ML20147E404

Notice of Violation from Insp on 970730-1212.Violation Noted:Cps Procedure 3509.01C001, Div 1 Nsps Bus Outage Checklist, Was Adequate in That Valve 1G33-F004 Returned to Svc Prior to Restoration of RWCU Pump Protection Logic

ML20147E404
Person / Time
Site:	Clinton
Issue date:	02/11/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20147E401	List: ML20147E397 ML20147E404 ML20147E407
References
50-461-96-09, 50-461-96-9, NUDOCS 9702180406
Download: ML20147E404 (4)

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NOTICE OF VIOLATION lilinois Power Docket No. 50-461 Clinton Power Station License No. NPF-62 During an NRC inspection conducted on July 30 through November 23,1996, violations of  !

NRC requirements were identified. In accordance with the " General Statement of Policy '

l and Procedure for NRC Enforcement Actions," 95 FR-1592, June 29,1995, the violations are listed below:

1. 10 CFR 50, Appendix B, Criterion V, requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of  ;

a type appropriate to the circumstances.

Contrary to the above, on October 30,1996, Clinton Power Station (CPS)  ;

Procedure 3509.01 COO 1, " Division i Nuclear System Protective System (NSPS) Bus i Outage Checklist," a procedure affecting quality, was inadequate in that valve 1G33-FOO4 was returned to service prior to restoration of reactor water cleanup pump protection logic, resulting in failure of the pump.

This is a Severity Level IV violation (Supplement 1).

2. Technical Specification (TS) 3.6.2.1.1 requires verification that suppression pool average temperature is within the applicable limits at a frequency of 5 minutes when performing testing which adds heat to the suppression pool.

CPS Procedure 9000.05, " Suppression Pool Temperature Log," required recording suppression pool temperature when performing testing which added heat to the suppression pool.

Contrary to the above, on July 11,1996, suppression pool temperature was not recorded every 5 minutes during Reactor Core Isolation Cooling System testing, an activity that added heat to the suppression pool.

This is a Severity Level IV violation (Supplement 1).

3. 10 CFR 50.54(l), " Conditions of Licenses," requires, in part, that the licensee shall designate individuals, licensed as senior operators pursuant to Part 55, to be responsible for directing the licensed activities of licensed operators.

10 CFR 55.53.(e), " Conditions of Licenses," requires in part, that to maintain active status, the licensee licensed operator shall actively perform the functions of an operator or senior operator on a minimum of seven 8-hour or five 12-hour shifts per calendar quarter.

10 CFR 55.4, " Definitions," defines actively performing the functions of an operator or senior operator to mean that an individual has a position on the shift crew that requires the individual to be licensed as defined in the facility's technical specifications, and that the individual carries out and is responsible for the duties covered by that position.

9702190406 970211 PDR ADOCK 05000461 0 PDR

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i Notice of Violation 10 CFR 55.53(f) requires, in part, that if paragraph 55.53(e) is not met then before ,

resumption of functions authorized by a license issued under this part an authorized  ;

representative of the facility licenses shall certify that the licensee has completed a  !

minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of shift functions under the direction of an operator or senior  ;

operator as appropriate and in the position to which the individual will be assigned.

Contrary to the above, during the second, third, and fourth quarter of 1996, the licensee designated individuals to be responsible for directing the licensed activities of licensed operators, had neither actively performed the required quarterly shifts nor completed a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of shift function under the direction of a senior operator.

This is a Severity Level IV violation (Supplement 1).

4. 10 CFR 50, Appendix B, Criterion XVI, requires, in part, that measures shall be established to assure that conditions adverse to quality are promptly identified and corrected.

Contrary to the above, conditions adverse to quality were not promptly corrected in tbst wors in safety tagging resulted in unintended isolation of power for security lighting on July 25, September 6, and September 29,1996.

This is a Severity Level IV violation (Supplement 1).

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! 5. 10 CFR 50, Appendix B, Criterion V, requires, in part, that activities affecting quality shall be accomplished in accordance with instructions, procedures, or drawings.

l Contrary to the above, on November 3,1996, while performing CPS 3882.01,

" Diesel Gene ~ator Overspeed Trip Test," an activity affecting quality, personnel

' performing the activity did not follow procedural steps 8.3.a and 8.3.i.

! This is a Severity Level IV violation (Supplement 1).

6. 10 CFR 50, Appendix B, Criterion XVI, requires, in part, that measures shall be i -. established to assure that conditions adverse to quality are promptly identified and l l corrected.

Contrary to the above, corrective actions to correct a lack of timeliness in performing use-history analyses (UHAs) identified in 1994, June 1995, January 1996, and August 1996 failed to correct the issue. Specifically, on October 25, i

1996,57 UHAs of measuring and test equipment had not been performed in a timely manner.

This is a Severity Level IV violation (Supplement 1). I i

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I Notice of Violation I 7. Technical Specification 5.4.1.a requires, in part, that procedures be implemented for activities recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978.

Regulatory Guide 1.33, Revision 2, Appendix A, Paragraph 7.e(4), requires that contamination controls be covered by procedures.

CPS Procedure 1024, " Contamination Control," required, in part that protective clothing was required for entry into contamination areas.

Contrary to the above, on October 3,1996, an individual failed to wear protective clothing when they crossed a contamination boundary while pushing a potentially contaminated laundry bag.

This is a Severity Level IV violation (Supplement 1).

8. Technical Specification 5.4.1.b, requires, in part, that written procedures shall be established, implemented and maintained covering the emergency operating  !

procedures (EOFs) required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1.

Contrary to the above, on Novernber 16,1996, it was identified that EOP-8,

" Secondary Containment Control," was not properly maintained in that it contained  !

errors in Table U that had not been corrected.

This is a Severity Level IV violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, Illinois Power Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region lil, 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 e 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 give to extending the response time. i

l Notice of Violation -4 Because the 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 POR without redaction. However, if it is necessary to include such information, it should clearly indicate the specific information

j. that should not be placed in the PDR, and provide the legal basis to support the request fer withholding the information from the public. j l

l j Dated at Lisle, Illinois this 11th day of February 1997 i

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