[Federal Register Volume 71, Number 250 (Friday, December 29, 2006)]
[Notices]
[Pages 78472-78474]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E6-22391]
[[Page 78472]]
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NUCLEAR REGULATORY COMMISSION
Technical Specification Improvement to Remove the Main Steam and
Main Feedwater Valve Isolation Time From Technical Specifications Using
the Consolidated Line Item Improvement Process
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of Availability.
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SUMMARY: Notice is hereby given that the staff of the Nuclear
Regulatory Commission (NRC) has prepared a model Application related to
changes to the Standard Technical Specifications (STS), Section 3.7.2,
``Main Steam Isolation Valves (MSIVs)'' and Section 3.7.3 ``Main
Feedwater Isolation Valves (MFIVs), Main Feedwater Regulation Valves
(MFRVs), and [associated bypass valves].'' The changes remove the
specific isolation time for the isolation valves from the associated
STS Surveillance Requirements (SRs). The bracketed isolation time in
the STS SRs is replaced with the requirement to verify the valve
isolation time is within limits. The specific isolation time required
to meet the STS surveillances would be located outside of the technical
specifications in a document subject to control by the 10 CFR 50.59
process.
The NRC staff has also prepared a model safety evaluation (SE) and
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 may request amendments
confirming the applicability of the SE and NSHC determination to their
reactors.
DATES: The NRC staff issued a Federal Register Notice (71 FR 193,
October 5, 2006) that provided a model SE and a model NSHC
determination relating to the removal of the specific isolation time
for the isolation valves from the associated STS SRs. The NRC staff
hereby announces that the model SE and NSHC determination may be
referenced in plant-specific applications to adopt the changes. The
staff has posted a model application on the NRC Web site to assist
licensees in using the consolidated line item improvement process
(CLIIP) to revise the Standard Technical Specifications (STS), Section
3.7.2, ``Main Steam Isolation Valves (MSIVs)'' and Section 3.7.3 ``Main
Feedwater Isolation Valves (MFIVs), Main Feedwater Regulation Valves
(MFRVs), and [associated bypass valves].'' The NRC staff can most
efficiently consider applications based upon the model application if
the application is submitted within one year of this Federal Register
Notice.
FOR FURTHER INFORMATION CONTACT: Peter C. Hearn, Mail Stop: O12H2,
Division of Inspection and Regional Support, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, telephone 301-415-1189.
SUPPLEMENTARY INFORMATION: 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 CLIIP includes an opportunity for the public to
comment on proposed changes to operating licenses, including the
technical specifications (TS), after a preliminary assessment by the
NRC staff and a 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 generic change to operating licenses
and to either reconsider the change or issue the announcement of
availability for the change proposed for adoption by licensees. Those
licensees opting to apply for the subject change to operating licenses
are responsible for reviewing the NRC staff's evaluation, referencing
the applicable technical justifications, and providing any necessary
plant-specific information. Each amendment application made in response
to the notice of availability will be processed and noticed in
accordance with applicable rules and NRC procedures. This notice
involves removal of the specific isolation time for the isolation
valves from the associated STS SRs.
Applicability: This proposed change to the standard technical
specifications (STS) was submitted by the Technical Specifications Task
Force (TSTF) in TSTF-491, Revision 2, ``Removal of Main Steam and Main
Feedwater Valve Isolation Times from Technical Specifications.''
This proposal to modify technical specification requirements by the
adoption of TSTF-491 is applicable to all licensees of Combustion
Engineering, Babcock & Wilcox, and Westinghouse Pressurized Water
Reactors who have adopted or will adopt in conjunction with the change,
technical specification requirements for a Bases Control Program
consistent with the TS Bases Control Program described in Section 5.5
of the STS. Licensees that have not adopted requirements for a Bases
Control Program by converting to the improved STS or by other means,
are requested to include the requirements for a Bases Control Program
consistent with the STS in their application for the change. The need
for a Bases Control Program stems from the need for adequate regulatory
control of some key elements of the proposal that are contained in the
Bases upon adoption of TSTF-491. The staff is requesting that the Bases
changes be included with the proposed license amendments consistent
with the Bases in TSTF-491. To ensure that the overall change,
including the Bases, includes appropriate regulatory controls, the
staff plans to condition the issuance of each license amendment on the
licensee's incorporation of the changes into the Bases document and on
requiring the licensee to control the changes in accordance with the
Bases Control Program.
To efficiently process the incoming license amendment applications,
the NRC staff requests that each licensee applying for the changes
addressed in TSTF-491 use the CLIIP to submit an application that
adheres to the following model. Any deviations from the model
application should be explained in the licensee's submittal.
The CLIIP does not prevent licensees from requesting an alternate
approach or proposing changes other than those proposed in TSTF-491.
Variations from the approach recommended in this notice may, however,
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: In a Federal Register Notice dated October 5, 2006
(71 FR 193), the NRC staff requested comment on the use of the CLIIP to
process requests to adopt the TSTF-491 changes. In addition, there have
been multiple notices published for plant-specific amendment requests
to adopt changes similar to those described in this notice.
The NRC staff's model SE and model application may be examined,
and/or copied for a fee, at the NRC's Public Document Room, located at
One White Flint North, 11555 Rockville Pike (first floor), Rockville,
Maryland. Publicly available records are accessible electronically from
the Agencywide
[[Page 78473]]
Documents Access and Management System (ADAMS) Public Library component
on the NRC Web site, (the Electronic Reading Room).
The NRC staff received no responses following the notice published
October 5, 2006 (71 FR 193), soliciting comments on the model SE and
NSHC determination related to the TSTF-491 changes. The NRC staff finds
that the previously published models remain appropriate references and
has chosen not to republish the model SE and model NSHC determination
in this notice. As described in the model application prepared by the
NRC staff, licensees may reference in their plant-specific applications
to adopt the TSTF-491 changes, the model SE, NSHC determination, and
environmental assessment previously published in the Federal Register
(71 FR 193; October 5, 2006).
Dated at Rockville, Maryland, this 20th day of December 2006.
For the Nuclear Regulatory Commission.
Timothy J. Kobetz,
Chief, Technical Specifications Branch, Division of Inspection and
Regional Support, Office of Nuclear Reactor Regulation.
FOR INCLUSION ON THE TECHNICAL SPECIFICATION WEB PAGE, THE FOLLOWING
EXAMPLE OF AN APPLICATION WAS PREPARED BY THE NRC STAFF TO FACILITATE
USE OF THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS (CLIIP). THE
MODEL PROVIDES THE EXPECTED LEVEL OF DETAIL AND CONTENT FOR AN
APPLICATION TO ADOPT TSTF-491, REVISION 2, REMOVAL OF THE MAIN STEAM
AND MAIN FEEDWATER VALVE ISOLATION TIME FROM TECHNICAL SPECIFICATIONS
USING CLIIP. LICENSEES REMAIN RESPONSIBLE FOR ENSURING THAT THEIR
ACTUAL APPLICATION FULFILLS THEIR ADMINISTRATIVE REQUIREMENTS AS WELL
AS NUCLEAR REGULATORY COMMISSION REGULATIONS.
U. S. Nuclear Regulatory Commission Document Control Desk Washington,
DC 20555
SUBJECT: PLANT NAME
DOCKET NO. 50-
APPLICATION FOR TECHNICAL SPECIFICATION CHANGE TSTF-491, REMOVAL
OF THE MAIN STEAM AND MAIN FEEDWATER VALVE ISOLATION TIME FROM
TECHNICAL SPECIFICATIONS USING CONSOLIDATED LINE ITEM IMPROVEMENT
PROCESS
Gentlemen:
In accordance with the provisions of 10 CFR 50.90 [LICENSEE] is
submitting a request for an amendment to the technical specifications
(TS) for [PLANT NAME, UNIT NOS.].
The proposed amendment would modify the TS by removing the specific
isolation time for the isolation valves from the associated STS
Surveillance Requirements (SRs).
Enclosure 1 provides a description of the proposed change, the
requested confirmation of applicability, and plant-specific
verifications. Enclosure 2 provides the existing TS pages marked up to
show the proposed change. Enclosure 3 provides revised (clean) TS
pages. Enclosure 4 provides the existing TS Bases pages marked up to
show the proposed change (for information only).
[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 [NAME, TELEPHONE NUMBER]
Sincerely,
[Name, Title]
Enclosures:
1. Description and Assessment
2. Proposed Technical Specification Changes
3. Revised Technical Specification Pages
4. Marked up Existing TS Bases Changes
cc: NRC Project Manager
NRC Regional Office
NRC Resident Inspector
State Contact
Enclosure 1
Description and Assessment
1.0 DESCRIPTION
The proposed amendment would modify technical specifications by
removing the specific isolation time for the isolation valves from the
associated STS Surveillance Requirements (SRs).\1\
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\1\ [In conjunction with the proposed change, technical
specifications (TS) requirements for a Bases Control Program,
consistent with the TS Bases Control Program described in Section
5.5 of the applicable vendor's standard TS (STS), shall be
incorporated into the licensee's TS, if not already in the TS.]
The changes are consistent with Nuclear Regulatory Commission (NRC)
approved Industry/Technical Specification Task Force (TSTF) TSTF-491
Revision 2. The availability of this TS improvement was published in
the Federal Register on [DATE] as part of the consolidated line item
improvement process (CLIIP).
2.0 ASSESSMENT
2.1 Applicability of TSTF-491, and Published Safety Evaluation
[LICENSEE] has reviewed TSTF-491 (Reference 1), and the NRC model
safety evaluation (SE) (Reference 2) as part of the CLIIP. [LICENSEE]
has concluded that the information in TSTF-491, as well as the 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. [NOTE: Only those changes proposed in TSTF-491 are
addressed in the model SE. The model SE addresses the entire fleet of
Combustion Engineering, Babcock & Wilcox, and Westinghouse Pressurized
Water Reactors. The plants adopting TSTF-491 must confirm the
applicability of the changes to their plant.]
2.2 Optional Changes and Variations
[LICENSEE] is not proposing any variations or deviations from the TS
changes described in TSTF-491 or the NRC staff's model safety
evaluation dated [DATE]. [NOTE: The CLIIP does not prevent licensees
from requesting an alternate approach or proposing changes without the
requested Bases or Bases control program. However, deviations 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.]
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Determination
[LICENSEE] has reviewed the proposed no significant hazards
consideration determination (NSHCD) published in the Federal Register
as part of the CLIIP. [LICENSEE] has concluded that the proposed NSHCD
presented in the Federal Register notice is applicable to [PLANT] and
is hereby incorporated by reference to satisfy the requirements of 10
CFR 50.91(a).
[[Page 78474]]
3.2 Verification and Commitments
As discussed in the notice of availability published in the Federal
Register on [DATE] for this TS improvement, plant-specific
verifications were performed as follows:
In addition, [LICENSEE] has proposed TS Bases consistent with TSTF-491
which provide guidance and details on how to implement the new
requirements. Finally, [LICENSEE] has a Bases Control Program
consistent with Section 5.5 of the Standard Technical Specifications
(STS).
4.0 ENVIRONMENTAL EVALUATION
The amendment changes requirements with respect to the installation or
use of a facility component located within the restricted area as
defined in 10 CFR Part 20. The NRC staff has determined that the
amendment adopting TSTF-491, Rev 2, 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 TSTF-491, Rev
2, involves no significant hazards considerations, and there has been
no public comment on the finding in Federal Register Notice 71 FR 193,
October 5, 2006. 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.
5.0 REFERENCES
1. TSTF-491, Revision 2, ``Removal of Main Steam and Main Feedwater
Valve Isolation Times from Technical Specifications.''
2. NRC Model Safety Evaluation Report
Enclosure 2
PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)
Enclosure 3
PROPOSED TECHNICAL SPECIFICATION PAGES
[Clean copies of Licensee specific Technical Specification (TS) pages,
corresponding to the TS pages changed by MaTSTF-491, Rev 0, are to be
included in Enclosure 3]
Enclosure 4
PROPOSED CHANGES TO TECHNICAL SPECIFICATION BASES PAGES
[FR Doc. E6-22391 Filed 12-28-06; 8:45 am]
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