ML092380588

Catawba, Units 1 & 2, License Amendment, Implement Technical Specification Task Force (TSTF) Changes Travelers TSTF-479, Revision 0, Changes to Reflect Revision [Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a] 10 CFR 5

ML092380588
Person / Time
Site:	Catawba
Issue date:	10/30/2009
From:	Thompson J H Plant Licensing Branch II
To:	Morris J R Duke Energy Carolinas
Thompson Jon, NRR/DORL/LPL 2-1, 415-1119
References
TAC MD9965, TAC MD9966
Download: ML092380588 (15)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 October 30, 2009 Mr. J. R. Morris Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745

SUBJECT:

CATAWBA NUCLEAR STATION, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS ADOPTING TSTF-479, REVISION 0, AND TSTF-497, REVISION 0 (TAC NOS. MD9965 AND MD9966)

Dear Mr. Morris:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 252 to Renewed Facility Operating License NPF-35 and Amendment No. 247 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively.

The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October 14, 2008. The amendments implement Technical Specification Task Force (TSTF) Changes Travelers TSTF-479, Revision 0, "Changes to Reflect Revision of [Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a] 10 CFR 50.55a," and TSTF-497, Revision 0, "Limit Inservice Testing [1ST] Program SR [Surveillance Requirements]

3.0.2 Application

to Frequencies of 2 Years or Less." TSTF-479 and TSTF-497 revised the Technical Specification Administrative Controls section pertaining to requirements for the 1ST Program, consistent with the requirements of 10 CFR 50.55a(f)(4) for pumps and valves which are classified as American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code), Class 1, Class 2, and Class 3. A copy of the related Safety Evaluation is also enclosed.

A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

J. Morris -2 If you have any questions, please call me at 301-415-1119.

Sincerely, Jon Thompson, Project Plant Licensing Branch Division of Operating Reactor Office of Nuclear Reactor Docket Nos. 50-413 and

Enclosures:

1. Amendment No. 252 to 2. Amendment No. 247 to 3. Safety Evaluation cc w/encls: Distribution via Listserv UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 252 Renewed License No. NPF-35 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment to the Catawba Nuclear Station. Unit 1 (the facility)

Renewed Facility Operating License No. NPF-35 filed by the Duke Energy Carolinas, LLC. acting for itself. and North Carolina Electric Membership Corporation (licensees), dated October 14,2008. complies with the standards and requirements of the Atomic Energy Act of 1954. as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; The facility will operate in conformity with the application.

the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

-2Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-35 is hereby amended to read as follows: Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 252 ,which are attached hereto, are hereby incorporated into this license. Duke Energy Carolinas, LLC, shall operate the facility in accordance with the Technical Specifications. This license is also amended to authorize revisions to the Updated Final Safety Analysis Report for the Catawba Nuclear Station to address sections where it currently references the "ASME [American Society of Mechanical Engineers]

Section XI of the ASME Boiler and Pressure Vessel Code." This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION G>te.-<< ...Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-35 and the Technical Specifications Date of Issuance:

October 30, 2009 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 DUKE ENERGY CAROLINAS, NORTH CAROLINA MUNICIPAL POWER AGENCY PIEDMONT MUNICIPAL POWER DOCKET NO. CATAWBA NUCLEAR STATION, UNIT AMENDMENT TO RENEWED FACILITY OPERATING Amendment No. 247 Renewed License No. NPF-52 The Nuclear Regulatory Commission (the Commission) has found that: The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility)

Renewed Facility Operating License No. NPF-52 filed by the Duke Energy Carolinas, LLC, acting for itself, North Carolina Municipal Power Agency No. 1 and Piedmont Municipal Power Agency (licensees), dated October 14, 2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

-2Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-52 is hereby amended to read as follows: Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 247, which are attached hereto, are hereby incorporated into this license. Duke Energy Carolinas, LLC, shall operate the facility in accordance with the Technical Specifications. This license is also amended to authorize revisions to the Updated Final Safety Analysis Report for the Catawba Nuclear Station to address sections where it currently references the "ASME [American Society of Mechanical Engineers]

Section XI of the ASME Boiler and Pressure Vessel Code." This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION G ((. .. L. .--' Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-52 and the Technical Specifications Date of Issuance:

October 30, 2009 ATTACHMENT LICENSE AMENDMENT NO. RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. AND LICENSE AMENDMENT NO. RENEWED FACILITY OPERATING LICENSE NO. DOCKET NO. Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove Licenses Licenses NPF-35, page 4 NPF-35, page 4 NPF-52, page 4 NPF-52, page 4 TSs TSs 5.5-6 5,5-6

in Appendix A. 8S r,vised through . .

,No. 252 whIch are,attacheej"-hereto.

are hflreby IncDrporated Inlo . I this renewed opeJElIlrig licef1&8.

Duke Energy CwOlinas, LlC sh811 operate' the facmty 10 with th8 Technical Specifications. " . . .. ".. Updated Final Safety AnalySiS, Report .'The Updated Finel Safety Analysis Report.supplement submitted puriuant to 10 ct:=R 54.21(d), Btl revhJed Deoember 16, 2002,* describes eer1a.ln future activities to be completed before the per10d of extended operation.

Duke shall . complete theM actlvitles no later than February 24. 2026. lind shall notify the NRC In writing When Implementation of these activities

'Is, compfBte and be verified bt NRC

' The Updat8ci Final Safety Analysls'Report a8 revlSedon December 16, 2002, above. shall* be Included In the'neJCt scheduled' update to the Updated Final safety AnalySis ReP9rt by' 10 CFR 50.71(6)(4), following

• issuance'of this renewed openiting liOef1se.

Unlil tt1Bt update Is co'mplet" Duke changes to the ptOgr8ms described

!nsuch withOut prior CommiSsion approval, proviijed that Duke evaluates each chilnge' pursuant to the criteria set forth In 10 CFR 50.59 and . otherwise comples with the requirements in that section. anti1wst Conditions , Duke Caroflnas.

LLC comply with the antitN8t conditions detineated in Appendix C to this renewed opereting license. Fire-Protection prOgram (Section 9',5,1, SER, SSER,#2, SSER #3,SSER #4, SSER #5)* Duke Energy Carolinas, LLC she" implement and maln,tain In enect 1111 proviSions . of approved fire protection program as in the U{)dlited Final Sefety Analysis Report, as emended; for flllf?"ty and -a8 approved in the SER through SUpplement

5. subject to the followtng provision:

' The fieans"" may make chBligeS to the apprgved fire program without prior approval of the Commission*

only If those changes would not adversely affect the ability to achieve and maintain safe shutdown In the event of a fire. .,-he pare nthetical ngtation following the title of this reneWed operating license cgndition denotes the lection of the Safety Evaluation Report and/of its supplements Wherein this renewed license condition is discussed, Renewed No. NPF-35 Amendment No. 252

SpecifiCations, .The Technical:Speciflcatlonis coniained if) as through 247 which are hereby Into 'I, renewed operiiltrig DUke Energy C.roli!las, LLC operate the ..

with the Tectrticaf . ". UPdated Final

. ,.The Updated Final Analysis RepOrt supplement purI",nt to 10 CfR as revtsed 9" DBcember 16, 2002"descrtbes cef18ln future activities to be completed the pertod Qf elCtendedoPeratlo,1.

Duke shall . complete these activities no later than February 24. 2026, end shalt notify the NRC In writing When Implementation of these ectlvltles Is complele and CM be by NRC

' The Up'dated Safely Analysis'.RePort as revised on " December 16; 2002, described above, shall be InclUded In the next scheduled' update to the Updated' Final Safety Analysis ReP9rt required by 10 CFR 5Q..71 (e')(4), following Issuance'of this renewed operating that , update Is complet",

Changes to the progrilms described In lJuch supplement wlthout prior Comm!Sslon approval, prOVided that DUke,evah,istes eich such change' pursuant to the crlter1a set forti In 10 CFR 50.59 and . otherwise with tbe requirements in that section. (4 Anllttu§t Conditions Duke Carolinas, LLC sI)aIl compty with the antitrust condlUons deYneated in Appendix C to this renewed operating .Iicense. Fire Protection Program 9.5.1, SER, SSER#2, S$ER #3, SSER #4, SS.ER #5). Duke Energy Carolln8s, LlC shall ImPlement and in effect all provisions of the approved fire protection program 'as in the Updated Flnal,Safety AnalysIS amended; for the facility' end'88 approved In the SER thr9ugh Supplement 5, subject to provision: ' . The may make changes to the fife pr:oteetion pJogram without prior approV81 of the Commission only If those chflnges would not adversely affect the ability to achieve and maintain safe shutdown In the event of a fire. *The perenthetlcal notation follo wing the tltltt of this renewed operating license condition denotes the section of the safety Evaluation Report and/or Its supplements wherein' this renewed ftcerise condition is discussed.

Renewed No.

Amendment No. 247 Programs and Manuals 5.5 5.5 Programs and Manuals (continued)

5.5.8 Inservice

Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components including applicable supports.

The program shall include the following: Testing frequencies applicable to the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows: ASME OM Code and applicable Required Frequencies for Addenda terminology for performing inservice testing inservice testing activities activities At least once per 7 days At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 At least once per 276 days Yearly or At least once per 366 days Biennially or every 2 years At least once per 731 days The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less for performing inservice testing activities; The provisions of SR 3.0.3 are applicable to inservice testing activities; and Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS. 5.5.9 Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure that SG tube integrity is maintained.

In addition, the Steam Generator Program shall include the following provisions: Provisions for condition monitoring assessments.

Condition monitoring assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the (continued)

Catawba Units 1 and 2 Amendment Nos. 252, 247 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 252 TO RENEWED FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT NO. 247 TO RENEWED FACILITY OPERATING LICENSE NPF-52 DUKE ENERGY CAROLINAS, LLC CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414

1.0 INTRODUCTION

By application dated October 14, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082940052), Duke Energy Carolinas, LLC (Duke, the licensee).

requested changes to the Technical Specifications (TSs) for the Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2). The amendments implement Technical Specification Task Force (TSTF) Change Travelers TSTF-479, Revision 0, "Changes to Reflect Revision of Title 10 of the Code of Federal Regulations (10 CFR) Part 50. Section 50.55a," and TSTF-497, Revision O. "Limit Inservice Testing (1ST) Program SR (Surveillance Requirements)

3.0.2 Application

to Frequencies of 2 Years or Less." TSTF-479 and TSTF-497 revised the TSs Administrative Controls section pertaining to requirements for the 1ST Program. consistent with the requirements of 10 CFR 50.55a(f)(4) for pumps and valves which are classified as American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code). Class 1, Class 2, and Class 3. This change would eliminate the ASME Code inconsistency between the revised 1ST program and the current TSs, as required by 10 CFR 50.55a(f)(5)(ii).

Additionally, the amendment would extend the applicability of Surveillance Requirement (SR) 3.0.2 provisions to other normal and accelerated frequencies specified as 2 years or less in the 1ST program.

2.0 REGULATORY EVALUATION

Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include Technical Specifications as part of the license. These TSs are derived from the plant safety analysis.

-2 Section 50.55a(f)(4) of 10 CFR Part 50 requires, in part, that ASME Code Class 1,2, and 3 components must meet the 1ST requirements of the ASME OM Code. Section 50.55a(f)(4)(ii) requires that 1ST programs be revised every 10 years (120 months) to comply with the requirements of the latest edition and addenda of the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Code) that is incorporated by reference in 10 CFR 50.55a(b)(3).

Section 50.55a(f)(5)(ii) requires that, if a revised 1ST program for a facility conflicts with the TSs for that facility, the licensee shall apply to the NRC for amendment of the TSs to conform the TSs to the revised program. The licensee is required to submit the application at least 6 months before the start of the period during which the provisions become applicable, in accordance with Section 50.55a(f)(4).

The Catawba 1 and 2 third 1 O-year interval 1ST program was developed to meet the requirements of the 1998 Edition through 2000 Addenda of the ASME OM Code pursuant to 10 CFR 50.55a(f)(4)(ii).

The third 10-year 1ST interval for Catawba 1 and 2 began August 19, 2005. The ASME OM Code was initially incorporated by reference in 10 CFR 50.55a(b)(3) in a final rule dated September 22, 1999 (64 FR 51370). Prior to the final rule, 1ST programs were required to meet the requirements of Section XI, Division 1, of the ASME Code. The rules for 1ST of pumps and valves were deleted from the ASME Code,Section XI, in the 2000 Addenda after the 1ST rules were placed in the ASME OM Code. The Catawba 1 and 2 third 10-year interval 1ST program for pumps and valves was developed to meet the requirements of the ASME OM Code. The licensee submitted this TS amendment to revise Section 5.5.8, "Inservice Testing Program," to reference the pump and valve 1ST reqUirements in the ASME OM Code and delete the references to ASME Code,Section XI, 1ST requirements.

This TS amendment addresses TS Task Force (TSTF) Change Travelers TSTF-479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a," and TSTF-497, Revision 0, "Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less." The NRC staff approved the incorporation of TSTF-479 and TSTF-497 into NUREG-1431, "Standard Technical Specifications (STS) Westinghouse Plants", on December 6, 2005, and October 4, 2006, respectively.

TSTF-479 addressed changes to Section 5.5.8, "Inservice Testing Program," to reflect the revisions to 10 CFR 50.55a referencing the ASME OM Code and the application of SR 3.0.2 to test frequencies specified in the 1ST program. TSTF-497 updated Section 5.5.8.b to specify that the provisions of SR 3.0.2 apply only to 1ST frequencies of two years or less. The NRC staff reviewed the proposed changes for consistency with TSTF-479, Revision 0, and TSTF-497, Revision 0, and to ensure that the TSs continue to meet 10 CFR 50.36, "Technical specifications." In general, licensees cannot justify TS changes solely on the basis of adopting the model Standardized TSs. To ensure acceptability, the NRC staff makes a determination that proposed changes maintain adequate safety.

-3 3.0 TECHNICAL EVALUATION

3.1 Specific

Changes Requested Duke proposed the following changes to the TSs for Catawba 1 and 2: TS 5.5.8, "Inservice Testing Program," would be revised to delete references to Section XI of the ASME Code and incorporate references to the ASME OM Code. TS 5.5.8.b would be revised to apply SR 3.0.2 to other normal and accelerated frequencies specified as 2 years or less in the Inservice Testing Program. Associated TS Bases Sections would be revised to replace references to the ASME Code,Section XI, with references to the ASME OM Code for consistency with the TS changes. Duke has not proposed any variation or deviation from the TS changes described in TSTF-479, Revision 0 and TSTF-497, Revision O. 3.2 Evaluation In 1990, ASME published the initial edition of the ASME OM Code, which provides rules for 1ST of pumps and valves. The ASME OM Code replaced ASME Code,Section XI, for 1ST of pumps and valves. The 1995 edition of the ASME OM Code was incorporated by reference into 10 CFR 50.55a on September 22, 1999. As a consequence, the TS 5.5.8 reference to Section XI of the ASME Code for 1ST requirements results in a reference to a deleted portion of the ASME Code. The TS changes do not eliminate any tests and do not relinquish the licensee of its responsibility to seek relief from Code test requirements when they are impractical.

The changes will eliminate the ASME Code inconsistency between the 1ST program and the TSs as required by 10 CFR 50.55a(f)(5)(ii).

Additionally, the proposed changes are consistent with the comparable Section 5.5.8 of the STS, contained in NUREG-1431.

The licensee's proposed change to TS 5.5.8.b applies SR 3.0.2 to the frequencies specified in TS 5.5.8.a and other normal and accelerated frequencies specified as two years or less in the 1ST program. This change recognizes that the 1ST program may direct that additional tests be performed, in accordance with the ASME OM Code that are not at the standard intervals listed in TS 5.5.8.a. This is consistent with the intent of the 25 percent extension to the surveillance frequency as described in the Bases for SR 3.0.2, in that the extension would provide operational flexibility, but would not significantly degrade the reliability that results from performing the surveillance at the specified frequency.

Further, the licensee's proposal to limit application of SR 3.0.2 to frequencies specified as 2 years or less limits the maximum incremental time period between surveillances that could be added by the 25 percent extension.

Without this limitation, some components, such as safety and relief valves which may be tested at surveillance intervals significantly greater than 2 years, could have extensions applied which would be much greater than needed for operational flexibility.

These aspects of the proposed change support ASME Code provisions which provide the basis for the 1ST program and are consistent with guidance contained in NUREG-1482, Revision 1, regarding maximum allowable extensions of test intervals.

-The licensee's TS revision fully adopts TSTF-479, Revision 0, and TSTF-497, Revision 0, changes to Section 5.5.8 of the Catawba 1 and 2 TSs to reflect the latest approved version of the ASME OM Code, the applicability of the provisions of SR 3.0.2, and additional wording to clarify that the test interval extension in the 1ST program applies only to test intervals of 2 years or less. The NRC staff also reviewed the changes against the requirements of 10 CFR 50.36 and found them to be acceptable.

Therefore, the NRC staff concludes that the licensee's proposed changes to the Catawba 1 and 2 TSs requirements do not result in any substantive change in the operating requirements, are consistent with the Commission's regulation, and conform to the requirements of 10 CFR 50.55a. On this basis, the NRC staff concludes that the proposed TS changes are acceptable.

4.0 STATE

CONSUL TATIOI\I In accordance with the Commission's regulations, the South Carolina State official was notified of the proposed issuance of the amendments.

The State official had no comments.

5.0 ENVIRONMENTAL

CONSIDERATION The amendments relate to changes in recordkeeping, reporting, or administrative procedures or requirements.

Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).

Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributors:

Y.S. Huang J. Bream Date: October 30, 2009 J. Morris -2 If you have any questions, please call me at 301-415-1119.

Sincerely, IRA! Jon Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414

Enclosures:

1. Amendment No. 252 to NPF-35 2. Amendment No. 247 to NPF-52 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

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PM NRRlLPL2-1/LA DIRS/ITSB/BC DCI/CPTB/BC NAME JThom son MO'Brien RElliott .IMcHale*

DATE 09/10/09 09/16/09 09/18/09 11/17/08 OFFICE NAME DATE OGC AJones** NLO 09/30/09 NRRlLPL2-1/BC GKulesa 10/29/09 NRR/LPL2-1/PM JThom son 10/30/09 OFFICIAL RECORD COpy