ML20212J121

Discusses Closeout of GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2

ML20212J121
Person / Time
Site:	Point Beach
Issue date:	06/20/1999
From:	Wichman K NRC (Affiliation Not Assigned)
To:	Craig C NRC (Affiliation Not Assigned)
References
GL-92-01, GL-92-1, NUDOCS 9906280371
Download: ML20212J121 (4)

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! June 20, 1999 L MEMORANDUM TO: Claudia Craig, Chief Project Section ill-1 Division of Licensing Project Management l

d FROM: Keith R. NOM, Cgged by:]

Component Integrity Section Materials and Chemical Engineering Branch Division of Engineering

SUBJECT:

CLOSEOUT OF GENERIC LETTER 92-01, REVISION 1,

SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY" FOR POINT BEACH UNITS 1 AND 2.

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 (10 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 closeout letter for the project manager (PM) to send to the licensee l

. indicating that they have adequately responded to the GL. The EMCB staff notes that the j tracking of the industry's RPV data and RPV integrity assessments is a continuing effort. The i 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 Point Beach Units 1 and 2 by forwarding the j attached closeout letter. Please be sure that Andrea Lee of EMCB/DE is included on distribution of the closeout letter sent to the licensee.

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%g . June 20, 1999 MEMORANDUM TO: Claudia Craig, Chief I Project Section lll-1 Division of Licensing Project Management FROM: . Keith R. Wichman, Chief Component integrity Section J Materials and Chemical Engineering Branch Division of Engineering

SUBJECT:

CLOSEOUT OF GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY" FOR POINT BEACH UNITS 1 AND 2 l

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, Si pp.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 l

[the) structural integrity of their reactor pressure vessels (RPVs) and to assess the impact of i

' that data on their RPV integrity analyses relative to the requirements of Section 50.60 of Title 10 of the Code of Federa/ Regulations (10 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 closeout 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 l 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 Point Beach Units 1 and 2 by fonvarding the attached closeout letter. Please be sure that Andrea Lee of EMCB/DE is included on distribution of the closecut letter sent to the licensee.

Attachment:

As stated CONTACT: Matthew A. Mitchell, EMCB/DE 415 3303 4

i t

U l Mr. John Doe l Vice President ' Engineering

!; XYZ Nuclear Electric Company 122345 Nuclear Radiation Avenue 1 Radioactive City, XX _12345

SUBJECT:

CLOSURE OF TAC NOS. MA0564 AND MA0565 - RESPONSE TO THE a REQUESTS FOR INFORMATION IN GENERIC LETTER 92-01, REVISION 1, {

SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," FOR i POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 I l

Deaf Mr. Doei

. On May 19,1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter 92- i 01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity," l

- 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 Federal Regulations (Appendices G and H to 10 CFR Part 50).

On August 16,1995, 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 Point Beach Nuclear Plant 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 August 19,1996. 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. 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 September 28,1998, you provided your final response to the staff regarding your assessment of the information in the topical reports noted above. 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 additional information in your September 28,1998 letter, the staff has revised the information in

' the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2. However, potential discrepancies related to the fluences assigned for the R. E. Ginna surveillance ATTACHMENT L i

capsule data (weld wire heat 61782) in the BAW-2325, Revision 1 report were discovered in the l

staff's review of R. E. Ginna. The fluence values recorded for this data and the assessment of the Point Beach Unit 1 weld using this information reflect what the staff believes to be the most accurate and up-to-date information submitted by R. E. Ginna. While this updated information i resulted in a net increase in the RTers value for the Point Beach Unit 1 weld manufactured from weld wire heat 61782, it remains a non limiting material.

l The new RVID 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 tne RVID are acceptable for your plant. No additional information is necessary with regard to the structuralintegrity assessments. Future submittals on P-T limits, PTS, or upper shelf energy (USE) should reference the most current information.

This closes the staff's efforts in regard to TAC numbers MA0564 and MA0565. The staff appreciates your efforts in regard to this matter.

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

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