ML20248E595

Notice of Violation from Insp on 980101-0228.Violation Noted:On 980225,NRC Determined That Written Equipment Control Procedures Were Not Established to Process Revs to Sys Valve Lineups

ML20248E595
Person / Time
Site:	Millstone
Issue date:	05/26/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20248E588	List: ML20248E584 ML20248E595 ML20248E613
References
50-245-98-206, 50-423-98-206, NUDOCS 9806030377
Download: ML20248E595 (3)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION Northeast Nuclear Energy Company Docket Nos: 50-245; 50-423 Millstone Nuclear Power Station License Nos: DPR-21; NFP-49 Units 1 and 3 During an NRC inspection conducted on January 1,1998, through February 28,1998, violatians 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:

A. Technical Specification 6.8.1.a requires that written procedures be established, implemented and maintained covering the activities referenced in Appendix A of Regulatory Guide 1.33, February 1978, item 1c, Administrative Procedures,

" Equipment Control."

Contrary to the above, on February 25,1998, the NRC determined that written equipment control procedures were not established to process revisions to system valve lineups and thereby ensure that the appropriate changes are communicated to the field.

This is a Severity Level IV violation (Supplement 1) for Docket No. 50-245.

B. 10 CFR 50.49 (a) requires each licensee to establish a program for qualifying the electric equipment important to safety (Millstone Unit 3 EQ program) as defined in 10 CFR 50.49 (b). 10 CFR 50.49 (b) included nonsafety-related electric equipment whose failure under postulated environmental conditions could prevent satisfactory accomplishment of safety functions specified in subparagraphs (1) through (iii) of section (b) (1) of 10 CFR 50.49.

Contrary to the above, nonsafety-related electrical equipment whose failure could prevent the accomplishment of safety functions was not qualified as listed in the following examples:

1. As of February 10,1998, there were 21 nonsafety-related solenoid operated valves (SOV) in the high pressure and low pressure safety injection systems and four nonsafety-related SOVs in the reactor coolant system (RCS), and their associated cables whose failure under postulated environmental conditions could prevent satisfactory accomplishment of safety functions specified in subparagraphs (1) through (iii) of section (b)(l) of 10 CFR 50.49, that were not included in the Millstone Unit 3 EQ program. (This violation was identified by the NRC, except for the four SOVs in the RCS system.)

2. As of September 26,1996, there were 12 electrical, nonsafety-related Target Rock SOVs in the post-accident sampling system and the primary sampling system, and their associated cables and electrical connections, whose failure under postulated environmental conditions could prevent satisfactory accomplishment of safety functions specified in subparagraphs 9806030377 980526 PDR 0 ADOCK 05000245 PDR ,

Enclosure 1 2 (1) through (iii) of section (b)(1) of 10 CFR 50.49, that were not included in the Millstone Unit 3 EQ program. (This item was identified and corrected by the licensee.)

3. As of September 26,1996, there were 21 unsealed NAMCO limit switches and associated terminal blocks, that were used to control 21 safety-related air-operated valves in the high pressure and low pressure safety injection systems, whose failure under postulated environmental conditions could prevent satisfactory accomplishment of safety functions specified in subparagraphs (1) through (iii) of section (b)(1) of 10 CFR 50.49, that were not included in the Millstone Unit 3 EQ program. (This item was identified and corrected by the licensee.)

This is a Severity Level IV violation (Supplement l} for Docket No. 50-423.

C. 10 CFR 50, Appendix B Criterion XVI Corrective Action requires, in part, that measures shall be established to assure that conditions adverse to quality such as nonconformances are promptly identified and corrected.

Contrary to the above, from April 1995 to November 1996, a nonconformance with an assumption of the accidert analysis for a steam generator tube rupture was not promptly corrected. Operating crews at Millstone 3 were unable to complete actions in the Emergency Operating Procedures to isolate a steam generator on tube rupture. This is a Severity Level IV Violation (Supplement 1) for Docket No. 50-423.

Pursuant to the provi.sions of 10 CFR 2.201, Northeast Nuclear Energy 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 Director, Special Projects, Nuclear Reactor Regulation, and a copy to the NRC Resident inspector at the facility that is the subject of this Notice within 30 days of receipt of 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 cc,ntested, 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 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 i the Director, Office of Enforcement, United States Nuclear Regulatory Commission, l Washington, DC 20555-0001.

Enclosure 11 3 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 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 financialinformation). If safeguards information is necessary to provide'an acceptable response, please provide the level of protection described in 10 CFR 73.21.

Dated at King of Prussia, Pennsylvania

• this 26th day of May,1998

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