Text

May 13, 2009

Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555

SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2, NRC INTEGRATED INSPECTION REPORT 05000456/2009002 AND 05000457/2009002

Dear Mr. Pardee:

On March 31, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Braidwood Station, Units 1 and 2. The enclosed inspection report documents the inspection results, which were discussed on April 17, 2009, with Mr. B. Hanson, and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. The report documents one NRC-Identified finding and one self-revealing finding of very low safety significance (Green). The NRC-Identified finding was determined to involve a violation of NRC requirements. However, because of the very low safety significance and because the issue was entered into your corrective action program, the NRC is treating the finding as a Non-Cited Violation (NCV), consistent with Section VI.A.1 of the NRC's Enforcement Policy. If you contest any NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to the Regional Administrator, U.S. Nuclear Regulatory Commission - Region III, 2443 Warrenville Road, Suite 210, Lisle, IL 60532-4352; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the Resident Inspector Office at the Braidwood Station. In addition, if you disagree with the characterization of any finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement to the Regional Administrator, Region III, and the NRC Resident Inspector at the Braidwood Station. The information you provide will be considered in accordance with Inspection Manual Chapter 0305. 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 NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-erm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/ Richard A. Skokowski, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77

Enclosure:

Inspection Report 05000456/2009002; 05000457/2009002

w/Attachment:

Supplemental Information cc w/encl: Site Vice President - Braidwood Station Plant Manager - Braidwood Station Manager Regulatory Assurance - Braidwood Station Chief Operating Officer and Senior Vice President Senior Vice President - Midwest Operations Senior Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director - Licensing and Regulatory Affairs Manager Licensing - Braidwood, Byron and LaSalle Associate General Counsel Document Control Desk - Licensing Assistant Attorney General J. Klinger, State Liaison Officer, Illinois Emergency Management Agency Chairman, Illinois Commerce Commission

SUMMARY OF FINDINGS

......................................................................................................... 1

REPORT DETAILS

..................................................................................................................... 3 Summary of Plant Status.........................................................................................................

REACTOR SAFETY

.................................................................................. 3

1R01 Adverse Weather Protection

Main article: IP 71111.01

.................................................... 3

1R04 Equipment Alignment

Main article: IP 71111.04

............................................................... 3

1R05 Fire Protection

Main article: IP 71111.05

......................................................................... 4

1R07 Annual Heat Sink Performance

Main article: IP 71111.07

................................................ 5

1R12 Maintenance Effectiveness

Main article: IP 71111.12

...................................................... 6

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

.. 6

1R15 Operability Evaluations

Main article: IP 71111.15

............................................................ 7

1R17 Evaluation of Changes, Tests, or Experiments and Permanent Plant Modifications

Main article: IP 71111.17

............................................................................ 8

1R19 Post-Maintenance Testing

Main article: IP 71111.19

..................................................... 11

1R20 Outage Activities

Main article: IP 71111.20

.................................................................... 12

1R22 Surveillance Testing

Main article: IP 71111.22

RADIATION SAFETY

.............................................................................. 14 2PS1 Radioactive Gaseous And Liquid Effluent Treatment And Monitoring Systems (71122.01)

OTHER ACTIVITIES

................................................................................ 18

4OA1 Performance Indicator Verification

Main article: IP 71151

.............................................. 18

4OA2 Identification and Resolution of Problems

Main article: IP 71152

................................... 19

4OA3 Follow-Up of Events and Notices of Enforcement Discretion

Main article: IP 71153

...... 21

4OA5 Other Activities......................................................................................... 24 4OA6

Management Meetings ............................................................................ 25

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

B. Hanson, Site Vice President

L. Coyle, Plant Manager

K. Aleshire, Emergency Preparedness Manager

G. Dudek, Site Training Director

R. Gadbois, Maintenance Director

D. Gullott, Regulatory Assurance Manager

D. Gustafson, Design Engineering Manager

J. Knight, Nuclear Oversight Manager

T. McCool, Operations Director

J. Moser, Radiation Protection Manager

T. Schuster, Chemistry Manager

M. Smith, Engineering Director Nuclear Regulatory Commission

R. Skokowski, Chief, Reactor Projects Branch 3

Attachment

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened

05000457/2009002-01 NCV Safety Injection Pipe Support Deficiencies (Section 1R17.1.b)

05000457/2009002-02 FIN Reactor Trip On Unit Auxiliary Transformer 241-1 Sudden Pressure Relay Actuation Due To 2C Heater Drain Pump Motor Electrical Fault (Section 4OA3.2)

Closed

05000457/FIN-2009002-01 NCV Safety Injection Pipe Support Deficiencies (Section 1R17.1.b)

05000457/FIN-2009002-02 FIN Reactor Trip On Unit Auxiliary Transformer 241-1 Sudden Pressure Relay Actuation Due To 2C Heater Drain Pump Motor Electrical Fault (Section 4OA3.2)

05000457/FIN-2008008-01 URI Additional Information Needed To Determine Adequacy Of Safety Injection Unit 2 SI06 Pipe Supports

05000456/2008003-03;

05000457/FIN-2008003-03 URI AFW Tunnel Hatches Margins of Safety

05000456/LER-2008-001-00 LER Non-Compliance Due To Inadequate Design Of AF Tunnel Access Covers Causing AF Valves Within The Tunnel To Be Inoperable

05000457/LER-2008-001-00 LER 2A Essential Service Water Train Inoperable Due to Strainer Fouling From Bryozoa Deposition And Growth

05000456/LER-2008-002-00 LER Unit 1 Containment Isolation Valve 1PS229B De-energized Open Instead of Closed per TS 3.6.3

05000457/LER-2008-002-00 LER Reactor Trip On Unit Auxiliary Transformer 241-1 Sudden Pressure Relay Actuation Due To 2C Heater Drain Pump

Motor Electrical Fault EA-03-009 ORD Establishing Interim Inspection Requirements for Reactor Vessel Heads at Pressurized Water Reactors

Discussed

05000456/2008005-03;

05000457/2008005-03 NCV Inadequate Corrective Action for Failure to Promptly Correct AF Tunnel Feedwater Tunnel Hatch Cover Design Deficiencies

05000456/2008004-04;

05000457/2008004-04 URI Bryozoan Infestation at the Lake Screenhouse Circulating Water

05000457/2008001-01 LER 2A Essential Service Water Train Inoperable Due to Strainer Fouling From Bryozoa Deposition And Growth

Attachment

LIST OF DOCUMENTS REVIEWED

The following is a partial list of documents reviewed during the inspection.

Inclusion on this list does not imply that the NRC inspector reviewed the documents in their entirety, but rather that selected sections or portions of the documents were evaluated as part of the overall inspection effort.

Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.

1R01 Adverse Weather Protection -

IR 866485; Snow Found in VA Plenums; January 14, 2009 -

IR 866980; Potential Frozen FP Piping (1SH15AY); January 15, 2009 -

IR 867388; Turbine Deck Temperatures As Low As 20 degrees F Due to Inop Heaters & Windows; January 15, 2009 -

IR 867539; U1 Non ESF (6.9KV) Switchgear Room at 30 Degrees F - 1VX07Y; January 15, 2009 -

IR 866667; Outside Air Louvers in U1 Heater Drain Vent Fan Room Are Not Closed; January 14, 2009 - Drawing M-50; Diagram of Diesel fuel Oil Unit 1; June 24, 1976 - Drawing M-50; Diagram of Diesel fuel Oil Units 1 & 2; June 24, 1976

- Drawing M-52; Diagram of Fire Protection Units 1 & 2; July 19, 1978 1R04 Equipment Alignment - BwOP

RH-E1; Electrical Lineup - Unit 1 Operating; Revision 6 - BwOP

RH-M1; Operating Mechanical Lineup - Unit 1 1A RH Train; Revision 12 - BwOP

SX-E1, Electrical Lineup - Unit 1 Essential Service Water System Operating, Rev. 7

- BwOP

SX-M1, Operating Mechanical Lineup Unit 1, Rev. 25 - 1BwOSR 3.7.8.1, Unit One Essential Service Water System Surveillance, Rev. 15 1R05 Fire Protection - Braidwood Station Pre-Fire Plans, Fuel Handling Building - Elevation 401' - Braidwood Station Pre-Fire Plans, Fuel handling Building - Elevation 426' and New Fuel Unloading Area at Elevation 411' 1R07A Heat Sink Review -

EC 357161; HX Visual Inspection Acceptance Criteria - Unit 0 CC HX Eddy Current Test Results; February 2009 -

ER-AA-340-1002, Revision 3, Attachment 1; HX/Component Data Sheet, March 11, 2009 -

IR 882927; 0CC01A: Preventatively Plugged 9 Tubes Per Eddy Current Test; February 20, 2009 1R12 Maintenance Effectiveness -

IR 849790, MRule FF Determination Inadequate for Rx Trip Breaker; November 26, 2008 -

IR 819918, U-2 Rx Trip Bkr Failed to Reclose During Surv.; September 19, 2008

- BwAR 1-BP-3.1, Rx Trip P4, Rev. 1 - 1BwEP

ES-0.1, Reactor Trip Response Unit 1, Rev. 200 - 1BwFR-H.1, Response to Loss of Secondary Heat Sink Unit 1, Rev. 200

Attachment - 1BwST-3, Heat Sink, Rev. 200 - Apparent Cause Report, Unit 2B Reactor Trip Breaker Failed to Re-close During SSPS Surveillance; Reactor Trip Breaker 1RD05E-RTA failed to Close During SSPS Testing; February 3, 2009 - Maintenance Rule Functional Failure Review -

IR 819918: October 14, 2008 - Maintenance Rule Evaluation - Rod Drive System, September 2008

- Maintenance Rule Evaluation - Rod Drive system, December, 2008 - Maintenance Rule Evaluation - Engineered Safety Features Actuation System, September 2008 - Maintenance Rule Evaluation - Engineered Safety Features Actuation System, December 200 1R13 Maintenance Risk Assessments And Emergent Work Control -

IR 869303; Secured 2B AF PP During Test - Aux LO PP Did Not Shutdown; January 21, 2009 -

IR 869819; 2B AF Pump Monthly Surveillance Performance and Operability; January 21, 2009 -

MA-AA-716-004; 2B AF PP Oil System; Revision 7 - 2BwOSR 3.7.5.4-2; Unit 2 Diesel Driven Auxiliary Feedwater Pump Surveillance; Revision 18 -

WC-MW-114; Diesel Driven Auxiliary FW Pump Surveillance; Revision 0 -

WO 01195323 01; U2 Diesel Driven Auxiliary FW Pump Monthly Surveillance; January 21, 2009 - 2B AF Pump Unavailable January 2009 (Unplanned Entry) Protected Equipment - Amendment No. 127 to Braidwood Technical Specifications; May 22, 2003 - Protected Equipment List, 2A SX Pump Work Windows with 2C WS Pump and 0B VA Non-accessible Plenum Out of Service; February 2009 - BwAP 1110-3, Attachment 3, Pre-Evaluated Plant Barrier Matrix, Rev. 16

- PBI No. 11572, Plant Barrier Impairment Permit for Flood Seal 1SXFSO1-2 Removal; February 6, 2009 - PBI No. 11923, Plant Barrier Impairment Permit for Flood Seal 1SXFSO1-3 Removal; February 6, 2009 - PBI No. 11571, Plant Barrier Impairment Permit for Flood Seal 1SXFSO1-5 Removal; February 6, 2009 1R15 Operability Evaluations -

IR 884516; Discrepancy of Relay Setpoint VS Design Range for 2AF013-K11; February 24, 2009 -

IR 892049; NRC Questions Re: 50.59 for Fuel Handling Building Crane Runway Extension; March 12, 2009 - Drawing 20E-1-4040AF12; Schematic Diagram AF Pump 1B (Diesel-Driven) Engine Startup Panel 1AF01J; January 12, 1979 - Drawing 20E-2-4040AF12; Schematic Diagram AF Pump 1B (Diesel-Driven) Engine Startup Panel 2AF01J; September 2, 1980 -

WO 776739-01, 1PS-DG080B DG 1B Turbo Lube Oil Pressure Switch Cal.; September 21, 2006 -

IR 873244, 1T-DG247B Suspect in Causing Low Discharge Temperatures; January 28, 2009 -

IR 872954, Turbo Lube Oil Low Pressure During 1B DG Run; January 28, 2009 - BwOP

DG-11, Diesel Generator Startup, Rev. 35 - Prompt Investigation for

IR 872954, Turbo Lube Oil Low Pressure During 1B DG Run; January 29, 2009 - Drawing M-152, Manufacturers Supplemental Diagram of Diesel Generator Jacket Water Schematic, Units 1 & 2, Rev. U

Attachment - Letter from J. Home to Cooper-Bessemer Owners Group Technical Committee, Lube Oil and Jacket Water Temperatures KSV nuclear Standby Engines; September 13, 1995 1R17 Evaluation of Changes, Tests, or Experiments and Permanent Plant Modifications - Calculation No. 13.2.29; Structural Calculations for the following Mechanical Component Supports 2SI06309X, 2SI06310X, 2SI06311G, 2SI06316X, 2SI06318X, 2SI06328X, 2SI06335X, 2SI06336X, 2SI06337X, 2SI06340S, 2SI06342X, 2SI06345X, 2SI06351X,

2SI06358X, 2SI06360X; Revision 2 - Calculation No.

BRW-97-0827-M; Piping Eval for Lead Shielding Installation on Subsystem 2SI06 Piping per Temp Lead Shielding Request

TSR 95-153, 96-018/045/053 & 97-120; Revision 0 - Calculation No.

BRW-97-0827-M; Piping Eval Lead Shielding on Subsystem 2SI06; Minor Revision 0A -

CC-AA-309-1011; General Station Piping Analysis; Revision 2 -

IR 00816677; NRC Mod/50.59 Insp 2SI06 Piping Subsystem Support; September 11, 2008 - BwOP

SI-1; Safety Injection System Startup; Revision 19 - 1BwOSR 5.5.8.SI-10A; Group A IST Requirements for 1A SI Pump (1S101PA); Revision 0 -

WO 01189386 01; ASME Surveillance Requirement for 1A SI Pump; February 5, 2009 -

OP-AA-108-115; Operability Determinations (CM-1); Revision 6

- Operability Evaluation No.08-007; Degraded Piping Subsystem 2SI06 Supports; September 16, 2008 - Regulatory Guide 1.84; Design & Fab Code Case Acceptability ASME Sect III Division I; Revision 24 1R19 Post Maintenance Testing -

IR 156533; Degraded Battery Charger Due to Loose Connecting Bolt -

IR 895814; Misinterpretation of Value Causes Unnecessary Resource Load; March 21, 2009 -

IR 895839; Charger Float Voltage Pot Won't Respond; March 21, 2009 -

IR 896342; Lack of Procedure Guidance for AF Battery, Charger OOS; March 21, 2009 - Clearance

00072627 Unit 2; 2B AF Pump Battery Charger #2B; March 23, 2009

-

MA-AA-716-004; Troubleshooting Log 2AF01EB-1; Revision 7 -

OP-AA-109-101; Supervision Clearance Acceptance/Release Checklist; Revision 3 - Master Materials Catalog 39831 - Master Materials Catalog 9866 - Material Request

01381735

-

WO 01006137-06; 24 Volt AF Bank 5 Year Capacity Test; March 26, 2009 - BwHP 4006-008; Repairing, Determinating, Terminating, Splicing, Taping, Cable Jacket Repair and Application of Raychem Kit on Cable; Revision 15 - MTL Request

01861475; EM Charger Float Voltage Pot - Drawing 20E-2-4469H; Internal Wiring Diagram Battery Charger 2AF01EA-1 & 2AF01EB-1 Part 1; September 10, 1985 - Drawing 20E-2-4469J; Internal Wiring Diagram Battery Charger 2AF01EA-1 & 2AF01EB-1 Part 2; September 10, 1985 - Drawing 20E-0-3322; Electrical Installation Auxiliary Building Plan Elevation 383-0, Cols. L-Q 15-21; October 14, 1980 - Drawing 20E-2-4030AF02; Schematic Diagram Auxiliary Building Feedwater Pump 2B (Diesel Driven) 2AF01PB; September 2, 1980 - Drawing 20E-2-4030AF12; Schematic Diagram Auxiliary Building Pump 2B (Diesel-Driven) Engine Startup Panel 2AF01J; September 2, 1980

Attachment - Drawing 20E-4008Y; Key Diagram 480V Auxiliary Building ESF

MCC 232X3 (2AP24E); May 31, 1978 1R22 Surveillance Testing -

IR 866770; Elevated Dose Rates in Radwaste Inner Truck Bay and Dock Area; January 14, 2009 -

IR 866788; 2A DG L.O. Temp (2TE-DG036A) High During Run; January 14, 2009

-

IR 867033; 2A DG 5L Cylinder Temperature Indication Varies; January 14, 2009 -

IR 895654; Increasing Vibration on 6V Point on 2AF01PB; March 20, 2009 -

WO 01031301 01; 2A DG Bypass of Automatic Trips Surveillance; January 14, 2009 -

WO 01195328 01; OP

IST-2A DG Operability Monthly; January 15, 2009 - 1BwOSR 3.4.13.1; Unit One Reactor Coolant System Water Inventory Balance Surveillance, Rev 22 - 2BwOSR 3.8.1.2-1; 2A DG Operability Surveillance; Revision 25 - 2BwOSR 3.8.1.13-1; 2A DG Bypass of Automatic Trips Surveillance; Revision 7 -

WO 01214127 01; OP Diesel Driven AF PP Monthly; March 24, 2009 -

WO 1198655-01, Unit One 1B Diesel Generator Operability Surveillance, dated 1/28/09 -

WO 1181421-01, Unit One ESFAS Instrumentation Slave Relay Surveillance, dated 1/28/09 2PS1 Radioactive Gaseous And Liquid Effluent Treatment And Monitoring Systems -

IR 732647; North Oil Separator Sample Results Higher Than Limit on Tritium; February 6, 2008 -

IR 724596; Liquid Release Early Termination; January 19, 2008 -

IR 738955; IEMA Identified Historical Radiological Environmental Monitoring Data Discrepancies; February 15, 2008 -

IR 754914; Nuclear Oversight Identifies Work Package Closures Lack Rigor; August 15, 2007 -

IR 755289; Nuclear Oversight Identifies Radiological Effluent Factors Not Trended for Offsite Dose Calculation Manual; March 27, 2008 -

IR 761706; RETS 2.1-1A Unplanned Entry Due to Loss of Sample Flow 0PR5J -

IR 765269; 2PR02J Loss of Sample Flow; April 19, 2008

-

IR 771232; Unplanned Limiting Condition for Operation Entered for Volume Control Radiation Monitor (0PR33J); May 2, 2008 -

IR 773067; Unit 2 Gas Effluent dose Projection Exceeds 0.3 millirem; May 8, 2008 -

IR 775616; 0PR02J Tripped Moments After Starting a Release; May 14, 2008 -

IR 781700; 2PR02J Unexpected Loss of Flow; June 1, 2008

-

IR 796534; Large Amount of Sludge Left in West Lagoon Post Cleaning; July 15, 2008 -

IR 808953; Vacuum Breaker 1 Weekly Composite Sample Not Valid; August 18, 2008 -

IR 815407; TR Lagoons Have a Lot of Lime/Sludge; September 8, 2008 -

IR 810671; Nuclear Oversight Identifies Deficiency in Chemistry Check-in Scope; August 25, 2008 -

IR 846176; No Sample at Vacuum Breaker 1 Remediation Composite Sampler; November 17, 2008 -

IR 846300; Vacuum Breaker Concern - Tritium Management; November 17, 2008 -

IR 846351; Vacuum breaker 1 Composite Sampler Not in Operations Radiological Environmental Technical Specifications Procedure; November 18, 1008 -

IR 859794; IDNS Questions Concerning Loss of Communications Alarms; December 23, 2008 -

IR 870595; Nuclear Oversight Identifies Deficiencies in Environmental Check-in; January 23, 2009

Attachment -

AT 795767; Check-in Self-Assessment: Radioactive Gaseous and Liquid Effluent Treatment and Monitoring; November 28, 2008 - BwOP

CW-28; Operation of the Exelon Remediation Pond Pump and Vacuum Breakers Number 1 and Number 2 Remediation Pumps; Revision 16; - BwOP

GW-500T1; Approval for Gas Decay Tank Release; Revision 33; - BwOP

WX-526T1; Liquid Release Tank Release Form; October 4, 2008

- BwOP

WX-526T1; Liquid Release Tank Release Form; November 27, 2008 - BwOP

WX-526T1; Liquid Release Tank Release Form; November 28, 2008 -

DRP 12-016; UFSAR Draft Revision Package - Revise UFSAR Table 11.2-5; October 15, 2007 -

DRP 12-077; UFSAR Draft Revision Package - Revise UFSAR Section 11 and Tables 11.2-1, 11.2-4, 11.2-18, 11.2-25; September 24, 2008 - Permit Number

2008237; Gaseous Release Permit Report - Abnormal; June 4, 2008 -

RP-AA-228; 10

CFR 75(g) and 10

CFR 72.20 Documentation Requirements; Revision 0 -

WO 897058; 1PR28J Calibration of the Gaseous Effluent Radiation Monitor; August 14, 2007 -

WO 894106; 0F-VA019 Calibration of Auxiliary Building Exhaust Tunnel Air Flow; July 12, 2007 -

WO 939467; 0PR10J Calibration of the Liquid Effluent Radiation Monitor; March 24, 2008

-

WO 945403; 2PR28J Calibration of the Gaseous Effluent Radiation Monitor; March 31, 2008 -

WO 959377; 0F-VA020 Calibration of Auxiliary Building Exhaust Tunnel Air Flow; July 1, 2008 -

WO 974402; 0PR01J Calibration of the Liquid Effluent Radiation Monitor; June 24, 2008 -

BD-08-16-01 to 23; Tritium Sample Results Collection Date September 16, 17, and 22, 2008 - ML0834300099, Tritium Sample Results from American Radiation Services, Inc., October 31, 2008 4OA1 Performance Indicator Verification -

LS-AA-2010; Monthly Data Elements for NRC/WANO Unit/Reactor Shutdown Occurrences; January 2008 - December 2008 -

LS-AA-2030; Monthly Data Elements for NRC Unplanned Power Changes per 7000 Critical Hours; January 2008 - December 2008 4OA2 Identification and Resolution of Problems -

IR 460074; Safety Concern - Sinkhole Under Walkway Blacktop; February 28, 2006 -

IR 499107; Concern w/Sections of B/D Piping not Properly Inspected; June 12, 2006 -

IR 564241; Need WO Made to Install Barricade per Safety Advisor Recommendation; December 1, 2006 -

IR 621686; Sink Hole in Ground Under Blacktop Approximately 3 Feet Deep; April 25, 2007 -

IR 634725; Safety - Sink Hole East of OFP811; May 29, 2007 -

IR 674695; Sink Hole Identified in the OCA; September 17, 2007 -

IR 686056; OFP590 Has Leak and is Leaking Onto Ground; October 17, 2007

-

IR 696881; Gravel Washout Along Roadway to Lake Screen House; November 9, 2007 -

IR 721198; Washout Areas Underneath EWS Fence; January 11, 2008 -

IR 733633; Underground Leak Removed Soil from Under FIN Team Building; February 8, 2008 -

IR 754139; Free Standing Junction Box 2JB005X Leaning Over; March 25, 2008 -

IR 788846; Sink Hole Located on North End of North Oil Separator; June 20, 2008 -

IR 814377; Sink Hole Discovered in VSO; September 9, 2008

-

IR 817791; EED WR #00255649; September 15, 2008 -

IR 836384; Washout Starting at

STI 11; October 27, 2008

Attachment -

IR 821393; Adverse Trend in Sinkholes Onsite; September 23, 2008 -

IR 865143; Sink Hole in Parking Lot; January 10, 2009 -

IR 876176; Trend on Sink Holes Identified from 2006 through 2008; February 4, 2009 -

OP-AA-102-103; Operator Work-Around Program; Revision 002 - Drawing S-147; Plant Area Drainage Plan; December 14, 1998 -

RS-02-173 Letter from Exelon to NRC; Request for Licensee Amendment to Add TS Surveillance Requirement for the diesel-Driven AF Pump; December 12, 2002 -

IR 649405; OPEX - Braidwood Station Review of North Anna Reactor Trip Due to Spurious SI Signal From Failed SSPS Card; July 12, 2007 - Apparent Cause Evaluation

744304; 2PB-0546C/D Found Neither Circuit Would Trip; March 4, 2008 Miscellaneous - Selected Control Room Log; January 1, 2008 - December 31, 2008

Attachment