ML20247L245

Notice of Violation from Insp on 980308-0418.Violation Noted:Procedure 7.2.63 Was Inappropriate to Circumstances & Had No Appropriate Acceptance Criteria,In That Required Torque Value Not Given in Flange Bolt Work Instructions

ML20247L245
Person / Time
Site:	Cooper
Issue date:	05/15/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20247L227	List: ML20247L219 ML20247L245 ML20247L272
References
50-298-98-02, 50-298-98-2, NUDOCS 9805220350
Download: ML20247L245 (3)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION Nebraska Public Power District Docket No.: 50-298 Cooper Nuclear Station License No.: DPR 46 I

During an NRC inspection conducted on March 8 through April 18,1998, two 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:  !

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A. 10 CFR Part 50, Appendix B Criterion V, requires, in part, that activities affecting quality shall be prescribed by documented procedures and instructions of a type appropriate to the circumstances... Instructions, procedures shallinclude appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished...

Contrary to the above,

1. Procedure 7.2.63, "High Pressure Coolant injection Stop Valve Hydraulic Cylinder Maintenance," was inappropriate to the circumstances and did not have appropriate acceptance criteria, in that the required torque value was not given in work instructions for the flange bolts. The procedure directed the flange bolts be tightened as opposed to being fastened with the specific torque value. The bolts were tightened without acceptance criteria, leading ultimately to stripped threads and a control oil leak from the high pressure coolant injection turbine stop valve hydraulic actuator.

2. On February 11,1998, Procedure 7.0.15 " Station Painting Guidelines,"

Revision 3ci, was not appropriate to the circumstances, in that it did not appropriately control the application of water-based paint with volatile organics in '

the reactor building Procedure 7.0.15 allowed several gallons of paint to be

, drying in the reactor building which contained a significant fraction of ether-based and acrylate-based compounds. These compounds could degrade the standby gas treatment system.

3. Emergency Operating Procedure 2A , " Containment Control," listed reactor l vessel level parameters for when operators should depressurize the plant with ,

I the water level at top of active fuel and at a level in the fuel bundle to prevent exceeding 1800*F. The water level parameters were based on a level that was biased 6 inches in the nonconservative direction, as a result of an increase in fuel length.

This is a Severity Level IV violation (Supplement 1) (50-298/98002-02). '

9805220350 980515 PDR ADOCK 05000298 G PDR

B. 10 CFR Part 50, Appendix B, Criterion XVI, requires, in part, measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances, are promptly identified and corrected.

Contrary to the above,

1. The licensee stated in the response to the Notice of Violation for Violation 298/97006-01, as corrective action for a condition adverse to quality, that a review of Technical Specifications would be performed to identify all operability verifications required prior to a mode change, by September 2,1997, and that procedures would be revised by October 15,1997. On March 11,1998, the licensee identified that this review did not find that the average power range monitors had not been required by procedures to be tested within a week prior to placing the mode switch in the run position.

2. In response to Violation 298/94026-07, the licensee identified that improper changes were made to emergency operating procedures because no operations review was required, for modifications, before 1991. For this condition adverse to quality, the licensee's actions were not comprehensive in that they did not conduct reviews to determine if other procedures had been adversely affected by earlier modifications.

This is a Severity Level IV violation (Supplement 1)(50-298/98002-03).

Pursuant to the provisions of 10 CFR 2.201, Nebraska Public Power District 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, Texas 76011, and a copy to the NRC Resident inspector at the facility that it he 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 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. 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.

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

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3-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 i that it can be placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your l response that identifies the information that should be protected and a redacted copy of your response th:4 deletes such information. If you request withholding of such material, you_must l specifically identify the portions of your response that you seek to have withheld and provide in l detail the bases for your claim of withholding (e.g., explain why the disclosure of information will l create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request 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.

I Dated at Arlington, Texas this 15th day of May 1998 l

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