ML19308C681

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Forwards Notice of Violation from 791127-1208 Insp of Maint Activities.Noncompliance Noted:Equipment Clearance Permit Was Approved W/O Verifing That All Redundant Engineered Safety Sys Were Available
ML19308C681
Person / Time
Site: Beaver Valley
Issue date: 12/31/1979
From: Stello V
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Crouch D
DUQUESNE LIGHT CO.
References
NUDOCS 8002010102
Download: ML19308C681 (2)


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DEC 311979 Duquesne Light Company License No. SOP-2768-1 Beaver Valley Power Station Docket No.

55-5619 ATTN: Mr. D. A. Crouch P.O. Box 4 Shippingport, Pennsylvania 15077

Dear Mr. Crouch:

This letter relates to the findings of an inspection at the Beaver Valley Power Station which was conducted November 27 through December 8,1979, by our Resident /

Inspector.

The inspection related principally to various maintenance activities occurring on November 27, 1979, which resulted in a portion of the emergency core cooling system (ECCS) being unavailable for automatic start, if it had been needed, concurrent with a loss of offsite power.

Based on the results of this inspection it appears that you took an action which was not in full compliance with the requirements of your NRC Senior Operators License, 50P-2768-1.

The specific citation is contained in the enclosed Notice of Violation. You are required to submit to this Office within twenty days of your receipt of this notice, a written statement in reply, including the reasons for the item of noncompliance and the action you plan to take to prevent recurrence of similar noncompliance (See 10 CFR 2.201).

Also enclosed for your information is a copy of enforcement correspondence on this same matter which has been sent to Duquesne Light Company, and a copy of IE Information Notice No. 79-20, Revision 1, entitled "NRC Enforcement Policy - NRC Licensed Individuals." You should have received a copy of the Information Notice in September of this year.

This notice was intended to remind licensed individuals of their personal responsibilities for adherence to the conditions of their license.

Copies of this Action together with your response will be sent to (1) your employer, Duquesne Light Company, (2) the NRC's public document room in Washington, D.C.,

(3) the local public document room in Alquippa, Pennsylvania and (4) the NRC's Operator Licensing Branch.

If you have any quehtions about this action, you may discuss them with Mr. Boyce Grier in the Region I office (215-337-5000) or with me (301-492-7397).

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V ctor S Director Office of Inspection and Enforcement l

Enclosures:

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Enclosures:

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Appendix A - Notice of Violation 2.

Criteria for Determining Enforcement Action and Categories of Noncompliance with AEC Regulatory Requirements-Modifications 3.

IE Information Notice No. 79-20, Revision 1 4.

USNRC letter to Duquesne Light Company cc w/ enclosure 1:

C. N. Dunn, Vice President, Operations Division F. Bissert, Technical Assistant Nuclear R. Washabaugh, QA Manager J. Werling, Station Superintendent G. Moore, General Superintendent J. J. Carey, Nuclear Technical Assistant R. Martin, Nuclear Engineer J. Sieber, Superintendent, Licensing and Compliance

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Appendix A NOTICE OF VIOLATION D. A. Crouch License No. 50P-2768-1 Docket No. 55-5619 Based on the results of an NRC inspection conducted on November 27 through December 8,1979, it appears that one of your activities was not conducted in full compijance with conditions of your Senior Operator License as indicated below.

This noncompliance is categorized as a violation.

Senior Operator License No. 50P-2768-1 states in part that "In directing the licensed activities of licensed operators...the licensee shall observe the operating procedures and other conditions specified in the facility license which authorizes operation of the facility...".

Appendix A to Operating License No. DPR-66, Technical Specification 3.5.2, states that with the plant in Mode 1 (Power Operation), two separate and independent ECCS subsystems shall be operable, and further states in section 3.5.2.c that each subsystem shall include an oper-able flow path capable of taking suction from the refueling water storage tank upon initiation of a safety injection signal.

Technical Specification 1.6 defines " operable" to mean, in part, "that all necessary attendant instrumentation, control electric power, cooling or seal water, lubrication or auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related safety functions."

Appendix A to Operating License No. OPR-66, Technical Sp'ecifications Section 6.8.1 requires that procedures be established, implemented and maintained consistent with all applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33 dated November 1972.

Included in RG 1.33 are procedures

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for plant operation and maintenance activities.

The Beaver Valley Power Station Operating Manual, Section 1.48.7, Revision 7, including Operating Manual Change Notice No.79-137 dated October 8,1979, and Special Operating Order No. 79-2, Clearance Procedure, issued April 25, 1979, collectively stipulate that the operators must at least visually verify that redundant Engineered Safety Features (ESF) systems are available prior to maintenance release and that signatures of the operators signify that removal of ESF equipment from service will not violate applicable Technical Specifications limiting conditions of operation.

Contrary to the above, on November 27, 1979, you participated in approving,an equipment clearance permit associated with a maintenance work request without verifying that all redundant engineered safety feature systems were available in that the approved maintenance work rendered both ECCS subsystems inoperable from approximately 8:30 a.m. to 10:30 a.m.

During this time:

a) the refueling water storage tank isolation valve MOV-CH-1150 was closed and incapable of auto-matic opening in response to a safety injection signal; and, b) the refueling water storage tank isolation valve MOV-CH-1158, in the redundant subsystem, was closed, had no emergency power available, and thus was incapable of automatic opening in response to a safety injection signal if there had been a condition of loss of offsite power.

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This violation had the potential for causing or contributing to an occurrence related to health and safety.

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