ML20210T642
| ML20210T642 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/17/1999 |
| From: | Olshan L NRC (Affiliation Not Assigned) |
| To: | Sumner H SOUTHERN NUCLEAR OPERATING CO. |
| References | |
| GL-92-01, TAC-MA1192, TAC-MA1193, NUDOCS 9908190128 | |
| Download: ML20210T642 (4) | |
Text
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jeg It UNITED STATES ee
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NUCLEAR REGULATORY COMMISSION [/A.JS( OMN
't WASHINGTON, D.C. 20555-0001
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August 17, 1999
~ Mr. H. L. Sumner, Jr.
Vice President - Nuclear Hatch Project Southern Nuclear Operating Company, Inc.
Post Office Box 1295 Birmingham, Alabama 35201-1295
SUBJECT:
HATCH NUCLEAR POWER STATION, UNITS 1 AND 2 RE: RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY"(TAC NOS. MA1192 AND MA1193)
Dear Mr. Sumner:
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:
(1) to 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 I
Reaulations (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 Reaulations (Appendices G and H to 10 CFR Part 50).
On August 14,1995, 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 Edwin I. Hatch 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 6,1996.
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 j
regarding the alloying chemistries of beltline welds in CE and B&W fabricated vessels. The additional alloying data were submided 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 i
in Topical Report BWRVIP-46. 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 I
your plants. On April 24,1998, 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 pressure-temperature (P-T) limits for Hatch in general, with respect to the contents of the RAI, the staff requested that you reassess the alloying chemistries for the I
beltline welds and RPV surveillance welds relative to the chemistries provided in the applicable g
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PDR ADOCK 05000321 p
PDR SC Filf CENTER CDPi
7, H. L. Sumner, Jr. August 17, 1999
. 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 Pait 50, as applicable to the licensing basis for your plant.
You provided your response to the staff's RAI for Hatch on July 28,1998. As a result of the staff's review of your responses to (1) GL 92-01, Revision 1, (2) GL 92-01, Rev.1, Supp.1, and (3) 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 (http1/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 integnity assessments. Future submittals on P-T limits or upper shelf energy (USE) should reference the most current information.
This closes the staff's efforts in regard to TAC Nos. MA1192 and MA1193. The staff appreciates your efforts in regard to this matter.
Sincerely, ORIGINAL SIGNED BY:
Leonard N. Olshan, Project Manager, Section 1 Project Directorate il Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366 cc: See next page Distribution:
- Docket File ~
OGC PUBLIC ACRS PD ll-1 R/F PSkinner, Ril CHawes LOlshan REmch DOCUMENT NAME: G:\\PDil-1\\ HATCH \\9201cise.wpd To receive a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No CoDY '
OFFICEC1PDil-1/PM PDil-1/LA h PDll/SC NAME LOlshan:cn CHawesC/D REmch DATE 6 flh /99 h/h/99 h/'h99
/
OFFICIAL RECORD COPY L
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H. L. Sumner, Jr.,
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 l
applicable to the licensing basis for your plant.
You provided your response to the staff's RAI for Hatch on July 28,1998. As a result of the staff's review of your responses to (1) GL 92-01, Revision 1, (2) GL 92-01, Rev.1, Supp.1, and (3) 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.
The new database diskettes are posted on the world-wide web at a location which is linked to l
the NRC home page (http /www.nrc. gov /NRR/RVID/index.html). We recommend that you 1
review this information. If the staff does not receive comments by September 1,1999, we will l
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 or upper shelf energy (USE) should reference the most current information.
This closes the staff's efforts in regard to TAC Nos. MA1192 and MA1193. The staff appreciates your efforts in regard to this matter.
l Sincerel t
Leonard N. Olshan, Project Manager, Section 1 l
Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366 cc: See next page t
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Edwin 1. Hatch Nuclear Plant cc:
Mr.' Ernest L. Bhke, Jr.
Charles A. Patrizia, Esquire Shaw, Pittman, Potts Paul, Hastings, Janofsky & Walker
. and Trowbridge _
loth Floor 2300 N Street, NW.
1299 Pennsylvania Avenue Washington, DC' 20037 Washington, DC 20004-9500 Mr. D. M. Crowe Chairman Manager, Licensing Appling County Commissioner.s Southern Nuclear Operating County Courthouse Company, Inc.
Baxley, Georgia 31513 P. O. Box 1295 Birmingham, Alabama 35201-1295 Mr. J. D. Woodard Executive Vice President Resident inspector Southern Nuclear Operating Plant Hatch Company, Inc.
11030 Hatch Parkway N.
P. O. Box 1295 Baxley, Georgia 31531 Birmingham, Alabama 35201-1295 Mr. Charles H. Badger Mr. P. W. Wells Office of Planning and Budget General Manager, Edwin I. Hatch Room 610 Nuclear Plant 270 Washington Street, SW.
Southern Nuclear Operating Atlanta, Georgia 30334 Company, Inc.
U.S. Highway 1 North Harold Reheis, Director P. O. Box 2010 Department of Natural Resources Baxley, Georgia 31515 205 Butler Street, SE., Suite 1252 Atlanta, Georgia 30334 Mr. R. D. Barker Program Manager Steven M. Jackson Fossil & Nuclear Operations Senior Engineer - Power Supply Oglethorpe Power Corporation Municipal Electric Authority 2100 East Exchange Place of Georgia P. O. Box 1349 1470 Riveredge Parkway, NW Tucker, Georgia 30085-1349 Atlanta, Georgia 30328-4684