ML20134B791

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Notice of Violation from Insp on 960907-1105.Violation Noted:W De-Ion Circuit Breakers Type Gm,Rev 1,was Not Appropriate for Circumstance
ML20134B791
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 01/23/1997
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20134B781 List:
References
50-331-96-07, 50-331-96-7, NUDOCS 9701310089
Download: ML20134B791 (2)


Text

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NOTICE OF VIOLATION IES Utilities Inc. Docket No. 50-331 Duane Arnold Energy Center License No. DPR-49 '

During an NRC inspection conducted on September 7 through November 5, 1996, violations of NRC requirements were identified. In accordance with the

" General Statement of Policy and Procedure for NRC Enforcement Actions," the violations are listed below:

l

1. Part 50 of 10 CFR, Appendix B, Criterion V, requires, in part, that activities affecting quality be prescribed by procedures of a type appropriate to the circumstances.

l Duane Arnold Administrative Control Procedure (ACP) 1410.5 ("Tagout  :

Procedure") states, in part, that all DAEC personnel or their supervisor  !

working under a tagout, shall verify the adequacy and safety of the I tagout boundary prior to accepting the tagout and walkdown and  ;

physically inspect the appropriate portion of the tagout boundary prior i to beginning work.

Contrary to the above:

J

a. On September 9, 1996, work instructions for maintenance on the l drywell pneumatic nitrogen compressor was not appropriate for the '

circumstance. The instructions did not ensure that tagouts established an appropriate boundary by. isolating the suction filter prior to beginning work.

b. On September 9, 1996, procedure CKTBKRW120-003, " Westinghouse De-Ion Oil Circuit Treakers Type GM and GMA," Revision 1, was not l appropriate for the circumstance. The procedure lacked sufficient '

detail on the exact location for test equipment hook-ups.

Consequently, a Division II 125 VDC Trouble alarm was received when the test equipment was hooked up incorrectly.

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

2. Part 50 of 10 CFR, Appendix B, Criterion V, requires, in part, that activities affecting quality be accomplished according to procedures of a type appropriate to the circumstances.
a. Duane Arnold ACP 1410.5 ("Tagout Procedure") states, in part, that the person hanging tags shall place the components in the position -

required by the Components Tagged Form following the sequence specified.

b. Procedure I.E/S-E209-004 (Elger Corp., Reg Transformer 1Y2A and Invertor 1025 Calibration") specified how to hook up DC leads to perform the testing. Additionally, Temporary Document Change Form (DCF) 95-T-0684 provided directions to lift a wire in the ground detection circuit. The wire needed to be lifted to prevent an alarm and possible damage to the inverter from occurring.

9701310089 970123 PDR ADOCK 05000331 G PDR

l Notice of Violation  ;

i c. Surveillance test Procedure (STP) 42A026-Q ("HPCI Steam Line High j DP Instrument Functional Test / Calibration") directed a relay block

be placed on contacts 1-2 of relay E41-K33.

j Contrary to the above:

! a. On October 8,1996, an operator did not follow the tagout sequence

specified on the tagout sheet and caused a reactor building closed j^ cooling water relief valve for a recirculation sample cooler to i lift. 1
b. On September 25, 1996, I&C technicians failed to hook up leads per procedure I.E/S-E209-004 (Elger Corp., Reg Transformer lY2A and Invertor 1025 Calibration") and failed to incorporate DCF 95-T-0684 into the procedure they were working. Consequently, control l room operators received several instrument AC and Division II 125 VDC Trouble alarms and various components were damaged.

On October 8, 1996, maintenance technicians failed to follow STP c.

42A026-Q and placed the relay block on contacts 11-12. As a result, a Primary Containment Isolation System (PCIS) closure of M02239 (HPCI outboard steam supply isolation valve) occurred. 1 This is a Severity Level IV violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, Duane Arnold Energy Center is hereby required to submit a written statement or explanation to the l U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, i Washington D.C. 20555 with a copy to the U.S. Nuclear Regulatory Commission, Region III, 801 Warrenville Road, Lisle, Illinois 60532-4351, and a copy to the NRC Resident Inspector at the Duane Arnold Energy Center within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This i 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 previously 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.

Dated at Lisle, Illinois

. this 23rd day of January 1997 i

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