Text

August 14, 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 INTEGRATED INSPECTION REPORT 05000456/2009003 AND 05000457/2009003

Dear Mr. Pardee:

On June 30, 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 July 15, 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. Based on the results of this inspection, six findings of very low safety significance (Green) were identified. Five of these findings involved violations of NRC requirements. Because of the very low safety significances and because the issues were entered into your corrective action program, the NRC is treating these findings as Non-Cited Violations (NCV), consistent with Section VI.A.1 of the NRC's Enforcement Policy. If you contest any Non-Cited Violation or Severity Level IV Violation, 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 05000456/2009003; 05000457/2009003

w/Attachment:

Supplemental Information cc w/encl: Site Vice President - Braidwood Station Plant Manager - Braidwood Station Manager Regulatory Assurance - Braidwood Station 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

REACTOR SAFETY

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

1R01 Adverse Weather Protection

Main article: IP 71111.01

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

1R04 Equipment Alignment

Main article: IP 71111.04

............................................................... 9

1R05 Fire Protection

Main article: IP 71111.05

......................................................................... 9

1R06 Flooding

Main article: IP 71111.06

................................................................................. 13

1R08 Inservice Inspection Activities

Main article: IP 71111.08P

.............................................. 13

1R11 Licensed Operator Requalification Program

Main article: IP 71111.11

........................... 17

1R12 Maintenance Effectiveness

Main article: IP 71111.12

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

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

19

1R15 Operability Evaluations

Main article: IP 71111.15

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

1R18 Plant Modifications

Main article: IP 71111.18

................................................................. 20

1R19 Post-Maintenance Testing

Main article: IP 71111.19

..................................................... 21

1R20 Outage Activities

Main article: IP 71111.20

.................................................................... 22

1R22 Surveillance Testing

Main article: IP 71111.22

.............................................................. 23

1EP6 Drill Evaluation

Main article: IP 71114.06

RADIATION SAFETY

.............................................................................. 28 2OS1 Access Control to Radiologically Significant Areas (71121.01)

OTHER ACTIVITIES

................................................................................ 31

4OA1 Performance Indicator Verification

Main article: IP 71151

.............................................. 31

4OA2 Identification and Resolution of Problems

Main article: IP 71152

................................... 32

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

Main article: IP 71153

...... 36

4OA5 Other Activities......................................................................................... 42 4OA6

Management Meetings ............................................................................ 42 4OA7 Licensee-Identified Violation .................................................................... 43

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

B. Hanson, Site Vice President

L. Coyle, Plant Manager

K. Aleshire, Emergency Preparedness Manager

G. Bal, Engineering Program Manager

G. Dudek, Site Training Manager

R. Gadbois, Maintenance Manager

D. Gullott, Regulatory Assurance Manager

J. Knight, Nuclear Oversight Manager

T. McCool, Operations Manager

J. Moser, Radiation Protection Manager

T. Schuster, Chemistry Manager

M. Smith, Engineering Manager Nuclear Regulatory Commission

R. Skokowski, Chief, Reactor Projects Branch 3

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened

05000456/2009003-01 FIN Failure to Control and Secure Material Adjacent to Unit 1 Transformer Yard Which Could Become Potential Missiles (Section 1R01.3)

05000456/2009003-02;

05000457/2009003-02 NCV Isolation of Lower Cable Spreading Room Carbon Dioxide Fire Suppression (Section 1R05.2)

05000457/2009003-03 SL IV Failure to Perform Appropriate 10 CFR 50.59 Review (Section 1R22.2)

05000456/2009003-04;

05000457/2009003-04 URI Failure of Containment Sump Suction Valve 1SI8811B to Stroke Open (Section 1R22.3)

05000456/2009003-05;

05000457/2009003-05 NCV Failure to Properly Evaluate Installation of ECCS Throttle Valves (Section 4OA2.3)

05000456/2009003-06;

05000457/2009003-06 NCV Failure to Promptly Identify Bryozoa Infestation Caused 2A SX subsystem to be inoperable (Section 4OA3.2)

05000456/2009003-07;

05000457/2009003-07 NCV Bryozoan Infestation at the lake Screenhouse Circulating Water forebays (Section 4OA3.3)

05000456/2009-001-00 LER Steam Generator Tube Exceeding Plugging Criteria Remained In Service During Previous Cycle

05000457/2008-001-01 LER Essential Service Water Train Inoperable due to Strainer Fouling from Bryozoa Deposition and Growth

05000457/2009-001-00 LER Reactor Trip on Over Temperature Delta Temperature due to a Signal Spike on One Channel with Another Channel Placed in the Tripped Condition for Surveillance Testing

Attachment

Closed

05000456/FIN-2009003-01 FIN Failure to Control and Secure Material Adjacent to Unit 1 Transformer Yard Which Could Become Potential Missiles

(Section 1R01.3)

05000456/2009003-02;

05000457/FIN-2009003-02 NCV Isolation of Lower Cable Spreading Room Carbon Dioxide Fire Suppression (Section 1R05.2)

05000457/2009003-03 SL-IV Failure to Perform Appropriate 10 CFR 50.59 Review (Section 1R22.2)

05000456/2009003-05

05000457/FIN-2009003-05 NCV Failure to Properly Evaluate Installation of ECCS Throttle Valves (Section 4OA2.3)

05000456/2009003-06;

05000457/FIN-2009003-06 NCV Failure to Promptly Identify Bryozoa Infestation Caused 2A SX subsystem to be inoperable (Section 4OA3.2)

05000456/2009003-07;

05000457/FIN-2009003-07 NCV Bryozoan Infestation at the lake Screenhouse Circulating Water forebays (Section 4OA3.3)

05000456/2008004-03;

05000457/FIN-2008004-03 URI Inadvertent Isolation of Lower Cable Spreading Room Carbon Dioxide Fire Suppression

05000456/2008004-04;

05000457/FIN-2008004-04 URI Bryozoan Infestation At The Lake Screenhouse Circulating Water Forebays

05000457/LER-2008-001-01 LER Essential Service Water Train Inoperable due to Strainer Fouling from Bryozoa Deposition and Growth

05000456/LER-2009-001-00 LER Steam Generator Tube Exceeding Plugging Criteria Remained In Service During Previous Cycle

05000457/LER-2009-001-00 LER Reactor Trip on Over Temperature Delta Temperature due to a Signal Spike on One Channel with Another Channel Placed in the Tripped Condition for Surveillance Testing

Attachment

LIST OF DOCUMENTS REVIEWED

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

Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of 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 - 0BwOA

ELEC-1; Abnormal Grid Conditions; Revision 7 - 0BwOA

ENV-1; Adverse Weather Conditions Unit 0; Revision 105 - 0BwOA

ENV-1; Adverse Weather Conditions Unit 0; Revision 106 - 0BwOA

ENV-4; Earthquake Unit 0; Revision 106

- BwAP 340-1; Use of Procedures for Operating Department; Revision 23 -

HU-AA-104-101; Procedure Use and Adherence; Revision 3 -

OP-AA-108-107; Switchyard Control; Revision 2 -

OP-AA-108-107-1001; Station Response to Grid Capacity Conditions; Revision 2 -

OP-AA-108-107-1002; Interface Agreement Between Exelon Energy Delivery and Exelon Generation for Switchyard Operations; Revision 4 -

IR 583639; NRC Mod 50.59 Inspection Identified an Inadequate 50.59 Evaluation; January 24, 2007 -

IR 601635; NRC Issued Green Severity Level IV NCV for Inadequate Mod 50.59; January 26, 2007 -

IR 767223 Procedure Enhancements for 0BwOA

ENV-4; April 24, 1008 -

IR 782043; Lake Screen House Acid Unloading Station is Degraded; June 2, 2008

-

IR 791323; Sulfuric Acid Tanks Not Emptied per BwOP

CF-45; June 27, 2008 -

IR 831223; NRC PI&R ID'd 50.59 Evaluation Not Completed for 1/2BwOA

ELEC-4; October 15, 2008 -

IR 922156; NOS Id - Issues Not Addressed for Summer Readiness; May 20, 2009 -

IR 922522; NOS Id Summer Readiness Letter Silent on Id Exceptions; May 21, 2009

-

IR 924051; 2B VP Chiller Failed to Restart After Shutdown for RCFC Monthly; May 26, 2009 - Braidwood Certification Letter for Summer Readiness; May 15, 2009 - 50.59 Evaluation

BRW-E-1006-196, Revision 1;

EC 357102 and

DRP 11-092, Revision 002,0 - Design Summary

EC 357102; Sulfuric Acid System Addition at Lake Screen House; Revision 01 - Work Planning Instructions

EC 357102; Sulfuric Acid System Addition at Lake Screen House; Revision 000 1R04 Equipment Alignment - BwOP

SX-E1; Electrical Lineup - Unit 1 Essential Service Water System Operating; Revision 7 - BwOP

SX-M1; Operating Mechanical Lineup Unit 1; Revision 25 1R05A Fire Protection - Braidwood Station Pre-Fire Plans; 2S-57 (Fire Zone 18.26-0); TSC Filters 0VV21/22F 451 Elevation Attachment - Braidwood Station Pre-Fire Plan Map; Grade Floor Plan Elevation 401-Figure 2.3-12; - Braidwood Station Pre-Fire Plan Map; Condensate Clean Up & Technical Support Center; Figure 2.3-41 -

OP-AA-201-003; Fire Drill Scenario 2SI01PA, 2A SI Pump, Electrical Fire; May 5, 2009 - Fire Drill Info;

AB-364-P18, S18, S19 and 2SI01PA Photographs - Braidwood Station Pre-Fie Plans, U2 Containment Pipe Penetration Area, Elevation 364 and SI Pump - Nuclear Accident Reporting System Form; 2A Room Fire Drill 2A SI Pump Motor Fire; May 5, 2009 - BwOP

FP-27T11; 364 SI Pump 1A Room and Containment Pipe Penetration Area; Revision 1 1R05Q Fire Protection - Braidwood Station Pre-Fire Plans 1D-11; Auxiliary building - General Area - Elevation 383'-0" (Fire Zone 11.4-0) - Braidwood Station Pre-Fire Plans 1D-13; Radwaste and Remote Shutdown Control Room - Elevation 383'-0" (Fire Zone 11.4C-0) -

Braidwood Station Pre-Fire Plan Map; Figure 2.3-13, Plan at EL. 383'-0" -

NES-MS-04.1; Seismic Prequalified Scaffolds; Revision 5

- BWAP 1100-23; Seismic Housekeeping Requirements for the Temporary Storage of Materials in Category I Areas; Revision 3 1R06 Flood Protection Measures -

IR 928040; NRC/IEMA Identified Walkdown Concerns; June 1, 2009 1R08 Inservice Inspection Activities -

IR 677540;

VT-2 Recordable Indication; September 29, 2007 -

IR 681083; FME Found in the 1C SG A1R13; October 6, 2007 -

IR 681140; Significant Corrosion on 1AF02EB-4; October 7, 2007 -

IR 683682; FME Found in the 1A SG A1R13; October 11, 2997 -

IR 687232; Minimum Wall on SX Piping; October 20, 2007

-

IR 689187; Leakage of Pressurizer Differential Pressure Cell; October 25, 2007 -

IR 689186; Leakage on 1PT-RC011 Fitting; October 25, 2007 -

IR 706376; 0SX115F SX Suction Valve Pit Flooded; December 3, 2007 -

IR 749749; 1CV06A-4 Spool Boric Acid Leakage; April 14, 2008 -

IR 766459; UT Detected Line SX38AA-2 Below Nominal Wall; April 23, 2008

-

IR 766927; PT Indication Discovered During Examination; April 24, 2008 -

IR 770787; Repeat Leakage 2RH606 ASME Bolted Connection, May 2, 2008 -

IR 899611; 1RC8042 (Significant Active Boric Acid Leakage); March 30, 2009 -

IR 901376; MT Indications Identified During ISI Exam; April 1, 2009 -

IR 904471; 1RC 8042C Loss of Base Metal; April 8, 2009

-

IR 904935; 1RC 8042C Structural Integrity Review Question by NRC; April 8, 2009 -

IR 905029; NRC identified weakness in Procedure ER=AP-335-001; April 9, 2009 -

IR 905551; NRC Identified Opportunity (Rx Head Exam Visual Training); April 9, 2009 - ASME Weld Record; 1AF02EB-4 Replacement (WO 01170562) FW 1-1; March 26, 2009 through April 4, 2009 - ASME Weld Record; 1AF02EB-4 Replacement (WO 01170562)

FW 22; March 26, 2009 through April 4, 2009

Attachment - ASME Weld Record; 1AF02EB-4 Replacement (WO 01170562) FW 2A-1; March 25, 2009 through April 4, 2009 - ASME Weld Map, 1AF02EB-4 Replacement (WO 01170562); Revision 4 - ASME Section XI Repair/Replacement Plan, 1AF02EB-4 Replacement (WO 01170562); Revision 5 - Attachment 1;

ER-AP-331-1001; Visual Examination NDE Report; 1RV-03-74-BMV; April 3, 2009 - Attachment 1;

ER-AP-331-1001; Visual Examination NDE Report;

VT-2 Examination of 1B RH Train; October 3, 2008 - Attachment 3;

ER-AP-331-1002; Boric Acid Evaluation Reactor Coolant Loop 1A to RH pump 1A Suction Isolation Valve; December 18, 2007 - Attachment 3;

ER-AP-331-1002; Boric Acid Evaluation Reactor Coolant Loop 1C Pressure Transmitter; December 18, 2007 - Attachment 3;

ER-AP-331-1002; Boric Acid Evaluation 1LT-0461 Pressurizer Level Transmitter RC loop; December 18, 2007 - Indication Sketch Sheet; 1MS-05-PG-4; April 10, 2009 - Liquid Penetrant Examination Report 900640-001, Safety Nozzle A; April 23, 2008 - Liquid Penetrant Examination Report 900640-035, Safety Nozzle A; May 3, 2008

- Liquid Penetrant Examination Report 900640-037, Safety Nozzle A; May 4, 2008 - Magnetic Particle Examination Report 1MS-07-SW08; April 3, 2009 - Magnetic Particle Examination Report 1MS-05-SW14 through SW17; April 10, 2009 - Magnetic Particle Examination Report 1MS-05-SW7 through SW10; April 7, 2009 - Magnetic Particle Examination Report 1MS-05-PG-01 through

PG-03; April 7, 2009

- Magnetic Particle Examination Report 1MS-05-PG-05 through

PG-08; April 10, 2009 - Magnetic Particle Examination Report 1MS-05-PG-13 through

PG-16; April 10, 2009 -

Memorandum, Braidwood U1 SG Inspection Degradation Assessment and Condition Monitoring Input Checklist for A1R14; January 22, 2009 - Procedure

ER-AP-331, Boric Acid Corrosion Control Program; Revision 4

- Procedure

ER-AP-331-1001, Boric Acid Inspection Locations, Implementation of Inspection Guidelines; Revision 4 - Procedure

ER-AP-331-1002, Boric Acid Corrosion Program Identification, Screening and Evaluation; Revision 5 - Procedure

ER-AA-335-01, Bare Metal Visual Examination for Alloy 600/82/182 Materials; Revision 0 - Procedure

ER-AA-335-04, Manual Ultrasonic Requirements for Non-PDI Examinations; Revision 1 - Procedure MRS 2.4.2 Gen-45, Standard In Situ Pressure Test Using the Computer Data Acquisition System; January 25, 2008 - Procedure Qualification Record, A-001; October 19, 1998 - Procedure Qualification Record, A-002; March 9, 1999 - Procedure Qualification Record, 1-50C; January 3, 1984 - Radiographic Examination Interpretation Report (and Film), FW 1-1,

FW-22 and

FW-2A-1; April 1, 2009 - Weld Rod Ticket,

ER 7052, Heat No.

2726532; March 24, 2009 - Welder Qualification, ID No BW40; March 13, 2009

- WPS 1-1-GTSM-PWHT; Revision 1 - Wesdyne Indication Assessment Weld 1RV-01-003; October 10, 2007 - Wesdyne Indication Assessment Weld 1RV-01-006; October 11, 2007 - Westinghouse Letter, In Situ Pressure Testing at Braidwood Unit 1 (A1R14); April 14, 2009 - Westinghouse Letter, Use of Appendix H Qualified Techniques at Braidwood A1R14; February 19, 2009

Attachment 1R11 Licensed Operator Requalification Program -

OP-AA-1; conduct of Operations; Revision 0 -

OP-AA-100; Description of the Exelon Nuclear conduct of Operations Manual; Revision 0 -

OP-AA-101-111-1001; Operations Philosophy Handbook; Revision 5 -

OP-AA-101-112; Roles and Responsibilities of Of-shift Personnel; Revision 5 -

OP-AA-101-113-1006; 4.0 Crew Critique Guidelines; Revision 0

- SGWLC Transient/Large Break RCS LOCA/ Cold Leg Recirculation UFSAR Timing/Loss of All AC UFSAR Timing Scenario #0931; Revision 0; February 27, 2009 - 1BwEP-0; Reactor Trip or Safety Injection - 1BwEP-1; Loss of Reactor or Secondary Coolant - 1BwEP

ES-1.3; Transfer to Cold Leg Circulation

- 1BwCA-0.0; Loss of All AC Power 1R12 Maintenance Effectiveness -

OU-AA-103; Shutdown Safety Management Program -

ER-AA-600; Risk management -

ER-AA-600-1044; Maintenance Rule Support -

ER-AA-2001; Plant Health Committee -

LS-AA-115; Operating Experience Procedure

-

ER-AA-1100; Establishing and Managing Engineering Programs -

ER-AA-2030; conduct of Plant engineering -

ER-AA-310-1001; Maintenance Rule - Scoping -

ER-AA-310-1002; Maintenance Rule - SSC Risk Significance Determination -

ER-AA-310-1003; Maintenance Rule -Performance Criteria Selection

-

ER-AA-310-1004; Maintenance Rule -Performance Monitoring -

ER-AA-310-1005; Maintenance Rule -Dispositioning Between (a)(1) and (a)(2) -

ER-AA-310-1006; Maintenance Rule -Expert Panel Roles and Responsibilities -

ER-AA-310-1007; Maintenance Rule -Periodic (a)(3) Assessment -

ER-AA-310-1008; Maintenance Rule -Exelon Maintenance Rule Process Map

- NRC Regulatory Guide (RD) 1.160, Monitoring the Effectiveness of Maintenance of Nuclear Power Plants - NRC RG 1.182; Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants - NUMARC 93-01; Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants -

WC-AA-101; On-Line Work Control Process -

WC-AA-104; Review and Screening for Production Risk -

ER-AA-310; Implementation of the Maintenance Rule; Revision 7 -

IR 903757; 1IA663 Ball Valve Stem Broken at Handle

-

IR 912149; Update UFSAR Table 6.2.58 -

IR 916116; Emergent Dose Required for BwOP

SA-10 -

IR 922629; Review Seismic Report

EC-2698, Rev 0 for 2 in Check Valve -

IR 923583; U2 Station Air Receiver Bottom Needs to be Painted -

IR 933226; NOS Id - Inadequate Job Prep for SAC 0SA01C Work -

IR 933304; 0SA02CA - Compressor Needs to be Replaced -

IR 935919; Acceptance Criteria per BwVX 800-2 Not Met on 1A Sampling

-

IR 936138; U0 SAC Tripped on Hi Vibes During PMT run - 0SA01C -

IR 936532; 75% MR Unavailability Has Been Exceeded on U0 SAC -

IR 938321; Troubleshooting Results for 0 SAC Failure Attachment -

IR 938708; One of Three Temporary Air Compressors Not Working Properly -

IR 941369; 1SA033 Failed As-Found LLRT - Seat Leakage -

IR 941445; 100 percent MR Unavailability has been Exceeded on Unit 0 SAC 1R13 Maintenance Risk Assessments and Emergent Work Control -

IR 862065; 1CV8382A Has a 0.4 GPM Leakby When Isolated; January 2, 2009 -

IR 909048; SI Pumps Discharge Pressures Indicating 1200 PSIB; April 18, 2009

-

IR 910512; 1CV8396B Needs Retorque, Leaking When Operated; April 22, 2009 -

IR 910523; Small Loss of Metal on Leading Edge of One Impeller Vane; April 22, 2009 -

IR 910646; 1FT-0531 High Side Test Tap Leaking; April 23, 2009 -

IR 912495; U1 PRT Pressure Rise Rate Went Up; April 28, 2009 -

IR 912948; U1 RCS Unidentified Leakrate Exceeds Action Level 3; April 28, 2009

- Complex Troubleshooting (Failure Mode Tree); High Levels of Unidentified RCS Leakage: Unit 1 - Drawing

CV-1, CVCS; June 20, 2008; Revision 10 - Drawing M-64, Sheet 38; Diagram of Chemical Volume & Boron Thermal Regeneration; June 4, 1985 -

WC-AA-101; On-Line Work Control Process -

WC-AA-104; Review and Screening for Production Risk

-

ER-AA-600; Risk Management 1R15 Operability Evaluations -

IR 902241; CV Full flow Testing Acceptance Criteria Issues (1CV01PA); April 3, 2009 -

IR 902597; A1R14 - Anomaly Noted During SI System Full flow Testing; April 3, 2009 -

IR 902815; SI Hot Leg ECCS Flow Trend; April 4, 2009

-

IR 902725; Perform Valve 1SI8822A Inspection to Support Troubleshooting; April 3, 2009 -

IR 910029; Long Term Fix to ECCS Throttle Valves Degradation; April 21, 2009 -

IR 909048; SI Pumps Discharge Pressures Indicating 1200 psig; April 22, 2009 -

IR 909535; NOS ID: NIRB Results for ECCS Flow Issue; April 20, 2009 [NRC Identified] -

IR 909601; 1SI8853B - 1B SI Pump Discharge Relief Valve Actuation; April 18, 2009

-

IR 909639; Need Engineering disposition to Vendor Exception; April 20, 2009 -

IR 910653; Possible SI System Siphoning to RWST; April 23, 2009 [NRC Identified] -

IR 909942; NRC Identified Discrepancy with 1A AF Pump Mission Time; April 21, 2009 -

IR 910882; Question on Temp Leak Repair Permit Requirements; April 23, 2009 - Complex Troubleshooting Data Sheet, SI/CV Cold Leg Injection Lines Flow Inbalance

- NFM0100126; Input to EDG Loading and Fuel Consumption Calculcation, Seq. 0 - EC Request

389963; Provide Bolt Torque Values on Aux Feedpump Bearing Housing and End Cover; April 17, 2009 -

EC 375171; Evaluate the Acceptability of the OIl Leak at the 1A AF Pump Outboard Bearing Cover; Revision 0 - Byron Station Design Information Transmittal;

BYR-04-029, Safety Analysis AF System Mission Time and AF Pump Flow Profile; Revision 2 -

WO 1164186-10;

MM-Repair Oil Leak at Outboard Bearing Cover; April 17, 2009 - Operability Evaluation 09-003, SI Pumps Discharge Pressure Indicating 1200 PSIG; Revision 0 - Drawing M-61; Diagram of Safety Injection Unit 1; June 4, 1985 -

MA-AA-716-004; RCS Inleakage from SI Cold Leg Discharge Check Valves; Revision 7

- BwOP

SI-1; Safety Injection System Startup; Revision 19 - BwOP

SI-2; Safety Injection System Shutdown; Revision 12

Attachment - BwVSR

SI-1; ECCS Injection Line Depressurization with Optional Leakage Test of SI8948A/B/C/D and SI1895A/B/C/D; Revision 1 1R18 Temporary Plant Modifications - Procedure

CC-AA-404; Maintenance Specification:

Application Selection, Evaluation and Control of Temporary Leak Repairs; Revision 8 -

WO 1228394-01;

MM-Temp Repair - Oil Leak at Outboard Bearing Cover; April 19, 2009

-

IR 908495; 1A AF PMP Seal Leak at Outboard End Plus Oil Leak at Housing; April 17, 2009 -

IR 910882; Question on Temp Leak Repair Permit Requirements; April 23, 2009 [NRC Identified] 1R19 Post Maintenance Testing - BwOP

HD-1; Heater Drain System Startup; Revision 23 - MEV Listing: UBRWWQ(3); CV Valve Fragnet Schedule with Weekend Work; April 30 - May 3, 2009 -

WO 1071057-03, Attachment A; Adjustment of DG Basler Voltage Regulator 1R20 Outage Activities - BwVS 500-6; Low Power Physics Test Program; Revision 22 - Furmanite America, Inc. Certificate of Calibration #101926; Digital Ring Gauge; February 25, 2009 - Trevitest Test Sheet; Valve 1MS017C; March 27, 2009 - Trevitest Test Sheet; Valve 1MS013B; March 27, 2009 - Trevitest Test Sheet; Valve 1MS015B; March 27, 2009 - Trevitest Test Sheet; Valve 1MS017B; March 27, 2009

- Trevitest Test Sheet; Valve 1MS013C; March 27, 2009 - Trevitest Test Sheet; Valve 1MS014C; March 27, 2009 - Trevitest Test Sheet; Valve 1MS015C; March 27, 2009 -

IR 899574; Material Identified on PZR Heater Lower Weld; March 30, 2009 -

IR 899611; 1RC8042 (Significant Active Boric Acid Leakage); March 30, 2009

-

IR 909402; 1RC01R Head Area (Additional Boric Acid Cleaning Required A1R15); April 18, 2009 - TIMQ102; Execute to PE Request Maintenance - TIMQ110; (BRW) Pressurizer Relief Tank Rupture Disc - TIMQ111; (BRW) Pressurizer Relief Tank Rupture Disc

- TIMQ112; (BRW) Pressurizer Relief Tank Rupture Disc - TIMQ120; Disc, Rupture, 18 Inches, Type BV, Disc and Vacuum Support Material 31 - TIMQ121; Disc, Rupture, 18 inches, Type BV, Disc and Vacuum Support Material 31 -

OU-AA-103; Shutdown Safety management Program 1R22 Surveillance Testing - 1BwOSR 3.8.1.10-1; 1A Diesel Generator Full Load Rejection and Simulated SI in Conjunction with UV During Load Test; Revision 7 - 1BwOSR 3.8.1.19-1; 1A Diesel Generator ECCS Sequencer Surveillance; Revision 8 -

OP-AA-108-111; Adverse Condition Monitoring and Contingency Plan; 1A DG Lube Oil Temperature Monitoring; Revision 5

Attachment -

IR 89124; 1A DG Unexpected Ventilation Indications; March 11, 2009 -

WO 1073973; Comprehensive Inservice Testing (IST) Requirements for Unit 1 Charging Pumps and Safety Injection System Check Valve Stroke Test; April 2, 2009 -

WO 1075542; Comprehensive Inservice Testing (IST) Requirements for Unit 1 Safety Injection Pumps and Safety Injection System Check Valve Stroke Test; April 2, 2009 2OS1 Access Control to Radiologically Significant Areas -

IR 837415-02; A1R14 Outage ALARA Planning and Controls; March 6, 2009 -

IR 837394-02; Access Control to Radiologically Significant Areas and ALARA Controls; February

8, 2009 -

IR 874206; Dose Rates Increasing in Radwaste; January 30, 2009 -

IR 877085; Lead Shielded Source Carrier Broken; February 5, 2009

-

IR 888340; Radioactive Material Shipper Not Informed of Incoming Radioactive Shipment; March 3, 2009 -

IR 883920; Radioactive Shipment Was Not Recognized as Radioactive Material; February 23. 2009 -

IR 898357; Personnel Contamination Events; March 26, 2009 -

IR 898876; Whole Body Counter Upgrades; February 25, 2009 -

IR 902224; Nasal Count of Four Thousand Unit-1 Containment 426 Cavity During Fuel Moves; April 3, 2009 -

IR 904570; Training: Thermoluminescent Dosimeter Issued Based on Bad Data; March 31, 2009 -

IR 905721; Radwaste Outer Door Locks Behind Individual, Needs Repair; April 10, 2009 -

RP-AA-203-1001; Personnel Exposure Investigation; Revision 6

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RP-AA-402; Braidwood Station 2009- 2013 Exposure Reduction Plan; Revision 0 -

RP-BR-1020; Radiological Controls For Steam Generator Work; Revision 0 -

RWP 10009754; A1R14: Lead Shielding Install/Maintain/Remove (Auxiliary and Containment Buildings); Revision 1 -

RWP 10009768; A1R14: Valve Team Outage Activities In Containment; Revision 2

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RWP 10009777; A1R14: Reactor Head Disassembly/Reassembly; Revision 2 -

RWP 10009821; A1R14: Manway and Diaphragm Removal, Installation and Bolt; Revision 3 -

RWP 10009815; A1R14: Steam Generator Eddy Current Testing and All Tube Repairs; Revision 2 4OA1 Performance Indicator -

LER 05000456/2007-001-00; Unit 1 Reactor Trip Following a 345 Kv Transmission Line Lightning Strike; June 27, 2007 -

LER 05000456/2007-002-00; Unit 1 Power Range N43 Positive Rate Trip Inoperable due to Miscalibration of time Constant; September 22, 2007 -

LER 05000456/2007-003-00; Improper Installation of Insulation on the Unit 1 Main Steam Safety Valve; October 24, 2007 -

LER 05000456/2008-001-00; TS Non-Compliance Due to Inadequate Design of Auxiliary Feedwater Tunnel Access Covers Causing Auxiliary Feedwater Valves Within the Tunnel to be Inoperable; December 16, 2008 -

LER 05000456/2008-002-00; Unit 1 Containment Isolation Valve 1PS229B De-energized Open Instead of Closed per TS 3.6.3; December 17, 2008 -

LER 05000457/2007-001-00; Unit 2 Manual Reactor Trip Due to High Condenser Backpressure Resulting from Circulating Water Pump Trips; August 8, 2007

Attachment -

LER 050004572008-001-01; 2A Essential Service Water Train Inoperable due to Strainer Fouling from Bryozoa Deposition and Growth; September 2, 2008 -

LER 05000457/2008-002-00; Reactor Trip on Unit Auxiliary Transformer 241-1 Sudden Pressure Relay Actuation Due to 2C Heater Drain Pump Motor Electrical Fault; December 27, 2008 -

WO 1229701 01; OP ASME Surveillance Requirements for 2CV01PA Pump, 2A Centrifugal Charging Assembly; May 6, 2009 - BwOSR 5.5.8.CV-4A; Group A 1st Requirements for 2A Centrifugal Charging Pump (2CV01PA) and Check Valve 2CV8480A Stroke Test; Revision 3 4OA2 Identification and Resolution of Problems -

IR 902241; CV Full flow Testing Acceptance Criteria Issues (1CV01PA); April 3, 2009 -

IR 918633; NRC ID - Potentially Inadequate 50.59 for ECCS Throttle Valves; May 12, 2009 -

IR 925110; NOS ID concerns with U2 ECCS Throttle Valve Op Evaluation; April 15, 2009 -

EC 364979; Evaluation of Wyle Test Report WLTR53637 - Generic Letter 2004-02; Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors; September 13, 2004 - Apparent Cause Report

906108; ECCS Throttle Valves Require Re-Adjustment and Flow Testing, Resulting in Significant Outage Impact; April 10, 2009 - Root Cause Investigation Report

902241-21; Braidwood U1 ECCS Flows Exceed Flow Balance Surveillance Criteria Due to Unanticipated Material Degradation of ECCS Throttle Valves; May 29, 2009 - Assignment Report #02; Conduct Complex Troubleshooter for U1 ECCS Full flow Test Failure; April 22, 2009 - 50.59 Review; Braidwood Unit 1

EC 360141 UFSAR Change Package #DRP 12-017; Modifications to the SI Throttle Valves 1SI8810A-D, 1SI8816A-D, 1SI822A-D - 50.59 Review; Braidwood Unit 2

EC 360143 UFSAR Change Package #DRP 12-038; Modifications to the SI Throttle Valves 2SI8810A-D, 2SI8816A-D, 2SI822A-D - Assignment Report #03; OTDM Associated with Complex Troubleshooter Approve OTDM Associated with U1 ECCS Full Flow Issues; April 17, 2009 - Assignment Report #04; Failure Analysis on Broken Piston Ring; June 17, 2009 - Assignment Report #05; Review Throttle Valve Cage Failure Analysis Report; June 24, 2009 - Assignment Report #10; Document Metallurgists Used in Decision Making Process PORC Follow-up Item from OTDM 90224 - Assignment Report #11; Perform FME Evaluation per Attachment 10 of

MA-AA-716-008 for Degraded Throttle Valve Condition; April 22, 2009 - Assignment Report #12; Revise Operating Procedures Unit 1; April 22, 2009 - Assignment Report #13; Incorporate Comments from PORC into

EC 375081; April 24, 2009 - Assignment Report #19; Complete root Cause Charter; May 1, 2009 - SDP Phase 1 Screening Worksheet; 50.59 Came to Wrong Conclusion Re: ECCS Throttle Valve Internals in A1R13

Attachment