ML20044G312
| ML20044G312 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/21/1993 |
| From: | Dromerick A Office of Nuclear Reactor Regulation |
| To: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| References | |
| GL-88-11, GL-92-01, GL-92-1, TAC-M83490, NUDOCS 9306020314 | |
| Download: ML20044G312 (4) | |
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WASHINGTON, O C. 20555-0001 May 21, 1993 Docket No. 50-219 Mr. John J. Barton Vice President and Director i
GPU Nuclear Corporation l
Oyster Creek Nuclear Generating Station Post Office Box 388
-l Forked River, New Jersey 08731
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Dear Mr. Barton:
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SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - OYSTER CREEK NUCLEAR GENERATING l
STATION - GPU NUCLEAR CORPORATION RESPONSES TO GENERIC LETTER 92-01, l
REVISION 1 (TAC NO. M83490) i By letter dated June 30, 1992, GPU Nuclear Corporation (GPUN) submitted your i
response to Generic Letter (GL) 92-01. The purpose of GL 92-01 is to-obtain information needed to assess compliance with requirements set forth in Appendices G and H to 10 CFR Part 50 and commitments made in response to GL 88-11 regarding reactor vessel structural integrity. Other regulations-requiring compliance are 10 CFR 50.60 and 10 CFR 50.61.
The staff has completed the preliminary review regarding this matter and has determined that additional information is required. Specifically the staff requires the following information related to Questions 2a and 2b in GL 92-01.
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Ouestion 2a in GL 92-01 The response to GL 92-01 cites two references regarding the USE of beltline welds. These sources indicate that the initial USE values for all beltline welds, except for the surveillance weld, are not known. A plant specific fracture mechanics analysis submitted on September 22, 1992, covers all plates l
with low USE values, but not welds.
In light of current information, previous
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staff approval of initial USE for welds is no longer applicable since the surveillance weld was made from wires of different heat and-flux, and cannot be considered representative of the beltline welds. A topical report, NED0-32205, titled "BWR Owners' Group Topical Report on Upper Shelf Energy Equivalent Margin Analysis" regarding beltline materials with low USE, was i
' submitted by General Electric Company 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 welds j
that do not have measured USE will meet requirements of Appendix G, i
)!i Ouestion 2b in GL 92-01
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GPUN's response indicates that data from the drop weight test and Charpy test for beltline materials is either absent or incomplete for initial RT[dE) was determination. An alternative method developed by General Electric i
used in derivina tha initial RT, from incomplete test data.
Provide all l
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f Mr. John J. Barton.
t 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, l
fabrication process, material specification, etc.) the beltline materials of l
this reactor vessel.
j The staff requests that GPUN provide its response to car request for additional information within 60 days from receipt of this letter.
The information requested by this letter is within the scope of thi verall burden estimated in Generic Letter 92-01, Revision 1, " Reactor Ve Structural Integrity,10 CFR 50.54(f)." The estimated average n1
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burden hours is 200 person hours for each addressee's response. This estimate 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.
l Sincerely, l
Original signed by 1
Alexander W. Dromerick, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation j
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Mr. John J. Barton 1 plate and weld Charpy test curves compilad 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.) the beltline materials of this reactor vessel.
i The staff requests that GPUN provide its response to our request for additional information 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 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, i
6 Alexan er W. Dromerick, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page r
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e t 9,. John J. Barton Oyster Creek Nuclear GPU Nuclear Corporation Generating Station CC:
Ernest L. Blake, Jr., Esquire Resident Inspector Shaw, Pittman, Potts & Trowbridge c/o U.S. Nuclear Regulatory Commission 2300 N Street, NW.
Post Office Box 445 Washington, DC 20037 Forked River, New Jersey 08731 Regional Administrator, Region I Kent Tosch, Chief U.S. Nuclear Regulatory Commission New Jersey Department of 475 Allendale Road Environmental Protection King of Prussia, Pennsylvania 19406 Bureau of Nuclear Engineering CN 415 BWR Licensing Manager Trenton, New Jersey 08625 GPU Nuclear Corporation 1 Upper Pond Road ParsipprJ.y, New Jersey 07054 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.
Post Office Box 388 Forked River, New Jersey 08731 I
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