ML20040E592

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Notice of Violation from Insp on 810926-1025
ML20040E592
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 11/24/1981
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20040E585 List:
References
50-259-81-32, 50-260-81-32, 50-296-81-32, NUDOCS 8202050151
Download: ML20040E592 (2)


Text

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APPENDIX A NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-259, 50-260 50-296 Browns Ferry 1, 2 and 3 License Nos. DPR-33, DPR-52 DPR-68 As a result of th? inspection conducted on September 26 - October 25, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7,1980),

the following violations were identified.

A.

10 CFR 50, Appendix B, Criterion V as implemented by TVA Topical Report 75-1, Table 17.2-5 requires that activities affecting quality shall be prescribed by documented instructions and procedures of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions or procedures.

Contrary to the above, the requirement that activities -affecting quality shall be prescribed by documented instructions or procedures and shall be accomplished in accordance with these instructions or procedures was not met, in that 1.

Tne Nuclear-Quality Assurance fianual (N-QAM) allows the shift engineer (SE)/ shift technician advisor (STA) to perform a review of emergency Trouble Reports (TRs) if the Quality Assurance (QA) staff is unavail-able; however, no documented instructions, procedures or formal training was provided to the SE/STA in how to perform a QA staff review of TRs.

2.

TVA Topical Report 17.2.1 and N-QAM 1.3.13 requires that the plant QA staff develop and implement a QC inspection or surveillance program.

This instruction was not adequately implemented in that from June 1981 to September 1981 approximately 50% of all surveys scheduled to be performed by Quality Control (QC) personnel were not performed.

This is a Severity Level IV Violation (Supplement I.D.I.)

B.

Technical Specification 3.5.F.2 requires that if the Reactor Core Isolation Cooling System (RCICS) is inoperable the High Pressure Coolant Injection System (HPCIS) shall be demonstrated operable immediately.

Contrary to the above, the requirement that HPCIS be demonstrated operable if RCICS is inoperable was not met, in that on September 1,1981, flow indicator controller (FIC-71-36A) for RCICS was removed for calibration without demonstrating HPCIS operable. The controller was removed for ap-proximately 10 minutes; however, operations personnel did not recognize that the RCIC system was inoperable, 8202050151 820121 PDR ADOCK 05000259 O

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Tennessee Valley Authority 2

Docket Nos. 50-259, 50-260 50-296 Brown Ferry 1, 2 and 3 License Nos. DPR-33, DPR-52 and DPR-68 This is a Severity Level IV Violation (Supplement I.D.2.).

This is applicable to Unit 2.

C.

10 CFR 50.72 requires that the licensee notify the NRC Operations Center within one hour by telephone of significant events including any event resulting in manual or automatic actuation of Engineered Safety Features, including the Reactor Protection System.

Contrary to the above, notification to NRC by telephone within one hour was not made on October 1,1981 when Unit I reactor was tripped by the Reactor Protection System during preparation for a main turbine over-speed trip test.

This is a Severity Level VI Violation (Supplement I.F.).

This is applicable to Unit 1.

Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including:

(1) admission or denial of the alleged viola-tions; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will be achieved.

Consideration may be given to extending your response time for good cause shown.

Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.

Date: NOV 2 41981 l

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