ML20134G300

Notice of Violation from Insp on 960908-1019.Violation Noted:On 960323,w/plant in Mode 5,operators Discovered SI Pump Discharge Valves EM HV-8802A & 8821A Handswitches Tagged Do Not Operate Closed But Still Power Available

ML20134G300
Person / Time
Site:	Wolf Creek
Issue date:	11/07/1996
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20134G297	List: IR 05000482/1996018 ML20134G294 ML20134G300
References
50-482-96-18, NUDOCS 9611130125
Download: ML20134G300 (2)

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ENCLOSURE 1 NOTICE OF VIOLATION ,

Wolf Creek Nuclear Operating Corporation Docket No.: 50-482 Wolf Creek Generating Station License No.: NPF-42 During an NRC inspection conducted on September 8 through October 19,1996, four violations of NRC requirements were identified in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600,the

! violations are listed below:

A. Technical Specification 3.5.4 requires that all safety injection pumps be inoperable during Modes 5 and 6 with the reactor vessel head on. The pumps are to be made inoperable by securing the motor circuit breaker in the open position. The inoperable pump may be energized for testing or for filling accumulators provided '

the discharge at the pump has been isolated from the reactor coolant system by a closed isolation valve with power removed from the valve operator or by a manual

isolation valve secured in the closed position.

Contrary to the above, on March 23,1996, with the plant was in Mode 5, l operators discovered that Safety injection Pump Discharge Valves EM HV-8802A and -8821 A handswitches were tagged "Do Not Operate" closed, but still had power available to them. The pump motor circuit breaker was racked closed so that i

Safety injection Pump A could be started.

This is a Severity Level IV violation (Supplement l) (482/9618 02) ,

l B. Technical Specification 3.9.4 requires that each penetration providing direct access from the containment atmosphere to the outside atmosphere be closed by an isolation valve, blind flange, manual valve, or be capable of being closed by an j operable automatic containment isolation valve. This Technical Specification is applicable during core alterations or movement of irradiated fuel within containment.

Contrary to the above, on March 14,1996, the licensee found that operators had l directed the opening of Containment isolation Valve BM-V046 to allow draining of i Steam Generators B and C. Core alterations were in progress at the time.

This is a Severity Level IV violation (Supplement 1) (482/96-18-03)

C. Techriical Specification 4.8.1.1.2.g.(6).(c) requires testing during shutdown to verify that all automatic diesel generator trips except those that remain during emergency operation be automatically bypassed upon loss of voltage on the emergency bus concurrent with a safety injection actuation signal, once per 18 months.

l l Contrary to the above, on July 23,1996, while the plant was at approximately 100 percent power, technicians performed Work Packages 114086 and 114087,

i. which accomplished a portion of the surveillance required by Technical

Specification 4.8.1.1.2.g.(6).(c).

9611130125 961107 "

PDR ADOCK 05000482 O PDR

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This is a Severity Level IV violation (Supplement 1) (482/9618-04)

D. Technical Specification 4.8.1.1.2.g.(6).(c) requires testing during shutdown to verify ,

that all automatic diesel generator trips except those that remain during emergency operation be automatically bypassed upon loss of voltage on the emergency bus concurrent with a safety injection actuation signal, once per 18 months.

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Contrary to the above, on July 23,1996, the licensee found that the required testing had not been performed for the volts per hertz relays which had been installed in the two emergency diesel generator control circuits during Refueling '

Outage Vill in February 1996.

This is a Severity Level IV violation (Supplement 1) (482/9618-07)

Pursuant to the provisions of 10 CFR 2.201, Wolf Creek Nuclear Operating Corporation is hereby required to submit a written statement or explanation to the U.S. Nuclear  ;

! Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a -

copy to the Regional Administrator, Region IV,611 Ryan Plaza Drive, Suite 400, Arlington, ^

l Texas 76011, and a copy to the NRC Resident inspector at the facility that _is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation l (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and l should include for each violation: (1) the reason for the violation, or, if contested, the

! basis for disputing the violation, (2) the corrective steps that have been taken and the ,

l results achieved, (3) the corrective steps that will be taken to avoid further violations, and i (4) the date when full compliance will be achieved. Your response may reference or l include previous docketed correspondence, if the correspondence adequately addresses the l

required response. If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should l l

not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the  :

response time. ,

l l Because your response will be placed in the NRC Public Document Room (PDR), to the l extent possible, it should not include any personal privacy, proprietary, or safeguards  ;

information so that it can be placed in the PDR without redaction. However,if you find it necessary to include such information, you should clearly indicate the specific information ,

that you desire not to be placed in the PDR, and provide the legal basis to support your

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request for withholding the information from the public. 1 l

L Dated at Arlington, Texas this 7th day of November 1996 d

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