ML20154A918
| ML20154A918 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/25/1998 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1940-98-20537, NUDOCS 9810050042 | |
| Download: ML20154A918 (2) | |
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l GPU Nuclear. Inc.
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U.S. Route #1 South NUCLEAR h*,'l,*lk*R,],* mas Tel609-9H 4000 1940-98-20537 September 25,1998 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555
Subject:
Oyster Creek Nuclear Generating Station Facility License No. DPR-16 Docket No. 50-219 Technical Specification Change Request No. 260 AdditionalInformation
References:
- 1) GPU Nuclear letter No. 1940-98-20391 dated July 23,1998, Technical Specification Change Request No. 260
- 2) Reda, R.J. (GE) letter to NRC Document Control Desk with attention to T.E. Collins, Acting Branch Chief of Reactor Systems Branch; Proposed Amendment 25 to GE Licensing Topical Report NEDE-24011-P-A (GESTAR II) on Cycle-Specific Safety Limit MCPR; December 13,1996.
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- 3) Reda, R.F. (GE) letter to NRC Document Control Desk with attention of T.E. Collins, Acting Branch Chief of Reactor Systems Branch; GESTAR Amendment 25 Supporting Information; December 13, Q dg 1996.
In Reference 1, GPU Nuclear requested the existing Safety Limit Minimum Critical Power Ratio (SLMCPR) contained in Technical Specification 2.1. A be kept applicable for the next operating cycle (Cycle 17). This letter contains information GPU Nuclear agreed to submit during a telephone conference with the NRC staff on September 17,1998.
The MCPR importance parameter (MIP) was discussed in Attachments 1 and 3 of Reference 1.
A value of 2.59 was indicated for end-of-cycle 17. Another parameter affecting the calculated SLMCPR is the flatness of the bundle pin-by-pin power /R-factor distributions. The flatness of the pin R-factor distribution within a particular bundle is characterized by the R-factor importance parameter (RIP). The RIP value for Oyster Creek Cycle 17 is 14.1. These 9810050042 900925 PDR ADOCK 05000219 P
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S 1940-98-20537 Page 2 of 2 parameters are proposed for generic use in References 2 and 3. These references are an addition to the references contained in Attachments 1 and 3 of Reference 1.
Should further information be required, please contact Mr. Paul F. Czaya of our Nuclear Safety and Licensing Department at 609-971-4139.
Very truly yours,
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Michael B. Roche b-Vice President and Director
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Oyster Creek PFC I
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Administrator, U.S. NRC Region I U.S. NRC Resident Inspector Oyster Creek U.S. NRC Project Manager 1
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