IR 05000352/2010002
| ML101250646 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/05/2010 |
| From: | Krohn P G Reactor Projects Region 1 Branch 4 |
| To: | Pardee C G Exelon Generation Co |
| KROHN P G, RI/DRP/PB4/610-337-5120 | |
| References | |
| IR-10-002 | |
| Download: ML101250646 (32) | |
Text
UNITED NUCLEAR REGULATORY REGION 475 ALLENDALE KING OF PRUSSIA, PENNSYLVANIA May 5, 2010 Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief NUclear Officer, Exelon Nuclear 4300 Road Warrenville, IL 60555 LIMERICK GENERATING STATION -NRC INTEGRATED REPORT 05000352/2010002 AND
Dear Mr. Pardee:
On March 31, 2010, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at the Limerick Generating Station Units 1 and 2. The enclosed integrated inspection report documents the inspection results which were discussed on April 16, 2010, with Mr. C. Mudrick 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 inspecltors reviewed selected procedures and records, observed activities, and interviewed personnel.
Bases 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 (PARS) component of the 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,Projects Branch 4 Division of Reactor Projects Docket Nos.: 50-352, 50-353 License Nos: NPF-39. NPF-85 Inspection Report 0500035212010002 and 05000353/2010002
w/Attachment:
Supplemental Information cc Distribution via ListServ May 5.2010 Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville.IL 60555 LIMERICK GENERATING STATION -NRC INTEGRATED INSPECTION REPORT 05000352/2010002 AND 05000353/2010002
Dear Mr. Pardee:
On March 31, 2010. the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at the Limerick Generating Station Units 1 and 2. The enclosed integrated inspection report documents the inspection results which were discussed on April 16. 2010. with Mr. C. Mudrick and other members of your staff. The inspe,:;tion 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.
Bases 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 ofthis 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 (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://WWVlI.nrc.gov/reading-rm/adams.html(the Public Electronic Reading Room).
Sincerely,IRA! Paul G. Krohn, Chief Projects Branch 4 Division of Reactor Projects Distribution w/encl: S. Collins, P. Krohn, DRP G. Cowan. Resident OA M. Dapas. A. Rosebrook, DRP L. Trocine. RI, OEDO D. Lew, E. Torres, DRP RidsNrrDorlLpl1-2 Resource J. Clifford.
DRP J. Bream, RidsNrrPMLimericK Resource D. Roberts, E. DiPaolo, DRP, SRI ROPreportsResource@nrc.gov P. Wilson, N. Sieller, DRP, RI SUNSI Review Complete:
AAR (Reviewer's Initials)
ML 101250646 DOCUMENT NAME:G;\DRP\BRANCH4\lnspeGtion Reports\Umerick\LIM 2010 1st Qtr\2010-o02.rev1.doc After declaring this document "An Official Agency Record" it will be released to the Pubic, To receive at copy of this document, indicate in the box: "C* =Copy without attachment/enclosure "E" =Copy with attachmentt.:mciosure "N" =No copy . RIIDRP RI/DRP RIIDRP EDiPaololvia AR PKrohn/PK 05/04110 10 OFFICIAL RECORD COpy U. S. NUCLEAR REGULATORY COMMISSION REGION I Dockelt Nos: 50-352, 50-353 License Nos: NPF-39, NPF-85 Report No: 05000352/2010002 and 05000353/2010002 Licensee:
Exelon Generation Company, LLC Facility:
Limerick Generating Station, Units 1 & 2 Location:
Sanatoga, PA 19464 Dates: January 1, 2010 through March 31,2010 Inspectors:
E. DiPaolo, Senior Resident Inspector N. Sieller, Resident Inspector A. Rosebrook, Senior Project Engineer J. Ayala, Project Engineer M. Balazik, Reactor Inspector A. Rao, Project Engineer T. Moslak, Health Physicist M. Patel, Reactor Inspector N. Lafferty.
Reactor Inspector J. D'Antonio, Operations Engineer Approved by: Paul G. Krohn, Chief Projects Branch 4 Division of Reactor Projects Enclosure TABLE OF
SUMMARY OF FINDINGS
...........................................................................................................
REPORT DETAILS
REACTOR SAFETY
...........................................................................................................1 R01 Adverse Weather Protection
...............................................................................
1R04 Equipment
Alignment
...........................................................................................1 R05 Fire Protection
.....................................................................................................'I R06 Flood Protection Measures ..................................................................................1 R07 Heat Sink Performance
........................................................................................1 R11 Licensed Operator Requalification Program .........................................................1 R 12 Maintenance Effectiveness
..................................................................................1 R 13 Ma intenance Risk Assessments and Emergent Work Contro I ............................1 R15 Operability Evaluations
........................................................................................
1R18 Plant Modifications
.............................................................................................1 R 19 Post-Maintenance Testing .................................................................................1 R20 Refueling and Other Outage Activities
...............................................................1 R22 Surveillance Testing ..........................................................................................RADIATION SAFETy .......................................................................................................2RS01 Radiological Hazard Assessment and Exposure Controls .................................2RS02 Occupational ALARA Planning and Controls .....................................................2RS0:3 In-Plant Airborne Radioactivity Control and Mitigatlon
........................................2RS04 Occupational Dose Assessment
.......................................................................OTHER ACTIVITI ES ........................................................................................................40A 1 PI Verification
.....................................................................................................40A2 Identification and Resolution of Problems ..........................................................40A3 Event Follow-up
...........................................................
- ..................................... 40A5 Other Activities
...................................................................................................40A6 Meetings, Including Exit .....................................................................................
=SUPPLEMENTAL
INFORMATION=
KEY POINTS OF CONTACT
Exelon Generation
Company C. Mudrick. Site Vice President
- E. Callan. Plant Manager D. Merchant, Manager, Radiation
Protection
- R. Dickinson, Manager of Nuclear Training
- P. Gardner, Director, Operations
- R. Kreider, Director, Maintenance
- T. Moore, Director, Engineering
- C. Rich, Dire!ctor, Work Management
- J. Hunter, Mianager, Regulatory
Assurance
- D. Palena, Manager, Nuclear Oversight
- S. Bobyock, Manager, Plant Engineering
- F. Michaels, Manager, Electrical
Engineering
Systems
- E. Dennin, Shift Operations
Superintendent
- C. Gray. Manager, Radiological
Engineering
- R. Harding, Engineer, Regulatory
Assurance
- R. Gosby, Radiation
Protection
Technician, Instrumentation
- J. Sprucinski, Senior Radiation
Protection
Technician
- D. Wahl, Environmental
Scientist
- D. Monahan, Simulator
Operatorflnstructor
- R. George, Manager, Electrical
Design
- C. Pragman, Exelon, Corporate
Fire Protection
Engineer
- P. Tarpinian, Probability
Risk Assessment
- K. Ferich, Limerick Emergency
Planning Manager
- M. Crim, Emergency
Preparedness
Coordinator
- R. Rogers, Exelon Facility and Equipment
Coordinator
Bell, Senior Radiation
Protection
Technician
- D. Kern, Senior Radiation
Protection
Technician
J. Risteter.
Radiation
Protection
Supervisor, Technical
Support
- B. Tracey, System Engineer
- J. Kirkpatriclc, Health PhysiCS Supervisor
Other Attendees
- M. Murphy, Inspector
Commonwealth
of Pennsylvania
LIST OF ITEMS
OPENED, CLOSED, AND
Opened
None
Closed
- 05000353/2009-001-00
- LER Valid Actuation
of the D23 Emergency
- Diesel Generator
- Bus Undervoltage
- Logic (Section 40A3.2)
- 05000352 &05000353/2009-007-01
- NOV Failure to Follow Worker Tagout Procedure (Section 40A5.1)
- 05000352 &
- 05000353/2009-007-02
- NOV Failure to provide Complete and Accurate Information
on Worker Tagout Clearance
- Forms (Section 40A5.1)
Opened and Closed
None
Discussed
None
LIST OF DOCUMENTS
REVIEWED Section 1 R01: Adverse Weather Protection
Procedures
- SE-9, Preparation for Severe Weather, Revision 27
- OP-AA-1 08-111-1 001, Severe Weather and Natural Disaster Guidelines, Revision 4
- SE-14, Snow, Revision 14
- OP-AA-106-101-1001, Event Response Guidelines, Revision 16
- WC-AA-101, On Line Work Control Process, Revision 17 Issue Reports
- IR 1021820, Old Spray Pond Shed Damaged
Section 1R04: EguiQment
- Alignment
Procedures
- OS78.1.8 (COL), Equipment Alignment for Control Room HVAC Isolution and Emergency Fresh Air Supply, Revision 10 S76.1.C SGTS and RERS Set up for Automatic Initiation, Revision 14 1 S76.1 C (COL), Equipment Alignment of Standby Gas Treatment System Reactor Enclosure, Revision 12 S76.8A Manual Start up and Shutdown of SGTS, Revision 18 Attachment
- IS 52.1.A (COL01), Equipment Alignment for Core Spray Loop 'A' Operation, Revision 14 Issue
- IR 1093561, Retorque system 051, loop 'A' drywell
- IR 766310. 1A RERS flow low per
- IR 811448, 1 A RERS flow element
replacement strategy
- IR 885367,
- FD-C-076-192A
failed causing a low flow trip of A RERS
- IR 1007300, Install test connection downstream of 1A RERS flow
- IR 1008425, 1AN213 tripped during SGTS/RERS
flow
- IR 1009012, Field wiring different from control
- IR 1009658, Nuts and washers loose and other missing on RERS
- IR 1011819, 1A RERS fan trip 2 min after lR
- 1048926, Recommend
- FT-076-195A
be recalibrated or
- Work Orders:
- C0229277, Repair/Replace the
- Miscetlaneous
- 8031-M-76, Reactor Enclosure and Refueling area HVAC P&ID, Sheet 6, Revision 32 Section 1 R05: Fire Protection
Procedures
- F-R-102, Revision 06, Unit1 A and C, RHR Heat Exchanger and Pump Room,
- PRB-Fire Plan F-R-108, Revision 08, Unit 1 RCIC Pump Room, 108 Pre-Fire Plant Pre-Fire Plan, F-R-11 0, Revision 8 Pre-Fire Plan, F-R-117, Revision 8 Pre-Fire Plan, F-R-113, Revision 8 Pre-Fire Plan, F-R-114, Revision 9
- ST-2-022-630-1, Fire Detection
-Smoke Detection Instrumentation Channel Functional Test, Zones 31 , 32, Revision 15
- ST-2-022-607-1, Fire Detection
-Smoke Detection Instrumentation Channel Functional Test and Supervisory Circuit Operability Test, Zones 33, 34, 35, 36, 37, 38, 39 and 40, Revision 19
- ST-2-022-649-1, Fire Detection
-Heat Detection Instrumentation Channel Functional Test and SuperVisory Circuit Operability Test, Zones 33 and 34, Revision 12 F-D-315D, Unit 2, D24 Diesel Generator and Fuel Oil-Lube Oil Tank Room (elevation
- 217), Fire Area 86, Revision 5 E-1661, Communication
& Fire Alarm Layout Reactor Enclosure Unit -1, Revision 10 E-1660, Communication
& Fire Alarm Layout Reactor Enclosure Unit*1, Revision 9 Procedures Special Event Procedure,
- SE-8, Fire Revision 34 Section 1 R06: Flood Protection Measures Procedures
- SE-4-1, Reactor Enclosure Flooding, Revision 8
- SE4-3, Flooding External to Power Block, Revision 4 Attachment
- SE-4, Flood, Revision 6 S09.3 B, Filling the Cooling Tower and Circulatory Water System, Revision 20 Issue IR IR Miscellaneous
Condition Report
- L91-220 Revision 2
Section 1R07: Heat Sink Performance
Procedures
- RT-2-011-395-2, 2BV211 Core Spray Room Cooler Air to Water Heat Transfer Test, Revision 6
- RT-2-011-394-1, 1 EV211 Core Spray Room Cooler Air to Water Heat Transfer Test, Revision 7
- RT-1-011-390-0, ESW Room Cooler Heat Transfer Performance Calculation Test, Revision
- RT-1-011-390-0, ESW Room Cooler Heat Transfer Performance Calculation Test, Revision
Section 1R12: Maintenance
- Effectiveness
- OP-AA-10B-115, Operability Determinations, Revision MaintenanCE' Rule Expert Panel Meeting Minutes for January Issue Reports
- IR 1019308. ESW increased frequency throttle valve flush
- IR 975559, IFV210 below minimum flow
- IR 1006912, Unit 1 "At! RHR unit cooler flow left below minimum
- IR 1034554, HPCI unit cooler maintenance rule functional failure
- IR 1001013, Gap identified in ESW performance monitoring criteria
- IR 1001431, ESW maintenance rule a (1) determination
- ER-AA-31 0-1 004, maintenance rule performance monitoring, Revision 8
- ER-AA-310-1001, maintenance rule scoping, Revision 3 Other Documents Technical Specification Bases 3/4.5.1 UFSAR Section 6.3. Emergency Core Cooling System A1683097, Evaluate Results of ESW and RHRSW NDE Examinations
Section 1R13: Maintenance
- Risk Assessments and Emergent Work Control Issue Reports
- IR 984431, 2009
- CDBI-Preconditioning of ESW Flow Verification Test
- IR 977266, Unit 1 HPCI Unit Coolers Found with No/Low Flow lR
- 979516, HPCI Unit Cooler Availability Assessment
- SE-9 "Preparation for Severe Weather, Revision 27
- EP-AA-111, Emergency Classification and Emergency Classification and Protection Action, Revision 15 Attachment
- OP-AA-108-111-1001, Severe Weather and National Disaster Guideline, Revision 4
- SE-14, "Snow" Revision 14;
- OP-AA-108-111w1001, "Severe Weather and National Weather Disaster Guidelines", Revision
- WC-AA-1 01" Online Work Control Process, Revision
- WC-LG-1 01**1001, Guideline for the Performance of Online Work/Online System Revision '12 Miscellaneous Operations Brief Sheet -LGS Paragon Model Revision T Changes. effective February 6, 2006
Section 1R15: Operability
- Evaluations Issue
- PI-042-2R011
requires
- IR 1023344, Unit 1, 'A' RHR pump room cooler (1AV 210) low
- IR 1031938, '8', RHR service water radiation monitor low
- IR 1047618, Unit 1, electro-hydraulic accumulators associated with turbine bypass found not fully charged
- IR 0885591, Pressure indication optimization
- PI-42-2R011
reads high
- IR 1023344, 1A-V210 low flow
- HV-078-02.0A
damper failed to close fully Procedures
- ST-6-107-595-2, Monthly Surveillance Log OPCON 1, 2, or 3, performed
- 2/15/09 ST -2-088-409-1, Remote Shutdown System Reactor Vessel Pressure Calibration (PT-042-1
- N006,
- PI-042-1 R011). Revision 8 MiscellaneoLis
- 09-0015-2, Temporary Change Control Form, dated 01112/09 09-0025-2, Temporary Change Control Form, dated 01/18/09 8031-M-42, Nuclear Boiler Vessel Instrumentation
- P&ID, Revision 21
Section 1R19: Post-Maintenance
- Testing Issue Report§.
- IR 1028881, Crankcase eductor air in-leakage
- IR 103020A, Room cooler over pressurization during pressure
- IR 1047688, U-042:"1 R61 a not able to be calibrated within tolerance Work Order
- C0230739, Rework 6" RCIC steam valve internals
- C0230736, Limitorque diagnostics and support for valve work R1
- 092911, Accident monitoring
-reactor vessel level calibration
- I functional
- R1160079, Steps outstanding for L 1-042-1R610
- R1096703, Inspect andoverhaul waterside components for control rod drive hydraulic control Unit 02-27; Attachment
Procedures
- Accident Monitoring
-Reactor Vessel Water Level Calibration/Functional Test, Revision 10 Miscellaneous
- A1565145, Evaluation
- 17, Engineering Evaluation of Deferral of Quarterly Stroke Testing of ESW Check Valve 011-1011 Test Results Evaluation
- 09-192, dated November 19, 2009 Exelon Nine-Month Response to Generic Letter 2008-01, October 14, 2008 Section 1
- Refueling and Other Outage Activities
Procedures
- M-041-079, Reactor Vessel Bottom Head Drain Cleaning and Plug Installation/Removal, Revision 3
- OU-AA-103, Shutdown Safety Management Program, Revision 10
- OU-AA-104, Shutdown Safety Management Program, Revision 10
- GP-6.2, Shutdown Operations-Refueling, Core Alterations and Core Off-Loading, Revision 45
- GP-3, Normal Plant Shutdown, Revision 129
- OU-AB-4001, BWR Fuel Handling Practices, Revision 4
- OP-AA-300-1520, Reactivity Management-Fuel Handling Storage and Refueling, Revision 2 S97.0.M, Refueling Platform Operation, Revision 27 Miscellaneous
- GEK-90-90391, Operation and Maintenance Instruction, RPV Bottom Head Drain Plug, May 1984 1R13 Shutdown Safety Plan, March 16, 2010 Section 1 R22: Surveillance Testing Procedures
'D' ESW Pump, Valve & Flow Test (1ST), Revision 75
- ST-2-042-933-2, RPS and NSSSS -Reactor Vessel Water Level-Low, Level 3; Division IB, Channel B Response Time Test, Revision 9
- ST-2-061-600-2, Reactor Coolant System Leakage Detection System -Drywell Floor Drain Sump Level and Flow Functional Test, Revision 9 ST-6-049-230-1.
- RCIC Pump, Valve and Flow Test (1ST). Revision 72
- RT-3-047-640-01, Fuel Channel Distortion Monitoring, Revision 15
- ST-6-092-118-1,014
- Diese1 Generator
- KV SFGD -Loss of Power LSF/SAA and Outage Testing, Revision 16 Issue Reports
- IR 1049144, D144-R-E-04
failed to shunt trip
- IR 1049131, 014 LOCAILOOP
auto start bypass light not lit
- IR 1049011, D134-C-B-14
seismic clip stripped Section 2RSi01 -2RS04
- RP-MA-403-1
- 001, Revision 3 Radiation Work Permit Processing
- Revision 3 Exposure Control and Authorization
- RP-AA-210, Revision 15 Dosimetry Issue, Usage, and Control
- RP-AA-220, Revision 5 Bioassay Program Attachment
- RP-LG-220-1001, Revision 5 Perform Calibration Checks and Whole Body Count on AccuScan RP-LG-220-1002.
- Revision 3 Perform Calibration Checks and Whole Body Count on FastScan
- RP-LG-225, Revision 1 Calibration of Canberra AccuScan and FastScan Whole Body Counters
- RP-AA-222, Revision 3 Timating Internal Exposure from In Vivo and In Vitro Bioassay Data
- RP-AA-250, Revision 4 External Dose Assessments From Contamination
- RP-LG-300-102, Revision 2 Removing Items from the Spent Fuel Pool, Reactor Cavity Equipment Pit, or Cask Pit
- RP-AA-301, Revision 2 Radiological Air Sampling Program
- RP-AA-350, Revision 7 Personnel Contamination Monitoring.
- Decontamination.
and Reporting
- Revision 2 Radiological Postings.
- Labeling, and Markings
- Revision 3 Emergent Dose Control and Authorization
- RP-AA-401, Revision 9 Operational
- Revision 1 Administration of the Radiation Work Permit Program
- RP-AA-460, Revision 19 Controls for High and Very High Radiation Areas
- RP-LG-460-1
- 2. Revision 4 Initial Entry into the Drywell RP-LG-460-1016.
- ReviSion 9 Radiation Protection Controlled Keys RT-0-100-460-0.
- Revision 3 High Radiation and Locked High Radiation Door Preventative Maintenance Inspection
- ST-0-107-493-0, Rev 12 Periodic Byproduct Material Leakage Test and InVentory
- Fire Detection-Smoke Detection Instrumentation Channel Functional Test, Zones 31,32, Revision 15
- Fire Detection-Smoke Detection Instrumentation Channel 10
- CFR 50. j'2 Event Notification
- 693, Technical Support Center Emergency Ventilation System Maintenance
- 200 F-01 Station Emergency Director Checklist, Revision F Radiation Protection Group Info 09-L-035, 09-L-036,
- ISSUE REEORTS (Access Control/ALARA
related
- 1053795,1053751,1046685,1046683,1046681,1046546,
- 1044977,
- 1045183,1042839.1051659,1051357,1048509,
- CAUSE
- Apparent Cause Evaluation for IR
- Radiation Work Permits (RWPl/ALARA
- PLANS
- RWP 86, DW Reactor Pressure Vessel Nozzle & Skirt In-Service Inspections/AP
- RWP 60, Rei3ctor Disassembly/AP
- RWP 63/64. Reactor Cavity Decontamination/AP:
- RP-LG-401-1001
&
- Suppression Pool Diving and Support 1 R 13 Refuel Floor -Middle
- STATION ALARA COUNCIL MEETING
- NUCLEAR OVERSIGHT
- NOSPA-10-'lT, Effectiveness of Radiological Controls during Air Sample Analysis Sheets Survey 10-02171, 1()-02206, 10-02459,10-02811,10-03061,10-03071, 10-02752,
- 10-02645, 10-01896, 10-02293, 10-02471, 10-02560, 10-02999, 10-03060,
- 10-02925,10-02840,
- MISCELLANEOUS
- Dose and Dose Rate Alarm Reports for period 1/1/2010
- Dosimeter Alarm Locked Door Daily Status Basis for Electronic Dosimeter Dose and Dose Rate Set BRAC Data Points for Unit Three Year Rolling Average Cumulative Exposure for Unit 1 and Unit
Section 40A1: Performance
- Indicator Verification
Miscellaneous
- NEI 99-02, Regulatory Assessment Performance Indicator
- GUideline, Revision 5 HPCI System Engineer's notebook RCIC System Engineer's notebook Miscellaneous short duration LCO log entries from 1/1/2009 through 12131/2009
Miscellaneous
control room log entries from 111/2009 through 12131/2009
Section 40A2: Problem Identification
& Resolution Issue Reports IR657596
- IR 787602
- IR 725476
- IR 888962
- IR 737527
- IR 900414
- IR 768797
- IR 907453
- IR 774682
- IR 909312
- IR 974132 Miscellaneous
- OP-AA-10B-'111, Adverse Condition Monitoring and Contingency Plan, Revision 5 Recirculation Flow Control System Training Manual, Revision 3 I! . I Attachment
LIST OF ACRONYMS
Agencywide
Documents
Access Management
System ALARA Plan Corrective
Action Program control room emergency
fresh air supply core spray circulating
water emergency
core cooling systems emergency
diesel generator
emergency
service water high radiation
areas high pressure coolant injection
Inspection
Manual Chapter issue report licensee event report locked high radiation
area Nuclear Regulatory
Commission
out of service operational
condition
Publicly Available
Records performance
indicator
plant piping and instrumentation
diagrams reactor core isolation
cooling reactor enclosure
recirculation
system residual heat removal residual heat removal service water rated thermal power radiation
work permit significance
determination
process structure, system, component
standby gas treatment
surveillance
test service water total effective
dose equivalent
technical
specification
updated final safety analysis report .uninterruptable
power supply very high radiation
area Attachment