ML18087A842
| ML18087A842 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 04/15/1983 |
| From: | LIDEN E A Public Service Enterprise Group |
| To: | VARGA S A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, NUDOCS 8304190236 | |
| Download: ML18087A842 (3) | |
Text
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- ublic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department April 15, 1983 Director of Nuclear Reactor Regulation
- u. s. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing
Dear Mr. Varga:
REQUIREMENTS FOR EMERGENCY RESPONSE CAPABILITY SUPPLEMENT 1 TO NUREG 0737 PRELIMINARY STATUS REPORT AND SCHEDULE SALEM GENERATING STATION UNITS NO. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 PSE&G hereby transmits its response to Generic Letter 82-33, concerning Emergency Response Capability.
We are currently developing our integrated schedule for implementation, which will be ready for review with the NRC Project Manager by June 1, 1983. 1. Safety Parameter Display System (SPDS) PSE&G is currently evaluating bids for a Data Acquisition System for the Emergency Response Facilities, of which the SPDS will be a part. We expect to complete these evaluations and issue a purchase order within three months. Following selection of a vendor for the SPDS, a delivery and installation schedule will be established.
At this point, however, PSE&G would like to reserve the right to request a pre-implementation review by the NRC following the award of a contract to a vendor. 2. Control Room Design Review (CRDR) The CRDR Program Plan was previously transmitted to A. 4 /)_ t/ the NRC by letter dated on February 14, 1983. . f"t"".J,)*
¥ The Energy People --8304190236 830415 PDR ADOCK 05000272 F PDR 95-2168 (80 M) 11-82 Mr. Steven A. Varga, Chief U.S. Nuclear Regulatory Commission 4/15/83 The CRDR effort is in progress and is approximately 85% complete.
We are evaluating the findings of the CRDR, and anticipate that the CRDR summary report will be submitted by December, 1983. The summary report will include an evaluation of the design and operation of the annunciator alarm systems (e.g., number of auditory codes used, color coding of annunciator tiles, use of single action switches to perform both the silence and acknowledge functions and the use of knee switches in the control room). The report will also address the design of the first-out panel system for potential improvements in reliability of information presented to the operators.
- 3. Regulatory Guide 1.97, Rev. 2 (RG 1.97) The method of implementing RG 1.97 guidance was described in our report, submitted by letter dated April 2, 1981. Implementation on Unit 2 will be completed during its first refueling outage, currently scheduled for completion in May, 1983. Implementation has been completed on Unit 1. 4. Emergency Operating Procedures (EOP) PSE&G's EOP upgrade is in progress utilizing the Westinghouse Generic Technical Guidelines submitted to the NRC in 1982. It is expected that the Procedures Generation Package will be submitted to the NRC by May 31, 1983. The preliminary schedule indicates that the revised EOPs will be implemented (without SPDS) by mid-1984.
A schedule for incorporating the SPDS into the EOPs will be provided upon completion of the SPDS design. 5. Emergency Response Facilities (ERF) The Salem ERFs consist of the Operational Support Center (OSC), Technical Support Center (TSC), and Emergency Operations Facility (EOF). The OSC is the area encompassed by the Senior Shift Supervisor's office, file room, and the aisleway between the individual unit Control Rooms. The TSC will be located on the third floor of the existing Clean Facilities Building.
It is expected that the design will be completed, and a contractor selected, by the fourth quarter of 1983.
- J. 'I
- Mr. Steven A. Varga, Chief U.S. Nuclear Regulatory Commission 4/15/83 The EOF is located at PSE&G's Nuclear Training Center in Salem, New Jersey, approximately 7.5 miles from the TSC. We have previously requested relief from the requirement for a backup EOF. The analysis presented in our letter of April 20, 1981 shows that this location is acceptable with regard to radiological exposure and habitability.
It is our intent to review our preliminary schedule with the NRC Project Manager to develop a mutually acceptable integrated schedule.
Since the SPDS has an effect on the schedules of the other items in this response, our integrated schedule may require modification based on vendor schedules and capabilities.
As this response is to be submitted in accordance with 10 CFR 50.54(f), the requisite affidavit will be transmitted to you by April 20, 1983. Should you have any questions, please do not hesitate to contact us. Very truly yours, CC: Mr. Donald C. Fischer Licensing Project Manager Mr. Leif Norrholm Senior Resident Inspector Manager -Nuclear Licensing and Regulation