ML20209D805

Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, Issue on 950519 to Plant. NRC Revised Info in Reactor Vessel Integrity Database & Is Releasing It as Rvid Version 2

ML20209D805
Person / Time
Site:	San Onofre
Issue date:	07/12/1999
From:	Raghavan L NRC (Affiliation Not Assigned)
To:	Ray H SOUTHERN CALIFORNIA EDISON CO.
References
GL-92-01, GL-92-1, TAC-MA0569, TAC-MA0570, TAC-MA569, TAC-MA570, NUDOCS 9907140041
Download: ML20209D805 (4)

Text

Ja p 4 UNITED STATES

5 -

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4 001

%***** July 12, 1999 Mr. Harold B. Ray  !

Executive Vice President l Southern Califomia Edison Company San Onofre Nuclear Generating Station P. O. Box 128 San Clemente, CA 92674-0128

SUBJECT:

SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 -

RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY"(TAC NOS. MA0569 AND MA0570)

Dear Mr. Ray:

On May 19,1995, the U.S. Nuclear Reguiatory 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) 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 Federa/ Regulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of 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 the San Onofre Nuclear Generating Station (SONGS) 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 August 5,1996. However, since the time of the staff's closure lettar, 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, Chicagc Bridge and Iron  !

(CB&l) boiling-water reactor data were submitted in Topical Report BWRVlP-46. As a result of the efforts by CE and B&W, the staff determined that additionalinformation was necessary relative to the structuralintegrity assessments for your plants. On April 8,1998, the staff issued a request for additionalinformation (RAl) in regard to the alloying chemistries of beltline welds, your assessment of surveillance data for your facility, pressure-temperature (P-T) limits, and pressurized thermal . shock (PTS) assessments (applicable only to pressurized-water reactors (PWRs)) for SONGS. In general, with respect to the contents of the RAI, the staff requested that l you reassess the alloying chemistries for the beltline welds and RPV surveillance welds relative 9907140041 990712 PDR ADOCK 05000361 P PDR

e July 12,1999 H. Ray I to the chemistries provided in the applica'ble topical report, and provide the impact of any changes te 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 SONGS on July.13,1998. 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 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,

. PTS (applicable only to PWRs), or upper-shelf energy should reference the most current information.

This closes the staff's efforts in regard to TAC No(s). MA0569 and MA0570. The staff appreciates your efforts in regard to this matter. If you have any questions conceming the reorganization, please write or call me at (301) 415-1471.

Sincerely, ORIG. SIGNED BY L. Raghavan, Senior Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362

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cc: See next page O DISTRIBUTION Docket File ADLee O)[

PUBLIC LSmith, RGN-IV PDIV-2 Reading OGC ACRS i o receive a copy of Inis cocument, inoicate v in tne oox OFFICE PDIV-2/PM C PDIV-D/LA C PDIV-2/SC 6 NAME LRaghavark CJamersonh SDembekh [

DATE l / 8 /99- 7 / 7 /99 / '7 / 9 /99 DOCUMENT NAME: G:\PDIV-2\ SONGS \ltr0569.wpd l OFFICIAL RECORD COPY 140005

H. Ray 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 SONGS on July 13,1998. 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 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 structuralintegrity assessments. Future submittals on P-T limits, PTS (applicable only to PWRs), or upper-shelf energy should reference the most current information.

l l

This closes the staffs efforts in regard to TAC No(s). MA0569 and MA0570. The staff appreciates your efforts in regard to this matter. If you have any questions concerning the reorganization, please write or call me at (301) 415-1471.

Sincerely, 7

L. Raghavan, Senior Project Manager, Section 2 Project Directorate IV & Decommissioning l Division of Licensing Project Management l Office of Nuclear Reactor Regulation Docket Nos. 50-361 and 50-362 j i

cc: See next page l

F l l

.. .. 1 I

San Onofre Nuclear Generating Station, Units 2 and 3 i cc:

h Mr. R. W. Krieger, Vice President Mayor Southem California Edison Company City of San Clemente i San Onofre Nuclear Generating Station 100 Avenida Presidio l P. O. Box 128 San Clemente, CA 92672 ,

San Clemente, CA 92674-0128 l Mr. Dwight E. Nunn, Vice President Chairman, Board of Supervisors Southern California Edison Company l County of San Diego San Onofre Nuclear Generating Station l 1600 Pacific Highway, Room 335 P.O. Box 128 l l' San Diego, CA 92101 San Clemente, CA 92674-0128 Alan R. Watts, Esq.

Woodruff, Spradlin & Sm' art I

, 701 S. Parker St. No. 7000 l l Orange, CA 92668-4720 '

1 Mr. Sherwin Harris Resource Project Manager Public Utilities Department  ;

l City of Riverside 3900 Main Street j

. Riverside, CA 92522 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower & Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Mr. Michael Olson San Onofre Liaison San Diego Gas & Electric Company P.O. Box 1831 San Diego, CA 92112-4150 Mr. Steve Hsu Radiologic Health Branch State Department of Health Services Post Office Box 942732 Sacramento, CA 94234 Resident inspector / San Onofre NPS

, c/o U.S. Nuclear Regulatory Commission Post Office Box 4329 San Clemente, CA 92674 June 1999 L