Notice of Opportunity for Comment on Model Safety Evaluation for 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, 11914-11918 [E7-4675]
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11914
Federal Register / Vol. 72, No. 49 / Wednesday, March 14, 2007 / Notices
applicants for employment is reviewed
by professional personnel of the Office
of Human Resources, in conjunction
with other information in the NRC files,
to determine the qualifications of the
applicant for appointment to the
position under consideration.
Submit, by May 14, 2007, comments
that address the following questions:
1. Is the proposed collection of
information necessary for the NRC to
properly perform its functions? Does the
information have practical utility?
2. Is the burden estimate accurate?
3. Is there a way to enhance the
quality, utility, and clarity of the
information to be collected?
4. How can the burden of the
information collection be minimized,
including the use of automated
collection techniques or other forms of
information technology?
A copy of the draft supporting
statement may be viewed free of charge
at the NRC Public Document Room, One
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Pike, Room O–1 F21, Rockville, MD
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available at the NRC worldwide Web
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doc-comment/omb/. The
document will be available on the NRC
home page site for 60 days after the
signature date of this notice.
Comments and questions about the
information collection requirements
may be directed to the NRC Clearance
Officer, Margaret A. Janney, Mail Stop:
T–5F52, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, by telephone at 301–415–7245, or
by Internet electronic mail to
InfoCollects@nrc.gov.
SUMMARY: Notice is hereby given that
the staff of the Nuclear Regulatory
Commission (NRC) has prepared a
model safety evaluation (SE) relating to
proposed 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 would
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 NRC staff has also prepared
a model application and model no
significant hazards consideration
(NSHC) determination relating to this
matter. 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. The NRC staff is requesting
comments on the Model SE, Model
Application and Model NSHC
determination prior to announcing their
availability for referencing in license
amendment applications.
Dated at Rockville, Maryland, this 8th day
of March, 2007.
For the Nuclear Regulatory Commission.
Margaret A. Janney,
NRC Clearance Officer, Office of Information
Services.
[FR Doc. E7–4672 Filed 3–13–07; 8:45 am]
ADDRESSES:
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NUCLEAR REGULATORY
COMMISSION
Notice of Opportunity for Comment on
Model Safety Evaluation for 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: Request for comment.
AGENCY:
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The comment period expires 30
days from the date of this publication.
Comments received after this date will
be considered if it is practical to do so,
but the Commission can only ensure
consideration for comments received on
or before this date.
DATES:
Comments may be
submitted either electronically or via
U.S. mail.
To submit comments or questions on
a proposed standard technical
specification change via the Internet,
use Form for Sending Comments on
NRC Documents, then select Proposed
Changes to Technical Specifications. If
you are commenting on a proposed
change, please match your comments
with the correct proposed change by
copying the title of the proposed change
from column one to the previous table
into the appropriate field of the
comment form.
Submit written comments to: Chief,
Rulemaking, Directives and Editing
Branch, Division of Administrative
Services, Office of Administration, Mail
Stop T–6D59, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
Hand deliver comments to 11545
Rockville Pike, Rockville, Maryland,
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between 7:45 a.m. and 4:15 p.m. on
Federal workdays.
Copies of comments received may be
examined at the NRC’s Public Document
Room, located at One White Flint North,
11555 Rockville Pike (first floor),
Rockville, Maryland.
Comments may be submitted by
electronic mail to CLIIP@nrc.gov.
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 for comment 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. In addition, this
notice for comment involves changes to
the STS that establish specific
Conditions and Action requirements for
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Federal Register / Vol. 72, No. 49 / Wednesday, March 14, 2007 / Notices
two motor driven AFW/EFW trains are
inoperable at the same time and 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.
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Applicability
This proposed change to adopt TSTF–
412 is applicable to all pressurized
water reactors (PWRs) designed by
Babcock and Wilcox (B&W),
Westinghouse, and Combustion
Engineering (CE). If approved, to
efficiently process the incoming license
amendment applications, the NRC staff
will request that each licensee applying
for the changes addressed by TSTF–412,
Revision 3, 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
This notice requests comments from
interested members of the public within
30 days of the date of publication in the
Federal Register. Following the NRC
staff’s evaluation of comments received
as a result of this notice, the NRC staff
may reconsider the proposed change or
may proceed with announcing the
availability of the change in a
subsequent notice (perhaps with some
changes to the SE or proposed NSHC
determination as a result of public
comments).
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If the NRC staff announces the
availability of the change, licensees
wishing to adopt the change will submit
an application in accordance with
applicable rules and other regulatory
requirements. The NRC staff will in turn
issue for each application a notice of
proposed action, which includes a
proposed NSHC determination. A notice
of issuance of an amendment of
operating license will also be issued to
announce the adoption of TSTF–412 for
each plant that applies for and receives
the requested change.
Dated at Rockville, Maryland, this 8th day
of March, 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 plantspecific 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 when two motor driven
AFW/EFW trains are inoperable at the same
time and the turbine driven AFW/EFW train
is inoperable either (a) due solely to one
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11915
inoperable steam supply, or (b) due to
reasons other than one inoperable steam
supply. The change is consistent with NRCapproved 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 when two motor driven
AFW/EFW trains are inoperable at the
same time and 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.
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Federal Register / Vol. 72, No. 49 / Wednesday, March 14, 2007 / Notices
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
technical specification improvement
was announced in the Federal Register
on [DATE ] ([xx FR xxxxx]) as part of
the consolidated line item improvement
process (CLIIP).
staff’s findings presented in that
evaluation are applicable to [PLANT]
and the evaluation is hereby
incorporated by reference for this
application.
2.0
Proposed Model Safety Evaluation
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
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).
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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
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Enclosure 2 to Model License
Amendment Request: PROPOSED
TECHNICAL SPECIFICATION
CHANGES
Enclosure 3 to Model License
Amendment Request: Changes to TS
Bases Pages
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 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 when two motor
driven AFW/EFW trains are inoperable
at the same time and 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.
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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
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
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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). [This
would typically apply to plants with
each AFW/EFW motor driven pump
having less than 100% of the required
flow.] Likewise, 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.
[This 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
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
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15:03 Mar 13, 2007
Jkt 211001
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 commensurate 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 Condition 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
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11917
does not apply when the Required
Actions are not met.
The second Condition following the
first ‘‘OR’’ in Condition D 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.
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.
STS 3.7.5, Bases (as Proposed)
Though changes to the STS Bases do
not require NRC approval per se,
changes to the STS Bases were reviewed
to assess their consistency with the
proposed changes to STS 3.7.5. The
proposed changes to the STS Bases
appeared to be consistent with the
proposed changes to STS 3.7.5.
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
E:\FR\FM\14MRN1.SGM
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11918
Federal Register / Vol. 72, No. 49 / Wednesday, March 14, 2007 / Notices
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.
cprice-sewell on PROD1PC66 with NOTICES
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]).
VerDate Aug<31>2005
15:03 Mar 13, 2007
Jkt 211001
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
PO 00000
Frm 00096
Fmt 4703
Sfmt 4703
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 xx day
of xxxxxxx, 2007.
For the Nuclear Regulatory Commission.
Project Manager.
Plant Licensing Branch [ ], Division of
Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. E7–4675 Filed 3–13–07; 8:45 am]
BILLING CODE 7590–01–P
POSTAL SERVICE
Board of Governors; Sunshine Act
Meeting
Board Votes To Close March 6, 2007,
Meeting
At its teleconference meeting on
February 27, 2007, the Board of
Governors of the United States Postal
Service voted unanimously to close to
public observation its meeting
scheduled for March 6, 2007, in
Washington, DC, via teleconference. The
Board determined that prior public
notice was not possible.
Postal Regulatory
Commission Opinion and
Recommended Decision in Docket No.
R2006–1, Postal Rate and Fee Changes.
ITEM CONSIDERED:
GENERAL COUNSEL CERTIFICATION: The
General Counsel of the United States
Postal Service has certified that the
meeting was properly closed under the
Government in the Sunshine Act.
CONTACT PERSON FOR MORE INFORMATION:
Requests for information about the
meeting should be addressed to the
E:\FR\FM\14MRN1.SGM
14MRN1
]]>Agencies
[Federal Register Volume 72, Number 49 (Wednesday, March 14, 2007)]
[Notices]
[Pages 11914-11918]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-4675]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
Notice of Opportunity for Comment on Model Safety Evaluation for
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: Request for comment.
-----------------------------------------------------------------------
SUMMARY: Notice is hereby given that the staff of the Nuclear
Regulatory Commission (NRC) has prepared a model safety evaluation (SE)
relating to proposed 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 would 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 NRC staff has also prepared a model
application and model no significant hazards consideration (NSHC)
determination relating to this matter. 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. The NRC staff is
requesting comments on the Model SE, Model Application and Model NSHC
determination prior to announcing their availability for referencing in
license amendment applications.
DATES: The comment period expires 30 days from the date of this
publication. Comments received after this date will be considered if it
is practical to do so, but the Commission can only ensure consideration
for comments received on or before this date.
ADDRESSES: Comments may be submitted either electronically or via U.S.
mail.
To submit comments or questions on a proposed standard technical
specification change via the Internet, use Form for Sending Comments on
NRC Documents, then select Proposed Changes to Technical
Specifications. If you are commenting on a proposed change, please
match your comments with the correct proposed change by copying the
title of the proposed change from column one to the previous table into
the appropriate field of the comment form.
Submit written comments to: Chief, Rulemaking, Directives and
Editing Branch, Division of Administrative Services, Office of
Administration, Mail Stop T-6D59, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001.
Hand deliver comments to 11545 Rockville Pike, Rockville, Maryland,
between 7:45 a.m. and 4:15 p.m. on Federal workdays.
Copies of comments received may be examined at the NRC's Public
Document Room, located at One White Flint North, 11555 Rockville Pike
(first floor), Rockville, Maryland.
Comments may be submitted by electronic mail to CLIIP@nrc.gov.
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 for comment 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. In
addition, this notice for comment involves changes to the STS that
establish specific Conditions and Action requirements for
[[Page 11915]]
two motor driven AFW/EFW trains are inoperable at the same time and 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 proposed change to adopt TSTF-412 is applicable to all
pressurized water reactors (PWRs) designed by Babcock and Wilcox (B&W),
Westinghouse, and Combustion Engineering (CE). If approved, to
efficiently process the incoming license amendment applications, the
NRC staff will request that each licensee applying for the changes
addressed by TSTF-412, Revision 3, 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
This notice requests comments from interested members of the public
within 30 days of the date of publication in the Federal Register.
Following the NRC staff's evaluation of comments received as a result
of this notice, the NRC staff may reconsider the proposed change or may
proceed with announcing the availability of the change in a subsequent
notice (perhaps with some changes to the SE or proposed NSHC
determination as a result of public comments).
If the NRC staff announces the availability of the change,
licensees wishing to adopt the change will submit an application in
accordance with applicable rules and other regulatory requirements. The
NRC staff will in turn issue for each application a notice of proposed
action, which includes a proposed NSHC determination. A notice of
issuance of an amendment of operating license will also be issued to
announce the adoption of TSTF-412 for each plant that applies for and
receives the requested change.
Dated at Rockville, Maryland, this 8th day of March, 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 when two motor driven AFW/EFW trains are
inoperable at the same time and 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 when two motor
driven AFW/EFW trains are inoperable at the same time and 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.
[[Page 11916]]
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
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
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 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 when two motor driven AFW/EFW trains are
inoperable at the same time and 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.
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 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
[[Page 11917]]
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). [This would typically apply to plants with each AFW/EFW motor
driven pump having less than 100% of the required flow.] Likewise, 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. [This
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 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 commensurate 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 Condition 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 Condition following the first ``OR'' in Condition D 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.
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.
STS 3.7.5, Bases (as Proposed)
Though changes to the STS Bases do not require NRC approval per se,
changes to the STS Bases were reviewed to assess their consistency with
the proposed changes to STS 3.7.5. The proposed changes to the STS
Bases appeared to be consistent with the proposed changes to STS 3.7.5.
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
[[Page 11918]]
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 xx day of xxxxxxx, 2007.
For the Nuclear Regulatory Commission.
Project Manager.
Plant Licensing Branch [ ], Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. E7-4675 Filed 3-13-07; 8:45 am]
BILLING CODE 7590-01-P
