ML20137A358
| ML20137A358 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 03/11/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20137A354 | List: |
| References | |
| 50-331-96-13, NUDOCS 9703200295 | |
| Download: ML20137A358 (2) | |
Text
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l IES Utilities Inc.
Docket No. 50-331
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Duane Arnold Energy Center License No. DPR-49 1
During an NRC inspection conducted on December 20,1996, through February 3,1997, 1
two violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," the violations are listed below:
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Duane Arnold Technical Specification 3.2.A, Table 3.2-A requires the Main Steam Line Radiation trip level setting to be.13x Normal Rated Power Background. The j
table requires a minimum of 2 (out of 2) operable channels per trip system. The action statement for less then 2 operable channels requires the channels to be j
restored within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and j
in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Contrary to the above, from November 24 to December 18,1996, with reactor power at approximately 100 percent rated power, the main steam line radiation monitors were set greater than 3x Normal Rated Power Background and appropriate actions were not taken. Specifically, the monitors were set at 1800 mR/hr while background radiation was typically 150 - 200 mR/hr.
This is a Severity Level IV violation (Supplement 1).
2.
Criterion XI of 10 CFR Part 50, Appendix B requires, in part, that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed in accordance with written test procedures which incorporate the requirements and acceptance limits contained in applicable design documents.
Contrary to the above, a.
From March 27 to December 30,1996, daily Surveillance Test Procedure (STP) 42D011, " Radiation Monitor Sensor Check," failed to incorporate correct acceptance limits for the offgas stack radiation hi-hi level alarm. As a result, technicians used an uncontrolled reference sheet which listed an outdated and incorrect value for the offgas stack radiation alarm.
b.
From October 25 to December 8,1996, STP 42A001, " Instrument Checks,"
failed to incorporate the correct acceptance limits. As a result, operators used incorrect acceptance limits when performing a daily surveillance of the emergency service water temperatures.
This is a Severity Level IV violation (Supplement 1).
9703200295 970311 PDR ADOCK 05000331 G
Notice of Violation Pursuant to the provisions of 10 CFR 2.201, Duane Arnold Energy Center is hereby
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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 U.S. Nuclear Regulatory Commission, Region l
lil,801 Warrenville Road, Lisle, Illinois 60532-4351, 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 steps that wil! be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your l
response may reference or include previously docketed correspondence, if the correspondence adequately addresses the required response. If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action es may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
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l Dated at Lisle, Illinois l
this 11th day of March 1997 l
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