ML20216D056

Notice of Violation from Insp on 970617-0728.Violations Noted:Inspectors Identified Four Valves in RHRSW Sys Flow Path That Were Not Locked Sealed or Otherwise Secured in Position & Not Verified in Correct Position within 31 Days

ML20216D056
Person / Time
Site:	Quad Cities
Issue date:	08/26/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20216D048	List: IR 05000254/1997011 ML20216D043 ML20216D056
References
50-254-97-11, 50-265-97-11, NUDOCS 9709090202
Download: ML20216D056 (2)

Text

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NOTICE OF VIOLATION Commonwealth Edison Company Docket Nos. 50 254; 50 265 Quad Cities Station, Units 1 and 2 License Nos. DPR-29; DPR 30 During an NRC inspection conducted on June 17 through July 28,1997, three 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:

1. Technical Specification Surveillan::e Requirement 4.8.A requires that each of the i required RHRSW [ Residual Heat Removal Service Water) subsystems be

! demonstrated operable at least once per 31 days by verifying that each valve, manual or power operated, in the flow path that is not locked, sealed, or otherwise l secured in position is in its correct position.

Contrary to the above, between July 17 and July 22,1997, the inspectors identified four valves in the RHRSW system flow path that were not locked, sealed, or otherwise secured in position and were not verified in the correct position within the past 31 days. Subsequently, the licensee identified an additional eleven valves in this condit ion. '

This is a Severity Level IV violation (Supplement 1). (50-254;265/97011-03)

2. 10 CFR Part 50, Appendix B, Criterion 111, " Design Control," requires, in part, that measures be established to ensure that the design basis is correctly translated into procedures.

Addendum #1 to Modification Approval Letters for Design Change Packages 9700134,9700141, and 9700144 stated that Merlin-Gerin SF6 4 kilovolt (kV) circuit breakers containing ty-wrap mounting enhancers for auxiliary switches were qualified for no greater than 150 breaker cycles or 18 spring discharges.

The modification approval letter for MO4-1(2)91-013 (installation of high pressure coolant injection system turbine exhaust vacuum breakers) recommended operating procedure changes that would require that the high pressure coolant injection system be declared inoperable when the turbine exhaust vacuum breakers were isolated.

Contrary to the above,

a. Quad Cities Operatirig Surveillance Procedure, OCOS 6500-08, _ Revision 1, dated April 18,1997, " Weekly 4 kV Breaker Monitoring," did not incorporate the maximum allowed breaker cycles as required by Addendum #1 to Modification Approval Letters for Design Change Packages 9700134,9700141, and 9700144.

Quad Cities Operating Procedure, OCOP 6500-04, Revision 8, dated April 18,1997, " Racking Out a 4160 Volt Horizontal Type AMH, AMHG or G26 Circuit Breaker," did not incorporate the maximum allowed breaker 9709090202 970826 PDR ADOCK 05000254 G PDR

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discharges'as required by Addendum #1 to Modification Approval Letters for Design Change Packages 9700134,9700141, and 9700144.

b. Operating procedure changes recommended in the modification approval letter for MO41(2)91-013 were not incorporcted into Quad Cities Operating

Procedure OCOP 2300-1, Revision 9 "HPCI Standby Operation." As a result ,

from April 17 to April 23,1996, the Unit 2 HPCI system turbine exhaust 4

vacuum breakers were isolated and the system was not declared inoperable.

This is a Severity Level IV violation (Supplement 1) (50 254;265/97011-04a,04b)

3. - Technical Specification 6.12.B requires that areas accessible to personnel with radiation levels greater than 1000 mrom/hr have doors locked or attended.

Contrary to the above, on July 2,1997, the inspectors identified that the gate trom

- the reactor building ground level to the Unit 1 "B" residual heat removal room was posted as a locked high radiation area but the gate was neither locked nor attended.

This is a Severity Level IV violation (Supplement IV). - (50 254:265/97011-05)

Pursuant to the provisions of 10 CFR 2.201, Commonwealth Edison is hereby required to submit a written statement of explanation to the U.S. Nuclear Regulatory Commission, ATTN:- Document Control Desk, Washington D.C. 20555 with a copy to the Regional- +

Administrator, Region lil, 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 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 at Lisle, Illinois, .

this 26th day of August,1997 i

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