ML20042F127
| ML20042F127 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/30/1990 |
| From: | Crimmins T Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-81-12, NLR-N90067, NUDOCS 9005070247 | |
| Download: ML20042F127 (2) | |
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Pubhc Service Electnc and Get i
comony Thomas he, Crimmins, Jr.
Pubhc Servico Doctoc and Gas Company P.O Dox 236. Hancocks Bridge. NJ 08038 609 339-4700
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vo r n e - a* o w ine enu APR 3 01990 1
NLR-N90067 l
l United States Nuclear Regulatory Commission
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l Document Control Desk J
Washington, DC 20555 Gentlemen HIGH/ LOW PRESSURE INTERFACE VALVES; COMMITMENT REVISION IN ACCORDANCE WITH 10CFR50.59 HOPE CREEK GENERATING STATION I
DOCKET NO. 50-354 l
l The purpose of this transmittal is to notify the NRC of a change to a licensing basis commitment for the Hope Creek Generating i
Station (HCGS).
This change is being made under the provisions of 10CFR50.59.
Public Service Electric and Gas (PSE&G) intends to restore electric power to solenoid operated pilot valves associated with high/ low pressure interfacing systems.
Updated Final Safety Analysis Report (UFSAR) revised pages 9A-105, 9A-106 and 9.5-73 include a commitment provided in response to Generic Letter 81-12, " Fire Protection Rule".
That commitment included removing power to solenoid actuators for the Low Pressure Coolant Injection (LPCI), Residual Heat Removal (RHR) system return, and Core Spray Supply bypass valves during power operation.
It was determined that disabling of these high/ low pressure system interface valves would alleviate a concern relating to spurious operation of these valves during a fire.
Under the postulated conditions, misoperation of these valves would subject the low pressure portion of the system's piping to damage and could result in uncontrolled loss of reactor coolant.
Since that commitment was made, PSE&G has determined that misoperation of these valves will not result in uncontrolled loss of reactor coolant.
Analysis performed for HCGS affected low q
pressure systems documents that stress levels on piping and pipe supports is well within the design capacity of the systems.
The report also concludes that sufficient relief capacity exists to j
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9005070247 900430 PDR ADOCK 05000354 p
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Document Control Desk 2
APR 3 0 Iga NLR-N90067 maintain system pressures within acceptable bounds.
The relief valves provided on the low pressure piping are directed to the suppression pool (torus) through a permanent drain pipe arrangement.
The maximum flow rate through the low pressure relief valves is well within the make up capacity of the non ECCS Reactor Core Isolation Cooling (RCIC) system.
It was further determined through the 10CFR50.59 Safety Evaluation Process that spurious operation and subsequent leakage was bounded by the scenarios detailed in Chapter 15 of the UFSAR and an unreviewed safety question does not exist.
Documentation supporting this change is available on site for your review.
Sincerely, v/
y m 3 - _---,
C Mr.
C.
Y. Shiraki Licensing Project Manager Mr. T. P. 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
.