ML20151F828
| ML20151F828 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/12/1988 |
| From: | Wilson R GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 5000-88-1542, NUDOCS 8804190015 | |
| Download: ML20151F828 (4) | |
Text
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GPU Nuclear Corporation
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c Pars ppany, New Jersey 07054 201-316 7000 TELEX 136 482 Wr;ter's Direct Oial Number:
April 12. 1988 5000-88-1542 U.S. Nuclear Regulatory Comission Document Control Desk Washington, D.C.
20555
Dear Sir:
Subject : Oyster Creek Nuclear Generating Station Docket No. 50-219 Technical Specification Change Request (TSCR) No.166 Supplemental Infonnation In response to a telephone request (4/4/88) from Mr. Dromerick of NRR, GPUN is submitting this supplement to our analysis concerning no significant hazards.
The proposed TSCR No.166 is a core reload and is similar to Example (iii) of the "Amendments not likely to Involve Significant Hazards Consideration" (48FR14870, April 6,1983).
As such, TSCR No.166 does not involve a significant hazards consideration as concluded in the attachment, Significant Hazards Determination.
If you have any further questions regarding this matter, please contact Mr.
Michael Laggart at (201)316-7%8.
Ve t ' ly yours, TN W
, F. Wi son Vice President Technical Functions RFW/JDL/pa(6654f) cc's on next page 0
8804190015 880412 PDR ADOCK 05000219
' 'y P
DCD GPU Nuclear Corporat1on is a subsd ary d Genera! PutOc Ut Lt es Corporat.oq
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1 cc: Mr. William T. Russell, A&ninistrator i
Region I U.S. Nuclear Regulatory Connission 475 Allendale Road i
King of Prussia, PA.
19406 NRC Resident Inspector l
Oyster Creek Nuclear Generating Station Forked River, N.J.
08731 r
I Mr. Alex Dromerick, Jr.
l U.S. Nuclear Regulatory Commission j
Washington, D.C.
20555 i
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"SIGNIFICANT HAZARDS DETERMINATION" GPU Nuclear has detemined that operation of the Oyster Creek Nuclear Generating Station in accordance with the proposed technical specifications does not involve a significant hazard.
The changes do not:
1.
Involve a significant increase in the probability or the consequence of an accident previously evaluated.
The probability of an accident is not dependent upon the core loading and there are no other changes to the plant configuration, availability of safety systems, the manner in which the safety systems are initiated or the way the plant is operated that will increase the probability of an accident. Cycle 12 introduces a new fuel design, GE8X8EB, which has been reviewed and approved by the NRC; letter from H. Berkow (NRC) to J. S. Charnley (GE) dated December 3,1985, "Acceptance for Approval of Fuel Designs Described in Licensing Topical Report NEDE-240ll-P-A-6, Amendment 10 for Extended Burnup Operation." The fuel design has been incorporated into the reload applications of other BWR plants.
The neutronic and mechanical design is not significantly different from designs currently in use at Oyster Creek and the fuel will not be operated in a manner that would cause the consequences of an accident to be increased.
2.
Create the possibility of a new or different kind of accident from any previously evaluated.
The Cycle 12 core loading does not involve any other change to the plant configuration, nor does it change the availability of safety systems or the manner in which they respond to initiating events.
Also, the design does not change the manner in which the core will be operated from previous cycles.
As such, the possibility of a new or different kind of accident from any previously evaluated is not created.
3.
Involve a significant reduction in a margin of safety.
The proposed Technical Specifications are based on analysis results which were perfomed in accordance with methods and procedures developed by GPUN and GE. The GPUN methods have been submitted to the NRC for their review and approval.
NRC approval requires GPUN to demonstrate the adequacy of the methods for the analyses to be perfomed, that the methods account for the uncertainties in the analyses, and that GPUN 1
can adequately employ the methods for their application.
All of the methods used by GPUN have been submitted to the NRC and have been l
approved except for TR-045 which is under review and addresses system transients using the RETRAN-02 computer code.
NRC approval of TR-045 is expected since the methods employed have been used by other utilities in similar applications, the methods acount for uncertainties and the methods provide results which are consistent with previous reload analyses.
Currently, the RETRAN-02 code itself is being reviewed by the NRC for use in reload analyses.
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I The GE LOCA analyses, NEDE-31462P, "0yster Creek Nuclear Generating Station SAFER /COREC00L/GESTR-LOCA LOSS-0F-COOLANT ACCIDENT ANALYSIS "
submitted with this reload application is based on a methodology previously approved by the NRC via a May 11, 1987 safety evaluation addressing NEDE-30996-P, Volume II.
This methodology has been used by other utilities in reload applications, and, ':n in the case of TR-045, t
NRC approval of the Oyster Creek application is expected.
j Therefore, the results of the analyses presented in TR-049 and NEDE-31462P and the technical specification changes based on these results will ensure that there is no significant reduction in the margin of safety.
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