ML20199K296

Notice of Violation from Insp on 970922-1102.Violation Noted:Operators Used Markings on Drawing EID0003 as Operator Aid W/O Documented Approval of Shift Supervisor & Root Valves Indicated on Attachment C Were Operated

ML20199K296
Person / Time
Site:	Wolf Creek
Issue date:	11/25/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20199K273	List: IR 05000482/1997019 ML20199K266 ML20199K296
References
50-482-97-19, NUDOCS 9712010074
Download: ML20199K296 (3)

Text

l 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 inspectior, conducted on September 22 through November 2,1997, five j violations of tMC readrements were identified. In accordance with the " General i Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600, the violations are listed below:

A. _ Criterion V of Appendix B to 10 CFR Part 50 requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, and ,

drawings appropriate to the circumstances, and shall be accomplished in accordance with these instructions, procedures, or drawings.

Procedure AP 210 003, " Control of Information Tagging," Revision 1, Step 6.6.10, requires operator aids to be approved and documented by the shift supervisor.

Centrary to the above, from October G notil October 22,1997, operators used markings on Drawing eld 0003 as an of.erator aid without documented approval of the shift supervisor.

This is a Severity Level IV violation (Supplement II (50-482/9719 01).

B. Technical Specification 6.8.1.a requires, in part, that written procedures be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

Regulatory Guide 1,33, Revision 2, February 1978, Section 8, recommends, in part, that procedures be established for surveillance tests.

Surveillance Procedure STS MT-008, " Main Steam Safety Valve Settings,"

Revision 8, Section 4.3, requires the test performers to not operate the root valves indicated on Attachment C.

Contrary to the above, on September 30,1997, the test performers closed then reopened Valve AB V0028, the instrument root valve indicated on Attachment C of Piocedure STS MT-008, causing an inadvertent opening of Valve AB PV0003,

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atmospheric relief valve for Steam Line C.

This is a Severity Level IV violation (St oplement II (50-482/9719-03),

C. Technical Specification 6.8.1.a requires, in part, that written procedures be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

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6 2-Regulatory Guide 1.33, Revision 2, February 1978, Section 9c, recommends, in part, that procedures be established for replacement of important filters.

Procedure MCM M7230 01, "NSSS Filter Changeout," Revision 9, Section 8.4, requires maintenance personnel to reinstall the hatch cover over the equipment compartment as part of the restoration.

Contrary to the above, on October 12,1997, maintenance personnel signed for the completion of Procedure MCM M7230 01 following the replacement of the filter cartridge without reinstalling the equipment hatch cover. The failure to re place the hatch cover resulted in the area near the fi%r to be accessible as radiation levels increased to 3 Rem per hour 12 inches from the filter housing after operritors returned the filter to service.

This is a Severity Level IV violation (Supplement 1)(50 482/9719 04).

D. Technical Specification 6.11 requires, in part, that radiation workers adhere to procedures for personnel radiation protection consistent with the requirements of 10 CFR Part 20.

Administrative Procedure AP 25A 001, " Radiation Protection Manual," Revision 2, Section 6.7.4, requires that access to the RCA tradiologically controlled areal be controlled by an approved RWP tradiation work permit).

Contrary to the above:

a. On October 5,1997, a mechanic accessed the radiologically controlled area using Radiation Work Permit 970009 and used an internally contaminated gauge while performing work in the radiologically controlled area, an activity prohibited by this radiation work permit,

b. On October 10,1997, a radiation worker exited the radiologically controlled area and logged out of Radiation Work Permit 972601. The worker subsequently reentered the radiologically controlled area without logging onto a radiation work permit and without obtaining any dosimetry,

c. - On October 26,1997, a radiation worker entered containment without an alarming dosimeter as required by Radiation Work Permit 970034.

o. On October 27,1997,'a radiation worker entered the radiologically controlled area without the thermoluminescent dosimeter required by Radiation Work Permit 970009.

This is a Severity Level IV violation (Supplement IV) (50 482/9719 05).

l 3-E. Criterion V of Appendix 8 to 10 CFR Part 50 requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, and drawings appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.

Administrative Procedure AP 28A-001,

• Performance Improvement Request,"

Revision 8, Step 6.11.1, requires that an effectiveness followup review be performed for all Significance levelI and 11 performance improvement requests.

Contrary to the above, on October 22,1997, effectiveness followup reviews were not performed for Performance improvement Requests 96-2966 and 2989. Both were Significance level ll performance improvement requests.

This is a Severity LevelIV violation (Supplement I)(50-482/9719 02).

Pursuant to the provisions of 10 CFR 2.201, Wolf Creek Nuclear Operating Corporation is hareby 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, 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 (Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and 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 results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or include previous docketed correspondence, if the correspondence adequate;y ddresses the 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 not be modified, suspended, or revoked, or why such other action as may be proner should not be taken. Where good cause is shown, consideration will be given to extending the response time.

Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it shotid 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 request for withholding the information from the public.

Dated at Arlington, Texas this 25th' day of November 1997

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