ML20198F471
| ML20198F471 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 11/05/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8511140363 | |
| Download: ML20198F471 (2) | |
Text
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Electnc and Gas E
Commm 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 N;
Robert L. Mitti General Manager Nuclear Assurance and Regulation November 5, 1985 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Mr. Walter Butler, Chief Licensing Branch 2 Division of Licensing Gentlemen:
ULTIMATE PLANT PROTECTION SYSTEM HOPE CREEK GENERATING STATION DOCKET NO. 50-354 This letter is to confirm information provided during the telecon held on October 30, 1985 between NRC Reactor Systems Branch and Public Service Electric & Gas Company (PSE&G),
concerning existing design features at HCGS which would provide ultimate plant protection capability.
As stated during the telecon, the existing design at HCGS provides cross-tie connections to the RHR system from both the service water system and the fire water system.
The service water system cross-tie is permanently piped and the fire water system cross-tie requires only a standard fire hose for connection.
All valves which normally isolate these cross-ties from the RHR system could be opened from the control room with emergency diesel generator power available.
In the event no power is available, these valves can be opened manually.
HCGS Emergency Operating Procedure Nos. OP-EO.ZZ-308 & OP-EO.ZZ-310 specifically identify the capability of these cross-ties to provide cooling water directly to the vessel upon loss of all other normal and backup sources.
8511140363 851105 ADOCK 0%y4 PDR i 9 The Energy People
% 4412 D* *) 4 e t
l' Director of Nuclear 2
11/5/85 Reactor Regulation Preliminary calculations have been performed which indicate that approximately 100 gpm would be more than adequate to maintain a flooded core with a boil-off rate of approximately 90 gpm.
The service water pump capacity is 16500 gpm and the diesel driven fire water pump capacity is 2500 gpm, both of which are far in excess of the 100 gpm required.
In addition to the above cross-ties, a PSE&G owned fire truck is also available onsite which could be used to supply the minimum 100 gpm makeup water supply by taking suction from the Delaware River or the fire system.
This water would be pumped into the fire water system via the fire system connection available in the Auxiliary Building.
A reactor pressure vessel vent path could also be established with a minimum of one channel of DC power availab,le.
Drywell and wetwell venting could be accomplished by opening the six (6) inch integrated leak rate test line.
Containment venting could be accomplished by opening the twenty-four (24) or twenty-six (26) inch purge line.
We hope the above information is sufficient to alleviate your concerns.
Very truly yours,
~.l.
i L
C D.H. Wagner USNRC Licensing Project Manager A.R.
Blough USNRC Senior Resident Inspector w