[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]



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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).

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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]
BILLING CODE 7590-01-P