ML20009E365

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Submits Supplemental Response to IE Bulletin 80-18, Maint of Adequate Min Flow Through Centrifugal Charging Pumps Following Secondary Side High Energy Line Rupture. Safety Injection Initiation Signal Will Be Removed from Pump
ML20009E365
Person / Time
Site: Salem  PSEG icon.png
Issue date: 07/14/1981
From: Schneider F
Public Service Enterprise Group
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-80-18, NUDOCS 8107280084
Download: ML20009E365 (3)


Text

$~hh fro -15(I FredIrick W. Schneider Public Service Electric and Gas Lemoany 80 Park Plaza Newark, N.J. 07101 201/430-7373 Vice Presnient Production July 14, 1981 Mr. Boyce H.

Grier, Director W

U.S. Nuclear Regulatory Commission 6

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g 631 Park Avenue

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Dear Mr. Grier:

N SUPPLEMENTAL RESPONSE NRC IE BULLETIN 80-18 4

MAINTENANCE OF ADEQUATE MINIMUM FLOW THROUGH CENTRIFUGAL CHARGING PUMPS FOLLOWING SECONDARY SIDE HIGH ENERGY LINE RUPTURE No. 1 AND 2 UNITS SALEM GENERATING STATION As a result of our continued evaluation of the potential problem described in IE Bulletin C0-18, we have developed a revised interim solution that includes plant modifications in conjunction with procedural changes.

It is our intent to remove the safety injection initiation signal from the centrifugal charging pump (CCP) miniflow isolation valves, CV 139 and CV 140, on both Salem units, thus preventing atomatic termination of miniflow.

Coupled with the circuitry j

modifications, manual valve CV 197, which directs Reactor Coolant l

Pum; (RCP) sealwater return flow to the suction of the CCP's, will ',e locked closed and manual valve CV 130, which will cause RCP sealwater return and CCP miniflow water to go to the Volume Control Tank (VCT), will be locked open.

This valve alignment will cause the VCT to fill solid during a Safety Injection Initiation; the VCT relief valve, CV 241, would then open, directing miniflow to the CVCS holdup tanks.

Procedurally, the operator will be instructed to terminate m1piflow below an RCS pressure 1500 psig (when the RCP's are stopped), and to reestablish miniflow if RCS pressure rises again to 2000 psig.

l Should an actual small-break LOCA occur with no rapid RCS de-pressurization, the emergency instructions will call for closure fjCIl 8107280084 810714 f,

I PDR ADOCK 05000272 G

PDR

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Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission 7/14/81 of the miniflow valves, CV 139 and CV 140 within 15 minutes of SI initiation.

Implementation of physical plant changes, procedure modifications, and training of necessary plant personnel will be completed during the next refueling outage for Unit No. 1 and during the first outage of sufficient length occurring after November 1, 1981 for Unit No.

2.

We are continuing to pursue a long-term resolution of this situation with Westinghouse.

Any additional modifications will be brought to your attention as a supplemental response to the Bulletin.

Very truly yours, 6

7

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CC Director Div. of Reactor Operations Inspection Washington, DC i

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STATE OF NEW JERSEY

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SS:

COUNTY OF ESSEX COUNTY OF ESSEX

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FREDERICK W. SCHNEIDER, being duly sworn according to law deposes and says:

I am a Vice President of Public Service Electric and Gas Company, and as such, I signed the letter dated July 14, 1981, to Mr. Boyce H. Grier, Director, NRC Office of Inspection and Enforce-ment, Region I, as a supplemental response to NRC Bulletin No. 80-18

" Maintenance of Adequate Minimum Flow Through Centrifugal Charging i

Pumps Following Secondary Side High Energy Line Rupture. "

The matters set forth in said response letter are true to the best of my knowledge, information and belief.

he

^4

'r FREDERICK W.~SCHNEIDER Subscribed and sworn to before me V4 this/h day of T &M

, 1981 8

8 Owa 6. Waian Notary Public of New Jersey My Commission expires on CI. /, / k'ef 3

.