ML20196J551

Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & DE Responses & 980729 for Fermi 2.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 as Result of Review of Responses

ML20196J551
Person / Time
Site:	Fermi
Issue date:	07/02/1999
From:	Kugler A NRC (Affiliation Not Assigned)
To:	Gipson D DETROIT EDISON CO.
References
GL-92-01, GL-92-1, TAC-MA1189, NUDOCS 9907070340
Download: ML20196J551 (5)

Text

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y 4 UNITED STATES g NUCLEAR REGULATORY COMMISSION

, wasHINeToN, D.C. 30006 4001

< ***** . . July 2, 1999 Mr. Douglas R. Gipson Senior Vice President .

Nuclear Generation Detroit Edison Company 6400 North Dixie Highway Newport, MI 48166 -

SUBJECT:

. FERMI 2 - RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION IN GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR J VESSEL STRUCTURAL INTEGRITY" (TAC NO. MA1189)

Dear Mr. Gipson:

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

- Revision 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

'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 Part 50).

On August 4,1995, you submitteo your initial response to GL 92-01, Rev.1, Supp.1, and provided the requested information relative to the structural integrity assessment for Fermi 2.

The staff evaluated your response to GL S2-01, Rev.1, Supp.1, and provided its conclusion relative to your response on August 19,1996. However, since the time of the staffs 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 i l Topical Reports CE NPSD-1039, Revision 2, and CE NPSD-1119, Revision 1, for CE-fabricated }

RPV welds, and BAW-2325, Revision 1, for B&W-fabricated RPV welds. In addition, Chicago O Bridge and iron (CB&l) boiling-water reactor 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

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necessary relative to the structural integrity assessments for your plant. On April 24,1998, the

- staff issued a request for additional information (RAI) in regard to the alloying chemistries of I beltline welds, your assessment of surveillance data for your facility, and pressure-temperature y (P-T) limits for Fermi 2. In general, with respect to the contents of the RAI, the staff requested that you reassess the alloying chemistries fo; the beltline welds and RPV surveillance welds relative to the chemistries provided in the applicable topical report, and provide the impact of i any changes to the best-estimate chemistries for your beltline RPV welds on the structural l 9907070340 990702

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1 integrity assessments for your facility relative to the requirements of 10 CFR 50.60 and Appendices G and H to 10 CFR Part 50, as applicable to the licensing basis for your plant. j You provided your response to the staffs RAl for Fermi 2 on July 29,1998. As a result of the i staffs review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, and the l Supp.1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database

1. (RVID) and is releasing it as RVID Version 2.

The new database files are posted on the World Wide Web at a location that is linked to the i

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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 additional information is necessary with regard to the structural integrity assessments. Future submittals on P-T limits or upper-shelf energy should reference the most current information. l l

This closes the staffs efforts in regard to TAC No. MA1189. The staff appreciates your efforts in l regard to this matter.  ;

Sincerely,  ;

~

Andrew J. Kugler, oject Manager, Section 1 Project Directorate lli i Division of Licensing Project Management l Office of Nuclear Reactor Regulation j Docket No. 50-341 cc w/ encl: See next page l

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l '. Mr. Douglas R. Gipson -

l Detroit Edison Company Fermi 2 l cc:

, John Flynn, Esquire l' SeniorAttorney

- Detroit Edison Company -

2000 Second Avenue Detroit, Michigan 48226 Drinking Water and Radiological Protection Division Michigan Department of-l Environmental Quality 3423 N. Martin Luther King Jr Blvd P. O. Box 30630 CPH Mailroom

- Lansing, Michigan 48909-8130 U.S. Nuclear Regulatory Commission Resident inspector's Office 6450 W. Dixie Highway -

Newport, Michigan 48166 Monroe County Emergency Management Division 963 South Raisinville Monroe, Michigan 48161 Regional Administrator, Region lil U.S. Nuclear Regulatory Commission 801 Warrenviile Road Lisle, Illinois 60532-4351 Norman K. Peterson Director, Nuclear Licensing Detroit Edison Company Fermi 2 - 280 TAC 6400 North Dixie Highway-Newport, Michigan 48166 f

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l D. Gipson . July 2, 1999 integrity assessments for your facility relative to the requirements of 10 CFR 50.60 and Appendices G and H to 10 CFR Part 50, as applicable to the licensing basis for your plant.

You provided your response to the staffs RAI for Fermi 2 on July 29,1998. 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 files are posted on the World Wide Web at a location that 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 additional information is necessary with regard to the structural integrity assessments. Future submittals on P-T limits or upper-shelf energy should reference the most current information.

This closes the staffs efforts in regard to TAC No. MA1189. The staff appreciates your efforts in repd to this matter.

Sincerely, Original signed by:

Andrew J. Kugler, Project Manager, Section 1 Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-341 cc w/ encl: See next page DISTRIBUTION:

. Docket File PUBLIC i PD3-1 Reading A.D. Lee, EMCB  !

OGC ACRS l' A. Vegel, Rill DOCUMENT NAME: G:\PDill-1\ FERMI \LTRA1189.wpd l To receive a copy of this document. Indicate in the box: "C" = Copy without attachment / enclosure *E" = Copy with attachment / enclosure "N" = No copy OFFICE PM:LPD3 C 1%$$D3 lC SC:LPD3 C  !

NAME AKugler QLyt dbAdoVe CCraig ('fLi('

DATE 07/ 2. /99 " 07/CLl99 07/ S /99 OFFICIAL RECORD COPY

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j. D. Gipson 2- July 2, 1999 integrity assessments for your facility relative to the requirements of 10 CFR 50.60 and ,

- Appendices G and H to 10 CFR Part 50, as applicable to the licensing basis for your plant .

l You provided your response : he staffs RAI for Fermi 2 on July 29,1998. As a result of the i

staffs review of your respons64 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 files are posted on the World Wide Web at a location that 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 L

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

This closes the staffs efforts in regard t'o TAC No. MA1189.' The staff appreciates your efforts in regard to this matter.

Sincerely, I Original signed by:

Andrew J. Kugler, Project Manager, Section 1 Project Directorate 111 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-341

~ cc w/ encl: See next page DISTRIBUTION:

Docket File PUBLIC PD3-1 Reading A.D. Lee, EMCB OGC ACRS A. Vogel, Rlli '

')OCUMENT NAME: G:\PDill-1\ FERMI \LTRA1189.wpd

- lo vue. vive a copy of this docuenent, Indicate in the hos: =cae Copy without %.. _ .-- '7 "F's Copy with sitachmenuenclosure "N's No copy OFFICE PM:LPD3 lC 1%$.RD3 lC SC:LPD3 , lC NAME AKugler @ @Boie CCraig ('JUC DATE- 07/ 2. /99 " 07/ CU99 07/(9 /99 OFFICIAL RECORD COPY

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