ML20140E831

Notice of Violation from Insp on 970406-0517.Violations Noted:Security Escorts Escorted More than Five Visitors Into Vital Areas W/O Specific Approval of Vice President of Plant Operations or Designee

ML20140E831
Person / Time
Site:	Wolf Creek
Issue date:	06/06/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20140E822	List: ML20140E818 ML20140E831 ML20140E851
References
50-482-97-09, 50-482-97-9, NUDOCS 9706120216
Download: ML20140E831 (3)

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ENCLOSURE 1 NOTICE OF VIOLATION i

Wolf Creek Nuclea Operating Corporation Docket No.: 50-482 Wolf Creek Generating Station License No.: NPF-42 During an NRC inspection conducted on April 6 through May 17,1997, five 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 6.8.1.a states, in part, that written procedures shall be I established and implemented covering the applicable procedures recommended in

, Appendix A of Regulatory Guide 1.33, Revision 2. j Regulatory Guide 1.33, Appendix A, Section 8.b, requires procedures for conducting surveillance tests listed in the Technical Specifications.

Following each containment entry, Technical Specification 4.5.2, Action c.2, requires a visualinspection of the affected areas in the containment to verify that no loose debris is present which could be transported to the containment sumps l and cause restriction of the pumps' suctions during a loss-of coolant condition.

4 Procedure STS EJ-001, " Containment inspection," Revision 9, Step 8.1.1, requires that the licensee verify by a visual inspection of all accessible areas that no loose  ;

d1bris is present in the containment.

Contrary to the above, between September 20,1996, and April 30,1997, the licensee failed to identify and remove debris from the containment.

This is a Severity LevelIV violation (Supplement 1)(50-482/9709-01).

B. 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 26C-004 requires operability determinations be documented in a log entry that includes a justification for the operability determination and completion of Form APF 26C-004-001.

Contrary to the above, on April 30,1997, the shift supervisor documented an operability determination for debris and other material found in containment without providing a justification for the operability determination and without completing Form APF 26C-004-OO1.

This is a Severity LevelIV violation (Supplement 1)(50-482/9609-0.3).

9706120216 970606 PDR ADOCK 05000482 O PDR

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l C. Technical Specification 3.6.3 states, in part, that containment isolation valves shall be operable and, with one or more containment isolation valves inoperable, the licensee must restore the valve to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, isolate the '

penetration, or be in hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Contrary to the above, on March 29,1996, the licensee entered Mode 4 with Containment isolation Valve EF HV0034 inoperable and operated in Mode 4 or higher until the penetration was isolated on October 9,1996.

This is a Severity Level IV violation (Supplement 1)(50-482/9704-04).

D. Technical Specification 6.8.1.a states, in part, that written procedures shall be established and implemented covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2.

Regulatory Guide 1.33, Appendix A, Section 2j, requires general plant operating procedures for hot standby to cold shutdown operations.

Contrary to the above, on February 11,1997, licensee personnel failed to properly establish Procedure GEN 00-006 in that it permitted operation of the normal charging pump with reactor coolant system temperature as low as 325 F, when engineering guidance in Design Change Package 04590 required that the normal charging pump be stopped and placed in pull-to-lock when the plant operated below 368 F.  ;

This is a Severity Level IV Violation (Supplement 1)(50-482/9709-06).

E. Technical Specification 6.8.1.c requires that written procedures be established, implemented, and maintained covering the implementation of the security plan.

The security plan is implemented, in part, by Security Procedure SEC 01-202,

" Personnel Access to Protected Area," Revision 31.

Security Procedure SEC 01-202, Step 6.5.2.6, requires the visitor-to-escort ratio to be no more than 10:1 in the protected area and 5:1 in the vital area, but may be increased on a case-by-case basis upon approval of the Vice President Plant Operations oi designee.

Contrary to the above, on May 8,1997, security escorts escorted more than five ,

visitors into vital areas without specific approval of the Vice President Plant Operations or designee.

This is a Severity Level IV Violation (Supplement 111)(50-482/9709-07).

j 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 Hegional 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 adequately addresses 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 proper 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 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 request for withholding the information from the public.

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Dated at Arlington, Texas I l

this 6th day of June 1997 i

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