ML20210P203

Discusses Staff Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity for Plant,Units 1 & 2

ML20210P203
Person / Time
Site:	Brunswick
Issue date:	08/05/1999
From:	Hansen A NRC (Affiliation Not Assigned)
To:	Keenan J CAROLINA POWER & LIGHT CO.
References
GL-92-01, TAC-MA1182, TAC-MA1183, NUDOCS 9908120115
Download: ML20210P203 (5)

Text

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- p nom k UNITED STAT S 2 S NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-4001 August 5, 1999 i Mr. J. S. Keenan, Vice President Brunswick Steam Electric Plant Carolina Power & Light Company )

Post Office Box 10429 Southport, North Carolina 28461

SUBJECT:

CLOSURE OF TAC NOS. MA1182 AND MA1183 - RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," FOR BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2

Dear Mr. Keenan:

1 On May 19,1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter 92-01, .

I R? vision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity," to holders of nuclear operating licenses. In issuing the GL the staff required addressees of the GL l to: '

(1) identify, collect and report any new data pertinent to the analysis of structural integrity of the reactor pressure vessels (RPVs) at their nuclear plants, and i

-(2) assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.60 and 50.61 to Part 50 of Title 10 of the. Code of Federal Regulations ,

(10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices G and H to Part 50 of Title 10 of the Code of Federa/ Regulations (Appendices G and H to 10 CFR 3 Part 50).

On August 17,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1 and provided the requested information relative to the structuralintegrity assessments for the Brunswick Steam Electric Plant (BSEP) Units 1 and 2. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on December 23, 1996. However, since the time of the staff's closure letter, the Combustion Engineering (CE)

Owners Group and the Babcock and Wilcox (B&W) Owners Group have each submitted I additional data regarding the alloying chemistries of beltline welds in CE and B&W fabricated I

vessels. The additional alloying data were submitted in Topical Reports CE NPSD-1039, Revision 2, CE NPSD-1119, Revision 1, for CE fabricated RPV welds, and BAW-2325, Revision 1, for B&W fabricated RPV welds. In addition, Chicago Bridge and Iron (CB&l) BWR data were submitted in Topical Report BWRVIP-46. As a result of the efforts by CE and B&W, the staff determined that additional information was necessary relative to the structural integrity r j assessments for your plants.

On June 17,1998, the staff issued a request for additional information (RAl) in regard to the DPD\ 3 I '

alloying chemistries of beltline welds, your assessments of surveillan::e data for your facility and '

pressure-temperature (P-T) limits for BSEP, Units 1 and 2. In general, with respect to the contents of the RAI, the staff requested that you reassess the alloying chemistries for the rypm' n 9908120115 990005 i 1* '

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2 beltline welds and RPV surveillance welds relative to the chemistries provided in the applicable topical report, and provide the impact of any changes to the best-estimate chemit,tries for your beltline RPV welds on the structural integrity assessments for your facility relative to the requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensing bases for your plants.

You provided your response to the staff's RAls for BSEP, Units 1 and 2 on September 21,1998.

As a result of the staff's review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, and the Supp.1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2.

The new database diskettes are posted on the world-wide-web at a location which is linked to the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for your plant. No additioral information is necessary with regard to the structural integrity assessments. Future s 'mittals on P-T limits or upper shelf energy (USE) should refererice the most current informa .. i .

This closes the staff's efforts in regard to TAC Nos. MA1182 and MA1183. The staff appreciates your efforts in regard to this matter.

Sincerely, Original signed by:

Allen Hansen, Pr: Ject Manager, Section 2 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 cc: See next page pistribution:

Docket File E. Dunnington ACRS PUBL{C' A.' Hansen B. Bonser, Rll PDll Rdg. OGC A. Lee, EMCB/DE DOCUMENT NAME:G:\PDil 2\ Brunswick \MA1182.cise.wpd LA:PDll-2 N PM:PDil-2 EMCB SRXB SQ:PDil;2 EDunnington . AHansenh KWichman* RCaruso* Mt 8/Y/99 f/[/99 3/3/99 6/3/99 [/I/99 OFFICIAL RECOPT OPY t.

s  % .

2 beltline welds and RPV surveillance welds relative to the chemistries provided in the applicable l topical report, and provide the impact of any changes to the best-estimate chemistries for your beltline RPV welds on the structural integrity assessments for your facility relative to the requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as ,

t applicable to the licensing bases for your plants. )

1 You provided your response to the staffs RAls for BSEP, Units 1 and 2 on September 21,1998.

As a result of the staffs review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, and the Supp.1 RAI, the staff has revised the information in the Reactor Vessel integrity Database (RVID) and is releasing it as RVID Version 2.

The new database diskettes are posted on the world-wide-web at a location which is linked to  !

the NRC home page (http://www.nrc. gov /NRR/RVID/index.html ). We recommend that you l review this information. If the staff does not receive comments by September 1,1999, we will l assume that the data entered into the RVID are acceptable for your plant. No additional l information is necessary with regard to the structuralintegrity assessments. Future submittals on P-T limits or upper shelf energy (USE) should reference the most current information.

This closes the staffs efforts in regard to TAC Nos. MA1182 and MA1183. The staff appreciates your efforts in regard to this matter.

1 Sincerely, l Original signed by:

Allen Hansen, Project Manager, Section 2 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 cc: See next page Distribution:

Docket File E. Dunnington ACRS PUBLIC A.Hansen B. Bonser, Ril PDil Rdg. OGC , A. Lee, EMCB/DE DOCUMENT NAME:G:\PDil-2\ Brunswick \MA1182.cise.wpd L A:PDil-2 MP PM:PDil-2 EMCB SRXB SS:PDili2 EDunnington AHansenh KWichman* RCaruso* t 8/ / /99 f/[/99 3/3/99 6/3/99 [///99 OFFICIAL RECORD COPY

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2 beltline welds and RPV surveillance welds relative to the chemistries provided in the applicable i topical report, and provide the impact of any changes to the best-estimate chemistries for your l belthne RPV welds on the structuralintegrity assessments for your facility relative to the I requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as t applicable to the licensing bases for your plants.

You provided your response to the staffs RAls for BSEP, Units 1 and 2 on September 21,1998.

l As a result of the staffs review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, and the Supp.1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2.

The new database diskettes are posted on the world-wide-web at a location which is linked to a

the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will l

assume that the data entered into the RVID are acceptable for your plant. No additional i information is necessary with regard to the structural integrity assessments. Future submittats on P-T limits or upper shelf energy (USE) should reference the most current information.

This closes the staffs efforts in regard to TAC Nos. MA1182 and MA1183. The staff appreciates your efforts in regard to this matter.

Sincerely,

/ > -

Allen Hansen, Project Manager, Section 2 Project Directorate li 1

Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 cc: See next page

i e 1

. 1

, s l Mr. J. S. Keenan Brunswick Steam Electric Plant Carolina Power & Light Company' Units 1 and 2 cc:

Mr. William D. Johnson Ms. Karen E. Long Vice President and Corporate Secretary Assistant Aitorney General p Carolina Power & Light Company State of North Carolina l Post Office Box 1551 Post Office Box 629 Raleigh, North Carolina 27602 Raleigh, North Carolina 27602 Mr. Jerry W. Jones, Chairman Mr. Robert P. Gruber Brunswick County Board of Commissioners Executive Director Post Office Box 249 Public Staff - NCUC 1 Bolivia, North Carolina 28422 Post Office Box 29520 Raleigh. North Carolina 27626-0520 ,

Resident inspector U.S. Nuclear Regulatory Commission 8470 River Road Director Southport, North Carolina 28461 Site Operations Brunswick Steam Electric Plant (

Mr. John H. O'Neill, Jr. Post Office Box 10429 Shaw, Pittman, Potts & Trowbridge Southport, North Carolina 28461 2300 N Street, NW.

Washington, DC 20037-1128 Mr. William H. Crowe, Mayor City of Southport Mr. Mel Fry, Director 201 East Moore Street l Division of Radiation Protection Southport, North Carolina 28461 N.C. Department of Environment and Netural Resources Mr. Dan E. Summers 3825 Garrett Dr. Emergency Management Coordinator Raleigh, North Carolina 27609-7721 New Hanover County Department of Emergency Management Mr. J. J. Lyash Post Office Box 1525 Plant Manager Wilmington, North Carolina 28402 Carolina Power & Light Company Brunswick Steam Electric Plant Mr. Terry C. Morton Post Office Box 10429 Manager Southport, North Carolina 28461 Performance Evaluation and Regulatory Affairs CPB 7 Public Service Commission Carolina Power & Light Company State of South Carolina Post Office Box 1551 Post Office Drawer 11649 Raleigh, North Carolina 27602-1551 Columbia, South Carolina 29211 Mr. K. R. Jury Manager - Regulatory Affairs Carolina Power & Light Compcny Post Office Box 10429 Southport, NC 28461-0429