ML20137E559

Notice of Violation from Insp on 970112-0302.Violation Noted:Plastic Valve Restraint on Valve 1301-36 Melted & Broken

ML20137E559
Person / Time
Site:	Pilgrim
Issue date:	03/18/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20137E556	List: ML20137E552 ML20137E559 ML20137E567
References
50-293-97-01, 50-293-97-1, NUDOCS 9703280028
Download: ML20137E559 (3)

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Enclosure 1 i i

Notice of Violation Boston Edison Company Docket No. 50-293 i Pilgrim Station License No. DPR-35 l I

As a result of an inspection conducted from January 12 to March 2,1997, the following .

violations of NRC requirements were identified. In accordance with the NRC Enforcement l Policy (60 FR 34381; June 30,1995), the violations are described below:

l Violation No.1 1

Pilgrim technical specifications, section 6.8, Procedures, requires that written procedures be established and implemented for activities covered in NRC Regulatory Guide 1.33, Appendix A.

Appendix "A", Sections 5 and 4.g, requires procedures be established and implemented for  ;

Abnormal conditions and operation of the RCIC system.

Example 1 BECo Abnormal Procedure 2.4.49, Loss of Normal Feed and Feedwater Valve Malfunction, step 4.2.2, specified to monitor vessel level and perform the following as appropriate: if level is increasing then the feedwater pump minimum flow valves may be cycled to aid in controlling vessel water level, if water level cannot be controlled, then manually scram the reactor and enter procedure 2.1.6.

Contrary to the above, on February 15,1997, the NRC observed operators respond to a FRV malfunction, enter procedure 2.4.49, and stop/ start the electric driven feed pumps several times to control reactor vessel water level to prevent the need for a reactor scram. Operators were never trained to include the practice of cycling feed pumps to maintain vessel level in this manner.

Example 2 l

BECo procedure 2.2.22, RCIC System, and 8.C.13, Locked Valve List, lists RCIC valve 1301- l 36 as locked open. Further, procedure 8.C.13 step 6.0[2] states not to use plastic valve l restraints where high temperature may cause the plastic to melt.

Contrary to the above during plant power operations, the NRC identified that a plastic valve restraint on valve 1301-36 had melted and broken. Additionai;y, a plastic valve restrai..t was also installed on the adjacent valve 1301-37.

This is a Severity Level IV violation (Supplement I).

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1 Violation No. 2 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, requires in part, that measures shall be established to assure that conditions adverse to quality are promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure i that the cause of the condition is determined and corrective action taken to preclude repetition. {

l Contrary to the above, the following corrective actions were not timely or effective to prevent recurrence of a condition adverse to quality:

Example No.1 The corrective actions taken by BECo in response to a self-identified defi::iency involving the standby switchyard batteries as reported in LER 97-01 were not scheduled timely enough in the ,

master surveillance test program (MSTP) to avoid the possibility of recurrence of the original l condition adverse to quality. The NRC identified that the MSTP had a surveillance test due date  ;

of October 31,1997 which could have exceeded the 5 year capacity test window.  ;

1 Examole No. 2 On February 15,1997, during the recovery from a low power scram, three significaM operator work-arounds conditions detracted from the operations ability to stabilize plant con, .tions during post scram conditions with a main steam isolation valve (MSIV) closure - a condition adverse to quality. These conditions involved the control rod bottom lights, MO-220-3 Main  ;

Steam Drain Line Isolation Valve, and the Reactor Water Cleanup letdown control valve CV- '

1239. When responding to the April 19,1996 low power reactor scram also involving MSIV isolation, the same three significant work-around conditions had an impact on the post scram recovery. The rod bottom lights and CV-1239 degraded equipment conditions were longstanding and had been accepted through compensatory measures in procedures.

This is a Severity Level IV violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, Boston Edison Company is hereby requested 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 Pilgrim, within 30 days of the date of the letter tra. smitting this Notice of Violation. The response should be clearly marked as " Reply to a Notice af Violation" and should include: (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. If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked, or why such action as may be f.;oper should not be taken.

Where good cause is shown, consideration will be given to extending the response time.

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l Because your response will be placed in the NRC Public Docket Room (PDR), to the extent possible, it should not include and personal, privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public, i

f Dated at King of Prussia, Pennsylvania this 18th day of March,1997 i

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