ML20046D087
| ML20046D087 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 08/06/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20046D083 | List: |
| References | |
| 50-331-93-13, EA-93-187, NUDOCS 9308160115 | |
| Download: ML20046D087 (2) | |
Text
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-i Iowa Electric Light and Power Company Docket No.
50-331 Duane Arnold Energy Center License No DPR-49 EA 93-187 i
During NRC inspections conducted on May 22 through July 7, 1993, and on July 22, 1993, 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, the violations are listed below:
i 1.
Technical specification 3.5.G.1 requires, in part, that during any I
period when one diesel generator is inoperable, continued reactor i
operation is permissible only during the succeeding 7 days,'unless that diesel generator is made operable sooner.
If this requirement cannot be met, an orderly shutdown shall be initiated, and the reactor shall be ir at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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Contrary to the above, on or about May 12, 1993, the "A" diesel generator became inoperable, was not restored to an operable condition l
within 7 days, and the reactor was not taken to hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This is a Severity Level IV violation (Supplement 1).
i (50-331/93013-01(DRP))
i 2.
Technical specification 6.8.1 requires, in part, that written i
procedures, including surveillance and testing requirements of equipment t
that cot'1d have an effect on the nuclear safety of the f acility, be implemented.
i a.
Surveillance Test Procedure (STP) BS-5, " Control Room Panel Shift Check List," a written procedure covering surveillance and testing requirements of equipment that could have an effect on the nuclear
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safety of the facility, requires that a control room operator check and record the status of plant equipment, and indicate those components not in their desired position.
Contrary to the above, on June 29, 1993, the midnight shift control room operator failed to properly check the status of the "B" core spray inboard isolation valve, and did not indicate that the circuit breaker for the valve was not in the desired position during the performance of, and as required by STP BS-5.
b.
Surveillance Test Procedure 4SA007, " Core Spray System Simulated Automatic Actuation," a written procedure covering surveillance and testing requirements of equipment that could have an effect or.
the nuclear safety of the facility, requires, in part, that all steps within section 7.2 be performed in sequence, and that all steps be carried through to completion.
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Contrary to the above, on July 22, 1993, Step 7.2.19 of STP 45A007-was completed out of sequence, and before step 7.2.18 was completed.
This is a Severity Level IV violation (Supplement 1).
(50-331/93013-02(DRP))-
Pursuant to the provisions of 10 CFR 2.201. Duane Arnold Energy. Center 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 III, 799 Roosevelt Road, Glen Ellyn, Illinois ~ 60137, and a copy to the NRC Resident Inspector at the Duane Arnold Energy Center, within 30 days of the date of the letter transmitting this Notice of Violation (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, or, if contested, the basis-for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective s:eps 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 i
action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending tne response time.
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LO%&s_. L A Dated at Glen Ellyn, Illinois Edward G. Greenmint-Oirector this 54 day of August, 1993 1 Division of Reactor Projects o
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