Text

February 9, 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 05000456/2008005; 05000457/2008005

Dear Mr. Pardee:

On December 31, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Braidwood Station, Units 1 and 2. The enclosed report documents the results of this inspection, which were discussed on January 8, 2009, with Mr. L. Coyle, 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, three NRC-identified findings and one self-revealed finding of very low safety significance were identified. The findings involved violations of NRC requirements. However, because of their very low safety significance, and because the issues were entered into your corrective action program, the NRC is treating the issues as non-cited violations (NCVs) in accordance with Section VI.A.1 of the NRC Enforcement Policy. Additionally, three licensee identified violations are listed in Section 40A7 of this report. If you contest the subject or severity of these NCVs, 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 a copy 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 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), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/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 05000456/2008005; 05000457/2008005

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

..................................................................................................................... 4 Summary of Plant Status.........................................................................................................

REACTOR SAFETY

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

1R04 Equipment Alignment

Main article: IP 71111.04

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

1R05 Fire Protection

Main article: IP 71111.05

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

1R07 Heat Sink Performance

Main article: IP 71111.07T

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

1R11 Licensed Operator Requalification Program

Main article: IP 71111.11

........................... 10

1R12 Maintenance Effectiveness

Main article: IP 71111.12

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

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

12

1R15 Operability Evaluations

Main article: IP 71111.15

.......................................................... 15

1R18 Plant Modifications

Main article: IP 71111.18

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

1R19 Post-Maintenance Testing

Main article: IP 71111.19

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

1R22 Surveillance Testing

Main article: IP 71111.22

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

1EP6 Drill Evaluation

Main article: IP 71114.06

OTHER ACTIVITIES

................................................................................ 24

4OA1 Performance Indicator Verification

Main article: IP 71151

.............................................. 24

4OA2 Identification and Resolution of Problems

Main article: IP 71152

................................... 26

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

Main article: IP 71153

...... 34

4OA5 Other Activities......................................................................................... 35 4OA6

Management Meetings ............................................................................ 36 4OA7 Licensee-Identified Violations .................................................................. 36

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

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

05000456/2008005-01;

05000457/2008005-01 NCV Inadequate Control of High Pressure Gas Cylinders.

05000456/2008005-02;

05000457/2008005-02 URI Evaluation of the licensee processes and controls regarding the management of on-line risk.

05000456/2008005-03;

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

05000456/2008005-04;

05000457/2008005-04 NCV Inadequate Corrective Action for Containment Spray Add Tank Drain Valve.

05000456/2008005-05;

05000457/2008005-05 NCV Failure to Analyze Inlet Piping Loads and Establish an Adequate HUT Quench Volume.

Closed

05000456/2008005-01;

05000457/FIN-2008005-01 NCV Inadequate Control of High Pressure Gas Cylinders.

05000456/2008005-03;

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

05000456/2008005-04;

05000457/FIN-2008005-04 NCV Inadequate Correction was Containment Spray Add Tank Drain Valve.

05000456/2008005-05;

05000457/FIN-2008005-05 NCV Failure to Analyze Inlet Piping Loads and Establish an Adequate HUT Quench Volume. Discussed None.

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. 1R04 Equipment Alignment PROCEDURES

Number Description or Title Date or Revision BwOP

CS-E1 Electrical Lineup Unit 1 Revision 2 BwOP

CS-M1 Operating Mechanical Lineup Unit 1 Revision 8 BwOP

DG-E1 Electrical Lineup Unit 1 1A DG Revision 6

BwOP

DG-M1 Operating Mechanical Lineup Unit 1 1A DG Revision 14

CAP DOCUMENTS

Number Description or Title Date or Revision

IR 843145 NRC Identified Two Potential Concerns November 10, 2008 1R05 Fire Protection PROCEDURES Number Description or Title Date or Revision BwAP 1100-5 Fire Department Response, Notification, and Mutual Aid Agreement and Expected Chain of Events During a Fire Revision 10

OP-AA-201-003 Fire Drill Scenario for November 17, 2008 Revision 9

OP-AA-201-003 Fire Drill Record for November 17, 2008 Revision 10

1R07 Heat Sink Performance PROCEDURES Number Description or Title Date or Revision BWAR 2-2-C5 "CC Hx Outlet Temperature High" Annunciator Response Revision 9 BwMP 3300-091 Lake Screen House Diver Related Inspections Revision 14 BwOP

CF-36 Operation of the Essential Service Water Chemical Injection System Revision 11b BWOSR 0.1-1, 2, 3 "Unit One Modes 1, 2, 3 Shiftly Rounds" Revision 51 BwVP 850-15 Essential Service Water System Performance Monitoring Program Revision 6 BwVSR 3.7.9.3 Braidwood Cooling Lake Hydrographic Revision 2

Attachment PROCEDURES Number Description or Title Date or Revision

CY-AA-120-400 Closed Cooling Water Chemistry Revision 10

CY-AA-120-410 Circulating/Service Water Chemistry Revision 1

CY-BR-120-4120 Braidwood Station Lake Chemistry Strategic Plan Revision 4

ER-AA-340

GL 89-13 Program Implementing Procedure Revision 4

ER-AA-340-1001

GL 89-13 Program Implementation Instructional Guide Revision 6

ER-AA-340-1002 Service Water Heat Exchanger and Component Inspection Guide Revision 3

ER-AA-340-1003

GL 89-13 Program Performance Indicators Revision 2

MAD 83-239 Ultimate Heat Sink Update Revision 1

CAP DOCUMENTS

Number Description or Title Date or Revision

IR 368450 Need WR to replace 1SX01AA Oil Cooler at next PM Work August 30, 2005

IR 493440 2SX01AA:

2A SX PP Lube Oil Cooler Piping Leak May 17, 2006

AR 00754916 Considerable Silting Identified on 2B Essential Service Water Pump Lube Oil Cooler March 26, 2008

WORK ORDERS Number Description or Title Date or Revision

WO 1112480-01 ASME Surveillance Requirements for 1B Essential Service Water Pump May 27, 2008

WO 1113992-01 IST-- For 2SX002B -- ASME Surveillance Requirements for 2B Essential Service Water Pump June 2, 2008

WO 1141838-01 IST-- For 1SX002B -- ASME Surveillance Requirements for Essential Service Water Pump August 25, 2008

WO 1145101-01 IST-- For 1SX002A -- ASME Surveillance Requirements for 1A Essential Service Water Pump September 2, 2008 WO 1A-1014959-01 Lake Screen House Forebay Inspection Report September 11, 2007WO 1B-1009126-01 Lake Screen House Forebay Inspection Report September 11, 2007WO 1C-881692-01 Lake Screen House Forebay Inspection Report September 11, 2007WO 2A-883681-01 Lake Screen House Forebay Inspection Report September 11, 2007

Attachment WORK ORDERS Number Description or Title Date or Revision WO 2B-1005761-01 Lake Screen House Forebay Inspection Report September 11, 2007WO 2C-883707-01 Lake Screen House Forebay Inspection Report September 11, 2007WO

539131 Heat Exchanger As-Found Inspection and Work Report August 30, 2005

WO 590895-01 Circulating Water Intake Bay Level Control Loop October 8, 2004

WR 98082726 Heat Exchanger As-Found Inspection and Work Report July 24, 2004

AUDITS, ACCESSMENTS AND

SELF-ASSESSMENTS Number Description or Title Date or Revision

194739-05 Self Assessment Check-In Report for the

GL 89-13 Essential Service Water System Performance Monitoring Program August 2004

441886-02 Self-Assessment Check-In report for the Generic Letter 89-13 Program: NRC Heat Sink Inspection September 2006

DRAWINGS Number Description or Title

M-42 Diagram of Essential Service Water Unit 1 and 2

M-137 Diagram of Residual Heat Removal Unit 2

CALCULATIONS Number Description or Title Date or Revision 200042(CQD) Essential Service Water Pump Oil Coolers for Pumps 1/2SX01PA/PB, Specification F/L-2758A

ATD-0054 Performance Analysis for Essential Service Water Cooled Lubricating Oil Heat Exchangers for the CV, SX, SI, and AF Lube Oil Heat Exchangers and CV and AF DD Gear Heat Exchangers

Revision 3

ATD-0063 Heat Load to the Ultimate Heat Sink During a Loss of Coolant Accident

ATD-0109 Thermal Performance of Ultimate Heat Sink During Postulated Loss of Coolant Accident

BRW-00-0017-M Byron/Braidwood Uprate Project Post LOCA

Revision 1

Attachment CALCULATIONS Number Description or Title Date or Revision Component Cooling Water System Temperature Analysis

BRW-00-0018-M Ultimate Heat Sink Evaluation for Power Uprate Heat Load Conditions Revision 0A

BRW-95-218 Evaluation of Essential Service Water Pump Operation with Degraded Lube Oil Coolers

EC 357161

ATI 349059-2 Acceptance Criteria for As Found Heat Exchanger Tube Blockage of the Clean-Only

GL 89-13 Coolers at Braidwood July 10, 2006

1R11 Licensed Operator Requalification Program PROCEDURES Number Description or Title Date or Revision

OP-AA-1 Conduct of Operations (No site Approval) 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 Off-shift Personnel Revision 5

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

1R13 Maintenance Risk and Emergent Work CAP DOCUMENTS

Number Description or Title Date or Revision

842881 Return to Service of 1A CS Pump has Potential to Result in All ECCS Inoperable November 10,

2008843097 Protected Equipment not Identified on Risk Assessment November 10,

2008861686 Potential Inadequate Risk Review Per 10CFR50.65(A)(4) December 31, 2008 1R15

Operability Evaluations PROCEDURES Number Description or Title Date or Revision BwOP

CS-8 Filling the Containment Spray Additive Tank Revision 9

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

OP-AA-108-115-1002 Supplemental Consideration for On-Shift Immediate Operability Determinations Attachment

OPERABILITY EVALUATIONS Number Description or Title Date or Revision

EC 371281 Evaluation - Temporary Modification to Install AFW Tunnel Seal Cover Plate Structural Support / Bracing Revision 2

EC 371283 Evaluation - Temporary Modification to Install AFW Tunnel Seal Cover Plate Structural Support / Bracing Revision 2

EC 371692 Review of Auxiliary Feedwater Tunnel Access Covers for Past Operability Associated with a Postulated MSLB August 14, 2008 OpEval 07-007 AFW Tunnel Cover Bolt Evaluation Uses Non-standard Safety Factor Revisions 0 through 4 CAP DOCUMENTS

Number Description or Title Date or Revision Byron

IR 620080 AFW Tunnel FSO Structural Cal Error April 21, 2007 Byron

IR 653093 The AFW tunnel Covers do not meet expected safety factors July 24, 2007 Byron

IR 851828 Unverified Assumption Used in Technical Evaluation Not Met December 3, 2008 Byron

IR 857487 Resolution of NRC URI Concerning AFW Tunnel Hatch Covers December 17,

2008575726 2CS023 Valve Hard to Operate January 5, 20007

654270 The AFW Tunnel Cover Bolt Eval. Uses Non-Standard Safety Factor July 26, 2007

783849 Load Factor Not Used For Evaluation of AFW Tunnel Cover June 6, 2008

789791 Potential Loss of Margin in MS Pressurization Calc June 24, 2008

790428 Creeping Margin Reduction in AF013 Operability June 26, 2008

792215 MSLB Calc Energy Release Error June 30, 2008

824756 Sodium Hydroxide Spill in Unit 2 CWA and 2A RH Pump Room September 30,

2008826323 Potential Chemical Intrusion to 2A RH Motor Windings October 3, 2008

826559 2A RH Pump Cleaning Activities October 4, 2008

826783 Elevated U-1 SI PP Discharge Header Pressure October 5, 2008

829488 Replace 2A RH Pump Motor October 10, 2008

832975 Rising 1A SI Accumulator Level - 1SI04TA October 19, 2008

833003 2CS023 Difficult to Operate October 19, 2008

840380 NRC Raised Concern that the Rising RH Pressure could be CC November 4, 2008

843113 NOS Identified No Piping Evaluation to November 10, 2008

Attachment CAP DOCUMENTS

Number Description or Title Date or Revision Support Removal of Cs Check Valve

843145 NRC Identified Two Potential Concerns November 10,

2008844176 Future On-Line Work Windows For 1B, 2A, and 2B CS In Question November 12,

2008844415 Possible Missed Technical Specification LCO Entry November 12,

2008849208 Operability Evaluation Needed for SX Strainer Questions November 24,

2008851851 Unverified Assumption Used in Technical Evaluation Not Met December 3, 2008

852425

NRC-Potential Inadequate OP EVAL for AFW Tunnel Hatches December 4, 2008

CALCULATIONS Number Description or Title Date or Revision Calc 3101-0025-01 Structural Analysis of Auxiliary Feedwater Flood Plates, Supporting Channels, and Expansion Anchors (by MPR Associates Inc.) Revision 1 Calc 5.6.3.9 Investigation of Det - 156, 157 Revision 4

DRAWINGS Number Description or Title Date or Revision Drawing M-46 Diagram of Containment Spray Revision AZ Drawing M-61 Diagram of Safety Injection Unit 1 Revision BC

1R18 Plant Modifications PROCEDURES Number Description or Title Date or Revision

LS-AA-104-1003 10

CFR 50.59 Screening Form for

EC 370519 Revision 1

LS-AA-128 Fire Protection Change Regulatory Review for

EC 370519 Revision 0

MODIFICATION PACKAGES Number Description or Title Date or Revision

EC 370519 Install a Performance Monitoring System for the 1A EDG Revision 0

Attachment 1R19 Post Maintenance Testing PROCEDURES Number Description or Title Date or Revision 1BwOSR 5.5.8.SI-10B Group A IST Requirements for 1B Safety Injection Pump (1SI01PB) Revision 0

1R22 Surveillance Testing PROCEDURES Number Description or Title Date or Revision 1BwOSR 5.5.8.SI-10B Group A IST Requirements for 1B Safety Injection Pump (1SI01PB) Revision 0 BwIP 2000-T24 Calibration Test Report Form for Calibration of 2FI-SX130 - 2B Auxiliary Feedwater Pump Cubicle Cooler Flow Instrument Revision 0 2BwOSR 3.7.5.4-2 Unit Two Diesel Driven Auxiliary Feedwater Pump Surveillance Revision 18 2BwOSR 3.7.5.AFW-3B Group A IST Requirements For Unit Two Diesel Driven Auxiliary Feedwater Pump Revision 0 BwOP

AFW-7 Auxiliary Feedwater Pump B Startup on Recirc Revision 30

1EP6 Drill Evaluation

DOCUMENTS

Number Description or Title Date or Revision Scenario Plan:

OBE Earthquake Following by Faulted and Ruptured Steam Generator October 8, 2008

4OA1 Performance Indicator Verification PROCEDURES

Number Description or Title Date or RevisionLS-AA-2001 Collection Report of NRC Performance Indicator Data

LS-AA-2002 Significance Determination Process Evaluation Revision 6

LS-AA-2003 Use of the INPO Consolidated Data Entry Database for NRC and WANA Entry

LS-AA-2200 Completed

LS-AA-2200 Procedures for Heat Removal System Revision 1

Attachment PROCEDURES

Number Description or Title Date or RevisionLS-AA-2200 Completed

LS-AA-2200 Procedures for Residual Heat Removal System Revision 1

LS-AA-2200 Completed

LS-AA-2200 Procedures for Cooling Water System Revision 1

MISCELLANEOUS Number Description or Title Date or RevisionNEI 99-02 Regulatory Assessment Performance Indicator Guideline

4OA2 Identification and Resolution of Problems

PROCEDURES

Number Description or Title Date or RevisionBraidwood Procedure 1BwGP 100-5 Plant Shutdown and Cooldown Revision 34 BOP

RH-6 Placing the RH system in Shutdown Cooling Revision 36

BWOP-AB-12 Recycle Holdup Tank Operation Revision 11

CAP DOCUMENTS REVIEWED Number Description or Title Date or Revision

649581 Potential Vulnerability with RH Suction Relief Discharge to HUT July 12, 2007

649581 Potential Vulnerability with RH Suction Relief Discharge to HUT July 12,2007

677075 Recycle Holdup Tank Level Administrative Controls September 28,

2007677075 Recycle Hold Up Tank Level Administrative Controls September 28,

2007694300 Inconsistent Use of Min Level for Relief Work November 4, 2007

781601 2A SG Pressure Alarm June 1, 2008

786494 2A Steam Generator Pressure Channel 2P-515 Spiking Low June 14, 2008

816500 0A RHUT Placard Needs Changing September 11,

2008816501 0B RHUT Placard Needs Changing September 11,

2008819001 Steam Generator 2A Pressure Channel Failure 2PI-515A September 17,

2008820140 Unplanned Entry Into a 6 Hour Shutdown LCO Action Statement September 19, 2008

Attachment CAP DOCUMENTS REVIEWED Number Description or Title Date or Revision

831252 Byron RHUT NRC Inspection Issues October 15, 2008

831252 BYRON RHUT NRC Inspection Issues October 15, 2008

833241 Byron RHUT PI&R Inspection Lessons Learned October 28, 2008

833241 BYRON RHUT P&IR Inspection Lessons Learned October 20, 2008

850880 NRC P&IR RHUT Inspection Procedure Enhancement December 1, 2008

858652 Containment Isolation Valve Found De-energized Open December 19, 2008 DRAWINGS Number Description or Title Date or Revision Chicago Bridge and Iron Drawing 62603 General Plan 27' X 24'-9" High Elliptical Roof Tank April 1, 1977 Drawing M-65 Diagram of Boric Acid Processing Sheet 2A Revision AO Drawing M-65 Diagram of Boric Acid Processing Sheet 2B Revision BA

Drawing M-65 Diagram of Boric Acid Processing Sheet 2C Revision AW

MISCELLANEOUS Number Description or Title Date or Revision

CN-CRA-00-47 Braidwood/Byron Doses from Recycle Holdup Tanks and Spent Resin Tank Failures June 7, 2000

CN-CRA-08-9 Byron/Braidwood RHUT Response to Opening of the RH Relief Valve September 25, 2008CN-CRA-07-50 Byron/Braidwood RHUT Response to Opening of the RH Relief Valve September 25, 2007 4OA3

Follow-Up of Events and Notices of Enforcement Discretion DRAWINGS Number Description or Title Date or Revision

AC-7 AC One Line Diagram Revision 6

Attachment MISCELLANEOUS Number Description or Title Date or Revision Event Notification 44743 Braidwood Unit 2 Automatic Reactor Trip December 27, 2008Operator Logs Control Room Operator Logs December 27, 2008 CORRECTIVE ACTION DOCUMENTS Number Description or Title Date or Revision

IR 860458 Unit 2 Reactor Trip December 27, 2008 4OA5

Other Activities PROCEDURES

Number Description or Title Date or Revision1BwOSR 3.8.1.14-1 Unit 1 1A Diesel Generator 24 Hour Endurance Run Revision 1 1BwOSR 3.8.1.14-2 Unit 1 1B Diesel Generator 24 Hour Endurance Run Revision 1 2BwOSR 3.8.1.14-1 Unit 2 2A Diesel Generator 24 Hour Endurance Run Revision 1 2BwOSR 3.8.1.14-2 Unit 2 2B Diesel Generator 24 Hour Endurance Run Revision 0

CALCULATIONS Number Description or Title Date or Revision Calculation 19-T-6; Diesel Generator Loading During LOOP/LOCA Revision 6

4OA7

Licensee Identified Violations CAP DOCUMENTS Number Description or Title Date or Revision

IR 653093 (Byron) The AFW Tunnel Covers Do Not Meet Expected Safety Factors July 24, 2007

IR 654270 The AFW Tunnel Cover Bolt Eval. Uses Non-Standard Safety Factor July 26, 2007

Attachment CALCULATIONS Number Description or Title Date or Revision Calc 5.6.3.9 Investigation of Det - 156, 157 Revision 4

Attachment