ML20236V697
| ML20236V697 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 07/28/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20236V685 | List: |
| References | |
| 50-331-98-08, 50-331-98-8, NUDOCS 9808040146 | |
| Download: ML20236V697 (3) | |
Text
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Alliant, IES Utilities Inc.
Docket No.: 50-331 Duane Amold Energy Center License No.: DPR-49 l
During an NRC inspection conducted on April 29 through June 9,1998, three violations of NRC I
requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
1, 10 CFR Part 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings,"
states, in part, that " Activities affecting quality shall be prescribed by documented j
instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings."
Integrated Plant Operating Instruction (IPOI) 7, Revision 51, "Special Operations,", " Primary Containment Closeout," Step 4(e), requires the licensee to verify that the drywell general area is free of trash, tools, and loose articles.
Contrary to the above, on May 13,1998, the licensee conducted a primary containment closeout inspection, an activity affecting quality, and failed to verify that the drywell general area was free of trash and tools. On May 13, after the licensee conducted its primary containment closeout inspection in accordance with IPOl 7, the inspectors found trash and a toolin the drywell general area consisting of tape rolled into balls, exposed fibrous insulation on a section of drywell cooling piping, tie-wrap pieces, nails, glass, sheet metal screws, wiring used to fasten insulation covers, and a carpenter's ruler.
This is a Severity Level IV violation (Supplement 1).
2.
Technical Specification 6.8.1.5 requires that written procedures involving nuclear safety, 1
including applicable check-off lists and instructions, covering preventive and corrective maintenance operations which could have an effect on the nuclear safety of the facility, be implemented and maintained.
Management Directive 24, Revision 12, " Post Maintenance Testing Program,"
l Step 5.0(1), requires that post-maintenance testing be performed, if appropriate, following corrective maintenance on components, regardless of quality level, to verify the ability of the system or component to perform its intended function.
Contrary to the above, on December 16,1997, adequate post-maintenance testing was not performed following corrective maintenance on the primary containment isolation system (PCIS) Group i reQay (A718-K057) for the recirculation sample line outboard isolation valve. Specifically, on April 3,1998, the relay failed to perform its intended function when an inadvertent PCIS Group I isolation signal was received. The failure was the result of mechanical binding caused by improper retainer replacement during corrective maintenance and relay reassembly on December 16,1997, i
This is a Severity Level IV violation (supplement 1).
f 9808040146 980728 7
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Notice of Violation i 3.
10 CFR 50.73(a)(2)(ii)(B) requires, in part, that the licensee report any event or condition that resulted in the nuclear power plant being in a condition that was outside the design basis of the plant within 30 days after discovery of the event or condition.
The Updated Final Safety Analysis Report, Section 3.6.1.2.4.5, in describing the compartment pressure analysis model stated, "The analyses conducted yielded pressure versus time relationships that were used to determine if the structures surrounding the affected compartments or vital equipment within the compartments were capable of withstanding the pressurization. In all the cases the analyses indicated that sufficient vent area was available to prevent over pressurization."
Contrary to the above, on May 5,1998, the licensee discovered that the high pressure coolant injection system compartment wall, a structure surrounding the affected compartment, was not capable of withstanding the pressurization due to a high energy line break in the high pressure coolant injection system room. This condition was outside the design basis as described in the Updated Final Safety Analysis Report. As of June 5, a licensee event report had not been submitted.
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:
I Document Control Desk, Washington D.C. 20555 with a copy to the U.S. Nuclear Regulatory Commission, Region Ill,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 (Netice). 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 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 I
required response. If an adequate reply is not received within the time.specified in this Notice, i
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 l
Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, j
DC 20555-0001.
I Because your response will be placed in the NRC Public Document Room (PDR), to the extsnt I
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 information is i
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 j
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Notice of Violation 3-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 unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at Lisle, Illinois this 28th day of July 1998 l
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