ML18153C670

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Notice of Violation from Insp on 910512-0608.Violation Noted:Failure to Prescribe Activities Affecting Quality by Adequate Instructions &/Or Procedures & Failure to Identify Conditions Adverse to Quality Re Reccurrence of Events
ML18153C670
Person / Time
Site: 05000218, Surry
Issue date: 07/08/1991
From: Sinkule M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18152A108 List:
References
50-280-91-14, 50-281-91-14, NUDOCS 9107160223
Download: ML18153C670 (2)


Text

.e ENCLOSURE 1 NOTICE OF VIOLATION Virginia Electric and Power Co.

Surry Units 1 and 2 Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37 During an NRC inspection conducted on May 12 - June 8, 1991, violations of NRC requirements were identified.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1991), the violations are listed below:

A.

10 CFR 50, Appendix B, Criterion V, as implemented by Operational Quality Assurance Program Topical Report (VEP l-5A, Section 17.2.5), requires, in part, that activities affecting quality be prescribed by documented instructions or procedures appropriate to the circumstanses.

B.

Contrary to the above, activities affecting quality were not prescribed by adequate instructions and/or procedures, as evidenced by the following examples:

1.

Technical Specification 3.11, Radioactive Gas Storage, was revised on April 17, 1991 and then implemented without providing instructions on how to accomplish the required actions.

This resulted, on May 24, 1991, in the failure to immediately reduce the oxygen concentration in the A waste gas decay tank as required by Technical Specification 3.11.A.1.b.

2.

Use of a turbine load limiter as described in Section 14.2.8 of the UFSAR, was not incorporated into station procedures.* This contri-buted to a June 6, 1991, Unit 1 power increase to 103 percent, which exceeded licensed power limits due to improper setting of the turbine load limiter.

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

10 CFR 50, Appendix B, Criterion XVI, as implemented by Operational

  • Quality Assurance Program Topical Report (VEP 1-5A, Section 17.2.16),

requires, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, and defective equipment are promptly identified and corrected.

Contrary to the above, conditions adverse to quality associated with the reoccurrence of seal head tank Tow level alanns on Unit 1 outside recirculation spray pump 1-RS-P-2A and Unit 2 low head safety injection pump 2-SI-P-lA were not promptly identified and corrected. This condition was identified on or before February 1990 and had not been corrected as of June 6, 19.91.

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

9107160223 910708 PDR ADOCK 05000280 Q

PDR

e Virginia Electric and Power Co.

Surry Units 1 and 2 2

e Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37 NRC Resident Inspector within 30 days of the date of the letter transmitting this Notice of Violation (Notice).

This reply should be clearly marked as a 11Reply to a Notice of Violation 11 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 which.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 may be issued to show cause 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.

Under the authority of Section 182 of the Act, 42 U.S.C. 2232, this *response shall be submitted under oath or affirmation.

Dated at Atlanta, Georgia this ~ay of July 1991 FOR THE NUCLEAR REGULATORY COMMISSION Marvin V. Sinkule, Chief Reactor Projects Branch 2 Division of Reactor Projects l