ML20247B731

Notice of Violation from Insp on 881201-31.Violations Noted: Failure to Ensure RCIC Sys Operability & Failure to Secure Very High Radiation Area Access Door

ML20247B731
Person / Time
Site:	River Bend
Issue date:	03/17/1989
From:	Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
References
EA-89-010, EA-89-10, NUDOCS 8903300020
Download: ML20247B731 (3)

Text

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.e APPENDIX NOTICE OF VIOLATION L

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L Gulf States Utilities- (GSU) Docket: 50-458--

F -River Bend Station (RBS) License: NPF-47' St. Francisville, Louisiana :EA 89-10 During an.NRC inspection conducted December 1-31, 1988, two violations'of NRC

. requirements were-identified. The violations involved failure to ensure reactor core isolation cooling -(RCIC) system operability and failure to secure.a.very

,, 'high- radiation area (VHRA) access' door. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions,".10 CFR Part 2 Appendix.C.(1988),theviolationsarelistedbelow:

A. Failure to Ensure RCIC System Operability

'RBS' Technical Specifications (TS) Limiting Condition for'.

Operation (LCO) 3.4.7.3 requires that the reactor core isolation '

cooling (RCIC) system be operable in Operational Conditions 1, 2, and 3 with' reactor steam dome pressure greater than 150 psig.

Contrary to the above,- RBS was operated in Operational Conditions 1, 2, and 3 during the period November 1985 to December 19,-1988, with the RCIC

. system inoperable. The RCIC system was considered inoperable because the turbine configuration was not in accordance with the seismically tested design configuration.

This is a Severity Level IV violation. (Supplements)(458/8826-01)

B. Failure'to Secure a VHRA Access Door RBS TS 6.12. 2' requires that accessible areas with radiation levels, such that a major portion of the body could receive'in I hour a dose greater than 1000 mrem, shall be'provided with locked' doors to prevent unauthorized entry and the keys shall be maintained under the administrative control-of the Control Operating Foreman on duty and/or the radiation protection supervisor. Doors shall remain locked, except during periods of access under an approved radiation work procedure (RWP)-that specifies the dose-rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

Radiation Protection Procedure RPP-0005, " Posting of Radiologically Controlled Areas " Revision 5, paragraph 7.4, requires that VHRA entrances be locked and remain locked, except during periods of access under an approved RWP. Doors must be locked or attended at all times.

Contrary to the above, on December 3, 1988, from approximately 7:45 a.m.

to 4:30 p.m. (CST), turbine building Door TB 123-20, which provided access to a VHRA around the moisture separator reheater tank, was not properly secured. TB 123-20'was not attended during the period the door was left 89033o002o 890317 /

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2 unsecured. Seven additional examples of events where VHRA access doors j were previously left unsecured are identified in NRC Inspection j Report 50-458/88-26.

This is a Severity Level IV violation. (Supplements)(458/8826-02)

C. 10 CFP 50.73 requires licensees to submit licensee event reports (LERs) to NRC within 30 days of the discovery of events which are described in this regulation. Among the events licensees are required to report is "Any operation or condition prohibited by the plant's Technical Specifications . . . ."

RBS TS 6.12.2, "High Radiation Area," states that, " areas with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose greater than 1000 mrem shall be provided with locked doors . . ." and that the, " doors shall remain locked except during periods of access under an approved RWP . . . ."

Contrary to the above, on at least seven occasions between June 1987 and Dacember 1988, doors to VHRAs were found unlocked, a condition prohibited by the plant's TS, and LERs were not submitted to NRC within 30 days of the discovery of these events.

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

Pursuant to the provisions of 10 CFR 2.201, Gulf States Utilities 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; the NRC Resident Inspector; and the Director, Office of Enforcement, within 30 days of the date of the letter transmitting this 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 if admitted, (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 l 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.

I FOR THE NUCLEAR REGULATORY COMMISSION P

f Robert D. Martin Regional Administrator 1

Dated this at Arlington, Texag,1989 day of g g L__--_

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