ML20032C423

Responds to IE Bulletin 80-17,Suppl 3, Failure of Control Rods to Insert During Scram at Bwr. Requests Relaxation of Immediate Scram Requirement on Control Rod Driveline High Temp Which Indirectly Indicates Possible Dump Vol Problems

ML20032C423
Person / Time
Site:	Oyster Creek
Issue date:	10/23/1981
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-80-17, NUDOCS 8111100389
Download: ML20032C423 (2)

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OYSTER CREEK NUCLEAR GENERATING STATION tl "BP&L M

(609)b93-6000 P O BOX 3R8

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Mr. Ronald Ihynes, Direc to r Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Commission NOV9 91997 Region I u,

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Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Bulletin #80-17, Supplement 3 - Relaxation of Requirement

% e subject IE Bulletin involves a single failure mechanism

he control rod drive control air system which could result in loss of scram functio..

The bulletin requires, among other things, that operating pros edures be revised to direct an immediate scram in the event of a marked change in the number of control rod drives (CRD) exceeding high temperature alarm set points. By letter dated August 29, 1980, it was confirmed that the Oyster Creek Station procedure had been revised to include this requirement.

Since the issuance of the subject bulletin, several modifications at the Oyster Creek Station have been completed that ef fectively preclude the single failure mechanism delineated in the bulletin.

In order to prevent a degradation of control air pressure to the extent of allowing scram outlet valve leakage an automatic scram fuNuon on low control air pressure has been incorporated which assures that a scram will be initiated prior to scrau valve leakage. W e scram is initiated at a control air pressure of 5512 psig which is well above the 4012 psig at which possible leakage could occur. Additionally, the scram dump volt.me water level Continuous Moitoring System (CMS) has been completed and functionally tested. This sytsem is currently in operation and forewarns the operator of any water buildup in a scram discharge volume thereby alerting him to the development of an inadequate dump volume condition.

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Mr. Ronald Haynes Page 2 Octobsr 23, 1981 Since the modifications discussed above provide direct mitigating action and indication for the event in question, it is our intent, with your concurrence, to remove from the procedure the immediate scram requirement on CRD-high ' temperatures which is an indirect Indication of possible dump volume problems.

Therefore, it is requested that a response f rom your office be provided indicating your position concerning this action.

If you should you have any questions, please contact Mr. Michael Laggart at (609) 693-6932.

Very truly yours, l

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/J. T. Carroll, Jr.

j/ cting Director -

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/ Oyster Creek JTC:GWB:lse cc: Di re c to r Of fice of Inspection and Enforcement U.S. Nuclear Regulato ry Commission Wa shington, D.C.

20555 NRC Resident Inspecto r Oyster Creek Nuclear Generating Str> tion Forked River, NJ 08731 t.

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