ML16342D395

From kanterella
Jump to navigation Jump to search
Notice of Violation from Insp on 960526-0706.Violation Noted:Failure to Follow Procedure STP I-38-B.1,Step 7.2, When Procedure Was Performed on Ssps Train B W/Residual Heat Removal Pump Train a Inoperable,On 960613
ML16342D395
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 07/31/1996
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML16342D396 List:
References
50-275-96-14, NUDOCS 9608120261
Download: ML16342D395 (2)


Text

C ENCLOSURE 1

NOTICE OF VIOLATION Pacific Gas and Electric Company Diablo Canyon Nuclear Power Plant Docket No.:

50-275 License No,:

DPR-80 During an NRC inspection conducted on May 26 through July 6,

1996, 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.

Diablo Canyon Technical Specification 6.8. I.a requires written procedures be established, implemented, and maintained covering the activities recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

Appendix A of Regulatory Guide 1.33, Section 8.b, states that specific procedures shall be written for surveillance tests, inspections, and calibrations listed in the Technical Specifications.

Procedure STP I-38-B.I, "SSPS Train B Actuation Logic Test in Modes 1,

2, 3 or 4," was written and implemented by the licensee to satisfy Technical Specification required periodic testing of the plant solid state protection system (SSPS),

Step 7.2 of Procedure STP 1-38-B.I required that ".

..if any ESF equipment in Train A is known to be inoperable, then do not perform this test unless it is known TS LCOs will not be violated."

B.

Contrary to the above, on June 13, 1996, while in Mode 1, operations and technical maintenance personnel failed to follow Procedure STP I-38-B. 1, Step 7.2, when the procedure was performed on SSPS Train B with the residual heat removal pump Train A inoperable, violating the Technical Specification Limiting Condition for Operation 3.5.2.

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

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, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures or drawings.

Diablo Canyon Administrative Procedure OM7. ID1, Revision 6, "Problem Identification and Resolution - Action Requests,"

Section 5.8.7, requires that action request (AR) stickers in the control room shall be removed after problem resolution prior to closure of the AR ~

9608i2026i 96073i PDR ADOCK 05000275 8

PDR

Contrary to the above, on Hay 15,

1996, the inspector noted that five AR stickers attached to annunciators, indications and controls on the Unit 1 main control boards had not been removed after problem resolution prior to closure of the AR.

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

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, w'ithin 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 will 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 indi ate the specific information that you desire not to be placed

'.n the

PDR, and provide the legal basis to support your request for withholding the information from the public.

Dated at Arlington, Texas this 3lstday of July 1996