ML18089A484
| ML18089A484 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/23/1983 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM NUDOCS 8401110094 | |
| Download: ML18089A484 (3) | |
Text
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department December 23, 1983 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing Gentlemen:
INADEQUATE CORE COOLING INSTRUMENTATION TMI ITEM II.F.2 SALEM GENERATING STATION NO. 1 AND 2 UNITS DOCKET NOS. 50-272 AND 50-311 PSE&G provides the following information in response to the items listed on Enclosure 1 of your letter of November 17, 1983.
- 1.
PSE&G has obtained the following documents used by Westinghouse for calibrating and testing the Unit 1 Reactor Vessel Level Instrumentation System (RVLIS):
- a.
Trip Report ICD-IS-(82)-080, used to check out, calibrate and collect heat-up data for Microprocessor RVLIS.
- b.
Procedure NSD-EIS-82-11, -"Pump Performance Curve Measurement," used to determine the wide-range delta p vs temperature curve.
- c.
Procedure NSD-EIS-82-09, "Vessel Level Monitor System Scaling Calculations for Salem Unit No. l."
These documents are regarded by Westinghouse as proprietary in accordance with applicable provisions of 10 CFR 2.790, and PSE&G is requesting Westinghouse approval before submitting them.
Our tentative schedule for submitting calibration and test information for Unit 2 is March 1, 1984.
This date is contingent on the receipt of documentation from Westinghouse.
The Energy People 8401110094 831223 PDR ADOCK 05000272
.p PDR 95-2168 (80M) 11-82
- u. S. Nuclear Regulatory Commission 12/23/83
- 2.
Validation of the Emergency Operating Procedures incorporating RVLIS is scheduled by or before January 9, 1984.
This will be performed by a walk-through of the procedures.
- 3.
Technical Specifications (T.S.) have been developed using the guidance of Generic Letter 83-37 (NUREG 0737, Technical Specifications).
Upon clarification of the environmental qualification requirements for Core Exit Thermocouples (CET's), these T.S. will be submitted.
- 4.
Our tentative schedule to submit an estimate of additional error in level indication is March 1, 1984.
This schedule is contingent on the date Westinghouse supplies the documentation.
- 5.
Clarification of the PSE&G position on CET's with respect to meeting the requirements of NUREG 0737 Item II.F.2,, will be submitted by March 1, 1984.
- 6.
Clarification of the PSE&G position on backup displays with respect to NUREG 0737 Item 2, Attachment 1 requirement, will be submitted by March 1, 1984.
- 7.
Clarification of the PSE&G position on primary displays with respect to NUREG 0737 Item II.F.2, Attachment 1, will be submitted by March 1, 1984.
- 8.
A detailed description of the final integrated display system will be provided by June 1, 1984 contingent on the date Westinghouse provides us the documentation.
The following is a schedule for the implementation milestones as listed on Enclosure 2 to your letter.
- 1.
The final design description will be submitted on or before March 1, 1984, contingent on receipt of documentation from Westinghouse.
- 2.
Generic Emergency Operating Procedures (EOP's) were approved on June 6, 1983.
- 3.
Installation of the RVLIS is complete.
- 4.
Functional testing and calibration will be completed and the documentation provided by March 1, 1984.
- u. S. Nuclear Regulatory Commission 12/23/83
- 5.
Revision of plant-specific EOP's is complete, and validation is scheduled for completion by January 9, 1984.
- 6.
The implementation letter report is tentatively scheduled to be submitted by March 1, 1984, assuming other schedule dates are met.
- 7.
Procedure walkthrough to complete task analysis will be scheduled with the NRC after the EOP's are validated.
- 8.
RVLIS will be turned on for operator training and familiarization when Items 5 and 6 are completed.
- 9.
NRC approval of the Salem RVLIS is expected after review of the implementation letter report.
- 10.
Implementation of modified operating procedures and emergency procedures is contingent on completion of Items 5 through 9 above.
Should you have any questions, please do not hesitate to contact us.
cc:
Mr. James Linville Senior Resident Inspector Mr. Donald C. Fischer Licensing Project Manager E. A. Liden Manager -
Nuclear Licensing and Regulation