meets the
eligibility criteria for categorical exclusion set forth in 10 CFR
51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact
statement or environmental assessment need be prepared in connection
with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed
above, that (1) there is reasonable assurance that the health and
safety of the public will not be endangered by operation in the
proposed manner, (2) such activities will be conducted in compliance
with the Commission's regulations, and (3) the issuance of the
amendments will not be inimical to the common defense and security or
to the health and safety of the public.
The proposed changes are consistent with NRC practices and policies
as generally reflected in the STS and as reflected by applicable
precedents that have been approved. Therefore, the NRC staff has
determined that the proposed changes to STS 3.7.5 should be approved.
MODEL NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION
Description of amendment request: The requested change, applicable
to all pressurized water reactors (PWRs) designed by Babcock and Wilcox
(B&W), Westinghouse, and Combustion Engineering (CE), would provide
changes to the Actions in the Standard Technical Specifications (STS)
relating to One Steam Supply to Turbine Driven Auxiliary Feedwater /
Emergency Feedwater (AFW/EFW) Pump Inoperable. The proposed change is
described in Technical Specification Task Force (TSTF) Standard TS
Change Traveler TSTF-412, Revision 3, and was described in the Notice
of Availability published in the Federal Register on [DATE] ([xx FR
xxxxx]).
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), an analysis of the issue
of no significant hazards consideration is presented below:
1. Does the proposed change involve a significant increase in the
probability or consequences of any accident previously evaluated?
Response: No
The Auxiliary/Emergency Feedwater (AFW/EFW) System is not an
initiator of any design basis accident or event, and therefore the
proposed changes do not increase the probability of any accident
previously evaluated. The proposed changes to address the condition of
one or two motor driven AFW/EFW trains inoperable and the turbine
driven AFW/EFW train inoperable due to one steam supply inoperable do
not change the response of the plant to any accidents.
The proposed changes do not adversely affect accident initiators or
precursors nor alter the design assumptions, conditions, and
configuration of the facility or the manner in which the plant is
operated and maintained. The proposed changes do not adversely affect
the ability of structures, systems, and components (SSCs) to perform
their intended safety function to mitigate the consequences of an
initiating event within the assumed acceptance limits. The proposed
changes do not affect the source term, containment isolation, or
radiological release assumptions used in evaluating the radiological
consequences of any accident previously evaluated. Further, the
proposed changes do not increase the types and amounts of radioactive
effluent that may be released offsite, nor significantly increase
individual or cumulative occupational/public radiation exposures.
Therefore, the changes do not involve a significant increase in the
probability or consequences of any accident previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No
The proposed changes do not result in a change in the manner in
which the AFW/EFW System provides plant protection. The AFW/EFW System
will continue to supply water to the steam generators to remove decay
heat and other residual heat by delivering at least the minimum
required flow rate to the steam generators. There are no design changes
associated with the proposed changes. The changes to the Conditions and
Required Actions do not change any existing accident scenarios, nor
create any new or different accident scenarios.
The changes do not involve a physical alteration of the plant
(i.e., no new or different type of equipment will be installed) or a
change in the methods governing normal plant operation. In addition,
the changes do not impose any new or different requirements or
eliminate any existing requirements. The changes do not alter
assumptions made in the safety analysis. The proposed changes are
consistent with the safety analysis assumptions and current plant
operating practice.
Therefore, the changes do not create the possibility of a new or
different kind of accident from any accident previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No
The proposed changes do not alter the manner in which safety
limits, limiting safety system settings or limiting conditions for
operation are determined. The safety analysis acceptance criteria are
not impacted by these changes. The proposed changes will not result in
plant operation in a configuration outside the design basis.
Therefore, it is concluded that the proposed change does not
involve a significant reduction in a margin of safety.
Based on the above, the proposed change involves no significant
hazards consideration under the standards set forth in 10 CFR 50.92(c),
and accordingly, a finding of no significant hazards consideration is
justified.
Dated at Rockville, Maryland, this th day of , 2007.
For the Nuclear Regulatory Commission.
Project Manager
Plant Licensing Branch [ ]
[[Page 39094]]
Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation
[FR Doc. E7-13845 Filed 7-16-07; 8:45 am]
BILLING CODE 7590-01-P
