IR 05000352/2010002: Difference between revisions

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{{Adams|number = ML101250646}}
{{Adams
| number = ML101250646
| issue date = 05/05/2010
| title = IR 05000352-10-002, 05000353-10-002; 01/01/2010 - 03/31/2010; Limerick Generating Station, Units 1 and 2; Routine Integrated Report
| author name = Krohn P G
| author affiliation = NRC/RGN-I/DRP/PB4
| addressee name = Pardee C G
| addressee affiliation = Exelon Generation Co, LLC
| docket = 05000352, 05000353
| license number = NPF-039, NPF-085
| contact person = KROHN P G, RI/DRP/PB4/610-337-5120
| document report number = IR-10-002
| document type = Inspection Report, Letter
| page count = 32
}}


{{IR-Nav| site = 05000352 | year = 2010 | report number = 002 }}
{{IR-Nav| site = 05000352 | year = 2010 | report number = 002 }}
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==Dear Mr. Pardee:==
==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).
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  
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  
Line 15: Line 35:


==Dear Mr. Pardee:==
==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).
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.


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) ML101250646 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  
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=
=SUMMARY OF FINDINGS=
Line 25: Line 63:


==REACTOR SAFETY==
==REACTOR SAFETY==
...........................................................................................................1R01 Adverse Weather Protection ...............................................................................1R04 Equipment Alignment ...........................................................................................1R05 Fire Protection .....................................................................................................'I R06 Flood Protection Measures ..................................................................................1R07 Heat Sink Performance ........................................................................................1R11 Licensed Operator Requalification Program .........................................................1R12 Maintenance Effectiveness ..................................................................................1R13 Maintenance Risk Assessments and Emergent Work Contro I ............................1R15 Operability Evaluations ........................................................................................1R18 Plant Modifications .............................................................................................1R19 Post-Maintenance Testing .................................................................................1R20 Refueling and Other Outage Activities ...............................................................1R22 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 ........................................................................................................40A1 PI Verification.....................................................................................................40A2 Identification and Resolution of Problems ..........................................................40A3 Event Follow-up ........................................................... : ..................................... 40A5 Other Activities ...................................................................................................40A6 Meetings, Including Exit .....................................................................................
...........................................................................................................1 R01 Adverse Weather Protection  
...............................................................................
{{a|1R04}}
==1R04 Equipment==


=SUPPLEMENTAL INFORMATION=
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
........................................................................................
{{a|1R18}}
==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==
==KEY POINTS OF CONTACT==
Exelon Generation Company  
Exelon Generation
: [[contact::C. Mudrick. Site Vice President E. Callan. Plant Manager D. Merchant]], Manager, Radiation Protection  
Company C. Mudrick. Site Vice President
: [[contact::E. Callan. Plant Manager D. Merchant]], Manager, Radiation
Protection  
: [[contact::R. Dickinson]], Manager of Nuclear Training  
: [[contact::R. Dickinson]], Manager of Nuclear Training  
: [[contact::P. Gardner]], Director, Operations  
: [[contact::P. Gardner]], Director, Operations  
Line 37: Line 99:
: [[contact::T. Moore]], Director, Engineering  
: [[contact::T. Moore]], Director, Engineering  
: [[contact::C. Rich]], Dire!ctor, Work Management  
: [[contact::C. Rich]], Dire!ctor, Work Management  
: [[contact::J. Hunter]], Mianager, Regulatory Assurance  
: [[contact::J. Hunter]], Mianager, Regulatory
Assurance  
: [[contact::D. Palena]], Manager, Nuclear Oversight  
: [[contact::D. Palena]], Manager, Nuclear Oversight  
: [[contact::S. Bobyock]], Manager, Plant Engineering  
: [[contact::S. Bobyock]], Manager, Plant Engineering  
: [[contact::F. Michaels]], Manager, Electrical Engineering Systems  
: [[contact::F. Michaels]], Manager, Electrical
: [[contact::E. Dennin]], Shift Operations Superintendent  
Engineering
: [[contact::C. Gray. Manager]], Radiological Engineering  
Systems  
: [[contact::R. Harding]], Engineer, Regulatory Assurance  
: [[contact::E. Dennin]], Shift Operations
: [[contact::R. Gosby]], Radiation Protection Technician, Instrumentation  
Superintendent  
: [[contact::J. Sprucinski]], Senior Radiation Protection Technician  
: [[contact::C. Gray. Manager]], Radiological
: [[contact::D. Wahl]], Environmental Scientist  
Engineering  
: [[contact::D. Monahan]], Simulator Operatorflnstructor  
: [[contact::R. Harding]], Engineer, Regulatory
: [[contact::R. George]], Manager, Electrical Design  
Assurance  
: [[contact::C. Pragman]], Exelon, Corporate Fire Protection Engineer  
: [[contact::R. Gosby]], Radiation
: [[contact::P. Tarpinian]], Probability Risk Assessment  
Protection
: [[contact::K. Ferich]], Limerick Emergency Planning Manager  
Technician, Instrumentation  
: [[contact::M. Crim]], Emergency Preparedness Coordinator  
: [[contact::J. Sprucinski]], Senior Radiation
: [[contact::R. Rogers]], Exelon Facility and Equipment Coordinator Bell, Senior Radiation Protection Technician  
Protection
: [[contact::D. Kern]], Senior Radiation Protection Technician  
Technician  
: [[contact::J. Risteter. Radiation Protection Supervisor]], Technical Support  
: [[contact::D. Wahl]], Environmental
Scientist  
: [[contact::D. Monahan]], Simulator
Operatorflnstructor  
: [[contact::R. George]], Manager, Electrical
Design  
: [[contact::C. Pragman]], Exelon, Corporate
Fire Protection
Engineer  
: [[contact::P. Tarpinian]], Probability
Risk Assessment  
: [[contact::K. Ferich]], Limerick Emergency
Planning Manager  
: [[contact::M. Crim]], Emergency
Preparedness
Coordinator  
: [[contact::R. Rogers]], Exelon Facility and Equipment
Coordinator
Bell, Senior Radiation
Protection
Technician  
: [[contact::D. Kern]], Senior Radiation
Protection
Technician
J. Risteter.
Radiation
Protection
Supervisor, Technical
Support  
: [[contact::B. Tracey]], System Engineer  
: [[contact::B. Tracey]], System Engineer  
: [[contact::J. Kirkpatriclc]], Health PhysiCS Supervisor Other Attendees  
: [[contact::J. Kirkpatriclc]], Health PhysiCS Supervisor
: [[contact::M. Murphy]], Inspector Commonwealth of Pennsylvania Attachment 
Other Attendees  
: [[contact::M. Murphy]], Inspector
Commonwealth
of Pennsylvania  


==LIST OF ITEMS==
==LIST OF ITEMS==
OPENED, CLOSED, AND Opened None  
OPENED, CLOSED, AND  
 
===Opened===
None  
===Closed===
===Closed===
: [[Closes LER::05000353/LER-2009-001]]-00 LER Valid Actuation of the D23 Emergency Diesel Generator Bus Undervoltage Logic (Section 40A3.2)  
: 05000353/2009-001-00  
: 05000352 &05000353/2009-007-01 NOV Failure to Follow Worker Tagout Procedure (Section 40A5.1)  
: 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 &  
: 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  
: 05000353/2009-007-02  
==LIST OF DOCUMENTS REVIEWED==
: NOV Failure to provide Complete and Accurate Information
Section 1 R01: Adverse Weather Protection Procedures
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
: SE-9, Preparation for Severe Weather, Revision 27
: OP-AA-1 08-111-1 001, Severe Weather and Natural Disaster Guidelines, Revision 4
: OP-AA-1 08-111-1 001, Severe Weather and Natural Disaster Guidelines, Revision 4
Line 76: Line 188:
: IR 1021820, Old Spray Pond Shed Damaged
: IR 1021820, Old Spray Pond Shed Damaged


==Section 1R04: EguiQment Alignment Procedures==
==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
: 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
: IS 52.1.A (COL01), Equipment Alignment for Core Spray Loop 'A' Operation, Revision 14 Issue
Line 82: Line 196:
: IR 766310. 1A RERS flow low per
: IR 766310. 1A RERS flow low per
: IR 811448, 1 A RERS flow element
: IR 811448, 1 A RERS flow element
: FE-076-195A replacement strategy
: FE-076-195A
replacement strategy
: IR 816856. 1A RERS damper
: IR 816856. 1A RERS damper
: IR 885367,
: IR 885367,
: FD-C-076-192A failed causing a low flow trip of A RERS
: FD-C-076-192A
failed causing a low flow trip of A RERS
: IR 1007300, Install test connection downstream of 1A RERS flow
: IR 1007300, Install test connection downstream of 1A RERS flow
: IR 1008425, 1AN213 tripped during SGTS/RERS flow
: IR 1008425, 1AN213 tripped during SGTS/RERS
flow
: IR 1009012, Field wiring different from control
: IR 1009012, Field wiring different from control
: IR 1009658, Nuts and washers loose and other missing on RERS
: IR 1009658, Nuts and washers loose and other missing on RERS
: IR 1011819, 1A RERS fan trip 2 min after lR
: IR 1011819, 1A RERS fan trip 2 min after lR
: 1048926, Recommend
: 1048926, Recommend
: FT-076-195A be recalibrated or Work Orders:
: FT-076-195A
be recalibrated or  
: Work Orders:
: C0229277, Repair/Replace the
: C0229277, Repair/Replace the
: FE-076-195A 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,
: FE-076-195A  
: 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
: 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-2-022-630-1, Fire Detection  
: 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
-Smoke Detection Instrumentation Channel Functional Test, Zones 31 , 32, Revision 15
: 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,
: 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-8, Fire Revision 34 Section 1 R06: Flood Protection Measures Procedures
: SE-4-1, Reactor Enclosure Flooding, Revision 8
: SE-4-1, Reactor Enclosure Flooding, Revision 8
: SE4-3, Flooding External to Power Block, Revision 4 Attachment
: 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
: 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==


==Section 1R07: Heat Sink Performance Procedures==
===Procedures===
: RT-2-011-395-2, 2BV211 Core Spray Room Cooler Air to Water Heat Transfer Test, Revision 6
: 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-2-011-394-1, 1 EV211 Core Spray Room Cooler Air to Water Heat Transfer Test, Revision 7
Line 110: Line 243:
: 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==
==Section 1R12: Maintenance==
: Effectiveness
: OP-AA-10B-115, Operability Determinations, Revision MaintenanCE' Rule Expert Panel Meeting Minutes for January Issue Reports
: 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 1019308. ESW increased frequency throttle valve flush
Line 122: Line 256:
: 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
: 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==
==Section 1R13: Maintenance==
: Risk Assessments and Emergent Work Control Issue Reports
: IR 984431, 2009
: IR 984431, 2009
: CDBI-Preconditioning of ESW Flow Verification Test
: CDBI-Preconditioning of ESW Flow Verification Test
Line 135: Line 270:
: 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
: 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==
==Section 1R15: Operability==
: Evaluations Issue
: IR 1017465,
: IR 1017465,
: PI-042-2R011 requires
: PI-042-2R011
requires
: IR 202245, OA, CREFAS damper failure to close
: IR 202245, OA, CREFAS damper failure to close
: IR 1023344, Unit 1, 'A' RHR pump room cooler (1AV 210) low
: IR 1023344, Unit 1, 'A' RHR pump room cooler (1AV 210) low
Line 144: Line 281:
: IR 0885591, Pressure indication optimization
: IR 0885591, Pressure indication optimization
: IR 0908974, RSP
: IR 0908974, RSP
: PI-42-2R011 reads high
: PI-42-2R011
reads high
: IR 1023344, 1A-V210 low flow
: IR 1023344, 1A-V210 low flow
: IR 1022245,
: IR 1022245,
: HV-078-02.0A damper failed to close fully Procedures
: HV-078-02.0A
: ST-6-107-595-2, Monthly Surveillance Log OPCON 1, 2, or 3, performed 02/15/09 ST -2-088-409-1, Remote Shutdown System Reactor Vessel Pressure Calibration (PT-042-1 N006,
damper failed to close fully Procedures
: 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
: 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§.==
==Section 1R19: Post-Maintenance==
: Testing Issue Report§.
: IR 1028881, Crankcase eductor air in-leakage
: IR 1028881, Crankcase eductor air in-leakage
: IR 103020A, Room cooler over pressurization during pressure
: IR 103020A, Room cooler over pressurization during pressure
: IR 1047688, U-042:"1 R61 anot able to be calibrated within tolerance Work Order
: IR 1047688, U-042:"1 R61 a not able to be calibrated within tolerance Work Order
: C0230739, Rework 6" RCIC steam valve internals
: C0230739, Rework 6" RCIC steam valve internals
: C0230736, Limitorque diagnostics and support for valve work R1
: C0230736, Limitorque diagnostics and support for valve work R1
: 092911, Accident monitoring -reactor vessel level calibration I functional R1160079, Steps outstanding for L1-042-1R610 R1096703, Inspect andoverhaul waterside components for control rod drive hydraulic control Unit 02-27; Attachment  
: 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===
===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
: 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-103, Shutdown Safety Management Program, Revision 10
: OU-AA-104, Shutdown Safety Management Program, Revision 10
: OU-AA-104, Shutdown Safety Management Program, Revision 10
Line 166: Line 321:
: OU-AB-4001, BWR Fuel Handling Practices, Revision 4
: 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
: 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
: 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-2-042-933-2, 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-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.
: ST-6-049-230-1. RCIC Pump, Valve and Flow Test (1ST). Revision 72
: RCIC Pump, Valve and Flow Test (1ST). Revision 72
: RT-3-047-640-01, Fuel Channel Distortion Monitoring, Revision 15
: RT-3-047-640-01, Fuel Channel Distortion Monitoring, Revision 15
: ST-6-092-118-1,014 Diese1 Generator 4 KV SFGD -Loss of Power LSF/SAA and Outage Testing, Revision 16 Issue Reports
: ST-6-092-118-1,014  
: IR 1049144, D144-R-E-04 failed to shunt trip
: Diese1 Generator  
: IR 1049131, 014 LOCAILOOP auto start bypass light not lit
: KV SFGD -Loss of Power LSF/SAA and Outage Testing, Revision 16 Issue Reports
: IR 1049011, D134-C-B-14 seismic clip stripped Section 2RSi01 -2RS04
: IR 1049144, D144-R-E-04
: RP-MA-403-1 001, Revision 3 Radiation Work Permit Processing
failed to shunt trip
: RP-AA-203. Revision 3 Exposure Control and Authorization
: 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  
: RP-AA-203.
: Revision 3 Exposure Control and Authorization
: RP-AA-210, Revision 15 Dosimetry Issue, Usage, and Control
: RP-AA-210, Revision 15 Dosimetry Issue, Usage, and Control
: RP-AA-220, Revision 5 Bioassay Program Attachment
: 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-220-1001, Revision 5 Perform Calibration Checks and Whole Body Count on AccuScan RP-LG-220-1002.
: RP-LG-220-1002. Revision 3 Perform Calibration Checks and Whole Body Count on FastScan
: 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-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-222, Revision 3 Timating Internal Exposure from In Vivo and In Vitro Bioassay Data
Line 186: Line 349:
: RP-LG-300-102, Revision 2 Removing Items from the Spent Fuel Pool, Reactor Cavity Equipment Pit, or Cask Pit
: 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-301, Revision 2 Radiological Air Sampling Program
: RP-AA-350, Revision 7 Personnel Contamination Monitoring. Decontamination. and Reporting
: RP-AA-350, Revision 7 Personnel Contamination Monitoring.
: RP-AA-376. Revision 2 Radiological Postings. Labeling, and Markings
: Decontamination.
: RP-AA-400, Revision 5 ALARA Program
and Reporting  
: RP-LG-400-1004. Revision 3 Emergent Dose Control and Authorization
: RP-AA-376.
: RP-AA-401, Revision 9 Operational ALARA Planning and Controls
: Revision 2 Radiological Postings.
: RP-AA-403. Revision 1 Administration of the Radiation Work Permit Program
: Labeling, and Markings
: RP-AA-400, Revision 5 ALARA Program RP-LG-400-1004.
: Revision 3 Emergent Dose Control and Authorization
: RP-AA-401, Revision 9 Operational  
: ALARA Planning and Controls RP-AA-403.
: Revision 1 Administration of the Radiation Work Permit Program
: RP-AA-460, Revision 19 Controls for High and Very High Radiation Areas
: RP-AA-460, Revision 19 Controls for High and Very High Radiation Areas
: RP-LG-460-1 02. Revision 4 Initial Entry into the Drywell
: RP-LG-460-1  
: RP-LG-460-1016. ReviSion 9 Radiation Protection Controlled Keys
: 2. Revision 4 Initial Entry into the Drywell RP-LG-460-1016.
: RT-0-100-460-0. Revision 3 High Radiation and Locked High Radiation Door Preventative Maintenance Inspection
: ReviSion 9 Radiation Protection Controlled Keys RT-0-100-460-0.
: ST-0-107-493-0, Rev 12 Periodic Byproduct Material Leakage Test and InVentory STFire Detection-Smoke Detection Instrumentation Channel Functional Test, Zones 31,32, Revision 15
: Revision 3 High Radiation and Locked High Radiation Door Preventative Maintenance Inspection
: ST-2-022-607-1 Fire Detection-Smoke Detection Instrumentation Channel 10
: ST-0-107-493-0, Rev 12 Periodic Byproduct Material Leakage Test and InVentory  
: CFR 50. j'2 Event Notification 45 693, Technical Support Center Emergency Ventilation System Maintenance
: ST
: EP-AA-112 200 F-01 Station Emergency Director Checklist, Revision F Radiation Protection Group Info 09-L-035, 09-L-036, ISSUE REEORTS (Access Control/ALARA related
: Fire Detection-Smoke Detection Instrumentation Channel Functional Test, Zones 31,32, Revision 15
: ST-2-022-607-1  
: Fire Detection-Smoke Detection Instrumentation Channel 10
: CFR 50. j'2 Event Notification  
: 693, Technical Support Center Emergency Ventilation System Maintenance
: EP-AA-112  
: 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,
: 1053795,1053751,1046685,1046683,1046681,1046546,
: 1044977,
: 1044977,
: 1045183,1042839.1051659,1051357,1048509, CAUSE Apparent Cause Evaluation for IR Radiation Work Permits (RWPl/ALARA PLANS
: 1045183,1042839.1051659,1051357,1048509,  
: CAUSE  
: Apparent Cause Evaluation for IR  
: Radiation Work Permits (RWPl/ALARA  
: PLANS
: RWP 91, DW CRD Exchange and associated Under Vessel Work/AP
: RWP 91, DW CRD Exchange and associated Under Vessel Work/AP
: RWP 81, DW Scaffold/AP
: RWP 81, DW Scaffold/AP
Line 209: Line 389:
: RWP 60, Rei3ctor Disassembly/AP
: RWP 60, Rei3ctor Disassembly/AP
: RWP 63/64. Reactor Cavity Decontamination/AP:
: RWP 63/64. Reactor Cavity Decontamination/AP:
: RP-LG-401-1001 & Attachment 
: RP-LG-401-1001  
: ALARA Work-ln-Progress/Post-Job Under Vessel CRD 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
: ALARA Work-ln-Progress/Post-Job Under Vessel CRD  
: 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 40A1: Performance Indicator Verification Miscellaneous==
==Section 40A2: Problem Identification==
: 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==
& Resolution Issue Reports IR657596
: IR657596
: IR 787602
: IR 787602
: IR 725476
: IR 725476
Line 232: Line 428:
: RTP SSC SGTS UFSAR UPS VHRA A-9
: RTP SSC SGTS UFSAR UPS VHRA A-9
==LIST OF ACRONYMS==
==LIST OF ACRONYMS==
Agencywide Documents Access Management System
Agencywide
: [[ALA]] [[]]
Documents
: [[RA]] [[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]]
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
}}
}}

Revision as of 02:18, 23 August 2018

IR 05000352-10-002, 05000353-10-002; 01/01/2010 - 03/31/2010; Limerick Generating Station, Units 1 and 2; Routine Integrated Report
ML101250646
Person / Time
Site: Limerick  Constellation icon.png
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)
v • d • e


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
FE-076-195A

replacement strategy

IR 816856. 1A RERS damper
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
FE-076-195A
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 975564, ESW, 1HV210 ESW flow below minimum
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
IR 1017465,
PI-042-2R011

requires

IR 202245, OA, CREFAS damper failure to close
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
IR 0908974, RSP
PI-42-2R011

reads high

IR 1023344, 1A-V210 low flow
IR 1022245,
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
RP-AA-203.
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

RP-AA-376.
Revision 2 Radiological Postings.
Labeling, and Markings
RP-AA-400, Revision 5 ALARA Program RP-LG-400-1004.
Revision 3 Emergent Dose Control and Authorization
RP-AA-401, Revision 9 Operational
ALARA Planning and Controls RP-AA-403.
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
ST
Fire Detection-Smoke Detection Instrumentation Channel Functional Test, Zones 31,32, Revision 15
ST-2-022-607-1
Fire Detection-Smoke Detection Instrumentation Channel 10
CFR 50. j'2 Event Notification
693, Technical Support Center Emergency Ventilation System Maintenance
EP-AA-112
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 91, DW CRD Exchange and associated Under Vessel Work/AP
RWP 81, DW Scaffold/AP
RWP 86, DW Reactor Pressure Vessel Nozzle & Skirt In-Service Inspections/AP
RWP 40, Suppression Pool Divingl AP
RWP 60, Rei3ctor Disassembly/AP
RWP 63/64. Reactor Cavity Decontamination/AP:
RP-LG-401-1001

&

ALARA Work-ln-Progress/Post-Job Under Vessel CRD
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
ADAMS AP CAP CREFAS CS *CW ECCS LER OOS OPCON RHRSW
RTP SSC SGTS UFSAR UPS VHRA A-9

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

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