IR 05000352/2010002

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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) 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

SUMMARY OF FINDINGS

...........................................................................................................

REPORT DETAILS

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 .....................................................................................

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 Attachment

LIST OF ITEMS

OPENED, CLOSED, AND Opened None

Closed

05000353/LER-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 02/15/09 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 anot 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 L1-042-1R610 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 4 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 02. 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 STFire 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 45 693, 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 & Attachment

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

ALA [[]]

RA 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]]