ML20217G310

Notice of Violations from Insp on 980211-0331.Violations Noted:On 980314,non-licensed Operators Performing Plant Operating Procedure 6600-7,rev 6,attachment H,Failed to Charge Breaker Closing Spring for Unit 2

ML20217G310
Person / Time
Site:	Quad Cities
Issue date:	04/23/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20217G284	List: ML20217G280 ML20217G310 ML20217G340
References
50-254-98-04, 50-254-98-4, 50-265-98-04, 50-265-98-4, NUDOCS 9804290109
Download: ML20217G310 (3)

Text

i NOTICE OF VIOLATION l

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 February 11 through March 31,1998, five 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 6.8.A.1 required that procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, be established, implemented and maintained.

Regulatory Guide 1.33, Revision 2, February 1978, Appendix A, Section 4.w.(2).(b) required instructions for energizing onsite electrical A.C. (Altemating Current) systems.

Quad Cities Operating Procedure 6500-7, Revision 6, " Racking in a 4160 Volt Horizontal Type AMH, AMHG, or G26 Breaker," Attachment H, required charging the breaker closing spring.

Contrary to the above, on March 14,1998, non-licensed operators performing Quad Cities Operating Procedure 6600-7, Revision 6, Attachment H, failed to charge the breaker closing spring for the Unit 2 Station Blackout Diesel Generator output breaker to Bus 71 when the breaker was retumed to service.

This is a Severity Level IV violation. (50-265/98004-01)

2. Technical Specification 6.8.A.1 required that procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, be established, implemented and maintained.

Regulatory Guide 1.33, Revision 2, February 1978, Appedix A, Section 1.c, required administrative controls for equipmerit control (locking and tagging).

Quad Cities Administrative Procedure 230-04, " Equipment out-of-service," Revision 20, Section D.2.b.(3), states " Components shall never be operated while an OOS (out-of-service) Card is attached."

Out-of-service (OOS) 970013277 required Valves 2-4799-919 and 2-4799-920, drain valves for the Unit 2 Instrument Air Compressor, to be tagged in the open position.

Contrary to the above, on March 26,1998, operators identified Valves 2-4799-919 and 2-4799-920, which were tagged as open, were in the closed position. The valves had been operated with the tags (OOS cards) attached.

This is a Severity Level IV violation. (50-265/98004-02) l i

3. Technical Specification Surveillance Requirement 4.4.A.1.C stated that while in Modes 1,2, and 5 (with any control rod withdrawn), the standby liquid control system shall be demonstrated operable at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that the heat 9804290109 DR 980423 ADOCK 05000254 PDR

. l Notice of Violation l tracing circuit is operable by determining the temperature of the pump suction piping to be greater than or equal to 83 degrees Fahrcnheit.

1 Contrary to the above, from September 23,1996, to December 19,1997, with Unit 1 in Modes 1,2, or 5 (with any control rod withdrawn) and from September 26,1996, to September 29,1997, with Unit 2 in Modes 1,2, or 5 (with any control rod withdrawn), the standby liquid control system was not demonstrated to be operable by determining the temperature of the pump suction piping to be greater than or equal to 83 degrees Fahrenheit. Temperature switches that provided input to an annunciator used to meet the surveillance requirement were found to be set below 83 degrees Fahrenheit.

This is a Severity Level IV violation. (50-254/98004-03; 50-265/98004-03)

4. Technical Specification 4.2.G.3.b required the performance of a source range monitor  !

channel functional test at least once per 31 days when the reactor was in Modes 3 or 4 or Mode 2 with intermediate range monitors on Range 2 or below.

Contrary to the above, from December 20,1997, until February 22,1998, for Unit 1, and from October 15,1997, until February 22,1998, for Unit 2, a channel functional test of source range monitors was not performed with the reactors in Modes 3 or 4 or Mode 2  ;

with intermediate range monitors on range 2 or below.

1 This is a Severity Level IV violation. (50-254/98004-04; 50-265/98004-04)

5. Technical Specification 4.8.F.2 required a visualinspection of snubbers to be performed as required by Table 4.8.F.1. Table 4.8.F.1 required the inspection interval to be determined and documented prior to any inspection. Preventive Maintenance item 104537 set the interval for the visual inspection of Unit 1 at 18 months.

Technical Specification 4.8.F.5 required that at least once per 18 months, a representative sample of snubbers be tested in accordance with a preselected sample  ;

plan.

Contrary to the above, from February 1,1996, until December 26,1997, Unit 1 snubbers l were not visually inspected, and from February 19,1996, until January 6,1998, functional testing of a predetermined representative sample of Unit i snubbers was not performed.

This is a Severity Level IV violation. (50-254/98004-05)

Pursuant to the provisions of 10 CFR 2.201, Commonwealth Edison 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 111, and a copy to the NRC Resident inspector at the facility that is the subject of this l

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 or severity level; (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

Notice of Violation -3 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 prepar should not be taken. Where good cause is shown, consideration will be given to extending the response time.

If you contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, i DC 20555-0001.

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l 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. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information, if you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please ,

provide the level of protection described in 10 CFR 73.21. l Dated at Lisle, Illinois this 23rd day of April 1998 i

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