ML022950365
| ML022950365 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/22/2002 |
| From: | Dave Hills NRC/RGN-III/DRS/MEB |
| To: | Skolds J Exelon Generation Co, Exelon Nuclear |
| References | |
| Download: ML022950365 (7) | |
Text
October 22, 2002 Mr. John L. Skolds, President Exelon Nuclear Exelon Generation Company, LLC Quad Cities Nuclear Power Station 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
UPCOMING QUAD CITIES PROBLEM IDENTIFICATION AND RESOLUTION (PI&R) INSPECTION
Dear Mr. Skolds:
On December 2, 2002, NRC will begin the required biennial problem identification and resolution (PI&R) inspection at your Quad Cities Nuclear Power Station. This inspection will be performed in accordance with the NRC baseline inspection procedure 71152.
Experience has shown that these inspections are extremely resource intensive both for the NRC inspectors and the utility staff. In order to minimize the impact that the inspection has on the site and to ensure a productive inspection for both sides, we have enclosed a request for documents needed for the inspection. The documents have been divided into two groups.
The first, which is primarily comprised of lists of information, is necessary in order to ensure the inspection team is adequately prepared for the inspection. This information should be provided to the Regional Office by no later than November 18, 2002. It is preferable that the information is provided electronically as much as possible. Alternatively, the information can be faxed or mailed, the lead inspector can make a short trip to the site to obtain the information, or a licensee employee can arrange to drop it by the regional office. The inspection team will review this information and will request specific items from the lists which will need to be available for further review when the team arrives onsite.
The second group of documents requested are those items which the team has already determined that they wish to review and wish to have waiting for them on the first day of the inspection.
The lead inspector for this inspection is V. Patricia Lougheed. If there are any questions about the material requested, or the inspection in general, please do not hesitate to call Patricia at 630-829-9760, or to contact her by e-mail at vpl@nrc.gov.
J. Skolds In accordance with 10 CFR 2.790 of the NRCs "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Mechanical Engineering Branch Division of Reactor Safety Docket Nos. 50-254; 50-265 License Nos. DPR-29; DPR-30
Enclosure:
Initial Document Request cc w/encl:
Site Vice President - Quad Cities Nuclear Power Station Quad Cities Nuclear Power Station Plant Manager Regulatory Assurance Manager - Quad Cities Chief Operating Officer Senior Vice President - Nuclear Services Senior Vice President - Mid-West Regional Operating Group Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing - Mid-West Regional Operating Group Manager Licensing - Dresden and Quad Cities Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Vice President - Law and Regulatory Affairs Mid American Energy Company M. Aguilar, Assistant Attorney General Illinois Department of Nuclear Safety State Liaison Officer, State of Illinois State Liaison Officer, State of Iowa Chairman, Illinois Commerce Commission W. Leach, Manager of Nuclear MidAmerican Energy Company
J. Skolds In accordance with 10 CFR 2.790 of the NRCs "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Mechanical Engineering Branch Division of Reactor Safety Docket Nos. 50-254; 50-265 License Nos. DPR-29; DPR-30
Enclosure:
Initial Document Request cc w/encl:
Site Vice President - Quad Cities Nuclear Power Station Quad Cities Nuclear Power Station Plant Manager Regulatory Assurance Manager - Quad Cities Chief Operating Officer Senior Vice President - Nuclear Services Senior Vice President - Mid-West Regional Operating Group Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing - Mid-West Regional Operating Group Manager Licensing - Dresden and Quad Cities Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Vice President - Law and Regulatory Affairs Mid American Energy Company M. Aguilar, Assistant Attorney General Illinois Department of Nuclear Safety State Liaison Officer, State of Illinois State Liaison Officer, State of Iowa Chairman, Illinois Commerce Commission W. Leach, Manager of Nuclear MidAmerican Energy Company DOCUMENT NAME: G:DRS\\ML022950365.wpd To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RIII RIII RIII NAME PLougheed:sd MRing DHills DATE 10/21/02 10/22/02 10/22/02 OFFICIAL RECORD COPY
J. Skolds ADAMS Distribution:
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Initial Document Request I.
Information Requested Expeditiously The following information is requested to be provided as soon as possible, but no later than November 18, 2002.
One copy each of the administrative procedure(s) governing the identification and resolution of problems, operability determinations, root cause analysis A list of Nuclear Oversight audits and self assessments performed since June 1, 2001 A list of systems either currently considered as maintenance rule (a)(1) systems or those which have been removed from (a)(1) status in the last quarter A list of the top ten risk significant systems A list of the top ten risk significant components A list of all significant condition reports (level 1 or 2) issued since June 1, 2001 A list of all root cause evaluations issued since June 1, 2001 A list of all operability evaluations or determinations performed since June 1, 2001 A list of all condition reports involving human performance errors since June 1, 2001 A list of all condition reports involving corrective action problems since June 1, 2001 A list of all condition reports involving operator work-arounds (including those where operator work-arounds were part of the solution) since June 1, 2001 A list of all condition reports involving temporary modifications (including those where temporary modifications were part of the solution) since June 1, 2001 A list of all condition reports where the issues were identified by the NRC since June 1, 2001 II Information Requested to be Available to the Inspectors At the Beginning of the Inspection A list of Corrective Action Program routine meetings, times and places A copy of each of the most recent Nuclear Oversight audits, surveillances, or self assessments of the corrective action program, the maintenance and work control program, operations area, and the engineering area A copy of the most recent minutes for onsite and offsite committee review meetings Copies of the corrective actions taken in response to the following condition reports:
80755 Battery Room Ventilation Air Handling Unit Drive Belt Failures Should Have Been Counted as MPFFs 88737 Incorrect Protective Action Recommendation During Dec. 2001 Drill 88870 Minor Error in ERO Participation Data for October 2001 89028 PI Assessment Concerns for Three Mini-Drills in Nov. 2001 90937 Drawing Error on 3-Way Valve (M-22; M-69) 91766 RHRSW Load is Different in QCOA 6100-03, 04 (SBO)
91837 Errors Identified on DGCW P&IDs M-22 Sht 5 & M-69 Sht 5 91880 Reduced Seismic Criteria Used to Qualify RHRSW Piping 92983 UFSAR Discrepancy 75% Minimum Motor Start Voltage 93012 Inconsistencies in UFSAR Section 3.4.1.2.1.2 Regarding RHRSW Vault Flood Protection 93016 Ultimate Heat Sink Instrument Uncertainties 93115 Calculation Qualification of Turned-down RHRSW Pump Anchor Bolts 93281 MCC Voltages in Degraded Volt Calculations 93308 Discrepancies Between ELMS and Voltage Calculations 93336 Op Evaluation for 1A RHR HX Leak Needs Enhancement 93368 IST Data Shows Higher Suction Losses for U1 DGCW/
RHRSW Pumps 93385 Different RHRSW Suction Minimum Water Level Values in Calculation and QCOA 0010-14 93394 CREVS Degraded Voltage Procedure Load Shedding Discrepancy 93444 RHRSW Vault Room Cooler Leak Operability Evaluation Inadequate Follow-up 95280 Failure to Adequately Determine the Cause of the 1995 2A Standby Liquid Control System Pump Trip 100473 Incorrect/incomplete Risk Assessment for HPCI Planned Maintenance 101320 Failure to Ensure the HPCI System Was Operable Prior to Exceeding 150 psig Reactor Pressure 102133 Corrected Error in ANS Data Provided by Contractor 104321 Failure to Complete Parts Evaluation Addressing the Change in Design Prior to Installing Hose Clamps 106480 Downward Trend in ERO Participation Data in Spring 2002 112360 Failure of Admin SRO to Participate in Shift Turnover Q2000-04468 Inadequate Fill and Vent Surveillance Performed on High Pressure Coolant Injection Resulting in Air in Discharge Piping Q2001-01312 Failure to Include Performance Indicator Data Q2001-01338 Potential Common Cause Inoperability of EDG Fuel Oil Transfer System Q2001-02135 Unplanned Spread of Contamination Q2001-02142 Dose Rates in 2A RHR Room Subgrating Q2001-02518 Potential Common Cause Inoperability of Emergency Diesel Generator Fuel Oil Transfer System Q2001-02901 Failure to Have Adequately Sized Standby Liquid Control System Q2001-03091 SRO Rotation Requirements of TQ-AA-106 Not Met During Annual Dynamic Exam