ML20135C811
| ML20135C811 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/27/1996 |
| From: | Eaton R NRC (Affiliation Not Assigned) |
| To: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| References | |
| TAC-M96405, NUDOCS 9612090102 | |
| Download: ML20135C811 (4) | |
Text
Mr. Michael B. Roche November 27, 1996 l
Vice Presid:nt and Director GPU Nuclear Corporation l,
Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING THE PRESSURE-TEMPERATURE (P-T) LIMITS CURVES FOR OYSTER CREEK NUCLEAR GENERATING STATION (TAC NO. M96405)
Dear Mr. Roche:
By~ letter dated August 23, 1996, GPU Nuclear submitted a request to amend the l
technical specifications by incorporation of updated P-T limits curves for 22, l
I 27, and 32 effective full power years. The enclosed RAI was prepared to i
clarify issues raised by the staff based upon the review on your submittal.
In order to complete our review, we request your response to this RAI within 30 days of receipt. Any questions regarding this request should be made to Ronald B. Eaton on (301) 415-3041.
Sincerely, l
Original signed by:
Ronald B. Eaton, Senior Project Manager Project Directorate I-2 i
l Division of Reactor Projects - I/II l
Office of Nuclear Reactor Regulation l
Docket No. 50-219 l
Enclosure:
As stated l
cc w/ encl:
See next page l
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November 27, 1996 Mr. Michael B. Roche Vice President and Director GPU Nuclear Corporation i
Oyster Creek Nuclear Generating Station Post Office Box 388 l
Forked River, New Jersey 08731
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING THE PRESSURE-TEMPERATURE (P-T) LIMITS CURVES FOR OYSTER CREEK NUCLEAR GENERATING STATION (TAC NO. M96405)
Dear Mr. Roche:
By letter dated August 23, 1996, GPU Nuclear submitted a request to amend the technical specifications by incorporation of updated P-T limits curves for 22, 27, and 32 effective full power years.
The enclosed RAI was prepared to clarify issues raised by the staff based upon the review on your submittal.
In order to complete our review, we request your response to this RAI within 30 days of receipt.
Any questions regarding this request should be made to Ronald B. Eaton on (301) 415-3041.
l Sincerely, ft x
B. Eaton, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-219
Enclosure:
As stated cc w/ encl:
See next page l
l i
REQUEST FOR ADDITIONAL INFORMATION Oyster Creek Nuclear Generatine Station License Amendment Reauest to Update Reactor Vessel Pressure-Temnerature Limits for
- 22. 27. and 32 Effective Full Power Years (EFPY)
(1). Section 4.2 of attachment GENE-B13-01769 to your August 23, 1996 submittal provides a very general discussion of the methodology used to -
assess non-beltline vessel components.
It is stated that this methodology is based upon detailed stress analyses of a BWR/6 design.
It is stated on page 4-2:
" Detailed stress analyses, specifically for the purpose of fracture toughness analysis, of non-beltline components were performed for the BWR/6.... stresses due to the most severe of these transients were used according to [7] to develop plots for allowable pressure (P) versus temperatura relative to the reference temperature (T - RT,) enc 1. "
og The BWR/6 con-beltline region results were applied to Oyster Creek by adding the highest Oyster Creer RT values discontinuities to the appropriatei versus (for the non-beltline 4
T-RT,,) curves for the n
BWR/6 CRD penetration or feedwater nozzle."
Provide the results of the stress analysi.e for the feedwater nozzle region of the BWR/6 model.
Provide in tabular form the generic pressure versus (T-RT relationship developed for the BWR/6 feedwater nozzle regYon) and explain 1
how this curve was developed.
(2)
Identify the location and instruments used for pressure and temperature measurements during vessel hydrostatic and leak rate testing.
Identify instrument error and explain how instrument uncertainties are accounted for in verifying compliance with the proposed leak rate testing pressure-temperature limit curve (Curve A).
I Enclosure
N. Roche Oyster Creek Nuclear GPU Nuclear Corporation Generating Station CC*
Ernest L.-Blake, Jr., Esquire
'Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW.
Washington, DC 20037.
Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 BWR Licensing Manager GPU Nuclear Corporation 1 Upper Pond Road Parsippany, NJ 07054 Mayor Lacey Township 818 West Lacey Road Forked River, NJ 08731 Licensing Manager Oyster Creek Nuclear Generating Station Nail Stop:
Site Emergency Bldg.
P.O. Box 388 Forked River, NJ 08731 Resident Inspector i
c/o U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731 Kent Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 l
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