ML20202E964

NOV from Insp on 971201-980120.Violation Noted:From 980108- 09,operators Failed to Initiate Actions within 1 H to Place Unit in Hot Shutdown When Both Unit 1 safety-related 4,160- Volt Buses Were Powered from Standby Emergency Power Supply

ML20202E964
Person / Time
Site:	Point Beach
Issue date:	02/10/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20202E939	List: ML20202E933 ML20202E964 ML20202E981
References
50-266-97-26, 50-301-97-26, NUDOCS 9802190095
Download: ML20202E964 (3)

Text

._ _

NOTICE OF VIOLATION Wisconsin Electric Power Company Docket Nos. 50 266;60 301 Point Beach Nuclear Plant Ucense Nos. DPR 24; DPR 27 During an NRC inspection conducted from December 1,1997, through January 20,1998, 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:

1. Technical Specification 15.3.0 B.

• Limited Conditions for Operation (LCO); General Considerations,' requires, in part, that in the event an LCO cannot be satisfied because of equipment failures or limitations beyond those specified in the

• permissible conditions" of the LCO, action shall be initiated within one hour to place the affected unit in hot shutdown within seven hours of entering this specification.

Technical Specification 15.3.7.A.1, " Aux!!iary Electrical Systems; Specifications," defines the electrical system LCO as requiring, in part, that both the normal power supply and a standby emergency power supply to all the safety related 4160/480 volt buses be operable, and that the buses be energized from their normal power supply.

Contrary to the above, from 7:04 p.m. on January 8,1998, through 12:44 a.m. on January 9,1998, operators failed to initiate actions within onu hour to place the Unit in hot shutdown when both Unit i safety related 4160 volt l'uses were powered from their standby emergency power supply, a limitation beyond those specified in the permissible conditions for the LCO.

This is a Severity Leven i violation (Supplement 1).

2. 10 CFR Part 50, Appendix 0, Criterion V,

• Instructions Procedures, and Drawings,"

requires, in part, that activilles affecting quality be prescribed by documented procedures of a type sopropriate to the circumstances.

Technical Specification 15.6.8.3,

• Plant Operating Procedures; Changes to Procedures,"

requires, in part, approval by the cognizant group head (duty shift superintendent in operations) and one of the duty and call superintendents for changes to procedures.

Contrary to the above, as of January 22,1998, OM (Operations Manual) 3.7,

• Emergency Operating Procedure Use and Adherence," Revision 4, a procedure prescribing activities affecting quality, was not appropriate to the circumstances. Specifically, Procedure OM 3.7 provided blanket authorization to change emergency and abnormal operating procedures by performing steps out of sequence, or by performing additional steps not specified in the procedures, without requiring approval by the cognizant group head and one of the duty and call superinte.idents.

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

3. 10 CFR Part 50, Appendix B, Criterion XI. " Test Control," requires, in part. that a test program be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed 9002190095 980210 PDR ADOCK 05000266 G PDR

Notice of Violation 2-l l

in accordance with written test procedures. Test procedures shallinclude provisions for assuring that adequate test instrumentation is available and used, and that the test is performed under suitable environmental conditions.

Contrary to the above, Test Procedure PC 56,

• Containment Accident Recirc Heat Exchanger Performance Monitoring Unit 2,* Part 2, Revision 5. performed for Unit 2 on December 20,1995, was not adequate to demonstrate that the 2HX 15D containment accident recirculation heat exchanger would perform satisfactorily in service.

Specifically, service water flow rate instrumentation accuracy and control of test conditions, including service water flow rate and temperature, were not adequate to ensure accurate test results.

This is a Severity Level IV violation (Supplement lj.

Pursuant to the provisions of 10 CFR 2.201, Wisconsin Electric 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 lit, and a copy to the NRC Resident inspector at the facility that is the subject of this Notice of Violation (Notice), within 30 days of the date of the letter transmitting this 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 or severity level; (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. For the third violation, the reason for the violation need not be discussed, but the issues discussed in the cover letter which forwards this Notice should be addressed. Your response may reference or include previous docketed correspondence, if the corres7ondence adequately addresses the required response. If an adequate replyis not received within the time spacified 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,

! If you contest this enforcement action, you should also provide a copy of your response to the Director, Offica of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.

Because your response will be placed in the NE eublic Document Room (PDR), to the extent possible, it should not include any persona' privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provido an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases foi your claim of withholding (e.g., explain why the disclosure of information will

,,,mium .

Notice of Violailon . 3 create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a requett for withholding confidential commercial or financial information), If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21, Dated at Lisle, Illinois this 10th day of February 1998 l

iei e. . . . . _ _ .