ML20216J394
| ML20216J394 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/14/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20216J390 | List: |
| References | |
| 50-317-98-80, 50-318-98-80, NUDOCS 9804210373 | |
| Download: ML20216J394 (2) | |
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NOTICE OF VIOLATION Baltimore Gas and Electric Docket No.: 50-317/318 Calvert Cliffs Nuclear Power Station i cense No.: DPR- 53/59 I
During an NRC inspection conducted on January 12-30,1998, violations of NRC l requirements were identified in accordanco with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600,the violation is listed below:
- 1. 10 CFR Part 50, Appendix B, Criterion XI, " Test Control," requires written test l procedures which incorporate acceptance limits contained in applicable design documents.
Contrary to the above, a post modification procedure, ETP 017, Rev. O, DGP 1 A Battery Pre-operational Test, dated June 16,1995, failed to incorporate an appropriate acceptance criterion for the battery service test. The acceptance i criteria, in the form of a test shutdown criterion at 111 volts, had no basis in any I design document. The battery test acceptance critoria failed to consider the minimum battery terminal voltage used to determine the acceptable operation of safety-related dc equipment as documented in calculation D-E-92-002, Rev.1, dated March 7,1995, as 117.6 volts.
This is a Severity Level IV violation (Supplement 1).
- 2. 10 CFR 50, Appendix B, Criterion XVI, Corrective Actions requires in part:
" Measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected."
Contrary to the above, between December 29,1997, and January 12,1998, two problems with the speed switch of emergency diesel generator 2B, which affected safety functions and operability, were identified but were not properly resolved and corrected. On December 29,1997, the local speed indicator (tachometer) for emergency diesel generator 2B failed to zero (0) while the engine was running at 900 RPM, but BG&E failed to identify the cause and correct the problem and improperly declared the diesel generator operable. Furthermore, following post maintenance testing on January 12,1998, BG&E failed to identify and correct problems with a failed speed switch which caused the diesel to be declared inoperable.
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Baltimore Gas and Electric 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 I, 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 9804210373 980414 PDR ADOCK 05000317 G PDR ,
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Notice of Violation 2 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 I; specified in this Notice, an order or a Demand for information may be issued as to why the j license should not be modified, suspended, or revoked, or why such other action as may i be proper should not be taken. Where good cause is shown, consideration will be given to l 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.
l 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 information is necessary to provide an acceptable response, then please provide I a bracketed copy of your response that identifies the information that should be protected l- and a redacted copy of your response that deletes such information. If you request l withholding of such material, you muft specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withhold-ing (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
!s information is necessary to provide an acceptable response, please provide the level of l protection described in 10 CFR 73.21.
i Dated at King of Prussia, Pennsylvania
- this 14th day of April,'1998 l
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