ML16342C623

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Notice of Violation from Insp on 940228-0308.Violation Noted:Ccw HX 1-2 Failed to Demonstrate Ability to Remove Design Basis Heat Load as Documented in Field Test Rept
ML16342C623
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 07/14/1994
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML16342C622 List:
References
50-275-94-08, 50-275-94-8, 50-323-94-08, 50-323-94-8, NUDOCS 9407190071
Download: ML16342C623 (4)


Text

NOTICE OF VIOLATION Pacific Gas and Electric Company Diablo Canyon Nuclear Plant Dockets:

50-275, 50-323 Licenses:

DPR-80, DPR-82 EA 94-056 (I

During an NRC inspection conducted on February 28, March 1, and March 8,

1994, a violation of NRC requirements was identified.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"

10 CFR Part 2, Appendix C, the particular violation is set forth below:

10 CFR Part 50, Appendix B, Criterion XVI, "Corrective Action," states, in part, that measures shall be established to assure that conditions adverse to quality, such as failures and nonconformances are promptly identified and corrected.

In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition.

Contrary to the above, during a test conducted on February 2,

1991, Component Cooling Water (CCW) Heat Exchanger 1-2 failed to demonstrate the ability to remove the design basis heat load, as documented in Field Test Report 420DC-91. 1156, and the measures established by the licensee did not assure that this significant condition adverse to quality-was promptly corrected or that the cause of the condition was determined.

Despite this condition being recognized in the above referenced Field Test Report dated November 22, 1991, in Action Request No. A0306715 dated May 10,

1993, and in Quality Assurance report SQA-93-0031 dated July 28,
1993, the licensee did not take prompt action to correct this condition, to assess the impact of fouling on heat exchanger performance or to determine the significance of this condition with respect to the operability of the Auxiliary Saltwater System (ASW).

This is a Severity Level III violation (Supplement I).

Pursuant to the provisions of 10 CFR 2.201, Pacific Gas and Electric Company 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 copies to the Regional Administrator, Region IV, and the Director, Walnut Creek Field Office, Region IV, and a copy to the NRC Resident Inspector at Diablo Canyon, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).

This reply shou'ld 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.

If an adequate reply is not received within the time specified in this Notice, an order or a

Demand for Information may be issued to show cause why the license should not be modified, suspended, or revoked, or why such other action as may 9407i9007i 9407i4 PDR ADOCK 05000275 8

PDR

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be proper should not be taken.

Where good cause is shown, consideration will be given to extending the response time.

Under the authority of Section 182

'f the Act, 42 U.S.C.

2232, this response shall be submitted under oath or

,affirmation.

Dated at Arlington, Texas this 14th day of July 1994

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