ML18096A734
| ML18096A734 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/21/1992 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NLR-N92049, NUDOCS 9205290012 | |
| Download: ML18096A734 (2) | |
Text
-*
Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1100 Vice President and Chief Nuclear Officer MAY 2 1 1992.
NLR-N92049 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
STATUS OF COMMITMENTS NUREG 0737 ITEM II.D.1 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The purpose of this letter is to provide the status of commitments made to the NRC by PSE&G in letters dated January 9, 1990 (NLR-N89223) and July 18, 1990 (NLR-N90140) pertaining to NUREG 0737, Item II.D.1.
PSE&G committed in January, 1990 to perform minor modifications to the Safety Relief Valve (SRV)/Power Operated Relief Valve (PORV) discharge piping during the 1992 refueling outage for Unit 1 and complete the Unit 2 thermal hydraulic analysis and any necessary modifications ~uring the Unit 2 Fall 1991 refueling outage (NLR-N89223).
These minor modifications were to result from the thermal hydraulic analytical criteria understood at that time.
Subsequently, the NRC issued the Safety Evaluation Report (SER) on NUREG 0737, Item II.D.1 for Salem Units 1 and 2 (May 10, 1990).
The NRC SER required the performance of additional thermal hydraulic analyses of the SRV/PORV discharge p.:j_ping for both Unit 1 and 2 utilizing more conservative assumptions. Preliminary analyses to support the additional NRC identified requirements have been completed.
Further analyses are currently ongoing to determine the impact on the SRV/PORV discharge piping.
Any modifications determined.to be necessary are currently planned to be completed during the respective-Unit refueling outages for 1993.
,,-~~~;-;;-;;:~--
~205290012 920521
\\,
pDR ADOCK 05000272 PDR
\\,.
Do*cument Control Desk NLR-N92049 2
MAY 2 1 1992 The NRC SER also identified three (3) additional open items that must be resolved to fully meet the requirements of TMI Item II.D.1.
These open items are related to PORV control circuitry qualification, block valve operator torque adjustment and development of procedures for inspection of piping following each PORV or SRV lift.
These open items have been completed.
Should you have any questions, please feel free to contact us.
Sincerely, 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 -
Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Chief NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625