ML18095A667

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Proposes Changes to Initial Approach Re RCS Level Indication & DHR Sys Continuous Performance Monitoring to Satisfy Commitments Made in 901023 Response to Generic Ltr 88-17
ML18095A667
Person / Time
Site: Salem  
Issue date: 12/28/1990
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-88-17, NLR-N90233, NUDOCS 9101090158
Download: ML18095A667 (5)


Text

Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations DEC 2 8 1990 NLR-N90233 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555 Gentlemen:

GENERIC LETTER (GL) 88-17 FOLLOWUP SALEM GENERATING STATIONS UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas Company (PSE&G) forwarded a letter, dated October 23, 1990, revising our previous Generic Letter (GL) 88-17 commitments.

We proposed changes to our initial approach regarding RCS level indication and Decay Heat Removal (DHR) system continuous performance monitoring.

We committed to notifying the NRC of our final decision by December 1990, including a schedule for implementation.

This letter satisfies that commitment.

RCS LEVEL INDICATIONS Salem presently 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 intends to measure RCS level by installing differential pressure transmitters connected to the RCS sample lines of loops 1 and 3.

The other port of both transmitters will be connected to the vent line in the pressurizer spray piping.

The RCS sample lines connect to the hot leg at a point lower than the minimum RCS level allowable during mid-loop operation.

Transmitter outputs will be connected to the Plant Computer (P-250).

Display and alarm functions will be provided on the P-250 CRT located on the control console.

9101090158 901228 PDR ADOCK 05000272 P

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Document Control Desk NLR-N90233 2

DEC 2 8 1990 RCS level measurement instrumentation is a permanent installation.

This replaces the current method of recalibrating RCS flow transmitters to monitor RCS level during mid-loop operation.

Figure 1 (attached) provides a conceptual drawing of the new transmitter installation.

CONTINUOUS MONITORING OF DHR 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 intends to utilize the P~250 Plant Computer for this monitoring function.

The P-250 currently monitors RCS temperature and RHR pump discharge flow.

RCS level and RHR pump suction pressure/discharge pressure/motor current will be added to this system.

RHR pump discharge pressure and motor current are presently displayed on the control console.

These data points will be routed to the Plant Computer.

RCS level and RHR pump suction pressure signals will originate from transmitters not currently installed.

RCS level instrumentation was discussed above.

RHR pump suction pressure will be provided by a transmitter connected to the RHR pump suction line.

Figure 2 (attached) provides a conceptual drawing of the new transmitter installation.

We plan to disconnect this transmitter from the RCS during plant operation.

Display and alarm functions will be provided on the P-250 CRT.

SUMMARY

The modifications discussed above will satisfy the GL 88-17 programmed enhancement for instrumentation, and closeout this issue.

PSE&G plans to fully implement these changes by the end of the 6th refueling outage for Unit 2 (fall of 1991) and the 10th refueling outage for Unit 1 (spring of 1992).

As a long-term plant improvement effort, PSE&G is presently investigating the feasibility of converting all Salem process computers (existing and future) to an Automation Network.

This system utilizes a data highway to provide plant process analysis, trending, reporting and display from a single work station.

our preliminary review suggests that this system can provide many advantages over our present approach to plant process computers.

If we elect to incorporate this system, DHR parameters would be monitored and displayed by a new plant computer; replacing the existing P-250.

Document Control Desk NLR-N90233 3

DEC 2 8 1990 Should you have any questions on this issue, do not hesitate to contact us.

Sincerely, Attachment c

Mr. J. c. stone Licensing Project Manager -

Salem Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

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I Figure 2 RHR Pump Suction Pressure Conceptual Drawing I

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