ML20216F984
| ML20216F984 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/03/1998 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20216F963 | List: |
| References | |
| 50-423-97-210, NUDOCS 9804170301 | |
| Download: ML20216F984 (3) | |
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NOTICE OF VIOLATION Northeast Nuclear Energy Company Docket No. 50 423 Millstone Nuclear Power Station License No. NPF-49 Unit 3 During an NRC inspection conducted on January 5 through 26 and January 26 through February 6,1998, several violations of NRC requirements were identified. In accordance with NUREG-1600, " General Statement of Policy and Procedure for NRC Enforcement Actions,"
these violations are listed below:
A. _ Technical Specification (TS) 6.8.1.a requires, in part, that written procedures, including system operating procedures, be ir, accordance with the applicable portions of Appendix A to Regulatory Guide (RG) 1.33, Revis)on 2, dated February 1978.
Contrary to the above, the following two examples were identified where the requirements of TS 6.8.1.a were not met.
- 1. Operating Procedure (OP) 3306, " Containment Recirculation Spray System," Revision 7, was inadequate. Specifically, the procedure allowed the opening of a recirculation spray system (RSS) pump inboard seal valve (s) (3RSS*V38 41), thereby, failing to maintain the RSS as required, a closed system outside of containment.
- 2. OP 3314A, " Auxiliary Building, Heating, Ventilation and Air Conditioning," Revision 21, was inadequate. Specifically, Steps 4.14 and 4.15 contains a note that allows manual operator action in place of the system designed automatic actuation and TS 3.0.3 was not to be entered.
This is a Severity Level IV violation (Supplement I).
B. 10 CFR Part 50, Appendix B, Criterion lit, requires, in part, that design control measures be provided for verifying or checking the adequacy of design.
Contrary to the above, certain measures for verifying the adequacy of the plant design were inadequate. Specifically,
- 1. The control circuitry for auxiliary building ventilation fans 3HVR*FN14A&B and 3HVR*13 A&B was designed such that the potential existed, that after the loss of electric power, the fans could fail to restart on restoration of electrical power.
- 2. The control circuitry for 3RSS*MOV38A&B as originally modified by design change DCR M3-97045 made the valves vulnerable to cycling if an input differential pressure signal should have failed low.
This is a Severity IV violation (Supplement 1).
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C. 10 CFR Part 50, Appendix B, Criterion XVI, requires, in part, that conditions adverse to.
quality are promptly identifed and corrected.
Contrary to the above, leaksge by valves in the fire protection system for Supplementary Leak Collection and Release (SLRCS) filter banks, 3HVR*FLT 3A&B, was not promptly corrected.
Specifically, despite having test results indicating leakage by the check valves in the fire protection system, the licensee did not correct the leakage or take other appropriate measures to assure leakage from the nonsafety system did not affect the function of the interfacing safety-related SLCRS charcoal filter banks.
This is a Severity Level IV violation (Supplement 1).
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Pursuant to the provisions of Title 10 of the Code of Federal Regulations (10 CFR), Section 2.201, Northeast Nuclear Energy Company (NNECO) 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 Director, Special Projects Office, and a copy to the NRC Resident inspector at Millstone within 30 days of the date of the letter
. transmitting this Notice of Violation (Notice). This reply should be clearty marked as a " Reply to a Notice of Violatien" 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) ?.a date when tuii 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, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
Under the authority of Section 182 of the Act,42 U.S.C. 2232, this response shall be submitted under oath or affirmation.
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 a bracketed copy of your response that identifies the information that should bs protected and a reda::ted copy of your response that deletes such information. If you request withholding of such material, you mWE1 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 l
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i create an unwarranted invasion of personal privacy or provide the information required by 10 i
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 Rockville, Maryland i
this 3* day of April,1998 1
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