ML17334B802
| ML17334B802 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/30/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17334B801 | List: |
| References | |
| 50-315-98-12, 50-316-98-12, NUDOCS 9807070190 | |
| Download: ML17334B802 (4) | |
Text
NOTICE OF VIOLATION Indiana Michigan Power Company Docket No.: 50-315; 50-316 Donald C. Cook Nuclear Power Plant License No.: DPR-58; DPR-74 During an NRC inspection conducted from April28, 1998, to June 11, 1998, two violations of NRC 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 XVI, requires, in part, that measures shall be established to assure that conditions adverse to quality are promptly identiTied and corrected, and that in the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition.
Surveillance Procedure 02-OHP 4030.STP.030, "Dailyand Shiftly Surveillance Checks,"
Revision 24, required, in part, that with no reactor coolant pumps operating, reactor vessel level must be recorded every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or the reactor vessel head must be vented once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The failure to comply with the surveillance procedure could allow an undetected void to occur in the reactor vessel, a significant condition adverse to quality.
Contrary to the above, on May 5, 1998, the licensee identified that the measures taken to correct a significant condition adverse to quality, the failure to properly vent the primary system, were not effective to preclude repetition of a similar event that occurred on December 16, 1997. As a result, the licensee failed to vent the reactor system head every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after stopping all the primary coolant pumps on May 3, 1998, as required by Surveillance procedure 02-OHP 4030.STP.030, Revision 24.
This is a Severity Level IVviolation (Supplement 1).
10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings,"
requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
Instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
Contrary to the above, on June 1, 1998, the inspectors identified that an activity affecting quality, the loading of safety-related borated ice into bags for temporary storage prior to transfer into the ice condenser, was performed by a procedure (Job Order C0043828) of a type inappropriate to the circumstances.
The procedure for completing the ice loading was inappropriate to the circumstances in that it did not contain appropriate quantitative or qualitative acceptance criteria to ensure that the borated ice was free from the introduction of foreign material.
This is a Severity Level IVviolation (Supplement 1).
9807070190 980630 PDR ADOCK 050003i5 6
Pursuant to the provisions of 10 CFR 2.201, Indiana Michigan Power Company 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, and a copy to the NRC Resident Inspector at the facilitythat is the subject of this Notice, 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, ifcontested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that willbe taken to avoid further violations, and (4) the date when full compliance will be achieved.
Your response may reference or include previous docketed correspondence, ifthe correspondence adequately addresses the required response.
Ifan 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.
Ifyou 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 willbe 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.
Ifpersonal privacy or proprietary information 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. Ifyou 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 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). Ifsafeguards 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 30th day of June 1998
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