ML20236R811
| ML20236R811 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 07/16/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20236R805 | List: |
| References | |
| 50-440-98-11, NUDOCS 9807220291 | |
| Download: ML20236R811 (2) | |
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4 NOTICE OF VIOLATION Centerior Service Company Docket No. 50-440 Perry Nuclear Power Plant License No. NPF-58 l
During an NRC inspection conducted on May 18 - 22,1998, two violations of NRC l
requirements were identified in accordance with " 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 lil, " Design Control" states, in part, that measures shall be established to assure that applicable regulatory requirements and the design basis, are correctly translated into specifications, drawings, proesdures, and instructions. These measures shall include provisions to assure that appropriate quality standards are specified and included in design documents and that deviations from such standards are controlled. The design control measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews.
Contrary to the above, calculation PRDC-0007, " Voltage Drop of DC Control Circuits,"
l-Rev. 4, dated May 18,1998, did not correctly translate the design basis in regard to the l
design inputs and conclusions. Examples included the following design basis L
deficiencies: (1) inverter DC current input was not calculated properly (effect of lower battery voltage and lower efficiency due to lower loading was not considered), (2) the battery terminal voltage calculation did not consider the effect of aging factor, temperature correcuon facict, and design margins, and (3) non-conservative control circuit cable lengths were used in the calculation. In addition, design control measures to provide verification of adequacy of design were ineffective in that design reviews failed to identify these deficiencies.
Thi is a Severity Level IV violation (Supplement 1).
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2.
10 CFR Part 50, Appendix B, Criterion XI, " Test Control," requires, in part, that a test I
program be established to assure that all testing required to demonstrate that structures, systems and components will perform satisfactorily in service is identified
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and performed in accordance with written test procedures which incorporate the L
requirements and acceptance limits contained in applicable design documents. Test procedures shall include provisions for assuring that all prerequisites for the given test have been met. Test results shall be documented and evaluated to assure that test requirements have been met.
Contrary to the above, as of May 20,1998, the as-tested instantaneous trip function of circuit breaker EF1804 used for emergency closed cooling pump motor 1P42C001 A, was inadequate. Specifically, the instantaneous trip function of circuit breaker EF1B04 L
was tested on November 10,1994, for instantaneous pickup value at 2270 amps instead of the upper limit acceptance criteria value of 2160 amps. Consequently, performance of the breaker trip device was' questionable and circuit protection and coordination could have been affected.
9907220291 990716 POR ADOCK 05000440 G
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Pursuant to the provisions of 10 CFR 2.201, Centerior Service Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, l
ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region ill, and a copy to the NRC Resident inspector at the facility that 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, 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 will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or include previous 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 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.
Bocause your response will be placed in the NRC Pubiic 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 infonnation 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 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 safeguaros 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 16th day of July 1998 i
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