ML20217E672

Notice of Violation from Insp on 970630-0718.Violation Noted:Safety Audit & Review Committee Composition Meeting Was Conducted W/O Senior Vice President as Chairperson & Quarterly Inservice Was Performed W/Valve Stroke Open

ML20217E672
Person / Time
Site:	Fort Calhoun
Issue date:	10/02/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20217E658	List: IR 05000285/1997013 ML20217E654 ML20217E672
References
50-285-97-13, NUDOCS 9710070127
Download: ML20217E672 (3)

Text

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s r EILCl.OSURE 1 i

l l NOTICE OF VIOL ? TION

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l Omaha Public Power District Docket No.: 50-285 Fort Calhoun Station License No.: DPR-40 During an NRC inspection conducted on June 30 through July 18,1997, three 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 5.5.2.2 requires, in part, that the safety audit and review committee composition shall have a senior vice president as the chairporson.

Contrary w the above, the licensee was conducting safety audit and review committee meetings since January 17,1997, without the senior vice president as the chairperson.

This is a Severity Level IV violation (Supplement 1)(285/97013 01).

B. 10 CFR Part 50, Appendix B, Criterion XI, states, in part, that "[al test program shall be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisf actorily inservice is identified and performed in accordance with written test procedures, which incorporate the requirements and acceptance limits contained in applicable design documents."

Contrary to the above, the established test program did not demonstrate that the component cooling water outlet valves from the component cooling water / raw water heat exchanger (HCV-489B/4908/491B/4928) would perform satisf actorily in service. The quarterly inservice test was performed in a manner such that the outlet valve was alwavs stroked open and closed immediately prior to the timed opening stroke test. This preconditioning of the valve prior to its stroke test precluded an accurate assessment of its initial o' ning capability. -

This is a Severity Level IV violation (Supplement I) (50-285/9713-02).

C. 10 CFR Part 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings,"

states that " activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circemstances and shall be accomplished in accordance with these instructions, procedures, or drawings."

Procedure SO-R-2, " Condition Report and Corrective Action," Revision 4, requires origination of a condition report for the following:

1 9710070127 971002 )

PDR ADOCK 05000285 i G PDR l

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" . . . equipment related events, documentation deficiencies, non-routine outside agency notifications, operational events, testing deficiencies, security infractions, human performance errors, personnel safety issues, radiological occurrences, or other circumstances which impact or potentially impact safe /or reliable operation of Fort Calhoun Station . . . . "

Contrary to the above, the licrt.sae failed to originate a condition report for the following licensee-identified dt, ciencies:

(1) Procedures S0-G 21, "Moef' .ation Control," Revision 62, and PED gel-56,

" Configuration Change Cic.e out," Revision 4, contained deficiencies that could potentially impact the cafe operation of the plant. These procedures allowed design documentatict to ha inconsistent with field installations for an extended period of time.

(2) The 4 way solenoid for Valve FCV 1904C had been replaced with a different l

model valve during or af ter the original plant startup, but no engineering change notice or drawing change had been processed to document the change.

This is a Severity Level IV violation (Supplement l} (50 285/9713-04).

For Violation A, the NRC has concluded, that information regarding the reason for the violation, the corrective actions taken and planned to correct the violation and prevent recurrence, and the date when full compliance will be achieved, is already adequately addressed in the enclosed report. However, you are required to submit a written statement or explanation pursuant to 10 CFR 2.201,if the description therein does not accurately reflect your corrective actions or your position. In that case, or if you choose to respond, clearly mark your response as a " Reply to a Notice of Violation," and send it 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).

For Violations B and C, pursuant to the provisions of 10 CFR 2.201, Omaha 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 inspec-tor 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 es 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,

9 3-(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 da' 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.

Dated at Arlington, Texas this 2nd day of October 1997 i

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