ML18152B402
| ML18152B402 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/02/1999 |
| From: | Edison G NRC (Affiliation Not Assigned) |
| To: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| GL-92-01, TAC-MA0576, TAC-MA0577, NUDOCS 9908050153 | |
| Download: ML18152B402 (4) | |
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UNITED STATES NUCLEAR REGuLATOR)' COMMISSION WASHINGTON, D.C. 20555--0001 Mr. J. P. O'Hanlon Senior Vice President - Nuclear Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060 August 2, 1999
SUBJECT:
CLOSURE OF REVIEW OF RESPONSE TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, "REACTOR VESSEL STRUCTURAL INTEGRITY," FOR THE SURRY POWER STATION, UNITS 1 AND 2 (TAC NOS. MA0576 AND MA0577)
Dear Mr. O'Hanlon:
On May 19, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter 92-01, Revision 1, Suppiement 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 1 O of the Code of Federal Regulations (10 CFR 50.60 and 1 O CFR 50.61 ), and to the requirements of Appendices G and H to Part 50 of Title 1 O of the Code of Federal Regulations (Appendices G and H to 1 O CFR Part 50).
On August 10, 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 Surry, Units 1 and 2. Ttle staff evaluated your response to GL 92-01, Rev. 1, Supp. 1, and provided its conclusion relative to your response on May 22, 1997. 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&I) BWR data were submitted in Topical Report BWRVIP-46. As a result of the efforts by CE and B&W, the staff determined that arjditional information was necessary relative to the structural integrity assessments for your plant.
On April 20, 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, pressure-temperature (P-T) limits, and pressurized thermal shock (PTS) assessments for Surry, Units 1 and 2. In general, with respect to the contents of the RAI, the staff requested that you
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J. P. O'Hanlon '
reassess the alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries provided in Topical Report BAW-2325, "Reactor Vessel Working Group, Response to RAI Regarding Reactor Pressure Vessel Integrity," May 1998. The RAI also requested that you 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 1 O CFR 50.60, 1 O CFR 50.61, and Appendices G and H to 1 O CFR Part 50, as applicable to the licensing basis for your plants.
You provided your response to the staff's RAI for Surry, Units 1 and 2 on June 18, 1998. The response included a request for approval of a proposed reactor vessel fluence analysis methodology for Surry and North Anna. The staff found the proposed methodology to be acceptable for referencing in licensing actions. Details of the staff's analysis are included in a safety evaluation dated April 13, 1999. As a result of the staff's review of your responses to:
(a) GL 92-01, Revision 1, (b) GL 92-01, Rev. 1, Supp. 1, and (c) 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 which is linked to the NRG 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, or upper shelf energy (USE) should reference the most current information.
This closes the staff's efforts in regard to TAC numbers MA0576 AND MA0577. The staff appreciates your efforts in regard to this matter.
Docket Nos. 50-280 and 50-281 cc: See next page Sincerely, Gordon E. Edison, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Offi_ce of Nuclear Reactor Regulation
Mr. J. P. O'Hanlon Virginia* Electric and Power Company cc:
Mr. Donald P. Irwin. Esq.
Hunton and Williams Riverfront Plaza, East Tower 951 E. Byrd Street Richmond, Virginia 23219 Mr. E. S. Grecheck Site Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883 Senior Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road*
Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, Virginia 23209 Robert 8. Strobe, M.D., M.P.H.
State Health Commissioner Office of the Commissioner Virginia Department of Health P.O. Box 2448 Richmond, Virginia 23218 Surry Power Station Office of the Attorney General Commonwealth of Virgin;a 900 East Main Street Richmond, Virginia 23219 Mr. J. H. McCarthy, Manager Nuclear Licensing & Operations Support Innsbrook Technical Center Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. W. R. Matthews Site Vice President North Anna Power Station Virginia Electric and Power Company P. 0. Box 402 Mineral. Virginia 23117
e J. P. O'Hanlon August 2, 1999.
reassess the alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries provided in Topical Report BAW-2325, "Reactor Vessel Working Group, Response to RAI Regarding Reactor Pressure Vessel Integrity,"* May 1998. The RAI also requested that you 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 1 O CFR 50.60, 1 O CFR 50.61, and Appendices G and H to 1 O CFR Part 50, as applicable to the licensing basis for your plants.
You provided your response to the staff's RAI for Surry, Units 1.and 2 on June 18, 1998. The response included a request for approval of a proposed reactor vessel fluence analysis methodology for Surry and North Anna. The staff found the proposed methodology to be acceptable for referencing in licensing actions. Detail.s of the staff's analysis are included in a safety evaluation dated April 13, 1999. As a result of the staff's review of your responses to:
(a) GL 92-01, Revision 1, (b) GL 92-01, Rev. 1, Supp. 1, and (c) 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 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 su.bmittals 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 MA0576 AND MA0577. The staff appreciates your efforts in regard to this matter.
Docket Nos. 50-280 and 50-281 cc: See next page Distribution:
Sincerely, Original signed by:
Gordon E. Edison, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation COoGket-FileC::.'.':i EDunnington OGC PUBLIC GEdison ACRS PDll-1 Reading RScholl(SE)
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