ML18095A553
| ML18095A553 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/23/1990 |
| From: | Crimmins T Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-17, NLR-N90176, NUDOCS 9011010114 | |
| Download: ML18095A553 (4) | |
Text
Public Service Electric and Gas Company Thomas M. Crimmins, Jr.
Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4700 Vice President - Nuclear Engineering OCT 2 3 1990 NLR-N90176 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REVISION TO GENERIC LETTER (GL) 88-17 COMMITMENTS SALEM GENERATING STATIONS UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 This letter redefines several hardware-related modifications and changes our estimated completion schedule.
Public Service Electric and Gas Company (PSE&G) believes that our proposed changes will result in better modifications over the long-term.
We are also revising our previous commitment to create an Engineering Standard as the basis document for procedures, instrumentation, equipment and NSSS interactions.
RCS LEVEL INDICATIONS PSE&G is committed to upgrading the existing RCS level indication design.
We are evaluating several diverse means for obtaining accurate level indication.
Salem recalibrates two independent RCS loop flow transmitters to provide continuous RCS level indication in the control room.
This arrangement meets the guidance of GL 88-17, and provides the primary indication of RCS level during mid-loop operations.
Local tygon tubing is a redundant and diverse level indicator used to verify the accuracy of the control room indicators.
Local indication is not continuous; field operators periodically valve it in to obtain a reading.
PSE&G previously committed to converting the existing tygon tubing into a permanent hard-pipe design.
After further review, we believe that upgrading this verification device is not the best available approach.
We are abandoning this approach.
The Westinghouse Owners Group (WOG) is evaluating more accurate RCS level ins.trumentation.
Recent studies show some differences between transmitters connected to the hot leg versus the cold leg, with the hot leg providing more accurate readings.
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Document Control Desk NLR-N90176 2
OCT 2 3 1990 PSE&G is contracting with an independent group to review several versions of hot leg instruments and provide their recommendations.
Options include in-series and parallel connections to existing devices and an ultrasonic system.
Additionally, Westinghouse is providing a proposal to upgrade our existing Reactor Vessel Level Indicating System (RVLIS) to include mid-loop level indication.
We will select an upgrade approach by December 1990.
CONTINUOUS MONITORING OF DECAY HEAT REMOVAL (OHR) SYSTEM PERFORMANCE DHR system performance monitoring includes several parameters:
RHR pump suction pressure/discharge pressure/motor amps, RHR flow and RCS level.
Most of these parameters are presently displayed in the Salem control room; although not in one concise location.
PSE&G previously committed to installing these indications on the Safety Parameter Display System (SPDS), as a status tree function.
Our SPDS has undergone several software modifications to meet GL 89-06 requirements.
We continue to work on the longer term SPDS hardware and software upgrades, as described in our letter dated January 23, 1990.
Adding another status tree function may adversely affect this continuing work.
We intend to review all available options and select the best approach.
These options include:
SPDS modification, expanding the capabilities of the plant P-250 computer and establishing a stand alone system for DHR monitoring.
We will select a DHR monitoring approach by December 1990.
ENGINEERING STANDARD PSE&G previously committed to creating an Engineering Standard to supplement the Westinghouse Owners Group (WOG) analysis documented in WCAP-11916.
This standard would have been the basis for Salem procedures, instrumentation, equipment and NSSS interactions.
PSE&G contracted with Westinghouse to develop a Salem specific mid-loop analysis report.
The WOG subsequently issued Abnormal Response Guidelines (ARG-1), to assist utilities in creating WCAP based recovery procedures for loss of decay heat removal.
WCAP-11916, WOG ARG-1 and the Salem specific report presently provide our mid-loop operation basis.
PSE&G has decided to forgo an Engineering Standard and maintain all mid-loop related analyses as stand alone documents.
These stand alone documents will be referenced in the RHR System
Document Control Desk NLR-N90176 3
OCT 2 3 1990 Configuration Baseline Document.
PSE&G plans to update these documents when a final design direction is determined for RCS level indication and continuous OHR monitoring, and as additional industry experience develops.
We believe that this approach provides greater long term benefit than an Engineering Standard and meets the intent of our previous commitment.
SUMMARY
PSE&G currently meets the GL 88-17 requirements for two independent RCS level indicators.
We believe that upgrading the existing local tygon tubing to a permanent hard-pipe design is not in our long term best interest.
Several options are under review that follow the most recent WOG guidance on RCS level indication.
A final upgrade approach will be selected by December 1990.
Most of the OHR system significant parameters are presently displayed in the Salem control room.
Our previous commitment to add a.DHR status tree function to the SPDS may not be the best course of action.
Several options are under review and a final approach will be selected by December 1990.
PSE&G intends to select modifications that will meet all current requirements and satisfy our expectations over the long-term.
We are attempting to take advantage of state-of-the-art instrumentation.
PSE&G will notify the NRC of our final decision by December 1990 and include a schedule for implementation.
PSE&G will maintain mid-loop related basis documents as stand alone documents in lieu of an Engineering Standard.
We will continue to emphasize mid-loop concerns through periodic training sessions and work other GL 88-17 modifications per our previous schedule.
Should you have any questions on this issue, do not hesitate to contact us.
Attachment
Document Control Desk NLR-N90176 c
Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief 4
New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 OCT 2 3 1990