ML20044G976
| ML20044G976 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/27/1993 |
| From: | Jabbour K Office of Nuclear Reactor Regulation |
| To: | Hairston W GEORGIA POWER CO. |
| References | |
| GL-88-11, GL-92-01, GL-92-1, TAC-M83469, TAC-M83470, NUDOCS 9306070120 | |
| Download: ML20044G976 (5) | |
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NUCLEAR REGULATORY COMMISSION l
f WASHINGTON. D.C. 20ElWOD1 May 27, 1993 l
i Docket Nos. 50-321 i
and 50-366 i
Mr.-W. G. Hairston, III l
Senior Vice President'-
Nuclear Operations l
. Georgia Power Company P. O. Box 1295 t
Birmingham, Alabama 35201 f
Dear Mr. Hairston:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING YOUR RESPONSES TO l
GENERIC LETTER 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL-INTEGRITY,"- EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M83469 AND M83470) l Generic Letter (GL) 92-01, Revision 1, was issued on March 6, 1992, to compile information necessary to confirm that licensees and permit holders satisfy the.
t requirements for ensuring reactor vessel integrity. ~ In the GL, the' staff requested responses to three questions. The purpose of the.three questions; i
~ 1) Appendix H to l
was to obtain information needed to assess compliance'with:
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10 CFR Part 50, (2) Appendix G to 10 CFR Part 50, and (3). commitments made in responses to GL 88-11.
By letter dated July 2, 1992, you responded to GL 92-01, Revision 1, by providing the information requested in the Required Information portion' of the GL.
The staff has completed its initial review of your response and has determined that additional information is needed.
Enclosed is a request for additional information (RAI). We request that the response to the RAI be provided within 60 days from receipt of this letter.
The information requested by this letter is within the scope of the overall burden estimated in Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity,10'CFR 50.54(f)." The estimated average number of burden hours is 200-person hours for each addressee's response. This estimate q
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Mr. W. G. Hairston, III May 27, 1993 pertains only to the identified response-related matters and does not include the time required to implement actions required by the regulations.
This action is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.
Sincerely,
/s/
Kahtan N. Jabbour, Project Manager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page DISTRIBUTION:
Docket File NRC & Local PDRs PDII-3 R/F SVarga Glainas DMatthews KJabbour LBerry OGC, 15B18 ACRS (10), P-315 EMerschoff, RII DMcDonald, 14B2 JStrosnder, 7D4 CFairbanks, 7D4 SSheng, 7D4 o
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KJABBOUR:cw DMCDONALD DMI/NkWS mE 5'/k'7/93 h f/1 #93 o9c3/93 I/d/93 DME 0FFICIAL RECORD COPY FILE NAME:G:\\ HATCH \\GL83469.RAI L
a Mr. W. G. Hairston, III May 27,1993 pertains only to the identified response-related matters and does not include the time required to implement actions required by the regulations. This action is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.
Sincerely, f48 bl.
Kahtan N. Jabbour, Project Fnnager Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page p
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Mr. W. G. Hairston, III Georgia Power Company Edwin I. Hatch Nuclear Plant cc:
Mr. Ernest L. Blake, Jr.
Mr. R. P. Mcdonald Shaw, Pittman, Potts and Trowbridge Executive Vice President -
2300 N Street, NW.
Nuclear Operations Washington, DC 20037 Georgia Power Company P. O. Box 1295 Mr. J. T. Beckham Birmingham, Alabama 35201 Vice President - Plant Hatch Georgia Power Company Mr. Alan R. Herdt, Chief P. O. Box 1295 Project Branch #3 Birmingham, Alabama 35201 U. S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Mr. S. J. Bethay Atlanta, Georgia 30323 Manager Licensing - Hatch Georgia Power Company Mr. Dan Smith P. O. Box 1295 Power Supply Operations Birmingham, Alabama 35201 Oglethorpe Power Corporation.
2100 East Exchange Place Mr. L. Sumner Tucker, Georgia 300B5-1349 General Manager, Nuclear Plant Georgia Power Company Charles A. Patrizia, Esquire Route 1, Box 439 Paul, Hastings Janofsky & Walker Baxley, Georgia 31513 12th Floor 1050 Connecticut Avenue, NW.
Resident Inspector Washington, DC 20036 U. S. Nuclear Regulatory Commission Route 1, Box 725 Baxley, Georgia 31513 Regional Administrator, Region II i
U. S. Nuclear Regulatory Commission
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101 Marietta Street, NW. Suite 2900 i
Atlanta, Georgia 30323 i
.l Mr. Charles H. Badger Office of Planning and Budget Room 610
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270 Washington Street, SW.
Atlanta, Georgia 30334 Harold Rehets, Director Department of Natural Resources 205 Butler Street, SE., Suite 1252 Atlanta, Georgia 30334 Chairman Appling County Commissioners County Courthouse i
Baxley, Georgia 31513
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ENCLOSURE' RE0 VEST FOR ADDITIONAL INFORMATION GENERIC LETTER 92-01. REVISION 1 EDWIN I, HATCH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-321 AND 50-366 HATCH UNIT 1 Ouestion 2a in GL 92-01 The response to GL 92-01 indicates that the limiting initial upper-shelf energy (USE) is 78 ft-lb for beltline plates and 95 ft-lb for beltline welds.
The plate USE is from the only plate data recorded in the FSAR for all beltline plates and the weld USE is from a generic derivation.
A topical report, NED0-32205, titled "BWR Owner's Group Topical Report on Upper Shelf Energy Equivalent Margin Analysis" regarding beltline materials with low USE, was submitted by General Electric Corporation on April 30, 1993. The licensee must either confirm that this topical report will be used as its licensing bases or provide its plant specific approach to demonstrate that all beltline materials that do not have measured USE will meet requirements of Appendix G, 10 CFR 50.
i HATCH UNITS 1 AND 2 Question 2b in GL 92-01 The response indicates that data from the drop weight test and Charpy test for beltline materials is either absent or incomplete for initial RT,3, determination.
An alternative method developed by General Electric (GE) was used in deriving initial RT for these materials.
wor In the GE method, the establishment of the slope for the transition zone of the Charpy curve is crucial in deriving the initial RT,33 from incomplete test data.
Provide all plate and weld Charpy test curves compiled by GE for establishing the 2*F per ft-lb slope for the transition zone of the Charpy curve. All test data must be from materials equivalent to (i.e., same vendor, fabrication time frame, fabrication process, material specification, etc.) beltline materials of these reactor vessels.
The resportse provides the copper value for the surveillance plate, G-4804-2, as 0.13 in Table 1 of Appendix A, and as 0.12 in Appendix C.
Address this discrepancy and describe the method used for determining the copper value.