ML16342D178

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Notice of Violation from Insp on 951029-1209.Violation Noted:Operators Failed to Follow Procedures When Terminating Reactor Coolant Sys Draindown Using Valve PCV-135 Versus Valve HCV-133 as Called for in Procedure OP A-2:III
ML16342D178
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 01/13/1996
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML16342D177 List:
References
50-275-95-16, NUDOCS 9601190425
Download: ML16342D178 (4)


Text

ENCLOSURE 1

NOTICE OF VIOLATION Pacific Gas and Electric Company Diablo Canyon Nuclear Power Plant Docket:

50-275 License:

DPR-80 During an NRC inspection conducted on October 29 through December 9,

1995, two violations of NRC requirements were identified.

In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"

(60 FR 34381; June 30, 1995),

the violations are listed below:

A.

Diablo Canyon Technical Specification 6.8. 1 states, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2.

Regulatory Guide 1.33, Appendix A, recommends procedures for draining the reactor vessel.

Contrary to the above, on November 9, 1995, operators failed to follow procedures when terminating a reactor coolant system draindown using Valve PCV-135 versus Valve HCV-133 as called for in Procedure OP A-2:III, "Reactor Vessel Draining to Half Loop/Half Loop Operations With Fuel In Vessel,"

Revision 13, Step 6.3.2.

This is a Severity, Level IV Violation (Supplement I).

B.

Diablo Can on Technical S ecification 6.8. 1 states i

p n part, that written procedures shall be established, implemented, and maintained using the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2.

Regulatory Guide 1:33, Appendix A, recommends procedures for nuclear instrument systems.

Contrary to the above, on November 6, 1995, licensee personnel failed to follow procedures in two instances during the performance of operational tests for nuclear instrument Channels NI 31 and 32.

1.

In one instance, operators, when testing Channel NI 31, selected a

count rate of only 60 counts per second (cps) when the actual reading was 10 cps when Procedure STP I-4A, "Analog Channel Operational Test Nuclear Source Range,"

Revision 19, Step 2.u.3 required a count rate of approximately 2 decades above the actual count (or approximately 1000 cps).

In another

instance, technicians testing Channel NI-32, which was providing input to Channel N34, switched the source range channel selector to the "OFF" position and did not switch the Channel N34 selector to the channel not being tested as required by Procedure STP I-4A, Step 2.a.5.

As a result, audible source range indication was lost in the control room and containment for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

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

960ii90425 960ii6 PDR ADQCK 05000275 8

PDR

C.

Diablo Canyon Technical Specification 6.8. I states, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2.

Regulatory Guide 1.33, Appendix A, Section 1,1, recommends procedures for the plant fire protection program.

Administrative Procedure OHS. ID2, Revision 2, "Fire System Impairment,"

Step 4. 1, requires that any person who identifies a condition that could represent an impairment of a fire system is responsible for notifying the fire protection specialist and the shift foreman.

Contrary to the above, on November 21,

1995, personnel performing housekeeping in the Diesel Generator 1-1 room blocked open Fire Door 107 without contacting a fire protection specialist or the shift foreman.

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, 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 will be given to extending the response time.

Because the 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 reduction.

However, if it is necessary to include such information, it should clearly indicate the specific information that should not be placed in the

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

Dated at Arlington, Texas, this 13th day of January 1996