ML20210P156

Submits Response to Requests for Addl Info Re GL 92-01,rev 1,Suppl 1, Rv Structural Integrity, for Pbap,Units 1 & 2. NRC Will Assume That Data Entered Into Rvid Are Acceptable for Plants,If Staff Does Not Receive Comments by 990901

ML20210P156
Person / Time
Site:	Peach Bottom
Issue date:	08/10/1999
From:	Buckley B NRC (Affiliation Not Assigned)
To:	Hutton J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
References
GL-92-01, TAC-MA1203, TAC-MA1204, NUDOCS 9908120094
Download: ML20210P156 (4)

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> g g NUCLEAR REGULATORY COMMISSION 1" WASHINGTON, D.C. 20555-0001 S

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\*****p August 10, 1999 l

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l Mr. James A. Hutton -

l Director-Licensing, MC 62A-1 {

PECO Energy Company  !

Nuclear Group Headquarters Correspondence Control Desk P.O. Box No.195 Wayne, PA 19087-0195

SUBJECT:

CLOSURE OF TAC NOS. MA1203 AND MA1204 - RESPONSE TO THE I REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL l INTEGRITY," FOR THE PEACH BOTTOM ATOMIC POWER STATION, UNITS l 2 AND 3

Dear Mr. Hutton:

On May 19,1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 92-01, Revision 'i, 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 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 (2) to 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 FederalRegulations (Appendices G and H to 10 CFR Part 50).

On August 15,1995, 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 Peach Bottom Atomic Power Station, Units 2 and 3. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on September 25,1996.

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 additional data regarding the alloying chemistries of beltline welds in CE and B&W fabricated 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 l

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 assessments for your plants. On August 24,1998, the staff issued a request for additional information (RAI) in regard to the alloying chemistries of beltline welds, your assessment of surveillance data for ,

9908120094 990810 ' O PDR ADOCK 05000277 I MI i

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'p qt l' , . Mr. James A. Hutton ~ 2 L

. your facility, and pressure-temperature (P-T) limits for the Peach Bottom Atomic Power Station,

! . Units 2 and 3. - In general, with respect to the contents of the RAI, the staff requested that you l  ; reassess the alloying chemistries for the beltline welds and RPV surveillance welds relative to l . the chemistries provided in the applicable 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 applicable to the licensing ba'ses for your plants.

You provided your response to the staff's RAI for the Peach Bottom Atomic Power Station, . i

. Units 2 and 3, on November 24,1998. As a result of the staff's review of your responses to j l 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.to 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 plants. No additional 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 staff's efforts in regard to TAC Nos. MA1203 an'd MA1204. ~The staff

,, appreciates your efforts in regard to this matter.

- Sincerely,'

ORIGINAL SIGNED BY-  !

Bartholomew C. Buckle'y, Sr. Project Manager, Section 2 Project Directorate l Division of Licensing Project Management i Office of Nuclear Reactor Regulation ~

Docket Nos. 50-277 and 50-278 l

cc: See next page DISTRIBUTION:

Docket File . PUBLIC PDI-2 r/f EAdensam (EGA1)

PO'Brien JClifford BBuckley CCowgill, RI OGC ACRS Document Name: G:\PDI-2\ PEACH BOTTOM \PB1203 I

OFC PM/PDI-2 LA/PDI EMCB/DE SC/PJDI 2 NAME RBuckley/vw MNi Aleh JChord DATE [ 4 /99 Sb/ /99 T/ f /99 I/ w/99 COPY YES/NO YES/NO YES/NO YES/NO OFFICIAL RECORD COPY l

L

Mr. James A. Hutton 2 your facility, and pressure-temperature (P-T) limits for the Peach Bottom Atomic Power Station, Units 2 and 3. In general, with respect to the contents of the RAI, the staff requested that you reassess the alloying chemistries for the 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 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 applicable to the licensing bases for your plants.

You provided your response to the staff's RAI for the Peach Bottom Atomic Power Station, Units 2 and 3, on November 24,1998. 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.

l 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 plants. No additional 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 staff's efforts in regard to TAC Nos. MA1203 and MA1204. The staff appreciates your efforts in regard to this matter.

Sincerely, h h, ts.C Bartholomew C. Buckley, Sr. Project Manager, Section 2 Project Directorate i Division of Licensing Project Management ,

Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278 cc: See next page i

Peach Bottom Atomic Power Station, Units 2 and 3 cc:

J. W. Durham, Sr., Esquire Chief-Division of Nuclear Safety Sr. V.P. & General Counsel PA Dept. of PECO Energy Company Environmental Resources 2301 Market Street, S26-1 P.O. Box 8469 Philadelphia, PA 19101 Harrisburg, PA 17105-8469 PECO Energy Company Board of Suprevisors ATTN: Mr. J. Doering, Vice President Peach Bottom Township Peach Bottom Atomic Power Station R. D. #1 1848 Lay Road Delta, PA 17314 Delta, PA 17314 Public Service Commission of PECO Energy Company Maryland ATTN: Regulatory Engineer, A4-SS Engineering Division Peach Bottom Atomic Power Station Chief Engineer Chief Engineer 6 St. Paul Center 1848 Lay Road Baltimore, MD 21202-6806 Delta, PA 17314 Mr. Richard McLean Resident inspectorMr. Richard McLean Power Plant and Environmental U.S. Nuclear Regulatory Commission Review Division Peach Bottom Atomic Power Station Department of Natural Resources P.O. Box 399 B-3, Tawes State Office Building Delta, PA 17314 Annapolis, MD 21401 Regional Administrator, Region I Dr. Judith Johnsrud U.S. Nuclear Regulatory Commission National Energy Committee 475 Allendale Road Sierra Club King of Prussia, PA 19406 433 Orlando Avenue State College, PA 16803 Mr. Roland Fletcher Department of Environment Manager-Financial Control & Co-Owner 201 West Preston Street Affairs Baltimore, MD 21201 Public Service electric and Gas Company A. F. Kirby, lil P.O. Box 236 External Operations - Nuclear Hacocks Bridge, NJ 08038-0236 Delmarva Power & Light Company P.O. Box 231 Manager-Peach Bottom Licensing Wilmington, DE 19899 PECO Energy Company Nuclear Group Headquarters PECO Energy Company Correspondence Control Desk Plant Manager P.O. Box No.195 Peach Bottom Atomic Power Station Wayne, PA 19087-0195 1848 Lay Road Delta, PA 17314 Mr. Bill Boffman Environmental Review Coordinator Environmental Protection Agency 1650 Arch Street Philadelphia, PA 19106-2029

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