ML20212H951

Discusses Closeout of GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, for Plant,Units 1,2 & 3.Closeout Ltr for Project Manager to Send to Licensee Encl

ML20212H951
Person / Time
Site:	Browns Ferry
Issue date:	06/20/1999
From:	Wichman K NRC (Affiliation Not Assigned)
To:	Peterson S NRC (Affiliation Not Assigned)
References
GL-92-01, GL-92-1, NUDOCS 9906280228
Download: ML20212H951 (4)

Text

i June 20, 1999 MEMORANDUM TO: Sheri R. Peterson, Chief Project Section 11-2 Division of Licensing Project Management

[ original signed by:]

FROM: Keith R. Wichman, Chief Component Integrity Sect!on l

Materials and Chemical Enginearing Branch i Division of Engineering j

SUBJECT:

CLOSEOUT OF GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY" FOR BROWNS FERRY UNITS 1,2, AND 3 On May 19,1995, the NRC issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity." In GL 92-01, Rev.1, Supp.1, the NRC requested that licensees perform a review of their reactor pressure vessel structural integrity

- assessments in order "to identify, collect, and report any new data pertinent to [the) analysis of

. [the) structural integrity of their reactor pressure vessels (RPVs) and to assess the impact of that data on their RPV integrity analyses relative to the requirements of Section 50.60 of )

Title 10 of the Code of Federal Regulations (10 CFR 50.60),10 CFR 50.61, Appendices G and (

H to 10 CFR Part 50 (which encompass pressurized the.~ mal shock (PTS) and upper shelf energy (USE) evaluations), and any potential impact on low temperature overpressure (LTOP) l limits or pressure-temperature (P-T) limits."

The attached is the closecut letter for the project manager (PM) to send to the licensee indicating that they have adequately responded to the GL. The EMCB staff notes that the tracking of the industry's RPV data and RPV !ntegrity assessments !s a continuing effort. The staff will review any new data or information as a plant specific action under a plant-specific TAC number, or as a topical report review depending on future submittats. The PM should close out the TAC numbers assigned to the GL for Browns Ferry Units 1,2, and 3 by forwarding the attached closecut letter. Please be sure that Andrea Lee of EMCB/DE is included on j distribution of the closeout letter sent to the licensea.

Attachment:

As stated CONTACT: Matthew A. Mitche!!, EMCB/DE ,

415-3303 kNI ,

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NUCLEAR REGULATORY COMMIS810N I WASHINGTON. D.C. 308e5 0001

% , June 20, 1999 MEMORANDUM TO: Sheri R. Peterson, Chief l Project Section ll 2 .

DMsion of Ucensing Project Management -

FROM: Keith R. W!chman, Chief A Component Integrity Section Materials and Chemical Engineering Branch

{

Division of Engineering

SUBJECT:

CLOSEOUT OF GENERIC LETTER 92-01, REVISION 1, SUPPLEiMNT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY" FOR BROWNS FERRY UNITS 1,2, AND 3 On May 19,1995, the NRC issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity." in GL 92-01, Rev.1. Supp.1, the NRC requested that licensees perform a review of their reactor pressure vessel structural integrity assessments in order "to identify, collect, and report any new data pertinent to [the] analysis of

[the) structural integrity of their reactor pressure vessels (RPVs) and to assess the impact of that data on their RPV integrity analyses relative to the requirements of Section 50.60 of Title 10 of the Code of FederalRegulations (1u CFR 50.60),10 CFR 50.61, Appendices G and H to 10 CFR Part 50 (which encompass pressurized thermal shock (PTS) and upper shelf energy (USE) evaluations), and any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits."

The attached is the closecut letter for the project manager (PM) to send to the licensee Indicating that they have adequately responded to the GL. The EMCB staff notes that the tracking of the industry's RPV data and RPV integrity assessments is a continuing effort. The staff will review any new data or information as a plant specific action under a plant specific TAC Number, or as a topical report review depending on future submittals. The PM should close out the TAC numbers assigned to the GL for Browns Ferry Units 1,2, and 3 by forwarding the attached closeout letter. Please be sure that Andrea Lee of EMCB/DE is included on distribution of the closeout letter sent to the licensee.

Attachment:

As stated CONTACT: Matthew A. Mitchell, EMCB/DE 415-3303

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1 l

I

l Mr. John Doe Vice President - Engineering XYZ Nuclear Electric Company 3

122345 Nuclear Radiation Avenue j Radioactive City, XX 12345

)

SUBJECT:

CLOSURE OF TAC NOS. MA1179, MA1180 AND MA1181 - RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER

. 92-01, REVISION 1, SUPPLEMENT 1 " REACTOR VESSEL STRUCTURAL INTEGRITY," FOR BROWNS FERRY NUCLEAR PLANT UNITS 1,2, AND 3 j

Dear Mr. Doei

- 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 (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 50.00 and 10 CFR 50.61), and io 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 17,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1, and provided the requested information relative to the structural integrity assessments for Browns Ferry Units 1,2, and 3. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on July 26,1996. 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 cubmitted in Topical Report BWRVIP-46. As a result of the efforts by CE, B&W, and the BWRVIP, the staff determined that additional information was necessary relative to the structural integrity assessments for your plants.

On June 10,1998, the staff issued a request for additional information (RAI) in regard to the alloying chemistries of beltline welds, your assessment of surveillance data for your facility, and the validity of your facility's pressure-temperature (P-T) limits. It was further indicated that your response should examine not only the aforementioned topical report, but also the information in

. the Framatome Technology analysis of electroslag welds which was referenced in a Dresden and Quad Cities P-T limits submittal dated September 20,1996.

ATTACHMENT x

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You provided your response to the staff's RAI for Browns Ferry Units 1,2, and 3 on September 8,1998. 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 RAl, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2. It should be noted that there are some variations in the data inputted by the staff, and the corresponding values reported by you in your response to the GL 92-01, Rev.1, Supp.1 RAl. The differences for Browns Ferry Units 1,2, and 3 are primarily with regard to the reported fluence values for the vessels, and the initial nil-ductility reference temperature and its associated uncertainty for the electroslag welds. These parameters were updated in the RVID based on information supplied in your December 15,1998, letter sent in response to the staff's RAI on your P-T limit submittal of March 3,1998. The deviations between the data are explained in the reference sections for  ;

each Unit, or the individual component screen notes (i.e., each forging, plate, and weld has a j specific area for notes which is a new feature of the database).

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 plant. No additional information is necessary with regard to the structural integrity assessments. Future submittals i on P-T limits or upper shelf energy (USE) should reference the most current information. I This closes the staff's efforts in regard to TAC numbers MA1179, MA1180, and MA1181. The ,

staff appreciates your efforts in regard to this matter. l l

Sincerely, XXXXXX, Project Manager Project Directorate X Division of Licensing Project Management Office of Nuclear Reactor Regulation 4

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