ML16342D762

Notice of Violation from Insp on 970608-0719.Violation Noted:Following Transfer of PY-16 Back to Normal Power Supply During Refueling Outage 1R8,backup Power Supply Breaker Remained Closed & Valves SI-1(2)-8964 Not Listed

ML16342D762
Person / Time
Site:	Diablo Canyon
Issue date:	08/08/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML16342D763	List: IR 05000275/1997010 ML16342D762 ML16342D764
References
50-275-97-10, 50-323-97-10, NUDOCS 9708190257
Download: ML16342D762 (4)

Text

ENCLOSURE 1 NOTICE OF VIOLATION Pacific Gas and Electric Company Diablo Canyon Nuclear Power Plant Docket Nos.:

License Nos.:

50-275 50-323 DPR-80 DPR-82 During an NRC inspection conducted on June 8 through July 19, 1997, two violations 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.

10 CFR Part 50, Appendix B, Criterion V (Instructions, Procedures and Drawings),

requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings appropriate to the circumstances and shalt be accomplished in accordance with these instructions, procedures, or drawings.

Operating Procedure OP J-10:IV, "Instrument AC System - Transfer of Panel Power Supp,y," Section 6.21, specifies the procedure to be followed for the transfer of instrument AC Panel PY-16 from its backup power supply to its normal power supply.

Section 6.21 requires that the backup power supply Breaker 52-1F-27 be open and the use of a transfer switch change form per Procedure-OP1.DC20, "Sealed Components."

Contrary to the above, following transfer of PY-16 back to its normal power supply during Refueling Outage 1R8, the backup power supply breaker remained closed.

Additionally, a change form had not been used, as required, when removing the seal installed when the transfer switch had been aligned to the backup power supply and when installing the seal following realignment of the power transfer switch to the normal power supply.

This is a Severity Level IV violation (Supplement I) (50-275/97010-01).

Be Technical Specification 4.6.1.1.a, states, in part, containment integrity shall be demonstrated at least once per 31 days by ve ifying that all penetrations not capable of being closed by operable containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions.

The Technical Specification 4.6.1.1.a surveillance requirement was implemented by STP I-1D, "Routine Monthly Checks Required By Licenses", Revision 48.

Contrary to the above, on July 9, 1997, instrument isolation Valves Sl-1(2)-8964 for 1(2)PI-942, required to be closed to maintain containment integrity, were not listed in STP l-1D, "Routine Monthly Checks Required By Licenses," Revision 48, and had not been verified closed on a 31-day frequency.

This is a Severity Level IV violation (Supplement I) (50-275;323/97010-02).

9708i90257 970808 PDR ADQCK 05000275 6

PDR

This is a Severity Level IV violation (Supplement I) (50-275;323/97010-02).

Pursuant to the provisions of 10 CFR 2.201, Pacific 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 IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, 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 wilt be given to extending the response time.

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.

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.

Dated yt Walnut Creek, California, this 8th day of August 1997