ML17300B300

Informs That as Result of NRC Review of Util Responses to GL 92-01,Rev 1,Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2. Staff Efforts Closed for TACs MA0561,MA0562 & MA0563

ML17300B300
Person / Time
Site:	Palo Verde
Issue date:	07/12/1999
From:	Kalyanam N NRC (Affiliation Not Assigned)
To:	James M. Levine ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
References
GL-92-01, GL-92-1, TAC-MA0561, TAC-MA0562, TAC-MA0563, TAC-MA561, TAC-MA562, TAC-MA563, NUDOCS 9907150048
Download: ML17300B300 (10)

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Mr. James M. Levine Senior Vice President, Nuclear Arizona Public Service Company Post Office Box 53999 Phoenix, AZ 85072-3999 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTONs D C 2055&4001 Ouly 12,. 1999

SUBJECT:

COMPLETION OF GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, "REACTOR VESSEL STRUCTURAL INTEGRITY,"FOR THE FOR THE PALO VERDE NUCLEAR GENERATING STATION (TAC NOS. MA0561, MA0562 AND MA0563)

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) 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 ofFederal 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 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 the Palo Verde Nuclear Generating Station (Palo Verde), 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 September 11, 1996.

However, since the time of the staffs closure letter, the Combustion Engineering (CE) Owners Group and the Babcock and Wilcox (B8W) 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 B8W-fabricated RPV welds.

In addition, Chicago Bridge and Iron (CB8 I) boiling water reactor data were submitted in Topical Report BWRVIP-46. As a result of the efforts by CE and B8W, the staff determined that additional information was necessary relative to the structural integrity assessments for your plants.

On March 30, 1998, the staff issued a request for additional information (RAI) in regard to the alloying chemistries of beltline welds, your assessment of surveillance data, pressure-temperature (P-T) limits, and pressurized thermal shock (PTS) assessments (applicable only to pressurized water reactors (PWRs))-for the Palo Verde units.

In general, with respect to the contents of the RAI, the staff requested that you 99'07i 50048 9"707%2 PDR ADQCK 05000528 P

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3uly 12, 1999 J. M. Levine r I

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 facilityrelative 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 March 30,,1998 letter on June 24, 1998. As a result of the staff's review of your responses to GL 92-01, jRevision,1and GLl92-01, Rev. 1, Supp. 1, the staff has revised the inform'ation in;the Reactor'Vessel,Integrity Database (RVID) and is releasing it as RVID Version,'2.',

The new database diskettes. are postedjon 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 willassume 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.

n This closes the staff's efforts in regard to TAC,Nos. MA0561, MA0562 and MA0563. The staff appreciates your efforts in regard to this matter.'f you have any questions, please contact me at (301) 415-3062.

Docket Nos. STN 50-528, STN 50-529 and STN 50-530 cc: See next page DISTRIBUTION Sincerely, ORIG.

SIGHED BY Nageewaran Kalyanam, Project Manager, Section 2

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Project Directorate IV & Decommissioning Division of Licensing. Project Management Office of Nuclear Reactor Regulation Docket File PUBLIC PDIV-2 Reading SRichards(clo)

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duly 12,. 1999 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, facilityrelative 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 March 30, 1998 letter on June 24, 1998. As a result of the staff's review of your responses to GL 92-01, Revision,1 and GL 92-01, Rev. 1, Supp. 1, 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 willassume 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 Nos. MA0561, MA0562 and.MA0563. The staff appreciates your efforts in regard.to this matter.

Ifyou:have.any questions, please contact me at (301) 415-3062.

Docket Nos. STN 50-528, STN 50-529 and STN 50-530 cc: See next page DISTR IBUTION Sincerely, ORIG.

SIGNED BY Nageswaran Kalyanam, Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of-Nuclear Reactor Regulation Docket File PUBLIC PDIV-2 Reading S Richards(clo).

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J'. M. Levine 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 facilityrelative 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 March 30, 1998 letter on June 24, 1998. As a result of the staff's review of your responses to GL 92-01,.Revision 1and GL 92-01, Rev'; 1, Supp. 1, 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 Nos. MA0561, MA0562 and. MA0563. The staff appreciates your efforts in regard to this matter.

If you have any questions, please contact me at (301) 4.1 5-3062.

Sincerely, Docket Nos. STN 50-528, STN 50-529 and STN 50-530 cc: See next page Nageswaran alyanam, Project-Manager, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

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Palo Verde Generating Station, Units 1, 2,.and 3 CC:

Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street Phoenix, AZ 85007 Mr. David Summers Public Service Company of New Mexico 414 Silver SW, ¹1206 Albuquerque, NM 87102 Douglas Kent Porter Senior Counsel Southern California Edison Company Law Department, Generation-Resources P.O. 'Box 800

Rosemead, CA 91770 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 40 Buckeye, AZ 85326 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower 8 Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Chairman, Board of Supervisors ATIN: Chairman 301 W. Jefferson, 10th Floor Phoenix, AZ 85003 Mr. Jarlath Curran Southern, California Edison Company 5000 Pacific Coast Hwy Bldg DIN San Clemente, CA 92672 Mr. Robert Henry Salt River Project 6504 East Thomas Road Scottsdale, AZ 85251 Terry Bassham, Esq.

General Counsel El Paso Electric Company 123 W. Mills EI Paso, TX 79901 Mr. John Schumann Los Angeles Department of Water 8 Power Southern California Public Power Authority P;O. Box 51111, Room 1255-C Los Angeles, CA 90051 Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street Phoenix, AZ 85040 Ms. Angela K. Krainik, Manager Nuclear Licensing Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034 Mr. John C. Horne Vice President, Power Generation El Paso Electric Company 2702 N. Third Street, Suite 3040 Phoenix, AZ 85004 May 19,1999

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