ML18100A861
| ML18100A861 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/31/1994 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLR-N94012, NUDOCS 9402150250 | |
| Download: ML18100A861 (2) | |
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Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations
'JANS 11994 NLR-N94012 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 Gentlemen:
SCHEDULE FOR ANALYSIS EFFECTING PEAK CLAD TEMPERATURE SALEM GENERATING STATION UNITS 1 & 2 DOCKET NOS. 50-272 AND 50-311 In accordance with the requirements of 10CFR50.46, Public Service Electric &. Gas (PSE&G) notified the NRC of changes to the calculated peak clad temperature (PCT) for Salem Units 1 & 2 via letter NLR-N93173 dated 10/29/93.
In that letter it was stated that PSE&G and Westinghouse were reviewing the need for further analyses or computer code changes to refine the PCT penalty associated with Safety Injection (SI) flow into the Reactor Coolant System broken loop.
It was anticipated that by 1/31/94 a schedule for completion of this issue would be provided.
On January 12, 1994, Westinghouse presented to the NRC the results of the investigations performed for safety injection in the broken loop and also discussed the test data and resulting correlation.
From discussions with Westinghouse following this meeting, PSE&G has been informed that Westinghouse agreed to provide to the NRC an addendum to WCAP-10054-P-A describing the SI model.used in NOTRUMP including SI to the broken loop.
This addendum will reference the improved condensation model (COS!)
described in WCAP-11767 and provide justification for application of this model to small break LOCA calculations.
The NRC will be requested to formally review the addendum to WCAP-10054.
Since the NRC review may affect the changes to the NOTRUMP evaluation model, PSE&G proposes not to reanalyze for the purpose of addressing the SI in the broken loop issue prior to completion of the NRC' s review..
In the interim,.PSE&G will track the PCT change reported in letter NLR-N93173, (+150°F/-150°F), as a permanent change to Salem's calculated PCT.
Once the NRC has completed review of the NOTRUMP addendum on SI in the broken loop, and, if resolution of this issue results in a change to the NOTRUMP coding, PSE&G would propose to capture the new model at the next licensing action requiring reanalysis of the small break LOCA and for which
~- Document Control Desk NLR-N94012 2 -
NOTRUMP would be used as the Evaluation Model.
'JANs 11994 If the NOTRUMP evaluation model coding is not changed as a result of resolution of this issue, then PSE&G proposes not to reanalyze, but to report the net effect on PCT identified in the NRC's SER as a permanent change at the next required 10CFR50.46 report.
Should you have any questions concerning this transmittal, please contact us.
c Mr. T. T. Martin, Administrator -
Region I
- u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. J. c. Stone, Licensing Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. s. Marschall (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625