IR 05000461/2010004
Download: ML103020027
Text
October 28, 2010
Mr. Michael Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT: CLINTON POWER STATION INTEGRATED INSPECTION REPORT 05000461/2010-004
Dear Mr. Pacilio:
On September 30, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Clinton Power Station. The enclosed report documents the results of this inspection, which were discussed on October 7, 2010, with Mr. F. Kearney, and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,/RA/ Mark A. Ring, Chief Branch 1 Division of Reactor Projects Docket No. 50-461 License No. NPF-62
Enclosure:
Inspection Report 05000461/2010-004;
w/Attachment:
Supplemental Information cc w/encl: Distribution via ListServ Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 50-461 License No: NPF-62 Report No: 05000461/2010-004 Licensee: Exelon Generation Company, LLC Facility: Clinton Power Station Location: Clinton, IL Dates: July 1, through September 30, 2010 Inspectors: B. Kemker, Senior Resident Inspector D. Lords, Resident Inspector J. Bozga, Reactor Inspector J. Draper, Reactor Engineer D. Reeser, Operations Engineer A. Scarbeary, Reactor Engineer John Cassidy, Senior Health Physicist S. Mischke, Resident Inspector, Illinois Emergency Management Agency Approved by: M. Ring, Chief Branch 1 Division of Reactor Projects Enclosure
SUMMARY OF FINDINGS
........................................................................................................... 1
REPORT DETAILS
....................................................................................................................... 2Summary of Plant Status
REACTOR SAFETY
....................................................................................................... 21R01Adverse Weather Protection (71111.01) ............................................................. 21R04Equipment Alignment (71111.04) ........................................................................ 31R05Fire Protection (71111.05) .................................................................................. 41R06Flooding Protection Measures (71111.06) .......................................................... 51R11Licensed Operator Requalification Program (71111.11Q) .................................. 61R12Maintenance Effectiveness (71111.12) ............................................................... 61R13Maintenance Risk Assessments and Emergent Work Control (71111.13) ......... 71R15Operability Evaluations (71111.15) ..................................................................... 81R18Plant Modifications (71111.18) .......................................................................... 101R19Post-Maintenance Testing (71111.19) .............................................................. 101R20Outage Activities (71111.20) ............................................................................. 111R22Surveillance Testing (71111.22) ....................................................................... 121EP6Drill Evaluation (71114.06)
RADIATION SAFETY
................................................................................................... 162RS5Radiation Monitoring Instrumentation (71124.05)
OTHER ACTIVITIES
..................................................................................................... 214OA1Performance Indicator Verification (71151) ....................................................... 214OA2Identification and Resolution of Problems (71152) ........................................... 254OA3 Follow-Up of Events and Notices of Enforcement Discretion (71153) .............. 304OA5Other Activities .................................................................................................. 324OA6 Management Meetings ...................................................................................... 32
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- K. Baker, Design Engineering Senior Manager
- R. Campbell, RP Technical Specialist
- T. Chalmers, Operations Director
- J. Cunningham, Security Manager
- A. Darelius, EP Manager
- J. Domitrovich, Work Management Director
- C. Dunn, Shift Operations Superintendent
- S. Fatora, Maintenance Director
- R. Frantz, Regulatory Assurance
- S. Gackstetter, Training Director
- W. Hafiz, Design Engineering
- G. Hall, Performance Improvement Program Manager
- M. Heger, Mechanical/Structural Design Engineering Manager
- N. Hightower, Radiological Engineering Manager
- M. Kanavos, Plant Manager
- D. Kemper, Regulatory Affairs Manager
- F. Kearney, Site Vice President D. Kemper; Regulatory Assurance Manager
- S. Lakebrink, Mechanical Design Engineering
- K. Leffel, Operations Support Manager
- S. O'Riley, EP Coordinator
- J. Peterson, Regulatory Assurance
- F. Pournia, Engineering Director
- J. Rappeport, Chemistry Manager
- S. Soliman, Senior Chemist
- J. Stovall, Radiation Protection Manager
- J. Ufert, Fire Marshall
- C. VanDenburgh, Nuclear Oversight Manager
Attachment
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened
- 05000461/2010004-01 URI Apparent Interaction Between Non-Safety Related and Safety-Related Portions of the NSPS Causing Spurious
Component Actuations (Section 1R15.b.(1))
Closed
- 05000461/LER-2010-002-01 LER Excessive Leakage Through Feedwater Isolation Valve 1B21F032B (Section 4OA3.1)
- 05000461/LER-2008-003-01 LER Excessive Leakage Through Feedwater Isolation Valve 1B21F032A (Section 4OA3.2)
- 05000461/FIN-2009004-04 URI RPV Head Strongback, Dryer/Separator Strongback and RPV Head Lifting Lugs Did Not Demonstrate Single Failure Proof Requirements of NUREG-0612, "Control of
- Heavy Loads at Nuclear Power Plants," Section 5.1.6
- Discussed None
- Attachment
LIST OF DOCUMENTS REVIEWED
The following is a partial list of documents reviewed during the inspection.
- Inclusion on this list does not imply that the NRC inspector reviewed the documents in their entirety, but rather that selected sections or portions of the documents were evaluated as part of the overall inspection effort.
- Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.
- 1R01 Adverse Weather Protection - Clinton Power Station Individual Plant Examination for External Events Final Report, September 1995 - Clinton Power Station Updated Final Safety Analysis Report, Section 3.4, "Water Level (Flood) Design," Revision 11 -
- CPS 4303.02, "Abnormal Lake Level," Revision 10
-
- CPS 4304.01, "Flooding," Revision 5a
-
- AR 01116277, "Received Annunciator 5013-8E High-High Level Floor/Equipment Drain" 1R04 Equipment Alignment -
-
- M05-1102, "P&ID Control Room HVAC (VC)," Sheet 1, Revision U
-
- CPS 3314.01, "Standby Liquid Control (SC)," Rev 11b -
- CPS 3314.01E001, "Standby Liquid Control Electrical Lineup," Rev 9a
-
- CPS 3314.01V001, "Standby Liquid Control Valve Lineup," Rev 10
-
- CPS 3314.01V002, "Standby Liquid Control Instrument Valve Lineup," Rev 6
-
- AR 01020914, "Missed PMT on Replaced Squib Valve, 1C41F004A"
-
- AR 01064429, "Evaluate Continued Need for LLRT on Containment Penetration 1MC116" -
- AR 01083187, "SLC Pump Calculation for NPSH Needs Revision" -
-
- CPS 3506.01P003, "Division 3 Diesel Generator Operations," Revision 4
-
- CPS 3506.01E001, "Diesel Generator and Support Systems Electrical Lineup," Revision 18a
-
- CPS 3506.01V001, "Diesel Generator and Support Systems Valve Lineup," Revision 13a -
- CPS 3506.01V002, "Diesel Generator and Support Systems Instrument Valve Lineup," Revision 11b - M05-1035, "Diesel Generator Cooling System," Sheet 8, Revision K - M05-1035, "Diesel Generator Aux System (Starting Air Exhaust and Combustion System),"
- Sheet 3, Revision AE
- M05-1035, "Diesel Generator Cooling System," Sheet 10, Revision D
- M05-1036, "Diesel Generator Fuel Oil System," Sheet 2, Revision T -
- CPS 3316.01, "Containment Combustible Gas Control," Revision 13a -
- CPS 3316.01V001, "Containment Combustible Gas Control Valve Lineup," Revision 6
-
- CPS 3316.01V002, "Containment Combustible Gas Control Instrument Valve Lineup," Revision 5 -
- CPS 3316.01E001, "Containment Combustible Gas Control Electrical Lineup," Revision 11a Attachment -
- CPS 3316.01E002, "Containment Combustible Gas Control 120 VAC Electrical Lineup," Revision 7b -
-
-
- CPS 9264.01, "Drywell/Containment Post-LOCA Vacuum Relief Setpoint Check," Revision 29b - M05-1063, "P&ID Combustible Gas Control System (HG) Clinton Power Station Unit 1," Revision N - M05-2063, "P&ID Combustible Gas Control System (HG) Clinton Power Station Unit 2," Revision F -
- WO 01367024-01, "1HG009A CGCS Compressor 1A Suction Valve Failed to Close," September 9, 2010 -
- AR 00889247, "'A' Mixing Compressor Suction Valve 1HG009A Failed to Open" -
- AR 01006218, "'A' Mixing Compressor Suction Valve 1HG009A Failed to Open"
-
- AR 01108595, "1HG009A; CGCS Compressor 1A Suction Valve; Failed to Close"
-
- AR 00826047, "1SX025A: Valve Operator & Valve Positioning Doesn't Match Up"
-
- AR 00953731, "5010-4D Trouble Isolated Phase Duct Coolers - IA1051 Shut" -
- AR 00956424, "1WS019B Cooling Water Valve Found Out of Position" -
- AR 00899300, "Spare Main Power Transformer Fans Control Switches Found in Auto"
-
- AR 00939875, "Secondary Containment LCO Action Not Entered When Required" 1R05 Fire Protection - Clinton Power Station Updated Final Safety Analysis Report, Appendix E, "Fire Protection Evaluation Report - Clinton Power Station Unit 1," Revision 11 - Clinton Power Station Updated Final Safety Analysis Report, Appendix F, "Fire Protection Safe Shutdown Analysis - Clinton Power Station Unit 1," Revision 11 -
- OP-AA-201-009, "Control of Transient Combustible Material," Revision 9 -
- OP-CL-201-009, "Control of Transient Combustible Material," Revision 1
-
- CPS 1893.04M351, "781 Control: Aux. Elect., Inverter & Battery Rooms Pre-fire Plan"; Rev 7
-
- CPS 1893.04M400, "712 Fuel:
- Basement Prefire Plan," Revision 5
-
- CPS 1893.04M740, "800 Turbine Deck Pre-fire Plan"; Rev 5 -
- CPS 1893.04M801, "699 Screen House: Div 2 & 3 SX Pump Rooms and Tunnel Pre-fire Plan"; Rev 6 1R06 Flooding Protection Measures
-
- CPS 4304.01, "Flooding," Revision 4e
-
- CPS 3813.01, "Condenser Pit Level Functional Test," Revision 9a
-
- CPS 1870.02, "Control of Drain Socks and Plugs," Revision 8 - Clinton Power Station Updated Safety Analysis Report, Revision 13 - NRC Information Notice 2009-006, "Construction-Related Experiences with Flood Protection Features," July 21, 2009 -
- SL-4576, "Internal Flooding - Safe Shutdown Analysis and INPO SOER No. 85-5 Comparison Evaluation Report" (Sargent & Lundy), January 31, 1990 - M05-1054, "P&ID Turbine Building Floor Drain (TF)," Sheet 1, Revision E - M05-1054, "P&ID Turbine Building Floor Drain (TF)," Sheet 2, Revision K - M05-1054, "P&ID Turbine Building Floor Drain (TF)," Sheet 3, Revision F
- Attachment - M05-1054, "P&ID Diesel Generator Building Floor Drain System (TF) Elevation 737'-0"," Sheet 40, Revision R - M05-1054, "P&ID Diesel Generator Building Floor Drain System (TF) Elevation 737'-0"," Sheet 41, Revision J - Engineering Change (EC)
- 380198, "Use of Floor Drain Socks in Safety Related Areas at CPS," Revision 0 -
- WO 01312346-01, "Change Out Floor Drain Socks in Power Block 1870.02," May 18, 2010
-
- WO 00896695-01, "1TF013 Remote Indication Lights Are Both Off," January 31, 2008
-
- WO 00896695-03, "Replace Actuator 1TF013 Due to Flooding," January 20, 2010 -
- AR 01023891, "1LSTF001B Failed to Actuate Per 3813.01" -
- AR 01092206, "Functionality Review of Condenser Pit Level Switch"
-
- AR 00221292, "Failed PMT on 'A' Level Switch During 3813.01"
-
- AR 01074284, "Supplemental Information for Floor Drain Socks Review"
-
- AR 01072011, "Use of Floor Drain Socks in Safety Related Areas" -
- AR 01092970, "Floor Drains in Divisional DG Trench Ways Not As Expected" -
- AR 00203272, "Condenser Pit High Level Alarm/1TF013 Closure Broke"
-
- AR 00458794, "1TF013 Remote Indication Lights Are Both Off"
-
- AR 00469129, "Maintenance Rule Functional Failure - TF System"
-
- AR 00497793, "1TF013 Will Not Isolate During Condenser Pit Flooding" -
- AR 00560611, "Potential Incorrect Decision By Expert Panel" -
- AR 00818292, "Maintenance Rule MPFF Incorrectly Classified As Not MPFF"
- 1R12 Maintenance Effectiveness
-
- EC 374726, "Limitorque Actuator Fatigue Life Extension," Revision 0 -
- ER-AA-302, "Motor-Operated Valve Program Engineering Procedure," Revision 5 -
- ER-AA-302-1001, "MOV Rising Stem Motor Operated Valve Thrust and Torque Sizing and Set-Up Window Determination Methodology," Revision 6 -
- ER-AA-302-1006, "Generic Letter 96-05 Program Motor-Operated Valve Maintenance and Testing Guidelines," Revision 9 -
- ER-AA-310, "Implementation of the Maintenance Rule," Revision 8 -
- ER-AA-310-1002, "Maintenance Rule Functions - Safety Significance Classification,"
- Revision 3
-
- ER-AA-310-1003, "Maintenance Rule - Performance Criteria Selection," Revision 3
-
- ER-AA-310-1004, "Maintenance Rule Performance Monitoring," Revision 8
- NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," Revision 2
-
- AR 01032936, "NOS ID Maintenance Rule Criteria for CW Not Appropriate"
- Maintenance Rule Failure Report for Circulating Water System, September 2008 through September 2010
- "Expert Panel Meeting Minutes - Thursday, March 25, 2010"
- "Circulating Water System Evaluation of Reliability Performance Criteria (Re:
- IR 1032936),"
- March 25, 2010
-
- ER-AA-310-1001, "Maintenance Rule - Scoping," Revision 4 - Maintenance Rule Scoping and Performance Criteria for Turbine Building Ventilation System, July 8, 2010 - Maintenance Rule Failure Report for Reliability Monitoring of Turbine Building Ventilation System, July 2008 through July 2010 - Clinton Power Station Updated Safety Analysis Report, Revision 13
-
- CPS 8501.25D001, "KAB Relay Calibration Data Sheet," Revision 3b Attachment -
- AR 00805082, "Engineering Should Evaluate Spare ERAT" -
- AR 00849593, "Rejected Service Request on MOV Valve Internals Inspections"
-
- AR 01081686, "Re-Evaluate MOV Criticality Classifications" -
- AR 01084600, "Need to Obtain a MOV HBC Grease Sample" -
- AR 01102406, "Evaluate Removing MOVs From ORM and USAR Tables" -
- AR 01107428, "1SX01FA:
- Oil Leaking From MOV"
-
- AR 01107888, "Need For MOV Risk Rank Reevaluation"
-
- AR 01119550, "MOV PM Procedure Change Will Adversely Impact CPS"
-
- AR 01120086, "Interference Seen On MOV Test Trace" -
- AR 01122366, "NRC Question On MOV Stroke Times" -
- AR 00838044, "1VT03CA:
- VT 'A' Fan Auto Tripped for No Apparent Reason"
-
- AR 00868203, "1VT03CA:
- VT Supply Fan Tripped"
-
- AR 00866452, "1VT04F:
- VT Shutdown Due to High DP on the Intake Filters"
-
- AR 00867272, "1VT01Y:
- AR 01030004, "Run Ventilation Systems Without Filters During Winter Months" -
- AR 01029903, "VT Tripped Due to Low Flow (High Suction Filter DP)
-
- AR 00860309, "1VT03CA:
- VT Fans Will Not Remain Running"
-
- AR 00867276, "1VT01Y Damper Failed Shut"
-
- AR 00911804, "Need to Verify 1VT09CA/CB/CC Fans Running" -
- AR 007236646, "C1R11 Leak Rate Test Failures for Maintenance Rule System 97 Need Evaluated" -
- AR 01044721, "Entered Loss of Instrument Air Off Normal 4004.01"
-
- AR 01048311, "1SA01D Dryer Inlet and Purge Valves Open at Same Time"
-
- WO 01117352-01, "1E12-F021/RHR C Test Valve to Suppression Pool Valve," September 15, 2010
- 1R13 Maintenance Risk Assessments and Emergent Work Control
-
- ER-AA-600, "Risk Management," Revision 5
-
- ER-AA-600-1012, "Risk Management Documentation," Revision 8 -
- ER-AA-600-1001, "On-Line Risk Management," Revision 6 -
- WC-AA-101, "On-Line Work Control Process," Revision 17
-
- WC-AA-104, "Integrated Risk Management," Revision 17
-
- CPS 3506.01C007, "Checklist to Extend 72 Hour LCO Action to 14 Day LCO for Diesel Generators (ITS 3.8.1.B.4 Bases)," Revision 0 -
- AR 01043647, "NSPS Circuit Card Not Repairable" -
- AR 01104812, "STS Failure, Unexpected Alarms and Data" -
- AR 01105478, "1G33F039 Spurious Isolation"
-
- AR 01105899, "RT Pump A Tripped 4 Seconds After Trip, Should Be 60 Seconds"
-
- AR 01105900, "STS Controller Power Supply Meter Reading Less Than 4 Amps"
-
- AR 01105962, "NSPS STS Equipment Classification On E03S and Parts Lists" -
- AR 01105965, "1G33AK03B:
- RWCU "B" Pump Time Delay Relay Does Not Pickup" -
- AR 01106292, "Entered 4010.02 Plant Chemistry Off-Normal"
-
- AR 01106315, "Rx Water Sample Results Enter Action Lvl 1"
-
- AR 01106516, "Discovered LPCI A Injection Valve Open"
-
- AR 01107300, "Document STS Failures During 9030.05 Test"
-
- AR 01108706, "Division 1 STS Universal I/O Card Failed During 9030.05" -
- AR 01108708, "Division 1 RCIC Load Driver Card Failed During 9030.05" -
- AR 01108749, "Determine Operating Options Of Self Test System"
-
- AR 01110069, "STS Off-Line"
-
- AR 01113608, "Division 2 EDG Quick-Start Time > 9080.02 Step 9.1.6 Criteria" Attachment -
- AR 01115155, "Division 1B [sic] Quick Start Time To Freq >/= 60 Hz was 11.580 seconds" -
- AR 01115308, "Division 2 DG A3 Relay Replacement Impacts
- WW 1039 (D3 Work Week)"
-
- AR 01115312, "Work Week 1102 Overloaded For EMD" - Prompt Investigation #1042507, "STS Circuit Card 1-B-A16-A112 Division 1
- NS4-5 logic card had failed its system test" -
- WO 01364893-16, "Post Maintenance Testing of Division 1
- NS4-5 Card and AC Load Driver Card 1H13P661-B-A16-A125," August 27, 2010 1R15
- Operability Evaluations -"Clinton, Reverse Engineering on 23 O-Rings,
- CPS-57679" (Test Results from Exelon
- PowerLabs, LLC Technical Services regarding O-Rings), August 11, 2009 -WO
- 01258808, "Replace O-Rings for 1C11F009 in C1R12," July 1, 2010 -WO
- 01268332, "Replace O-Rings for 1C11F182 in C1R12," June 30, 2010
-Operability Evaluation
- 950308-02, "Non-Safety O-Rings Installed in Safety-Related/EQ
- Valves," Revision 0
- V70900-45, "Valve, Solenoid 3-Way, Dual Coil," Sheet 27, Revision A
- Vendor Manual:
- Meggit Safety Systems 107OM4015, "Containment Atmosphere Hydrogen Analyzer - Operation and Maintenance Manual -
- EC 370685, "Replace Div 1 H2O2 Containment Atmosphere Monitoring"; Rev 1-4
-
-
-
- CPS 9000.10, "Accident Monitoring and Remote Shutdown Instrumentation Log"; Rev 32a -
- CPS 9437.17A, "Containment/Drywell Atmosphere H2 Monitoring System Channel Calibration"; Rev 0 -
- CPS 9437.17, "Containment/Drywell Atmosphere H2/O2 Monitoring System Channel Calibration"; Rev 42a - 50.59 Screening No.
- CL-2009-S-011, "Replace Div 1 H2O2 Containment Atmosphere Monitor
- EC 370685"; Revision 1 - Clinton Power Station Updated Final Safety Analysis Report, Revision 13 - NRC Regulatory Issue Summary 2005-20, "Revision to NRC Inspection Manual Part 9900 Technical Guidance, 'Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety,'" Revision 1 -
- AR 00950308, "Non-Safety O-Rings Installed in Safety-Related/EQ Valves" -
- AR 01021972, "C1R12:
- Vacuum Breaker 1SX303B IST Failed Closing Test" -
- AR 01093674, "Actions Needed by OPS to Declare H2 System Operable" -
- AR 01094253, "Unresolved Questions Div 1 H2 Monitor (1CM01SA) -
-
- AR 01099260, "Div 2 H2O2 Inoperable (1CM01SB)"
-
- AR 01105478, "1G33F039 Spurious Isolation"
-
- AR 01106214, "Received Main Control Room Annunciator 5063-1D RCIC Pump Suction Pressure High" -
- AR 01106516, "1E12F042A:
- Discovered LPCI A Injection Valve Open"
-
- AR 01108387, "Review Common Cause Failure for VP/WO Isolation on 3/15/10"
-
- AR 01108706, "Division 1 Self Test System Failure Assessment" -
- AR 01108708, "Division 1 Self Test System Failure Assessment" -
- AR 01108749, "Determine Operating Options of Self Test System" -
- AR 01110657, "1C71AK615B:
- Division 2 Self Test Observations"
-
- AR 01107679, "Div 3 Battery Room Is At 69F, Required To Be >/= To 68F"
-
- AR 01109546, "Div 3 Battery Room Is 68F And Is An OOS Round"
-
- AR 01110971, "NRC RI Question On Div 3 Battery Room Temp" -
- CPS 8433.01, "Generic Procedure for 125VDC Battery Maintenance," Revision 24
- Attachment -
- CPS 9382.01, "125VDC Battery Pilot Cell Check," Revision 35 -
- WO 00932592-02, "Valve 1WO060 has Erratic Operation," September 13, 2010
-
- DC-ME-09-CP, Revision 12, June 25, 1990 1R18 Plant Modifications - Adverse Condition Monitoring and Contingency Plan, "Degraded I/P 1N66K001A," June 30, 2010 - Operational and Technical Decision Making Plan #1077422, "Offgas Recombiner Drain Control Valve (1N66F016A) I/P Converter (1N66K001A)," June 28, 2010 -
- EC 380630, "Provide Temporary Air Supply For 1N66F016A To Support Maintenance Of Valve I/P 1N66K001A," Revision 0 - 50.59 Screening Number
- CL-2010-S-019 for EC #380630, "Provide Temporary Air Supply For 1N66F016A To Support Maintenance Of Valve I/P 1N66K001A," Revision 0 -
- AR 01086770, "Need Swagelok Plug Installed On IA Drain Line Valve" -
- AR 01111519, "TCC Enhancement for Div 1 STS Temp Power" -
- AR 01116280, "Work Not Aligned With OTDMP"
-
- WO 01346216-01, "I/P For 1N66K001A Recombiner Drain Control Valve," June 29, 2010
-
- WO 01346216-03, "IM Replace 1N66K001A and Remove Temp IA Supply
- 1R19 Post-Maintenance Testing -
- CPS 8800.01, "Maintenance Procedure for Fisher Controls Diaphragm/Actuators," Revision 36b -
- MA-AA-743-310, "Diagnostic Testing and Evaluation of Air Operated Valves," Revision 5
-
- CPS 9068.03, "Primary Containment Recombiner and Valve Operability Test," Revision 33a - M05-1052, "P&ID Shutdown Service Water (SX)," Sheet 1, Revision AU - M10-9105, "P&ID/C&I Diagram Hydrogen Recombiner Room Cooling System (VG)," Sheet 23, Revision A - M05-1105, "P&ID Hydrogen Recombiner Room Cooling System (VG)," Sheet 4, Revision E -
- AR 01108136, "1SX185A Max Friction Is Out of Its Acceptance Criteria"
-
- CPS 9377.01, "Fire Protection Diesel 24VDC Battery Pilot Cell Check," Revision 29 -
- CPS 1893.06, "Fire Protection Maintenance and Testing Program," Revision 10d -
- CPS 9071.01, "Diesel Driven Fire Pumps Operability Test," Revision 36a
-
- CPS 3317.01, "Fuel Pool Cooling and Cleanup," Revision 23c
-
-
- WO 01279637-02, "Post-Maintenance Test Fuel Pool Cooling Pump 1B Motor," August 13, 2010 -
- WO 01367024-01, "EM Troubleshoot/Investigate 1HG009A Fail to Close," September 8, 2010
-
- WO 01367024-02, "Post-Maintenance Test Stroke 1HG009A -
- CPS 9068.01," September 2, 2010 -
- WO 01367024-03, "EM Install Quicklook Test Gear/Measure Thrust," September 2, 2010 -
- WO 01211045-01, "Replace Diesel Fire Pump 'A' Battery Charger Regulator Circuit Boards," July 20, 2010
- Attachment -
- WO 01011258-01, "Overhaul Actuator and Replace Accessories 1SX185A," September 2, 2010 -
- WO 01011258-06, "OPS PMT 1SX185A," September 2, 2010 -
- CPS 1893.06, 'Fire Protection Maintenance and Testing Program,' for Minimum Acceptable Voltage for the Fire Protection Diesel Engine Battery While on Float Charge," Revision 0 - National Fire Protection Association (NFPA)-20, "Standard for the Installation of Stationary Pumps for Fire Protection," 2010 Edition -
- AR 01072095, "Need Engineering Change Request to Lower Fire Protection Battery Acceptance Voltage" -
- AR 01099159, "1HG009B at 3626 Strokes Triggers Actuator Refurbishment"
-
- AR 01101191, "Schedule Setup to Create Unneeded FC Swaps, Increased Dose"
-
- AR 01100597, "FC Cooling Loop Swap Not Identified On
- WW 1033 Schedule"
-
- AR 01108595, "1HG009A; CGCS Compressor 1A Suction Valve; Failed to Close" -
- 1R20 Outage Activities Crane and Heavy Lift Inspection (OpESS FY2007-03) - Design Record File F13-00062, Analysis of Head Strongback Carousel Due to Increased Loading Configuration, dated April 1993 - General Electric Report MPL No. F13-E008, Dryer and Separator Strongback, dated April 20, 1982 - Illinois Power Letter U-0249 L30-81 (06-19)-L to NRC, Subject:
- December 22, 1980 letter on Control of Heavy Loads, dated June 22, 1981 - Illinois Power Letter U-0294 L30-81 (09-25)-L to NRC, Subject:
- Clinton Power Station Units 1 and 2 Docket Nos. 50-461 and 50-462, dated September 25, 1981 - Illinois Power Letter U-06850982-L L30-83 (12-21)-L to NRC, Subject:
- Clinton Power Station Unit 1 Control of Heavy Loads (NUREG-0612), dated December 21, 1983 - Illinois Power Letter U-0800 L30-85(02-21)-6 B48-85(02-21)-6 1A.120 to NRC, Subject:
- Clinton Power Station Unit 1 Control of Heavy Loads (NUREG-0612), dated February 21, 1985 -
- NEI 08-05, "Industry Initiative on Control of Heavy Loads", dated July 2008 -
- NUREG-0853, Safety Evaluation Report Related to the Operation of Clinton Power Station, Unit No. 1, February 1982 - Supplement No. 2 to
- NUREG-0853, Safety Evaluation Report Related to the Operation of Clinton Power Station, Unit No. 1, May 1983 - Supplement No. 5 to
- NUREG-0853, Safety Evaluation Report Related to the Operation of Clinton Power Station, Unit No. 1, January 1986 - Task Interface Agreement 2010-004, "Final Response to Task Interface Agreement Single-Failure-Proof Design for Reactor Pressure Vessel Head Strongback, Dryer/Separator Strongback, and Reactor Pressure Vessel Head Lifting Lugs at Clinton Power Station", dated August 27, 2010, (ADAMS ML No. 101890187) Condition Reports Reviewed During NRC Inspection (OpESS FY2007-03) -
- AR 00966834, "Strongback Unresolved Issue Status" Attachment 1R22 Surveillance Testing -
-
-
-
- CPS 9072.01, "Steam Bypass Valve Tests," Revision 32b - American Society of Mechanical Engineers (ASME) Operations and Maintenance (OM) Code, Subsection ISTB, "Inservice Testing of Pumps in Light-Water Reactor Nuclear Power Plants,"
- 2004 Edition - ASME OM Code, Subsection ISTC, "Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants," 2004 Edition -
- AR 01097917, "Potentially Broke RCIC Suction Check Valve Operator" -
- AR 01095477, "Initial Results From Division 1 SX Flow Balance" -
- AR 01093693, "SX Flow Balance As-Found Flow Discrepancies"
-
- AR 01069618, "Locked Valve Throttling Per
- CPS 3211.01V001"
-
- AR 01084667, "1C85ADS032:
- Bypass Valve #4 Would Not Indicate Over 60 Percent Open" -
- AR 01097575, "Bypass Valve #4 Position Transmitter Card Found Degraded" -
- AR 01102051, "Tracking NRC Questions on SX Flow Balance" -
- AR 01118458, "FC Pump Motor Cooler Flow Measurement During SX Flow Balance"
-
- AR 01092223, "HPCS Valve Operability Surveillance Start Delayed"
-
- AR 01092226, "Enhancement to 9051.02, HPCS Valve Operability Test"
-
- AR 01092363, "9051.01 HPCS Pump & Water Leg Pump Resource Requirements"
-
- AR 01092477, "HPCS Flow Rate Spikes Outside Prescribed Band During 9051.01" -
- WO 01332170-01, "OP HPCS Pump & Water Leg Pump Operability (RCIC Storage Tank)," July 19, 2010 -
- WO 01349084-01, "OP HPCS Discharge Header Filled & Flow Path Verification," July 19, 2010 2RS5 Radiation Monitoring Instrumentation (71124.05) - 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 8/12/10 - 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 7/15/10 - 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 6/20/10 - 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 5/14/10
- 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 4/19/10
- 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 3/21/2010
- 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 2/15/10 - 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 6/20/10 - 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 1/30/10
- 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 12/20/09
- 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 11/13/09
- 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 10/18/09
- 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 9/18/09 - 9000.10R20; Log Accident Mon and Remote S/D Pnl Instr Log; dated 8/14/09 - 9437.65A20; CNMT/DW High Range Gamma Mon (CM059) CC (On Line); dated 10/8/09
- 9437.65; (Sections 8.8, 8.10, 8.11, 8.12) (Outage); dated 12/14/09
- Attachment - 9437.65B20; CNMT/DW High Range Gamma Mon (CM060) CC; dated 5/28/09 - 9437.65; (Sections 8.8, 8.10, 8.11, 8.12) (Outage); dated 12/14/09
- 9437.65C20; CC CNMT/DW High Range Gamma Mon (CM061); dated 1/19/10 - 9437.65C20; CC CNMT/DW High Range Gamma Mon (CM061); dated 7/12/10 - 9437.65D20; CC CNMT/DW High Range Gamma Mon (CM062); dated 11/21/08
- 9437.62F25; CC Calib of Liquid PRM (CC-1RIX-PR037); 07/21/2009
-
- RP-CL-751; Calibration of the RADECO H-809V, H-809B,
- HD-29/A, and EBERLINE
- RAS-1; Revision 0 -
- RP-CL-751 Attachment 4; RADECO
- HD-29/A Calibration Data Sheet; dated 3/31/10 - CPS No. 7211.05D006; Reference Reading for Source Check Plaque; 8/21/2010 -
- RP-CL-726; Operation and Calibration for the Eberline
- PM-7 Portal Monitors; Revision 2
-
- RP-CL-726; Attachment D;
- PM-7 Portal Monitor Calibration Record; Portal Monitor Serial Number 511; 10/11/2009 -
- RP-CL-812; Operation and Calibration of the Gamma Portal Monitor (PM-12); Revision 3 -
- RP-CL-812; Attachment A;
- PM-12 Calibration Record; Instrument Number 120; 1/5/2010 -
- RP-CL-728; Calibration of the NE Small Article Monitor (SAM); Revision 1
-
- RP-CL-728-1001; Attachment 1; Calibration Data Sheet;
- SAM 12 Serial No. 189; 4/25/2010
- CPS No. 7911.52; Calibration of
- PCM-1; Revision 0a
- CPS No. 7911.52D001;
- PCM-1 Calibration Data Sheet; Serial No. 1454; 2/15/2010 - CPS No. 7911.53; Calibration of
- PCM-2; Revision 0a - CPS No. 7911.53D001;
- PCM-2 Calibration Data Sheet; dated 11/8/09
-
- CPS 7910.90; Calibration of the FASTSCAN Whole Body Counter; Revision 4b
-
- CPS 7910.90F001; Annual FASTSCAN Body Counter Calibration; 9/8/2010
- 2009 Radiation Protection Comparative Report;
- NOSA-COMP-09-06;
- AR 849452-06; 11/4/2009 - Focused Area Self-Assessment (FASA); Radiation Monitoring Instrumentation; Assignment Number
- 01031551; 6/1/2010 - NUPIC Audit/Survey; Exelon Powerlabs (Mid Atlantic Division); NUPIC Audit/Survey Number 20402; 4/21/2009 - Review of 10CFR 60 Source Term Results; 9/20/2010 - Issue
- 01115988;
- PM-12 Portal Monitor Not Initialed After Source Check; 9/21/2010 - Issue
- 01116482; RP Calibration Performed But No Record Exists; 9/22/2010
- Issue
- 01116487; RP Calibration Performed But No Record Exists; 9/22/2010
-
- RP-CL-805; Calibration and Operation of the Gamma Calibrator; Revision 0
- 4OA1 Performance Indicator Verification -
- LS-AA-2200, "Mitigating System Performance Index Data Acquisition & Reporting," Revision 1 -
- AR 01050527, "1DG01KA: Loose Governor Linkage" -
- AR 01009827, '1DG633PA: Div 1
- DG 12VDC Fuel Priming Pump Not Running" - Nuclear Energy Institute Document 99-02, "Regulatory Assessment Performance Indicator
- Guideline," Revision 6
-
- CPS 9000.01D001, "Control Room Surveillance Log - Mode 1, 2, 3 Data Sheet," Revision 52d
- Nuclear Energy Institute 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6 - MSPI Derivation Reports, Period June 2010, for Heat Removal System, High Pressure Injection System, Residual Heat Removal System, Generation Date July 19, 2010 - RM Document Number
- CL-MSPI-01, "Clinton MSPI Basis Document," Revision 1
-
- LS-AA-2001; Collecting and Reporting of NRC Performance Indicator Data; Revision 13
- Attachment -
- LS-AA-2140 (Equivalent); Monthly Data Elements for NRC Occupational Exposure Control Effectiveness; July 2009 through August 2010 - 9911.59R20 Rec Gaseous Rad Effluent Surv - Monthly; July 2009 through August 2010 4OA2 Identification and Resolution of Problems -
- ER-AA-380, "Primary Containment Leakrate Testing Program," Revision 7 - Federal Register Volume 60, Number 186, September 26, 1995
- Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," September 1995. - Nuclear Energy Institute 94-01, "Industry Guideline for Implementing Performance-based Option of 10 CFR Part 50, Appendix J," Revision 0 - Surveillance Testing Performance Data from January 2010 through June 2010
- Local Leak Rate Testing Performance Data from January 2005 through June 2010 - Common Cause Analysis (AR 01098330), "The Use of Grace with Surveillances," September 7, 2010 -
- AR 01082317, "ITS Surveillance Scheduled Within 1 Hour of End of 25% Overrun"
-
- AR 01098830, Request CCA [Common Cause Analysis] for Use of Grace with Surveillances"
-
- ER-AA-335-007, "Ultrasonic Inspection for Determination of Sedimentation in Piping Systems or Components and Fluid Level Measurements," Revision 2 -
- CPS 3309.01, "High Pressure Core Spray," Revision 16a -
-
- EC 380824, "NRC
- GL 2008-01 Gas Intrusion Evaluate Changing Periodic UT from Monthly to Quarterly," Revision 0 -
- EC 371609, "Generic Letter 2008-01:
- Air Intrusion in ECCS Systems:
- RHR-A/LPCS," Revision 1 -
- EC 371659, "Generic Letter 2008-01:
- Air Intrusion in ECCS Systems:
- RHR-B/RHR-C," Revision 1 -
- EC 371660, "Generic Letter 2008-01:
- Air Intrusion in ECCS Systems:
- HPCS," Revision 1 -
- AR 00439211, "Plug and Stem Separated on 1FC004A" -
- AR 00725079, "1SX014A, Division 1 SX System Isolation Valve Leaks By Seat"
-
- AR 00828402, "Implement
- GL 2008-01 Commitments"
-
- AR 00847216, "NRC Finding 2008004-02:
- Failure to Evaluate Stray Voltage"
-
- AR 00847646, "NRC
- NCV 2008004-03:
- Inadequate PM of 1SX014A"
-
- AR 00924603, "1FC004A:
- FC Surge Tank High Level" -
- AR 00976237, "SR Rejection for New PMs for 1FC004A & B Valves" -
- AR 00988801, "NRC
- GL 2008-01 Request for Additional Information"
-
- AR 00992875, "NRC
- FIN 2009004-02:
- Ineffective Corrective Actions for 1FC004A Stem/Disc Failure" -
- AR 01067445, "NRC
- NCV 2010002-01:
- Transient Combustible Material Control" -
- AR 01067453, "NRC
- NCV 2010002-02:
- Transient Combustible Material Control" -
- AR 01067457, "NRC
- NCV 2010002-03:
- Unanalyzed Interconnecting Floor Drains"
-
- AR 01067460, "NRC
- NCV 2010002-04:
- Examination Limitations for a Weld"
-
- AR 01067467, "NRC
- FIN 2010002-05:
-
- AR 01067471, "NRC
- URI 2010002-06:
- OPDRV Procedure 50.59"
-
- AR 01067474, "NRC
- URI 2010002-07:
- Cause for Turbine Overspeed Trip" -
- AR 01067517, "NRC
- NCV 2010002-08:
- SGTS Flow/Heater Operability Surveillance" -
- AR 01067520, "NRC
- URI 2010002-09:
- Contaminated Individual"
-
- AR 01090277, "NOS ID Inadequate Extent of Condition for Repeat Failures"
-
- AR 01090447, "1FC004A Air Line Separated" Attachment -
- AR 01091157, "Change
- GL 2008 Air Void Ultrasonic Test Frequency from Monthly to Quarterly" -
- AR 01092819, "NRC Questions and Discussion" -
- AR 01098890, "NCV 2010003-02:
- 10CFR50.59 Review of OPDRV Procedure" -
- AR 01098906, "NRC
- NCV 2010003-04:
- ERO Augmentation Testing"
-
- AR 01098915, "NRC
- NCV 2010003-05:
- Dryer Cavity Gate Seal Failure"
-
- AR 01098887, "NRC
- NCV 2010003-01:
- Reportability for Potential RHR Pump Room Flood"
-
- AR 01098898, "NRC
- FIN 2010003-03:
- Failure to Evaluate EFCV Functionality"
-
- AR 01099320, "CA
- 1033113-03 Extension Paperwork" - Service Request #63892, "New PMs for the 1FC004A & B Valves" -
- WO 01349084-02, "EP Perform UT Testing to Check for Accumulated Air (HPCS)," July 19, 2010 4OA3 Follow-Up of Events and Notices of Enforcement Discretion -
- LER 05000461/2010-002-01, "Excessive Leakage Through Feedwater Isolation Valve 1B21F032B," Supplement 1, August 23, 2010 -
- LER 05000461/2008-003-01, "Excessive Leakage Through Feedwater Isolation Valve 1B21F032A," Supplement 1, August 23, 2010 4OA5 Other Activities - NRC Form 748 (Equivalent); National Source Tracking Transaction Report; Clinton Power Station; 9/22/2010
- Attachment
LIST OF ACRONYMS
- USED [[]]
CAP Corrective Action Program CPS Clinton Power Station
DC Direct Current
GPM Gallons Per Minute
- LL [[]]
- MS [[]]
- NS [[]]
- PA [[]]
- RC [[]]
IC Reactor Core Isolation Cooling
- RE [[]]
RPV Reactor Pressure Vessel RT Reactor Water Cleanup
SR Surveillance Requirements
- UFS [[]]
AR Updated Final Safety Analysis Report
URI Unresolved Item
UT Ultrasonic Tests
VAC Volts Alternating Current
WO Work Order
October 28, 2010 Mr. Michael
President and Chief Nuclear Officer (CNO), Exelon Nuclear
4300 Winfield Road
Warrenville,
- POWER [[]]
- INTEGR [[]]
- ATED [[]]
- INSPEC [[]]
- TION [[]]
- REPORT 05000461/2010-004 Dear Mr. Pacilio: On September 30, 2010, the U.S. Nuclear Regulatory Commission (
NRC) completed an inspection at your Clinton Power Station. The enclosed report documents the results of this
inspection, which were discussed on October 7, 2010, with Mr. F. Kearney, and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed
personnel. Based on the results of this inspection, no findings of significance were identified. In accordance with
- NRC 's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the
- NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely, /RA/ Mark
Enclosure: Inspection Report 05000461/2010-004; w/Attachment: Supplemental Information cc w/encl: Distribution via ListServ