Notice of Opportunity to Comment on Model Safety Evaluation and Model License Amendment Request on Technical Specification Improvement Regarding the Removal of the Main Steam and Main Feedwater Isolation Valve Times Using the Consolidated Line Item Improvement Process, 58884-58888 [E6-16450]
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Federal Register / Vol. 71, No. 193 / Thursday, October 5, 2006 / Notices
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scoping process for the EIS to the Chief,
Rules and Directives Branch, Division of
Administrative Services, Office of
Administration, Mailstop T–6D59, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, and
should cite the publication date and
page number of this Federal Register
notice. Comments may be handdelivered to the NRC at 11545 Rockville
Pike, Rockville, Maryland, between 7:30
a.m. and 4:15 p.m. on Federal workdays.
To be considered in the scoping process,
written comments must be postmarked
or delivered by December 4, 2006.
Electronic comments may be sent by the
Internet to the NRC at
Vogtle_EIS@nrc.gov. Electronic
submissions must be sent no later than
December 4, 2006, to be considered in
the scoping process. The staff will not
consider comments submitted later than
as specified above unless time permits.
Comments will be available
electronically and accessible through
the NRC’s ERR link https://www.nrc.gov/
nrc.gov/reading-rm/adams.html at the
NRC Homepage.
Participation in the scoping process
for the EIS does not entitle participants
to become parties to the proceeding to
which the EIS relates. Notice of a
hearing regarding the application for an
ESP will be the subject of a future
Federal Register notice.
At the conclusion of the scoping
process, the NRC will prepare a concise
summary of the determination and
conclusions reached, including the
significant issues identified, and will
send a copy of the summary to each
participant in the scoping process. The
summary will also be available for
inspection through the ERR link. The
staff will then prepare and issue for
comment the draft EIS, which will be
the subject of separate notices and a
separate public meeting. Copies will be
available for public inspection at the
above-mentioned addresses, and one
copy per request will be provided free
of charge. After receipt and
consideration of the comments, the NRC
will prepare a final EIS, which will also
be available for public inspection.
Information about the proposed
action, the EIS, and the scoping process
may be obtained from Mark Notich at
(301) 415–3053 or mdn@nrc.gov.
Dated at Rockville, Maryland, this 2nd day
of October, 2006.
For the Nuclear Regulatory Commission.
Thomas A. Bergman,
Acting Director, Division of New Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. E6–16559 Filed 10–4–06; 8:45 am]
BILLING CODE 7590–01–P
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NUCLEAR REGULATORY
COMMISSION
Notice of Sunshine Act Meeting
AGENCY HOLDING THE MEETINGS: Nuclear
Regulatory Commission.
DATE: Week of October 9, 2006.
PLACE: Commissioners’ Conference
Room, 11555 Rockville Pike, Rockville,
Maryland.
STATUS: Public and Closed.
ADDITIONAL MATTERS TO BE CONSIDERED:
Week of October 9, 2006
Tuesday, October 10, 2006
12:55 p.m. Affirmation Session
(Public Meeting) (Tentative). a. Entergy
Nuclear Vermont Yankee, LLC and
Energy Nuclear Operations, Inc.,
(Pilgrim Nuclear Power Station and
Vermont Yankee Nuclear Power
Station), Massachusetts Attorney
General’s Petition for Backfit Order
(Tentative).
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Additional Information
Affirmation of Entergy Nuclear
Operations, Inc., (Pilgrim Nuclear Power
Station), Massachusetts Attorney
General’s Petition for Backfit Order,
tentatively scheduled for Thursday,
October 5, 2006, at 12:55 p.m. has been
rescheduled tentatively on Tuesday,
October 10, 2006 at 12:55 p.m.
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The schedule for Commission
meetings is subject to change on short
notice. To verify the status of meetings
call (recording)—(301) 415–1292.
Contact person for more information:
Michelle Schroll, (301) 415–1662.
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The NRC Commission Meeting
Schedule can be found on the Internet
at: https://www.nrc.gov/what-we-do/
policy-making/schedule.html.
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The NRC provides reasonable
accommodation to individuals with
disabilities where appropriate. If you
need a reasonable accommodation to
participate in these public meetings, or
need this meeting notice or the
transcript or other information from the
public meetings in another format (e.g.
braille, large print), please notify the
NRC’s Disability Program Coordinator,
Deborah Chan, at 301–415–7041, TDD:
301–415–2100, or by e-mail at
DLC@nrc.gov. Determinations on
requests for reasonable accommodation
will be made on a case-by-case basis.
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This notice is distributed by mail to
several hundred subscribers; if you no
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longer wish to receive it, or would like
to be added to the distribution, please
contact the Office of the Secretary,
Washington, DC 20555 (301–415–1969).
In addition, distribution of this meeting
notice over the Internet system is
available. If you are interested in
receiving this Commission meeting
schedule electronically, please send an
electronic message to dkw@nrc.gov.
Dated: October 2, 2006.
R. Michelle Schroll,
Office of the Secretary.
[FR Doc. 06–8530 Filed 10–3–06; 10:40 am]
BILLING CODE 7590–01–M
NUCLEAR REGULATORY
COMMISSION
Notice of Opportunity to Comment on
Model Safety Evaluation and Model
License Amendment Request on
Technical Specification Improvement
Regarding the Removal of the Main
Steam and Main Feedwater Isolation
Valve Times Using the Consolidated
Line Item Improvement Process
Nuclear Regulatory
Commission.
ACTION: Request for comment.
AGENCY:
SUMMARY: Notice is hereby given that
the staff of the U.S. 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 Standard
Technical Specification NUREG–1430,
1431, 1432, (STS) 3.7.2, ‘‘Main Stream
Isolation Valves (MSIVs);’’ NUREG–
1430, STS 3.7.3, ‘‘Main Feedwater Stop
Valves (MFSVs), Main Feedwater
Control Valves (MFCVs), and Associated
Startup Feedwater Control Valves
(SFCVs);’’ NUREG–1431, STS 3.7.3,
‘‘Main Feedwater Isolation Valves
(MFIVs), Main Feedwater Regulation
Valves (MFRVs), and Associated Bypass
Valves;’’ and NUREG–1432, STS
3.7.3,’’Main Feedwater Isolation Valves
(MFIVs), and MFIV Bypass Valves.’’
These valves are herein referred to
generically as the Main Steam and Main
Feedwater Isolation Valves. The
Babcocks and Wilcocks Owners Group
(BWOG), the Combustion Engineering
Owners Group (CEOG) and the
Westinghouse Owners Group (WOG)
participants in the Technical
Specifications Task Force (TSTF)
proposed these changes to the STS in
TSTF–491, Revision 2 ‘‘Removal of
Main Steam and Feedwater Valve
Isolation Times.’’
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The purpose of these models is to
permit the NRC to efficiently process
amendments to incorporate these
changes into plant-specific Technical
Specifications (TS) for Babcock and
Wilcock Pressurized Water Reactors
(BWPWR), Combustion Engineering
Pressurized Water Reactors (CEPWR)
and Westinghouse Pressurized Water
Reactors (WPWR). Licensees of nuclear
power reactors to which the models
apply can request amendments
conforming to the models. In such a
request, a licensee should confirm the
applicability of the model LAR, model
SE and NSHC determination to its plant.
The NRC staff is requesting comments
on the model LAR, model SE and NSHC
determination before announcing their
availability for referencing in license
amendment applications.
DATES: The comment period expires
November 6, 2006. Comments received
after this date will be considered if it is
practical to do so, but the Commission
is able to ensure consideration only for
comments received on or before this
date.
ADDRESSES: Comments may be
submitted either electronically or via
U.S. mail. Submit written comments to:
Chief, Rulemaking, Directives, and
Editing Branch, Division of
Administrative Services, Office of
Administration, Mail Stop: T–6 D59,
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.
Submit comments by electronic mail
to: CLIIP@nrc.gov. Copies of comments
received may be examined at the NRC’s
Public Document Room, One White
Flint North, Public File Area O1–F21,
11555 Rockville Pike (first floor),
Rockville, Maryland.
FOR FURTHER INFORMATION CONTACT:
Peter C. Hearn, Mail Stop: O–12H2,
Division of Inspection and Regional
Support, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone (301) 415–1189, e-mail
pch@nrc.gov.
SUPPLEMENTARY INFORMATION:
Background
Regulatory Issue Summary 2000–06,
‘‘Consolidated Line Item Improvement
Process for Adopting Standard
Technical Specifications Changes for
Power Reactors,’’ was issued on March
20, 2000. The CLIIP is intended to
improve the efficiency and transparency
of NRC licensing processes. This is
accomplished by processing proposed
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changes to the STS 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. This notice is
soliciting comment on a proposed
change to the STS that relocates the
Main Steam and Main Feedwater
Isolation Valves Closure Times for the
Babcock and Wilcock PWR STS
Revision 3.0 of NUREG–1430,
Combustion Engineering PWR STS
Revision 3.0 of NUREG–1432 and
Westinghouse PWR STS Revision 3.0 of
NUREG–1431 to a Licensee Controlled
Document that is referenced in the
Bases. 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 for proposed adoption by
licensees. Those licensees opting to
apply for the subject change to TSs are
responsible for reviewing the staff’s
evaluation, referencing the applicable
technical justifications, and providing
any necessary plant-specific
information. Following the public
comment period, the model LAR and
model SE will be finalized, and posted
on the NRC Web page. Each amendment
application made in response to the
notice of availability will be processed
and noticed in accordance with
applicable NRC rules and procedures.
This notice involves relocating the
Main Steam and Main Feedwater
Isolation Valves Closure Times for the
Babcock and Wilcock PWRs,
Combustion Engineering PWRs and
Westinghouse PWRs to a Licensee
Controlled Document that is referenced
in the Bases. By letter dated May 18,
2006, the BWPWR, CEPWR and the
WPWR OG proposed these changes for
incorporation into the STS as TSTF–
491, Revision 2. These changes are
accessible electronically from the
Agency-wide Documents Access and
Management System’s (ADAMS) Public
Electronic Reading Room on the Internet
(ADAMS Accession No. ML061500078)
at the NRC Web site https://
frwebgate.access.gpo.gov/cgi-bin/
leaving.cgi?from=leavingFR.html&log=
linklog&to=https://www.nrc.gov/readingrm/adams.html. 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–
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397–4209, 301–415–4737, or by e-mail
to pdr@nrc.gov.
Applicability
These proposed changes will revise
the Sections 3.7.2 and 3.7.3 for the
Babcock and Wilcock, Combustion
Engineering and Westinghouse plants.
To efficiently process the incoming
license amendment applications, the
NRC staff requests that each licensee
applying for the changes addressed by
TSTF–491, Revision 2, using the CLIIP
submit an LAR that adheres to the
following model. Any variations from
the model LAR should be explained in
the licensee’s submittal. 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.
Significant variations 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–491.
Public Notices
This notice requests comments from
interested members of the public within
30 days of the date of this publication.
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 model LAR,
model SE or model 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 consideration of
issuance of amendment to facility
operating license(s), a proposed NSHC
determination, and an opportunity for a
hearing. A notice of issuance of an
amendment to operating license(s) will
also be issued to announce the revised
requirements for each plant that applies
for and receives the requested change.
Dated at Rockville, Maryland this 28th day
of September 2006.
For the Nuclear Regulatory Commission.
Timothy J. Kobetz,
Chief, Technical Specifications Branch,
Division of Inspection and Regional Support,
Office of Nuclear Reactor Regulation.
Attachments—For inclusion on the
Technical Specification Web Page the
following example of an application was
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prepared by the NRC staff to facilitate
the adoption of Technical Specifications
Task Force (TSTF) Traveler TSTF–491,
Revision 2. The model provides the
expected level of detail and content for
an application to adopt TSTF–491,
Revision 2. Licensees remain
responsible for ensuring that their actual
application fulfills their administrative
requirements as well as NRC
regulations.
U.S. Nuclear Regulatory Commission,
Document Control Desk, Washington,
DC 20555.Subject: Plant Name, Docket
No. 50-[XXX,] Re: Application For
Technical Specification Improvement
To Adopt TSTF–491, Revision 2
‘‘Removal of Main Steam and Feedwater
Valve Isolation Times.’’
Dear Sir or Madam:
In accordance with the provisions of
Section 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 changes
would revise Sections 3.7.2, ‘‘Main
Steam Isolation Valves’’ and 3.7.3,
‘‘Main Feedwater Isolation Valves’’. The
changes are consistent with NRCapproved Industry Technical
Specification Task Force (TSTF)
Standard Technical Specification
Change Traveler, TSTF–491, Revision 2
‘‘Removal of Main Steam and Feedwater
Valve Isolation Times.’’ The availability
of this TS improvement was announced
in the Federal Register on [DATE]
([ ]FR[ ]) as part of the consolidated
line item improvement process CLIIP.
Enclosure 1 provides a description
and assessment of the proposed
changes, as well as confirmation of
applicability. Enclosure 2 provides the
existing TS pages and TS Bases markedup to show the proposed changes.
Enclosure 3 provides final TS pages and
TS Bases pages.
[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,
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Name, Title
Enclosures:
1. Description and Assessment of
Proposed Changes
2. Proposed Technical Specification
Changes and Technical Specification
Bases Changes
3. Final Technical Specification and
Bases pages
cc: NRR Project Manager, Regional
Office, Resident Inspector, State
Contact, T. Kobetz.
1.0 Description
This letter is a request to amend
Operating License(s) [LICENSE
NUMBER(S)] for [PLANT/UNIT
NAME(S)].
The proposed changes would revise
Technical Specification 3.7.2 ‘‘ Main
Steam Valves Closure Times’’ and 3.7.3
‘‘Main Feedwater Isolation Valves
Closure Times’’ to allow relocating the
closure times to a Licensee Controlled
Document that is referenced in the
BasesTechnical Specification Task
Force (TSTF) change traveler TSTF–491,
Revision 2, ‘‘Removal of Main Steam
and Feedwater Valve Isolation Times’’
was announced for availability in the
Federal Register on [DATE] as part of
the consolidated line item improvement
process CLIIP.
2.0 Proposed Changes
Consistent with NRC-approved
TSTF_491, Revision 2, the proposed TS
changes include: Relocating the main
steam and main feedwater isolation
closure times to a Licensee Controlled
Document that is referenced in the
Bases.
3.0 Background
The background for this application is
as stated in the model SE in NRC’s
Notice of Availability published on
[DATE ]([ ] FR [ ]), the NRC Notice for
Comment published on [DATE] ([ ] FR
[ ]), and TSTF–491, Revision 2.
4.0 Technical Analysis
[LICENSEE] has reviewed References
1 and 2, and the model SE published on
[DATE] ([ ] FR [ ]) as part of the CLIIP
Notice for Comment. [LICENSEE] has
applied the methodology in Reference 1
to develop the proposed TS changes.
[LICENSEE] has also concluded that the
justifications presented in TSTF–491,
Revision 2 and the model SE prepared
by the NRC staff are applicable to
[PLANT, UNIT NOS.], and justify this
amendment for the incorporation of the
changes to the [PLANT] TS.
5.0 Regulatory Analysis
A description of this change and its
relationship to applicable regulatory
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requirements and guidance was
provided in the NRC Notice of
Availability published on [Date] ([FR
[ ]), the NRC Notice for Comment
published on [Date] ([ ] FR [ ]) and
TSTF–491, Revision 2.
6.0 No Significant Hazards
Consideration
[LICENSEE] has reviewed the
proposed no significant hazards
consideration determination published
in the Federal Register on [DATE] ([ ]
FR [ ]) 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).
7.0 Environmental Evaluation
[LICENSEE] has reviewed the
environmental consideration included
in the model SE published in the
Federal Register on [DATE] ([ ] FR [ ])
as part of the CLIIP. [LICENSEE] has
concluded that the staff’s findings
presented therein are applicable to
[PLANT] and the determination is
hereby incorporated by reference for
this application.
8.0 References
1. Federal Register Notices: Notice for
Comment published on [DATE] ([ ] FR
[ ]).
Notice of Availability published on
[DATE] ([ ] FR [ ]).
Model Safety Evaluation—U.S.
Nuclear Regulatory Commission.
Office of Nuclear Reactor Regulation‘‘Technical Specification Task Force
TSTF–491, Revision 2, ‘‘Removal of
Main Steam and Feedwater Valve
Isolation Times.’’
Model Safety Evaluation—U.S.
Nuclear Regulatory Commission, Office
of Nuclear Reactor Regulation—
‘‘Technical Specification Task Force
TSTF–491, Revision 2,’’—‘‘Removal of
Main Steam and Feedwater Valve
Isolation Times.’’
1.0 Introduction
By letter dated [ll, 20l],
[LICENSEE] (the licensee) proposed
changes to the technical specifications
(TS) for [PLANT NAME]. The requested
changes are the adoption of TSTF–491,
Revision 2, ‘‘Removal of Main Steam
and Feedwater Valve Isolation Times’’
which was proposed by the Technical
Specification Task Force (TSTF) by
letter on May 18, 2006. The proposed
changes would revise Technical
Specification 3.7.2 ‘‘ Main Steam Valves
Closure Times’’ and 3.7.3 ‘‘Main
Feedwater Isolation Valves Closure
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Times.’’ The proposed TSTF would
allow relocating the isolation valve
closure times to a Licensee Controlled
Document that is referenced in the
Bases. Technical Specification Task
Force (TSTF) change traveler TSTF–491,
Revision 2, was announced for
availability in the Federal Register on
[DATE] as part of the consolidated line
item improvement process CLIIP.
2.0 Regulatory Evaluation
Section 182a of the Atomic Energy
Act (the ‘‘Act’’) requires applicants for
nuclear power plant operating licenses
to include TS as part of the license. The
TS ensure the operational capability of
structures, systems and components that
are required to protect the health and
safety of the public. The Commission’s
regulatory requirements related to the
content of the TS are contained in 10
CFR Section 50.36. That regulation
requires that the TS include items in the
following specific categories: (1) Safety
limits, limiting safety systems settings,
and limiting control settings
(50.36(c)(1)); (2) Limiting Conditions for
Operation (50.36(c)(2)); (3) Surveillance
Requirements (50.36(c)(3)); (4) design
features (50.34(c)(4)); and (5)
administrative controls (50.36(c)(5)).
In general, there are two classes of
changes to TS: (1) Changes needed to
reflect modifications to the design basis
(TS are derived from the design basis),
and (2) voluntary changes to take
advantage of the evolution in policy and
guidance as to the required content and
preferred format of TS over time. This
amendment deals with the second class
of changes.
In determining the acceptability of
revising STS 3.7.2 and 3.7.3, the staff
used the accumulation of generically
approved guidance in NUREG–1430,
‘‘Standard Technical Specifications,
Revision 3 Babcock and Wilcox Plants,’’
dated June, 2004; NUREG–1431,
Revision 3, ‘‘Standard Technical
Specifications, Westinghouse Plants,’’
dated June, 2004; and NUREG–1432,
‘‘Standard Technical Specifications,
Revision 3 Combustion Engineering
Plants,’’ dated June, 2004.
Licensees may revise the TS to adopt
current improved STS format and
content provided that plant-specific
review supports a finding of continued
adequate safety because: (1) The change
is editorial, administrative or provides
clarification (i.e., no requirements are
materially altered), (2) the change is
more restrictive than the licensee’s
current requirement, or (3) the change is
less restrictive than the licensee’s
current requirement, but nonetheless
still affords adequate assurance of safety
when judged against current regulatory
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standards. The detailed application of
this general framework, and additional
specialized guidance, are discussed in
Section 3.0 in the context of specific
proposed changes. Nomenclature
specific to the Westinghouse Plants is
used in the following Technical
Evaluation.
3.0 Technical Evaluation
The NRC staff has reviewed the
justification for the proposed TSTF as
described in the September 13, 2005
submittal. The detailed evaluation
below will support the conclusion 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 amendment will not
be inimical to the common defense and
security or to the health and safety of
the public.
3.1 Main Steam Isolation Valves
(MSIV)
One MSIV is located in each main
steam line outside of the containment.
Closing the MSIVs isolates each steam
generator from the others and isolates
the turbine, steam bypass system and
other auxiliary steam supplies from the
steam generator.
By isolating the steam flow from the
secondary side of the steam generator
the MSIVs prevent over cooling the
reactor core following a high energy line
break (HELB). By preventing core
overcooling the MSIVs protect the
reactor core from being damaged.
TSTF–491 is proposing to relocate the
required closure times for the MSIVs to
the Licensee Controlled Document
(LCD) that is referenced in the Bases.
Changes to LCDs are subject to the 10
CFR 50.59 process. The 10 CFR 50.59
criteria provide adequate assurance that
prior staff review and approval will be
requested by the licensee for changes to
the Bases or LCD requirements with the
potential to affect the safe operation of
the plant. Furthermore, the MSIVs are
subject to periodic testing and
acceptance criteria in accordance with
the Inservice Testing (IST) Program.
Compliance with the IST Program is
required by Section 5.5.7 of the
Standard Technical Specifications (STS)
and 10 CFR 50.55. The IST Program
includes specific reference value
baseline operating times for valves that
are not subject to arbitrary changes.
10 CFR 50.36 requires the inclusion of
the periodic testing of the MSIVs in the
Surveillance Requirements not the
actual closure time of the valves. TSTF–
491 change maintains the periodic
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58887
testing requirements for MSIVs in
accordance with 10 CFR 50.36.
Based on the requirements of 10 CFR
50.36, 10 CFR 50.59 and IST Program,
the staff concludes that relocating the
MSIV closure time to the LCD as
referenced in the Bases is acceptable.
3.2 Main Feedwater Isolation Valve
(MFIV), Main Feedwater Regulation/
Control Valve (MFRV) and Associated
Bypass Valves (BV)
The MFIVs and BVs or the MFRVs
and BVs isolate the nonsafety related
portions from the safety related portions
of the system. In the event of a
secondary side pipe rupture inside
containment, these valves limit the
quantity of high energy fluid that enters
the containment through the break and
provide a pressure boundary for the
controlled addition of auxiliary
feedwater to the intact loops.
By isolating the feedwater flow from
the affected steam generator the MFIVs,
MFRVs and BVs prevent overcooling the
reactor core and over pressurizing of the
containment from feedwater pump
runout.
As with the MSIVs, TSTF–491 is also
proposing to relocate the required
closure times for the MFIVs, MFRVs and
BVS to the LCD that is referenced in the
Bases. Changes to the Bases or LCD are
subject to the 10 CFR 50.59 process. The
10 CFR 50.59 criteria provide adequate
assurance that prior staff review and
approval will be requested by the
licensee for changes to the Bases or
Licensee Controlled Document
requirements with the potential to affect
the safe operation of the plant.
Furthermore, the MFIVs, MFRVs and
BVs are subject to periodic testing and
acceptance criteria in accordance with
the Inservice Testing (IST) Program.
Compliance with the IST Program is
required by Section 5.5.7 of the
Standard Technical Specifications (STS)
and 10 CFR 50.55. The IST Program
includes specific reference value
baseline operating times for valves that
are not subject to arbitrary changes.
10 CFR 50.36 requires the inclusion of
the periodic testing of the MFIVs,
MFRVs and BVs in the Surveillance
Requirements not the actual closure
time of the valves. TSTF–491 maintains
the periodic testing requirements for
MFIVs, MFRVs and BVs in accordance
with 10 CFR 50.36.
Based on the requirements of 10 CFR
50.36, 10 CFR 50.59 and the IST
Program, the staff concludes that
relocating the MFIVs, MFRVs and BVs
closure times to the LCD as referenced
in the Bases is acceptable.
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58888
Federal Register / Vol. 71, No. 193 / Thursday, October 5, 2006 / Notices
Environmental Consideration
consistent with NRC approved Industry/
Technical Specification Task Force
(TSTF) Standard Technical Specifcation
Change Traveler, TSTF–491, Revision 2.
Basis for proposed no-significanthazards-consideration determination:
As required by 10 CFR 50.91(a), an
analysis of the issue of no-significanthazards-consideration is presented
below:
The amendment[s] change[s] 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 or
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 no
public comment on such finding
published [DATE] ([ ] FR [ ]).
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
amendment will not be inimical to the
common defense and security or to the
health and safety of the public.
Proposed No Significant Hazards
Consideration Determination
Description of Amendment Request:
[Plant name] requests adoption of an
approved change to the standard
technical specifications (STS) for
Babcock and Wilcock PWR STS
Revision 3.0 of NUREG–1430,
Combustion Engineering PWR STS
Revision 3.0 of NUREG–1432 and
Westinghouse PWR STS Revision 3.0 of
NUREG–1431 plant specific technical
specifications (TS), to allow relocating
the main steam and main feedwater
isolation valve closure times to a
Licensee Controlled Document that is
referenced in the Bases. The changes are
Criterion 1—The Proposed Change Does Not
Involve a Significant Increase in the
Probability or Consequences of an Accident
Previously Evaluated
The proposed change allows relocating
main steam and main feedwater valve
isolation times to the Licensee Controlled
Document that is referenced in the Bases.
The proposed change is described in
Technical Specification Task Force (TSTF)
Standard TS Change Traveler TSTF–491
related to relocating the main steam and
main feedwater valves isolation times to the
Licensee Controlled Document that is
referenced in the Bases and replacing the
isolation time with the phase, ‘‘within
limits.’’
The proposed change does not involve a
physical alteration of the plant (no new or
different type of equipment will be installed).
The proposed changes relocate the main
steam and main feedwater isolation valve
times to the Licensee Controlled Document
that is referenced in the Bases. The
requirements to perform the testing of these
isolation valves are retained in the TS. Future
changes to the Bases or licensee-controlled
document will be evaluated pursuant to the
requirements of 10 CFR 50.59, ‘‘ Changes, test
and experiments’’, to ensure that such
changes do not result in more than minimal
increase in the probability or consequences
of an accident previously evaluated.
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 consequences of any
accident previously evaluated. Further, the
proposed changes do not increase the types
and the amounts of radioactive effluent that
may be released, nor significantly increase
individual or cumulative occupation/public
radiation exposures.
Therefore, the changes do not involve a
significant increase in the probability or
consequences of any accident previously
evaluated.
Criterion 2—The Proposed Change Does Not
Create the Possibility of a New or Different
Kind of Accident from any Previously
Evaluated
The proposed changes relocate the main
steam and main feedwater valve isolation
times to the Licensee Controlled Document
4.0
State Consultation
In accordance with the Commission’s
regulations, the [lll] State official
was notified of the proposed issuance of
the amendment. The State official had
[(1) no comments or (2) the following
comments—with subsequent
disposition by the staff].
mstockstill on PROD1PC61 with NOTICES
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that is referenced in the Bases. In addition,
the valve isolation times are replaced in the
TS with the phase ‘‘within limits’’. The
changes do not involve a physical altering of
the plant (i.e., no new or different type of
equipment will be installed) or a change in
methods governing normal pant operation.
The requirements in the TS continue to
require testing of the main steam and main
feedwater isolation valves to ensure the
proper functioning of these isolation valves.
Therefore, the changes do not create the
possibility of a new or different kind of
accident from any previously evaluated.
Criterion 3—The Proposed Change Does Not
Involve a Significant Reduction in the Margin
of Safety
The proposed changes relocate the main
steam and main feedwater valve isolation
times to the Licensee Controlled Document
that is referenced in the Bases. In addition,
the valve isolation times are replaced in the
TS with the phase ‘‘within limits’’.
Instituting the proposed changes will
continue to ensure the testing of main steam
and main feedwater isolation valves. Changes
to the Bases or license controlled document
are performed in accordance with 10 CFR
50.59. This approach provides an effective
level of regulatory control and ensures that
main steam and feedwater isolation valve
testing is conducted such that there is no
significant reduction in the margin of safety.
The margin of safety provided by the
isolation valves is unaffected by the proposed
changes since there continue to be TS
requirements to ensure the testing of main
steam and main feedwater isolation valves.
The proposed changes maintain sufficient
controls to preserve the current margins of
safety.
Based upon the reasoning above, the
NRC staff concludes that the
amendment request involves no
significant hazards consideration.
For the Nuclear Regulatory Commission.
Project Manager, Plant Licensing Branch,
Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. E6–16450 Filed 10–4–06; 8:45 am]
BILLING CODE 7590–01–P
OFFICE OF PERSONNEL
MANAGEMENT
Submission for OMB Emergency
Clearance and 60 Day Notice for
Comment for a Reinstatement, With
Change, of a Previously Approved
Collection: OPM Form 1300,
Presidential Management Fellows
Program Online Application and
Resume Builder
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
E:\FR\FM\05OCN1.SGM
05OCN1
]]>Agencies
[Federal Register Volume 71, Number 193 (Thursday, October 5, 2006)]
[Notices]
[Pages 58884-58888]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-16450]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
Notice of Opportunity to Comment on Model Safety Evaluation and
Model License Amendment Request on Technical Specification Improvement
Regarding the Removal of the Main Steam and Main Feedwater Isolation
Valve Times 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 U.S. 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 Standard Technical Specification NUREG-1430, 1431, 1432,
(STS) 3.7.2, ``Main Stream Isolation Valves (MSIVs);'' NUREG-1430, STS
3.7.3, ``Main Feedwater Stop Valves (MFSVs), Main Feedwater Control
Valves (MFCVs), and Associated Startup Feedwater Control Valves
(SFCVs);'' NUREG-1431, STS 3.7.3, ``Main Feedwater Isolation Valves
(MFIVs), Main Feedwater Regulation Valves (MFRVs), and Associated
Bypass Valves;'' and NUREG-1432, STS 3.7.3,''Main Feedwater Isolation
Valves (MFIVs), and MFIV Bypass Valves.'' These valves are herein
referred to generically as the Main Steam and Main Feedwater Isolation
Valves. The Babcocks and Wilcocks Owners Group (BWOG), the Combustion
Engineering Owners Group (CEOG) and the Westinghouse Owners Group (WOG)
participants in the Technical Specifications Task Force (TSTF) proposed
these changes to the STS in TSTF-491, Revision 2 ``Removal of Main
Steam and Feedwater Valve Isolation Times.''
[[Page 58885]]
The purpose of these models is to permit the NRC to efficiently
process amendments to incorporate these changes into plant-specific
Technical Specifications (TS) for Babcock and Wilcock Pressurized Water
Reactors (BWPWR), Combustion Engineering Pressurized Water Reactors
(CEPWR) and Westinghouse Pressurized Water Reactors (WPWR). Licensees
of nuclear power reactors to which the models apply can request
amendments conforming to the models. In such a request, a licensee
should confirm the applicability of the model LAR, model SE and NSHC
determination to its plant. The NRC staff is requesting comments on the
model LAR, model SE and NSHC determination before announcing their
availability for referencing in license amendment applications.
DATES: The comment period expires November 6, 2006. Comments received
after this date will be considered if it is practical to do so, but the
Commission is able to ensure consideration only for comments received
on or before this date.
ADDRESSES: Comments may be submitted either electronically or via U.S.
mail. Submit written comments to: Chief, Rulemaking, Directives, and
Editing Branch, Division of Administrative Services, Office of
Administration, Mail Stop: T-6 D59, 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.
Submit comments by electronic mail to: CLIIP@nrc.gov. Copies of
comments received may be examined at the NRC's Public Document Room,
One White Flint North, Public File Area O1-F21, 11555 Rockville Pike
(first floor), Rockville, Maryland.
FOR FURTHER INFORMATION CONTACT: Peter C. Hearn, Mail Stop: O-12H2,
Division of Inspection and Regional Support, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, telephone (301) 415-1189, e-mail pch@nrc.gov.
SUPPLEMENTARY INFORMATION:
Background
Regulatory Issue Summary 2000-06, ``Consolidated Line Item
Improvement Process for Adopting Standard Technical Specifications
Changes for Power Reactors,'' was issued on March 20, 2000. The CLIIP
is intended to improve the efficiency and transparency of NRC licensing
processes. This is accomplished by processing proposed changes to the
STS 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. This notice is soliciting comment on
a proposed change to the STS that relocates the Main Steam and Main
Feedwater Isolation Valves Closure Times for the Babcock and Wilcock
PWR STS Revision 3.0 of NUREG-1430, Combustion Engineering PWR STS
Revision 3.0 of NUREG-1432 and Westinghouse PWR STS Revision 3.0 of
NUREG-1431 to a Licensee Controlled Document that is referenced in the
Bases. 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 for
proposed adoption by licensees. Those licensees opting to apply for the
subject change to TSs are responsible for reviewing the staff's
evaluation, referencing the applicable technical justifications, and
providing any necessary plant-specific information. Following the
public comment period, the model LAR and model SE will be finalized,
and posted on the NRC Web page. Each amendment application made in
response to the notice of availability will be processed and noticed in
accordance with applicable NRC rules and procedures.
This notice involves relocating the Main Steam and Main Feedwater
Isolation Valves Closure Times for the Babcock and Wilcock PWRs,
Combustion Engineering PWRs and Westinghouse PWRs to a Licensee
Controlled Document that is referenced in the Bases. By letter dated
May 18, 2006, the BWPWR, CEPWR and the WPWR OG proposed these changes
for incorporation into the STS as TSTF-491, Revision 2. These changes
are accessible electronically from the Agency-wide Documents Access and
Management System's (ADAMS) Public Electronic Reading Room on the
Internet (ADAMS Accession No. ML061500078) at the NRC Web site https://
frwebgate.access.gpo.gov/cgi-bin/
leaving.cgi?from=leavingFR.html&log=linklog&to=https://
www.nrc.gov/reading-rm/adams.html. 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
These proposed changes will revise the Sections 3.7.2 and 3.7.3 for
the Babcock and Wilcock, Combustion Engineering and Westinghouse
plants.
To efficiently process the incoming license amendment applications,
the NRC staff requests that each licensee applying for the changes
addressed by TSTF-491, Revision 2, using the CLIIP submit an LAR that
adheres to the following model. Any variations from the model LAR
should be explained in the licensee's submittal. 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. Significant variations 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-491.
Public Notices
This notice requests comments from interested members of the public
within 30 days of the date of this publication. 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 model LAR, model SE or model 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 consideration of issuance of
amendment to facility operating license(s), a proposed NSHC
determination, and an opportunity for a hearing. A notice of issuance
of an amendment to operating license(s) will also be issued to announce
the revised requirements for each plant that applies for and receives
the requested change.
Dated at Rockville, Maryland this 28th day of September 2006.
For the Nuclear Regulatory Commission.
Timothy J. Kobetz,
Chief, Technical Specifications Branch, Division of Inspection and
Regional Support, Office of Nuclear Reactor Regulation.
Attachments--For inclusion on the Technical Specification Web Page
the following example of an application was
[[Page 58886]]
prepared by the NRC staff to facilitate the adoption of Technical
Specifications Task Force (TSTF) Traveler TSTF-491, Revision 2. The
model provides the expected level of detail and content for an
application to adopt TSTF-491, Revision 2. Licensees remain responsible
for ensuring that their actual application fulfills their
administrative requirements as well as NRC regulations.
U.S. Nuclear Regulatory Commission, Document Control Desk,
Washington, DC 20555.Subject: Plant Name, Docket No. 50-[XXX,] Re:
Application For Technical Specification Improvement To Adopt TSTF-491,
Revision 2 ``Removal of Main Steam and Feedwater Valve Isolation
Times.''
Dear Sir or Madam:
In accordance with the provisions of Section 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 changes would revise Sections
3.7.2, ``Main Steam Isolation Valves'' and 3.7.3, ``Main Feedwater
Isolation Valves''. The changes are consistent with NRC-approved
Industry Technical Specification Task Force (TSTF) Standard Technical
Specification Change Traveler, TSTF-491, Revision 2 ``Removal of Main
Steam and Feedwater Valve Isolation Times.'' The availability of this
TS improvement was announced in the Federal Register on [DATE] ([ ]FR[
]) as part of the consolidated line item improvement process CLIIP.
Enclosure 1 provides a description and assessment of the proposed
changes, as well as confirmation of applicability. Enclosure 2 provides
the existing TS pages and TS Bases marked-up to show the proposed
changes. Enclosure 3 provides final TS pages and TS Bases pages.
[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 of Proposed Changes
2. Proposed Technical Specification Changes and Technical Specification
Bases Changes
3. Final Technical Specification and Bases pages
cc: NRR Project Manager, Regional Office, Resident Inspector, State
Contact, T. Kobetz.
1.0 Description
This letter is a request to amend Operating License(s) [LICENSE
NUMBER(S)] for [PLANT/UNIT NAME(S)].
The proposed changes would revise Technical Specification 3.7.2 ``
Main Steam Valves Closure Times'' and 3.7.3 ``Main Feedwater Isolation
Valves Closure Times'' to allow relocating the closure times to a
Licensee Controlled Document that is referenced in the BasesTechnical
Specification Task Force (TSTF) change traveler TSTF-491, Revision 2,
``Removal of Main Steam and Feedwater Valve Isolation Times'' was
announced for availability in the Federal Register on [DATE] as part of
the consolidated line item improvement process CLIIP.
2.0 Proposed Changes
Consistent with NRC-approved TSTF--491, Revision 2, the proposed TS
changes include: Relocating the main steam and main feedwater isolation
closure times to a Licensee Controlled Document that is referenced in
the Bases.
3.0 Background
The background for this application is as stated in the model SE in
NRC's Notice of Availability published on [DATE ]([ ] FR [ ]), the NRC
Notice for Comment published on [DATE] ([ ] FR [ ]), and TSTF-491,
Revision 2.
4.0 Technical Analysis
[LICENSEE] has reviewed References 1 and 2, and the model SE
published on [DATE] ([ ] FR [ ]) as part of the CLIIP Notice for
Comment. [LICENSEE] has applied the methodology in Reference 1 to
develop the proposed TS changes. [LICENSEE] has also concluded that the
justifications presented in TSTF-491, Revision 2 and the model SE
prepared by the NRC staff are applicable to [PLANT, UNIT NOS.], and
justify this amendment for the incorporation of the changes to the
[PLANT] TS.
5.0 Regulatory Analysis
A description of this change and its relationship to applicable
regulatory requirements and guidance was provided in the NRC Notice of
Availability published on [Date] ([FR [ ]), the NRC Notice for Comment
published on [Date] ([ ] FR [ ]) and TSTF-491, Revision 2.
6.0 No Significant Hazards Consideration
[LICENSEE] has reviewed the proposed no significant hazards
consideration determination published in the Federal Register on [DATE]
([ ] FR [ ]) 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).
7.0 Environmental Evaluation
[LICENSEE] has reviewed the environmental consideration included in
the model SE published in the Federal Register on [DATE] ([ ] FR [ ])
as part of the CLIIP. [LICENSEE] has concluded that the staff's
findings presented therein are applicable to [PLANT] and the
determination is hereby incorporated by reference for this application.
8.0 References
1. Federal Register Notices: Notice for Comment published on [DATE]
([ ] FR [ ]).
Notice of Availability published on [DATE] ([ ] FR [ ]).
Model Safety Evaluation--U.S. Nuclear Regulatory Commission.
Office of Nuclear Reactor Regulation-``Technical Specification Task
Force TSTF-491, Revision 2, ``Removal of Main Steam and Feedwater Valve
Isolation Times.''
Model Safety Evaluation--U.S. Nuclear Regulatory Commission, Office
of Nuclear Reactor Regulation--``Technical Specification Task Force
TSTF-491, Revision 2,''--``Removal of Main Steam and Feedwater Valve
Isolation Times.''
1.0 Introduction
By letter dated [----, 20--], [LICENSEE] (the licensee) proposed
changes to the technical specifications (TS) for [PLANT NAME]. The
requested changes are the adoption of TSTF-491, Revision 2, ``Removal
of Main Steam and Feedwater Valve Isolation Times'' which was proposed
by the Technical Specification Task Force (TSTF) by letter on May 18,
2006. The proposed changes would revise Technical Specification 3.7.2
`` Main Steam Valves Closure Times'' and 3.7.3 ``Main Feedwater
Isolation Valves Closure
[[Page 58887]]
Times.'' The proposed TSTF would allow relocating the isolation valve
closure times to a Licensee Controlled Document that is referenced in
the Bases. Technical Specification Task Force (TSTF) change traveler
TSTF-491, Revision 2, was announced for availability in the Federal
Register on [DATE] as part of the consolidated line item improvement
process CLIIP.
2.0 Regulatory Evaluation
Section 182a of the Atomic Energy Act (the ``Act'') requires
applicants for nuclear power plant operating licenses to include TS as
part of the license. The TS ensure the operational capability of
structures, systems and components that are required to protect the
health and safety of the public. The Commission's regulatory
requirements related to the content of the TS are contained in 10 CFR
Section 50.36. That regulation requires that the TS include items in
the following specific categories: (1) Safety limits, limiting safety
systems settings, and limiting control settings (50.36(c)(1)); (2)
Limiting Conditions for Operation (50.36(c)(2)); (3) Surveillance
Requirements (50.36(c)(3)); (4) design features (50.34(c)(4)); and (5)
administrative controls (50.36(c)(5)).
In general, there are two classes of changes to TS: (1) Changes
needed to reflect modifications to the design basis (TS are derived
from the design basis), and (2) voluntary changes to take advantage of
the evolution in policy and guidance as to the required content and
preferred format of TS over time. This amendment deals with the second
class of changes.
In determining the acceptability of revising STS 3.7.2 and 3.7.3,
the staff used the accumulation of generically approved guidance in
NUREG-1430, ``Standard Technical Specifications, Revision 3 Babcock and
Wilcox Plants,'' dated June, 2004; NUREG-1431, Revision 3, ``Standard
Technical Specifications, Westinghouse Plants,'' dated June, 2004; and
NUREG-1432, ``Standard Technical Specifications, Revision 3 Combustion
Engineering Plants,'' dated June, 2004.
Licensees may revise the TS to adopt current improved STS format
and content provided that plant-specific review supports a finding of
continued adequate safety because: (1) The change is editorial,
administrative or provides clarification (i.e., no requirements are
materially altered), (2) the change is more restrictive than the
licensee's current requirement, or (3) the change is less restrictive
than the licensee's current requirement, but nonetheless still affords
adequate assurance of safety when judged against current regulatory
standards. The detailed application of this general framework, and
additional specialized guidance, are discussed in Section 3.0 in the
context of specific proposed changes. Nomenclature specific to the
Westinghouse Plants is used in the following Technical Evaluation.
3.0 Technical Evaluation
The NRC staff has reviewed the justification for the proposed TSTF
as described in the September 13, 2005 submittal. The detailed
evaluation below will support the conclusion 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 amendment will not be inimical to the common
defense and security or to the health and safety of the public.
3.1 Main Steam Isolation Valves (MSIV)
One MSIV is located in each main steam line outside of the
containment. Closing the MSIVs isolates each steam generator from the
others and isolates the turbine, steam bypass system and other
auxiliary steam supplies from the steam generator.
By isolating the steam flow from the secondary side of the steam
generator the MSIVs prevent over cooling the reactor core following a
high energy line break (HELB). By preventing core overcooling the MSIVs
protect the reactor core from being damaged.
TSTF-491 is proposing to relocate the required closure times for
the MSIVs to the Licensee Controlled Document (LCD) that is referenced
in the Bases. Changes to LCDs are subject to the 10 CFR 50.59 process.
The 10 CFR 50.59 criteria provide adequate assurance that prior staff
review and approval will be requested by the licensee for changes to
the Bases or LCD requirements with the potential to affect the safe
operation of the plant. Furthermore, the MSIVs are subject to periodic
testing and acceptance criteria in accordance with the Inservice
Testing (IST) Program. Compliance with the IST Program is required by
Section 5.5.7 of the Standard Technical Specifications (STS) and 10 CFR
50.55. The IST Program includes specific reference value baseline
operating times for valves that are not subject to arbitrary changes.
10 CFR 50.36 requires the inclusion of the periodic testing of the
MSIVs in the Surveillance Requirements not the actual closure time of
the valves. TSTF-491 change maintains the periodic testing requirements
for MSIVs in accordance with 10 CFR 50.36.
Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and IST
Program, the staff concludes that relocating the MSIV closure time to
the LCD as referenced in the Bases is acceptable.
3.2 Main Feedwater Isolation Valve (MFIV), Main Feedwater Regulation/
Control Valve (MFRV) and Associated Bypass Valves (BV)
The MFIVs and BVs or the MFRVs and BVs isolate the nonsafety
related portions from the safety related portions of the system. In the
event of a secondary side pipe rupture inside containment, these valves
limit the quantity of high energy fluid that enters the containment
through the break and provide a pressure boundary for the controlled
addition of auxiliary feedwater to the intact loops.
By isolating the feedwater flow from the affected steam generator
the MFIVs, MFRVs and BVs prevent overcooling the reactor core and over
pressurizing of the containment from feedwater pump runout.
As with the MSIVs, TSTF-491 is also proposing to relocate the
required closure times for the MFIVs, MFRVs and BVS to the LCD that is
referenced in the Bases. Changes to the Bases or LCD are subject to the
10 CFR 50.59 process. The 10 CFR 50.59 criteria provide adequate
assurance that prior staff review and approval will be requested by the
licensee for changes to the Bases or Licensee Controlled Document
requirements with the potential to affect the safe operation of the
plant. Furthermore, the MFIVs, MFRVs and BVs are subject to periodic
testing and acceptance criteria in accordance with the Inservice
Testing (IST) Program. Compliance with the IST Program is required by
Section 5.5.7 of the Standard Technical Specifications (STS) and 10 CFR
50.55. The IST Program includes specific reference value baseline
operating times for valves that are not subject to arbitrary changes.
10 CFR 50.36 requires the inclusion of the periodic testing of the
MFIVs, MFRVs and BVs in the Surveillance Requirements not the actual
closure time of the valves. TSTF-491 maintains the periodic testing
requirements for MFIVs, MFRVs and BVs in accordance with 10 CFR 50.36.
Based on the requirements of 10 CFR 50.36, 10 CFR 50.59 and the IST
Program, the staff concludes that relocating the MFIVs, MFRVs and BVs
closure times to the LCD as referenced in the Bases is acceptable.
[[Page 58888]]
4.0 State Consultation
In accordance with the Commission's regulations, the [------] State
official was notified of the proposed issuance of the amendment. The
State official had [(1) no comments or (2) the following comments--with
subsequent disposition by the staff].
5.0 Environmental Consideration
The amendment[s] change[s] 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 or 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 no public comment on such finding
published [DATE] ([ ] FR [ ]). 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
amendment will not be inimical to the common defense and security or to
the health and safety of the public. Proposed No Significant Hazards
Consideration Determination Description of Amendment Request: [Plant
name] requests adoption of an approved change to the standard technical
specifications (STS) for Babcock and Wilcock PWR STS Revision 3.0 of
NUREG-1430, Combustion Engineering PWR STS Revision 3.0 of NUREG-1432
and Westinghouse PWR STS Revision 3.0 of NUREG-1431 plant specific
technical specifications (TS), to allow relocating the main steam and
main feedwater isolation valve closure times to a Licensee Controlled
Document that is referenced in the Bases. The changes are consistent
with NRC approved Industry/Technical Specification Task Force (TSTF)
Standard Technical Specifcation Change Traveler, TSTF-491, Revision 2.
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:
Criterion 1--The Proposed Change Does Not Involve a Significant
Increase in the Probability or Consequences of an Accident Previously
Evaluated
The proposed change allows relocating main steam and main
feedwater valve isolation times to the Licensee Controlled Document
that is referenced in the Bases. The proposed change is described in
Technical Specification Task Force (TSTF) Standard TS Change
Traveler TSTF-491 related to relocating the main steam and main
feedwater valves isolation times to the Licensee Controlled Document
that is referenced in the Bases and replacing the isolation time
with the phase, ``within limits.''
The proposed change does not involve a physical alteration of
the plant (no new or different type of equipment will be installed).
The proposed changes relocate the main steam and main feedwater
isolation valve times to the Licensee Controlled Document that is
referenced in the Bases. The requirements to perform the testing of
these isolation valves are retained in the TS. Future changes to the
Bases or licensee-controlled document will be evaluated pursuant to
the requirements of 10 CFR 50.59, `` Changes, test and
experiments'', to ensure that such changes do not result in more
than minimal increase in the probability or consequences of an
accident previously evaluated.
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 consequences of any accident previously
evaluated. Further, the proposed changes do not increase the types
and the amounts of radioactive effluent that may be released, nor
significantly increase individual or cumulative occupation/public
radiation exposures.
Therefore, the changes do not involve a significant increase in
the probability or consequences of any accident previously
evaluated.
Criterion 2--The Proposed Change Does Not Create the Possibility of a
New or Different Kind of Accident from any Previously Evaluated
The proposed changes relocate the main steam and main feedwater
valve isolation times to the Licensee Controlled Document that is
referenced in the Bases. In addition, the valve isolation times are
replaced in the TS with the phase ``within limits''. The changes do
not involve a physical altering of the plant (i.e., no new or
different type of equipment will be installed) or a change in
methods governing normal pant operation. The requirements in the TS
continue to require testing of the main steam and main feedwater
isolation valves to ensure the proper functioning of these isolation
valves.
Therefore, the changes do not create the possibility of a new or
different kind of accident from any previously evaluated.
Criterion 3--The Proposed Change Does Not Involve a Significant
Reduction in the Margin of Safety
The proposed changes relocate the main steam and main feedwater
valve isolation times to the Licensee Controlled Document that is
referenced in the Bases. In addition, the valve isolation times are
replaced in the TS with the phase ``within limits''. Instituting the
proposed changes will continue to ensure the testing of main steam
and main feedwater isolation valves. Changes to the Bases or license
controlled document are performed in accordance with 10 CFR 50.59.
This approach provides an effective level of regulatory control and
ensures that main steam and feedwater isolation valve testing is
conducted such that there is no significant reduction in the margin
of safety.
The margin of safety provided by the isolation valves is
unaffected by the proposed changes since there continue to be TS
requirements to ensure the testing of main steam and main feedwater
isolation valves. The proposed changes maintain sufficient controls
to preserve the current margins of safety.
Based upon the reasoning above, the NRC staff concludes that the
amendment request involves no significant hazards consideration.
For the Nuclear Regulatory Commission.
Project Manager, Plant Licensing Branch, Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E6-16450 Filed 10-4-06; 8:45 am]
BILLING CODE 7590-01-P
