ML20199G989

Forwards SER Accepting Pressure Temp Limit Curves & Low Temp Overpressure Protection Sys Limits Methodology & Pressure Temp Limits Rept Submitted by Commonwealth Edison Co

ML20199G989
Person / Time
Site:	Byron, Braidwood
Issue date:	01/21/1998
From:	Capra R NRC (Affiliation Not Assigned)
To:	Kingsley O COMMONWEALTH EDISON CO.
Shared Package
ML20199G993	List: ML20199G989 ML20199H003
References
TAC-M98799, TAC-M98800, TAC-M98801, TAC-M98802, NUDOCS 9802040389
Download: ML20199G989 (6)

Text

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NUCLEAR RECULATORY CEMMISSIEN WASHINGTON, D.C. 30MH001 4,*****

January 21, 1998 Mr. Oliver D dngsley, President Attn.: Regulatory Services Nuclear Generation Group Commonwealth Edison Company Executive Towers West lli ,

1400 Opus Place, Suite 500 l Downers Grove,IL 60515

SUBJECT:

BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2, ACCEPTANCE FOR REFERENCING OF PRESSURE TEMPERATURE LIMITS REPORT (TAC NUMBERS M98799, M98800, M98801, AND M98802)

REFERENCES:

1. Letter from R. R. Assa, NRC, to D. L. Farrar, Commonwealth Edisen Company,' Exemption from Requirements of 10 CFR 50.60 Braidwood Station, Unit 1, July 13,1995,

2. Letter from C. l. Grimes, NRC, to R. A. Newton, Westinghouse Electric Corporation, " Acceptance for Referencing of Topical Report WCAP 14040, Revision 1,' Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Ccoldown Limit Curves '" October 16,1995. (Also known as WCAP 14040-NP-AL

3. Letter from G. F. Dick, NRC, to I. M. Johnson, Commonwealth Edison Company,

• Exemption from Requirements of 10 CFR 50.60, ' Acceptance Criteria for Fracture Prevention Measures for Lightwater Nu; lear Power Reactors for Nomial Operation'- Byron Station, Units 1 and 2,"

November 29,1996.

4. Letter from J. B. Hosmer, Commonwealth Edison Company, to NRC Document Control Desk,

• Reactor Vessel Integrated Surveillance Program 10 CFR 50, Appendix H Section 111. C," May 6,1997.

(WCAP-14824, Revision 1 is Attached).

5. Letter from J. B. Hosmer, Com; anwealth Edison Company, to NRC Document Control Desk, "Ap,..wuon for Amendment to Appendix A.

Technical Specifications, far Facility operating Licenses Relocation of Pressure and Temperature Limits," May 21,1997. l

6. Letter from J. B. Hosmer, Commonwealth Edison Company, to NRC L, y g' U V Document Control Desk, "Supp'ement to the Application for Amendment to Appendix A, Technical Specifications, for Facility Operating Licenses hhII O Relocation of Pressure and Temperature Limits," November 18,1997.

(WCAP 14940 and rata to WCAP-14940 and WCAP-14970 are Attached).

Contact:

Maggalean W. Weston, (301) 415-3151 b0 00 54 llllll l lll llll lllll P PDR .. . , . . .

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Mr. Oliver D. Kingsley 2 January 21, 1998

7. Letter from J. B. Hosmer, Commonwealth Edison Company, to NRC Document Control Desk, *SupplementalInformation Pertaining to Byron &

Braidwood's Reactor Vesse; integrated Surveillance Prograni,'

December 3,1997. (WCAP-14824, Revision 2, and Erratum to WCAP.

14824, Revision 2 are Attached).

8. Letter from G. F. Dick, NRC, to I. M. Johnson, Commonwealth Edison Company,

• Exemption from Requirements of 10 CFR 50.60 - Braidwood Nuclear Station, Unit 2,* December 12,1997,

9. Letter from H. G. Stanley, Commonwealth Edison Company, to NRC Document Control Desk, *SupplementalInformation Pertaining to Technical Specification Amendment Regarding Pressure Tempera'ure Curves Byron and Braidwoed Nuclear Power Stations,' January 8,1998.

(Errata to WCAP 14824 Revision 2, WCAP-14940 and WCAP-14970 are Attached).

10. Letter from H. G. Stanley, Commonwealth Edison Company, to NRC Document Control Desk, *SupplemertalInformation Pertaining to Technical Specification Amendment Regarding Pressure Temperature Curves Byron and Braidwood Nuclear Power Stations,' January 13, 1998,

11. Letter from G. F. Dick, NRC, to O. D. Kingsley, Commonwealth Edison Company. *Exemptior, from Requirements of 10 CFR 50.60 Byron, Units 1 and 2, and Braidwood, Units 1 and 2,* January 16,1998.

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12. Letter from R. A. Capra, NRC, to O. D. Kingsley, Commonwealth Edison l Company, " Integration of Reactor Pressure Vessel Surveillance Program j for Byron and Braidwood, Units 1 and 2," January 16,1998.

1 We have completed our review of the pressure temperature (P/T) limit curves and low temperature overpressure protection (LTOP) system limits methodology and the pressure temperature limits report (PTLR) (as referenced above), submitted by the Commonwealth Edison Company (Comed). We find the methodology to be acceptable for referencing in the administrative controls section of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2, technical specifications (TS) to the extent specified and under the limitations delineated in your submittals and the associated NRC safety evaluation, which is enclosed. The safety evaluation defines the basis for acceptance of the submittals. Our acceptance applies only to the matters described in the submittals.

The NRC reviewed Comed's method for integrating the data from the reactor pressure vessel surveillance capsules as a part of the methodology for developing the P/T limit curves. While the staff finds the method acceptable, as stated in the safety evaluation, the NRC notes that Comed should (1) re-evaluate the appropriate method for determining the best estimate chemical composition as additional chemical composition data become available, (2) assess the impoet of the assumption that the vessel weld has the same RTm value as determined from the surveillance weld in future revisions to the PTLR and/or when additional surveillance data

e 1

Mr. Oliver D. Kingsley 3 January 21, 1998 become available, and (3) address the methort for assessing the credibilliy of the surveillance capsule data, including the method for accounting for irradiation environment .id chemical composition differences, la future revisions to the PTLR.

The methodology for review relating to the P/T limit curves and the LTOP system limits was provided in the references listed above. Reference 2 included WCAP-14040-NP A which provided parts of the inethodology used for determining the amptance of the Byron and Braidwood methodology.

The methodology in WCAP 14040 NP A, along with supplements provided by Comed will bo

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used to calculate future changes to the P/T limit curves and LTOP system limits. Comed may generate new P/T limit curves and LTOP system limits in accordance with this methodology without prior approval of the staff. However, changes to the methodology must first be reviewed and approved by the staff. Syst(..n limits may be subject to audit by the staff through inspections as necessary.

We do not intend to repeat our review of the matters described in the submittals if the submittals appear as references in other license applientions relating to your plants, except to ensure that the material in the submittals is still applicable to your plants as indicated in the conclusion section of the safety valuation.

Should our criteria or regulations change so that our conclusions as to the acceptability oi .no methodology is invalidated, licensees referencing these documents will be expected to revise and resubmit their respective documentation, or submit justification for the continued effective applicability of the documents without revision of their respective documentation.

Sincerely, YUG.fW Robert. A. Capra, Director Project Directorate ill 2 Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation Docket No. STN 50-454, STN 50-455 STN 50-456 r.nd STN 50-457

Enclosure:

Safety Evaluation l cc w/ encl: See next page

Mr. Oliv:r D. Kingsley 3 January 21, 1998 become available, and (3) address the method for assessing the credibility of the surveillance c ,psuie data, including the inethod for accounting for irradiation environment and chemical composition differences, in future revisions to the PTLR. 1 The methodology for review relating to the P/T limit curves and the LTOP system limits was provided in the references listed above. Reference 2 included WCAP 14040-NP A which provided parts of the methodology used for determining the acceptance of the Byron and i Braldwood methodology. l

! The methodology in WCAP-14040-NP A, alcag with supplements provided by Comed will be used to calculate future changes to the P/T limit curves and LTOP system limits. Comed may

, generate new P/T limit curves and LTOP system limits in accordance with this methodology l

without prior approva! of the staff. However, changes to the methodology must first be reviewed and approved Sy the staff. System limits may be subject to audit by the staff through inspections as necese ",.

We do not intend to repeat our review of the matters described in the submittals if the submittals appear as references in other license applications relating to your plants, except to enscrc that the materialin the submittals is still applicable to your plants as indicated in the conclusion section of the safety evaluation.

Should our criteria or regulations change so that our conclusions as to the acceptability of the r.iethodology is invalidated, licensees referencing these documents will be expected to revise and resubmit their respective documentation, or submit justification for the continued effective applicability of the documents without revision of their respective documentation.

Sincerely, Origin 31 S);ned By Robert. A. Capra, Director Project Directorate 1112 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation Docket No. STN 50-454, STN 50-455 STN 50-456 and STN 50 457

Enclosure:

Safety Evaluation cc w/ encl: See next page Distribution-N ocket D File BSheron JStrosnider RZimmerman Byron R/F GHolahan KWichman EAdensam Braidwood R/F EWeiss TCollins RCapra PUBLIC ESullivan MShuaibi GDick OGC BElliot WDBeckner SBailey ACRS LLois MWWeston RAssa ABeach, R-lil KKarwoski TSB R/F THarris DOCUMENT NAME: G:\MWW\B_BRPTLR.LTR To receive a copy of this document, Indicate in the boa: *C" a copy w/o attachmenvenclosure *E'

• Copy w'sttachmenvenclosure *N" a No copy _

OFFICE - TSB.ADP- 4; - j j ,m PM PDill-2 lf PM.PDill 2/ o l5 N,AME MWWestort(//g/)7/ SBailey <ed GDick M' DATE / d()/99 l /Al /98 / 2 / /98' OFFICE C/S $8 QSW D C/EMCB DE - p C C/TSB.ADP af) PD PDill-2 l l NAMEAm TCc)thAF ESuthvan 6W WDBeckner' RCapra mob DATE F \ /M /98 l /M /98 OI~ J/ t\ /98 1 /2.1 /98

\ OFFICIAL RECORD NPY 7

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O. Kingsley Byronsreldwood Stesons .

Commonwealth Edison Company January 21, 1998 ,

cc:

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Mr. Wluiam P. Poirier, Director Anomey General  !

Wesenshouse Electric Corporaton 500 8. Second Street i Energy Systems Businees Unit Springleid,lHinois 62701 Post Ofnce Box 355, Bay 236 W.

Plamburgh, Pennsylvania 15230 tilinois (Jepartment of Nuclear safety Office of Nuclear Facility Safety Joeoph Gallo 1035 Outer Park Drive Gallo & Ross Springleid,lilinois 62704 1250 Eye St., N.W., Sune 302 .

Washington, DC 20005 Commonwealth Edison Company Byron Stat >n Managt.

MichaelI. Miller, Esquire 4450 N. German Church Road Sidley and Ausen Byron, Illinois 61010-9794 One First Natonal Plaza

! Chicago, Illinois 60603 Commonwealth Edison Company -

Site Vice Proeident- Byron '

Howard A. Leamer 4450 N. German Churcre Road

- Environmentallaw and Policy Byron, Illinois 61010-9794  !

Center of the L16dwest 203 N. LaSalle St. Suite 1390 U.S. Nuclear Reguietory Commission Chicago, Illinois 60601 Braidwood Resident inspectors Ofnce .

. RR t, Box 79 U.S. Nuclear Regulatory Commiselon Braceville, Illinois 60407 1

Byron Residentinspectors Ofnce 4 4448 N. German Church Road Mr. Ron Stephens Byron, Illinois 61010-g750 lilinois Emergency Services and D:saster Agency

. Regional Administrator, Region 111 110 E. Adams Street U.S. Nuclear Regulatory Commission Springneld, Illinois 62706 -

801 Warrenville Road Lisle, Illinois 60532 4351 Chairman -

. Will County Board of Supervisors 4 Ms. Lonaine Creek Will County Board Courthouse

. RR 1 Box 182 Joliet,6:linois 60434 i Mantono, Illinois 60950 i Commonwealth Edison Company

. Chairman, Ogle County Board Braidwood Station Manager Poet Oftco Box 357 ' RR t, Box 84 ,

Oregon, Illinois 61061 Braceville, Illinois 60407 '

Mrs. Phillip B. Johnson Ms. BrHget Little Rorem 1907 Stratford Lane Appleseed Coordinator

. Rockford, Illinois 61107 117 N. Linden Street Essex, Illinois 60935

George L. Edgar i Morgan, Lewis and Bochius Document Control Dssk-Licensing l

1800 M Street, N.W. Commonwealth Edison Company i Washington,DC 20036 1400 Opus Place, Guite 400 Downers Grove, Illinois 60515

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4

0. Kingsley Commonweahh Edison Company Byron /Brandwood Stations .

January 21, 1998 Commonwealth E.dison Comp &

Site Wee Preeldent- Braidwood RR 1 Box 84 BracevWie,ll 60407 Mr. Michael J. Wallace Nuclear Services Senior Vice President Commonwealth Edison Company Executive Towers West lil 1400 Opus Place, Suite 900 Downers Grove.IL 60515 Mr. Gene H. Stanley PWR's Vice President Commonwealth Edison Company Executive Towers Westlit 1400 Opus Place, Suite 900 Downers Grove,ll 60515 Mr. Steve Perry BWR's Mce President Commonwealth Edison Company Executive Towers West til 1400 Opus Place, Suite 900 Downers Grove,IL 60515 Mr. Dennis Farrar Regulatory Services Manager Commonwealth Edison Company E s'tive Towers West til NS Opus Place, Suite 500 Downers Grove,IL 60515 Ms. Irene Johnson, Licensing Director Nuclear Regulatory Services Corr.monwealth Edisnn Company Executive Towers West lil 1400 Opus Place. Suite 500 Downers Grove,IL 60515 Commonwealth Edison Company Reg. Assurance Supervisor - Braidwood RR 1 Box 79 Braceville,lilinois 60407 Commonwealth Edison Company Reg. Assmnce Supervisor- Byron 4450 N. German Church Road Byron, Illinois 61010-9794

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