ML20202G454

Notice of Violation from Insp on 971223-980204.Violations Noted:Between 960102 & 04,for Total of 58 Hours While Plant in Power Operating Conditions,Containment Isolation Valves CV5704B & CV5718B for Well Water Sys,Inoperable

ML20202G454
Person / Time
Site:	Duane Arnold
Issue date:	02/06/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20202G435	List: ML20202G428 ML20202G454 ML20202G473
References
50-331-98-02, 50-331-98-2, EA-98-003, EA-98-044, EA-98-3, EA-98-44, NUDOCS 9802200132
Download: ML20202G454 (3)

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NOTICE OF VIOLATION

- lE8 Utilities Inc. Docket No.: 50 331-Duane Amold Energy Center --- License No.: DPR-49 EA 98-003 EA 98-044 I During an NRC inspection conducted on December 23,1997, through February 4,1998, four-violations of NRC requirements were identified. In accordance with the " General Statement of =

= Policy and Procedure for NRC Enforcenient Actions," NUREG-1600, the violations are listed

below;

1. Technical Specification (TS) 3.7.B.1 requires, in part, that during power operating .

conditions, all primary containment isolation valves shall be operable'except as specified in TS 3.7.B.2.

Technical Specification 3.7.B.2 requires, in part, that with one or more primary l containment isolation valves inoporcbis, maintain at least one isolation valve operable in each affected penetration that is open.

Technical Specification 3.7.B.3 requires, in part, that if TS 3.7.B.1 and 3.7.B.2 cannot be 5 met, an orderly shutdown shall be initiated and the reactor shall be in at least hot I

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 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 />.

- a. Contrary to the above, between January 2 and January 4,1996, for a total of 58 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br /> while the plant was in power operating conditions, containment isolation Valves CV5704B and CV5718B for the well water system were inoperable, Specifically, safety-related air compressor 1K-4 was removed from service for '

maintenance, thereby rendering the two well water containment isolation valves, -

. one in each of two containment penetrations, inoperable. The licensee did not place the unit in hot shutdown within 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).

b. Contrary to the above, between January 28 and January 31,1997, for 91.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, while the plant was in power operating conditions, containment isolation Valves CV5704A and CV5718A for the well water system were inoperable. Specifically, safety-related air compressor 1K-3 was removed from service for maintenance, thereby rendering the well water containment isolation valves, one in each of two containment penetrations, inoperablec The licensee did not place the unit in hot shutdown within 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).

c. Contrary to the above, on April 15,1997, for 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />, while the plant was in power operating conditions, containment isolation Valves CV5704A and CV5718A for the well water system were inoperable. Specifically, safety-related air compressor 1K-3 was removed from service for maintenance, thereby rendering the two well water containment isolation valves, one in each of two containment 9802200132 900206 PDR ADOCK 05000331 O PDR '

Notice of Violation 2-penetrations, inoperable. The licensee did not place the unit in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, This is a Severity Level IV violation (Supplement 1).

2. 10 CFR 50.59 requires, in part, that a test or experiment not described in the safety analysis repor'. (SAR) may be performed, provided a written safety evaluation (SE) is performed which provides the bases for the determireation that the test or experiment does not involve an unreviewed safety question.

Contrary to the above, the licensee performed 100 percent load testing on the safety-related control building chiller on November 19,1997, a test not described in the SAR, and no SE was performed.

This is a Severity Level IV violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, Duane Amold Energy Center is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, WasHngton D.C. 20555 with a copy to the U.S. Nuclear Regulatory Commission, Region til,801 Warrenville Road, Lisle, Illinois 60532-4351, and a copy to the NRC Resident inspector at the Duane Amold Energy Center within 30 days of the date of the letter transmitting this Notice of Violation (Notice). Thh raply 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 or severity level, (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 be achieved. Your response may reference i

or include previously docketed correspondence,if the correspondence adequately addresses the required respense. 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 as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.

If you contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.

Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. If personal privacy, or proprietary informatbn is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information if you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwerranted invasion of personal privacy or provide the information required by

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Notice of Violation- 3-10 CFR 2.790(b) to support a request for withholding confidential commercial or financial - -

Information). If safeguards inforrnation is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.

Dated at Lisle, Illinois this 6th day of February 1998

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