ML18107A251

Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses

ML18107A251
Person / Time
Site:	Salem
Issue date:	04/27/1999
From:	Eric Simpson Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N990200, NUDOCS 9905040059
Download: ML18107A251 (3)

Text

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• Public Service Electric and Gas Company E. C. Simpson Public Service Electric: and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Senior Vice President - Nuclear Engineering APR27 1999.

LR-N990200 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

SALEM LOSS OF COOLANT ACCIDENT PEAK CLAD TEMPERATURE MARGIN TRACKING ~ 30-DAY NOTIFICATION SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 In accordance with the requirements of 10CFRS0.46, Public Service Electric and Gas (PSE&G) hereby submits the 30-day fuel clad temperature report. This report describes the changes to the calculated Peak Clad Temperature (PCT) for the Salem Generating Station (SGS) Large and Small Break Loss of Coolant Accident (LB LOCA and SB LOCA) An~lyses ..

• PSE&G's last report to the NRC (Ref: LR-N980286, Dated June 10, 1998) identified the Salem Units 1 and 2 Large Break. (LB) LOCA-PCT to be 2029°F and the Small Break Vi (SB) LOCA-PCT to be 1652°F. No new penalties have been assessed for the current (0 Salem Unit 1 Cycle 13 analysis. Thus the LOCA-PCT for Salem Unit 1 remains unchanged.

S1C13 Large Break LOCA-PCT =2029°F <tftDI S1C13 Small Break LOCA-PCT =1652°F However, the LB and SB LOCA-PC.T for Salem Unit 2 applicable to the upcoming Cycle 11 will change from the last report to the NRC. A penalty of 10°F will be assessed .for

• the Small Break LOCA due to the impact of fully enriched annular pellets used in the Robust Fuel Assembly (RFA) feed fuel.

For the Large Break LOCA assessment, the last "Analysis of Record" was re-evaluated through plant-specific analysis using the latest computer codes for the evaluation model incorporating the effects of the Intermediate Flow Mixers (IFMs), RFA Features, and updates to the evaluation model.

9905040059 990427 PDR ADOCK 05000272 P PDR 11:\ Printed on

':I Recycled Paper

APR 211999

- Document Control Desk ,.._,, LR..-N990200 The last analysis of record identifies a LB LOCA-PCT of 1978°F. Incorporating the effect of the IFMs, RFA, and updates to the evaluation model, the sum of the LiPCT's

(+75°F) for the LB LOCA-PCT exceeds the 50°F threshold established in 10CFR50.46.

Salem Unit 2 is currently in its tenth refueling outage. Therefore, providing the PCT report to the NRC by initial criticality of Salem 2 Cycle 11 (expected to occur by May 22, 1999) will meet the 30-Day 10CFR50.46 reporting requirement induced by the sum of the LiPCT's for the LB LOCA-PCT.

A LB LOCA re-analysis is not necessary to demonstrate compliance with 10 CFR 50.46 because the PCT assessments were made using plant-specific data and the latest computer codes for the evaluation model.

Thus, the new LOCA-PCT for Salem Unit 2 will be: .

S2C11 Large Break LOCA-PCT =2053°F S2C11 Small Break LOCA-PCT = 1662°F Should there be any questions regarding this submittal, please contact Mr. T. K. Ross of my Staff at (609) 339-1222.

• 95-4933

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APR 211999 Document Control Desk. ,c,,_ LR.. N990200 Attachments C Mr. Hubert J. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD '20852 Mr. S. Morris - Salem (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 95-4933