ML20128H536
| ML20128H536 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/21/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8505300533 | |
| Download: ML20128H536 (3) | |
Text
k PS G Company Putsc Serwco Electnc and Gas 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulation May 21, 1985 Director of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:
Mr. Walter Butler, Chief Licensing Branch 2 Division of Licensing Gentlemen:
HOPE CREEK GENERATING STATION DOCKET NO. 50-354
'10CFR50.62 - ATWS RULE COMPLIANCE Pursuant to 10CFR50.62 (c) (6), Public Service Electric and Gas Company hereby. submits the following information to demonstrate compliance with paragraph (c) (1) through (c)
(5) of 10CFR50.62 for Hope Creek Generating Station.
10CFR 50.62 (c) -Requirements (1)~Each pressurized water reactor must have equipment from sensor output to final actuation device, that is diverse from the reactor trip system, to auto-matically initiate the auxiliary (or emergency) feedwater system and initiate a turbine trip under conditions indicative of an ATWS.
This equipment must be designed to. perform its function in a reliable manner and be independent (from sensor output to the final actuation device) from the existing reactor trip system.
Response
HCGS is a boiling water reactor, therefore, this requirement is-not applicable to HCGS.
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9P I D 8505300533 850521 PDR ADOCK 05000354 The Energy People A
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Director ~of Nucleart 2
5/21/85 LReactor' Regulation (2) Each pressurized water reactor manufactured by Combustion. Engineering or by Babcock and Wilcox
.must have a diverse scram system from the sensor output _to interruption of power to the control rods.
This scram system must be designed to perfora its function.in a reliable manner and be c
. independent from the existing reactor trip. system-(from -sensor output to -interruption of power to the control' rods).
e
Response
-HCGS is a;boilirg. water reactor, therefore, this requirement-isynot applicabla to HCGS.
[4 6
' (3) Eact boiling water reactor must have an alternate rod
-fection.(ARI) system that is diverse (from
.the reactor trip system) from sensor output to the
. final actuation device.
The ARI system must have redundant scram air header exhaust valves.
The ARI must be designed to perform :its function in a
. reliable manner and be independent -(from the exist-Ofgf[g:'
ing. reactor trip system) from sensor output to the bn.
j final actuation device.
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' Response HCGSchas implemented anLAlternate' Rod Insertion (ARI) system that is diverse-from the reactor trip system.
E lti (4) Each boiling water reactor must have a-standby liquid control system-(SLCS) with a minimum flow
+
capacity and boron content equivalent in control capacity to-86 gallons per minute of 13 weight percent sodium pentaborate. solution.
The SLCSTand its injection location must be designed to perform t
its: function in-a reliable manner.
The SLCS initiation must be automatic:and must be' designed-to perform its function in a. reliable manner for
-plants: granted a construction permit'after July 26,.
'1984, and i for plants granted ~ a construction permit prior.to July 28, 1984, that have already been designed and built to include this feature.
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,.m Director of Nuclear 3
5/21/85 Reactor Regulaticn
Response
The HCGS standby liquid control system (SLCS) has a minimum flow capacity of 86 gpm of 13 weight percent sodium penta-borate solution.
The SLCS initiation is automatic.
Boron injection is through the core spray nozzle and the SLCS pipe is connected to the core spray pipe upstream of the HPCI line connection to the core spray.
(5) Each boiling water reactor must have equipment to trip the reactor coolant recirculating pumps auto-matically under conditions indicative of an ATWS.
This equipment must be designed to perform its Tg function is a reliable manner.
Response
The HCGS reactor coolant recirculating pumps are tripped automatically under conditions indicative of an ATWS.
10 CFR 50.62'(d) Implementation
Response
The HCGS ATWS components are safety-related.
The quality assurance requirements of ATWS components comply with Regulatory Guide 1.30, Rev. O.
The above items are pres-ently incorporated in the HCGS design and will be installed and operational by initial fuel load, scheduled for January 1986.
Should you have any questions in this regard, please contact us.
Very truly yours,
/-
C D.
H. Wagner USNRC Licensing Project Manager A.
R.
Blough USNRC Senior Resident Inspector
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