ML20237D667
| ML20237D667 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/11/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20237D662 | List: |
| References | |
| 50-254-98-12, 50-265-98-12, NUDOCS 9808270121 | |
| Download: ML20237D667 (4) | |
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Commonwealth Edison Company Docket Nos.: 50-254; 50-265 Quad Cities Station, Units 1 and 2 Ucense Nos.: DPR-29; DPR-30 During an NRC inspection conducted May 29 through July 16,1998, four violations of NRC requirements were identified. In accordance with the " General Statement of Policy and 1
Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
1.
Technical Specification 6.8.A.1 states written procedures shall be established,'
implemented, and maintained covering the activities referenced in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
l Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, Section 8.b.(2)(q),
' includes surveillance test procedures for emergency diesel generator systems.
Quad Cities Operating Surveillance 6600-01, Revision 24, dated May 29,1998, " Diesel l
Generator Monthly Load Test," Attachment A, Step H.7.i.(4), required an operator to
" Throttle Air Box Drain [ valve) one tum from full closed."
Contrary to the above, on June 22,1998, while performing Quad Cities Operating Surveillance Procedure 6600-01, Revision 24, an operator failed to position the throttle air l
box drain valve one tum from full closed, as required. Instead, the operator incorrectly opened the crank case drain valve.
This is a Severity Level IV violation (Supplement I). (50-254/98012-02) 2.
Title 10 CFR Part 50, Appendix B, Criterion Ill, " Design Control" requires, in part, that measures shall be established for the selection and review for suitability of application of parts and equipment that are essential to the safety-related functions of systems and components. It further states that design control measures shall provide for verifying or checking the adequacy of design.
Contrary to the above, from January 1991 through April 1998, Square D Type EQ 1933G2 relays were designated and used as replacement paris for Quad Cities emergency diesel generators, without verification of design adequacy. Specifically, the ability of the relay to perform the intended safety function under vibration conditions during normal operations and in the event of a design basis earthquake had not been evaluated.
This is a Severity Level IV violation (Supplement I). (50-254/98012-03) l-i i
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9000270121 990811 F
PDR ADOCK 05000254 G
3.
Title 10 CFR Part 50, Appendix B, Criterion V, " Instructions, Procedures, Drawings,"
requires, in part, that activities affecting quality shall be prescribed by procedures and shall be accomplished in accordance with these procedures.
- Quad Cities Administrative Procedure 0400-03, Revision 3, dated June 3,1996,
" Instrument / Equipment Setpoint Change," described the process for changing an equipment setpoint. Steps D.2.b and D.2.m(2) required the cognizant engineer to complete a safety evaluation or screening and to determine if changes were required to design base documents.
Contrary to the above, second level undervoltage relay setpoint changes for 4.16 kV
- safety-related Buses 23-1'and 24-1 were implemented on June 13,1996, and were not accomplished in accordance with Quad Cities Administrative Procedure 0400-03,
" Instrument / Equipment Setpoint Change." No safety evaluation or screening was completed and no changes to the Updated Final Safety Analysis Report, a design base document, were identified.
This is a Severity Level IV violation (Supplement 1). (50-265/98012-04) l
' 4.
10 CFR 50.59 (a)(1)l" Changes, tests and experiments," requires, in part, that the holder of a license authorizing operation af a utilization facility may make changes in the facility as described in the safety analysis report without prior Commission approval, unless the proposed change involves an unroviewed safety question.
10 CFR 50.59(b)(1), requires, in part, that the licensee shall maintain records of changes f
in the facility as described in the safety analysis report."These records must include a written safety evaluation which provides the bases for the determination that the change does not involve an unreviewed safety question.
Updated Final Safety Analysis Report 8.3.1.8, " Analysis of Station Voltages," states, in -
part, " adequate margin exists between the calculated minimum running voltage and the National Electric Manufacturers Association standard that minimum voltage be limited to 90 percent of equipment rated voltage."
The UFSAR Section 9.2.1.2 described the residual heat removal service water pump 3
room cooler. It stated, "The RHR service water pumps are located in watertight vaults in
- the turbine building condensate pump room. Each vault has one vault cooler for each pump in the vault. The cooler starts when its associated pump starts. The coolers are designed to maintain the vault at er below 120 degrees Fahrenheit during pump operation l
.with half the tubes plugged."
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Notice of Violation The UFSAR Section 9.5.5 described the emergency diesel generator cooling water pump room cooler it stated, " A vault cooler is supplied for each DG cooling water pump to prevent the pump motors from overheating. Each cooler maintains vault temperature at or below 120 degrees Fahrenheit during operation of its respective pump. The vault
' cooler starts when its respective pump starts. Each vault cooler is supplied with cooling water from the respective pump's discharge line and the cooling water is retumed to the pump's suction line."
Contrary to the above, as of April 1998, the licensee changed the facility as described in Updated Final Safety Analysis Report 8.3.1.8,9.2.1.2, and 9.5.5 when the 2C and 2D
- RHR Service Water Pump Room Cooler Ventilation Fans and the 2 EDG Cooling Water Pump Room Cooler Ventilation Fans were permitted to have calculated running voltages
- under degraded voltage conditions less than the 90 percent minimum voltage allowed by
- the ' National Electric Manufacturers Association standard. This change was performed without completing a written safety evaluation which provides the bases for the determination that the change in the facility does not involve an unreviewed safety question.
This is a Severity Level IV violation (Supplement 1). (50-265/98012-05)
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 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 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.
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, DC 20555-0001.
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
Notice of Violation 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 q
information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at Lisle, Illinois
-- this 11 day of August 1998 l
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