Text

November 5, 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: BYRON STATION, UNITS 1 AND 2 INTEGRATED INSPECTION REPORT 05000454/2009004; 05000455/2009004

Dear Mr. Pardee:

On September 30, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Byron Station, Units 1 and 2. The enclosed inspection report documents the inspection findings which were discussed on October 9, 2009, with D. Enright 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, two NRC-identified findings of 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, a licensee identified violation is listed in Section 4OA7 of this report. If you contest the subject or severity of a Non-Cited 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 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 Byron 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 Byron Station. The information that 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 and its enclosure 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. 50-454; 50-455 License Nos. NPF-37; NPF-66

Enclosure:

Inspection Report No. 05000454/2009-004 and 05000455/2009-004

w/Attachment:

Supplemental Information cc w/encl: Distribution via ListServ

Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos: 50-454; 50-455 License Nos: NPF-37; NPF-66 Report Nos: 05000454/2009004 and 05000455/2009004 Licensee: Exelon Generation Company, LLC Facility: Byron Station, Units 1 and 2 Location: Byron, IL Dates: July 01, 2009, through September 30, 2009 Inspectors: B. Bartlett, Senior Resident Inspector J. Robbins, Resident Inspector S. Bakhsh, Lead ISFSI Inspector J. Bozga, Reactor Inspector J. Cassidy, Senior Health Physicist T. Go, Health Physicist D. Jones, Reactor Inspector M. Learn, Reactor Engineer E. Love, Safety Inspector V. Meghani, Reactor Inspector M. Mitchell, Health Physicist C. Morell, Safety Inspector J. Neurauter, Engineering Branch 1 R. Ng, Project Engineer J. Pearson, Senior Safety Inspector C. Tilton, Senior Reactor Engineer C. Thompson, Resident Inspector, Illinois Department of Emergency Management Approved by: R. Skokowski, Chief Branch 3 Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS

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

REPORT DETAILS

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

REACTOR SAFETY

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

1R08 Inservice Inspection Activities

Main article: IP 71111.08P

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

1R11 Licensed Operator Requalification Program

Main article: IP 71111.11

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

1R12 Maintenance Effectiveness

Main article: IP 71111.12

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

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

......10

1R15 Operability Evaluations

Main article: IP 71111.15

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

1R18 Plant Modifications

Main article: IP 71111.18

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

1R19 Post-Maintenance Testing

Main article: IP 71111.19

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

1R20 Outage Activities

Main article: IP 71111.20

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

1R22 Surveillance Testing

Main article: IP 71111.22

......................................................................14

1EP6 Drill Evaluation

Main article: IP 71114.06

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

RADIATION SAFETY

..................................................................................................16 2OS1 Access Control to Radiologically Significant Areas (71121.01).......................16 2OS2 As-Low-As-Is-Reasonably-Achievable (ALARA) Planning and Controls (71121.02).......................................................................................................19 2PS2 Radioactive Material Processing and Transportation (71122.02)....................21

OTHER ACTIVITIES

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

4OA1 Performance Indicator (PI) Verification

Main article: IP 71151

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

4OA2 Identification and Resolution of Problems

Main article: IP 71152

..........................................27

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

Main article: IP 71153

.............28

4OA5 Other Activities................................................................................................31

4OA6 Management Meetings....................................................................................40 4OA7 Licensee-Identified Violations..........................................................................41

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

D. Enright, Site Vice President

J. Anderson, Byron ISFSI Project Manager

B. Barton, Radiation Engineering Manager

E. Blondin, Mechanical Design Manager

G. Contrady, Programs Manager

S. Greenlee, Engineering Director

D. Anthony, NDE Manager

B. Grundmann, Corporate Licensing, Cantera

D. Gudger, Regulatory Assurance Manager

T. Spelde, Byron ISFSI Project Manager

D. Thompson, Radiation Protection Manager Nuclear Regulatory Commission

R. Skokowski, Branch Chief

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened

05000455/2009-001-00 LER Late Entry into TS Condition associated with Reactor Coolant System Leakage Characterization resulting in a condition

prohibited by TSs (Section 4OA3.1)

05000454/2009-004-01

05000455/2009-004-01 URI Assigning appropriate 10 CFR 61 waste stream to radioactive waste shipments (Section 2PS2.4)

05000454/2009-004-02

05000455/2009-004-02 NCV Diesel Oil Storage Vents Not Seismically Qualified or Tornado Resistant (Section 4OA3.2)

05000454/2009-004-03

05000455/2009-004-03 NCV Inadequate Evaluation of Seismic Restraint on the FHB Crane Trolley (Section 4OA5.1)

05000454/2009-004-04

05000455/2009-004-04 URI Use of Friction in Design of FHB Crane to Single Failure Proof (Section 4OA5.1)

05000454/2009-004-05

05000455/2009-004-05 URI Unresolved Technical Concerns on Design of Seismic Restraint on FHB Crane Trolley (Section 4OA5.1) Closed 0500455/2009-001-00 LER Late Entry into TS Condition associated with Reactor Coolant System Leakage Characterization resulting in a condition prohibited by TSs (Section 4OA3.1)

Attachment

05000454/2009-004-02

05000455/2009-004-02 NCV Diesel Oil Storage Vents Not Seismically Qualified or Tornado Resistant (Section 4OA3.2)

05000454/2009-004-03

05000455/2009-004-03 NCV Inadequate Evaluation of Seismic Restraint on the FHB Crane Trolley (Section 4OA5.1)

05000454/2009-003-02

05000455/2009-003-02 URI Diesel Oil Storage Vents Not Seismically Qualified or Tornado Resistant (Section 4OA5.1)

05000454/2008003-07

05000455/2008003-07 VIO Design Basis Re-Analysis of the Ultimate Heat Sink (Section 4OA5.5)

Discussed

05000454/2009-007-03

05000455/2009-007-03 URI Application of Single Failures to the Chapter 15 Accident (Section 4OA5.5)

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.

Section 1R04: Equipment Alignment (Quarterly) Drawing

M-61, Sheet 1A, Revision AQ; Diagram of Safety Injection Drawing M-61, Sheet 3, Revision AH; Diagram of Safety Injection BOP

SI-M1A; Train A Safety Injection System Valve Lineup, Revision 2 BOP

SI-M1; Safety Injection System Valve Lineup, Revision 21

BOP

SI-E1A; Safety Injection System Train A Electrical Lineup, Revision 2

BOP

SI-E1; Safety Injection System Electrical Lineup, Revision 7

BOP

CS-M1A; Containment Spray System Train A Valve Lineup, Revision 2 BOP

CS-M1; Containment Spray System Valve Lineup, Revision 13 BOP

CS-E1A; Containment Spray System Train A Electrical Lineup, Revision 1

BOP

CS-E1; Containment Spray System Electrical Lineup, Revision 4

Corrective Action Documents As a Result of NRC Inspection

IR 950853; NRC Plant Walkdown Identified Issues, August 07, 2009

IR 969121; NRC Identified Leak on 1RH607 - Active Dripping Stem Leak, September 22, 2009

IR 971348; Engineering Recommendation to Tighten Bolting, September 22, 2009

IR 971350; Need a Work Request for RP to Decontaminate, September 22, 2009

IR 971351; Engineering Recommendation to Tighten Bolting, September 22, 2009

Section 1R05: Fire Protection (Quarterly) Byron Station Pre-Fire Plans, Zone 11.1A-0; Auxiliary Building 330' Elevation, Essential Service Water Pump Room, Revision 4

Byron Station Pre-Fire Plans, Zone 9.2-2; Auxiliary Building 401' Elevation, 2A Diesel Generator and Day Tank Room, Revision 5 Byron Station Pre-Fire Plans, Zone 8.2-2 South; Turbine Building 369' Elevation, Unit 2 Turbine Building Basement South, Revision 4

Byron Station Pre-Fire Plans, Zone 8.2-2 North; Turbine Building 369' Elevation, Unit 2 Turbine Building Basement North, Revision 5

Byron Station Pre-Fire Plans, Zone 8.1-0; Turbine Building 369' Elevation, Clean and Dirty Oil Tank room, Revision 5 Byron Station Pre-Fire Plans, Zone 8.2-1 South; Turbine Building 369' Elevation, Unit 1 Turbine Building Basement South, Revision 4

Byron Station Pre-Fire Plans, Zone 8.2-1 North; Turbine Building 369' Elevation, Unit 1 Turbine Building Basement North, Revision 5

Byron Station Pre-Fire Plans, Zone 11.1B-0; Auxiliary Building 330' Elevation, Essential Service Water Pump Room, Revision 4

BAP 1100-16T2; Hourly Fire/Flood Watch Inspection Log, Revision 2

BAP 1100-16T4; Supervisor Fire Watch Tracking Sheet, Revision 1

IR 899937; NSRB Issues Identified During Plant Tour, March 30, 2009

Attachment Corrective Action Documents As a Result of NRC Inspection

IR 946717; NRC Identified Issues with Auxiliary Building Equipment, July 28, 2009

IR 946721; 2AF004A Packing Leak 1Drop/15 Seconds, July 28, 2009

IR 946890; 0VA265Y Appears to Be Stuck Open, July 28, 2009

IR 953539; NRC Issues / Improvement Items, August 14, 2009

Section 1R07: Heat Sink Performance

IR 963011; One Tube Left Blocked in Unit-0 CC HX, September 09, 2009

IR 968169; Indication of Leak By From SX Isolations to 0CC01A, September 21, 2009

WO 803906 03; Support Eddy Current Testing Concurrent with

GL 89-13, September 08, 2009 Corrective Action Documents As a Result of NRC Inspection

IR 955731; NRC Identified Grass Growing in 0B SXCT Basin, August 18, 2009 Section 1R08P:

Inservice Inspection Activities

IR 962727; WR Needed To UT Pipe Due To Internal Pitting; September 8, 2009

IR 964561; B1R16 M3 Valve Packing BA Leakage, 1RC090D; September 14, 2009

IR 965007; NOS ID Rejected Weld; September 15, 2009

EXE-ISI-11; Liquid Penetrant Examination; Revision 2

EXE-UT-350; Procedure for Acquiring Material Thickness and Weld Contours; Revision 2

EXE-PDI-UT-2; Ultrasonic Examination of Austenitic Piping Welds in Accordance with

PDI-UT-2; Revision 5

ER-AA-335-025; Oversight of Vendor NDE Activities; Revision 4

ER-AA-335-1000; Nondestructive Examination (NDE) Program; Revision 4

ER-AA-335-1002; Nondestructive Examination (NDE) Training; Revision 2

ER-AA-335-001; Qualification and Certification of Nondestructive Examination (NDE)

Personnel; Revision 2

ER-AA-335-010; Guidelines for ASME Code Allowable Flaw Evaluation and ASME Code Coverage Calculations; Revision 1

CY-AP-130-3100; Deposit Sampling and Analysis; Revision 0

ER-AP-331; Boric Acid Corrosion Control (BACC) Program; Revision 5

ER-AP-331-1001; Boric Acid Corrosion control (BACC) Inspection Locations, Implementation and Inspection Guidelines; Revision 4

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

ER-AP-331-1004; Boric Acid Corrosion Control (BACC) Training and Qualification, Revision 3

Section 1R12: Maintenance Effectiveness (Quarterly)

1A RCFC Upper Motor 90 Degree from UMX Vibration Data, September 29, 1994 to September 23, 2009

BIP 2500-154; Calibration of RCFC Vibration Switch, Revision 3

ECR 388104; Adjusting the Vibration Switch 1VS-VP001 with Fan in Low Speed vs Hi Speed, February 17, 2009 Maintenance Rule Monthly Evaluation, VP - Containment HVAC, September 13, 2009 OTDM 2009-06, 1A Reactor Containment Fan Cooler (RCFC) has High Vibration in High Speed, Revision 1

Attachment

IR 122508; 1A RCFC High Speed Breaker Cell Switch Broken, September 11, 2002

IR 597788; The Cell Switch Failed During Surveillance on 2B High Speed BRKR, March 1, 2007

IR 852965; Elevated Vibrations on 1A RCFC Fan, December 5, 2008 IR 1A RCFC Vibrations Have Increased, December 9, 2008

IR 857362; 1A RCFC Evaluation Results, December 17, 2008

IR 967192; 1A RCFC Troubleshooting Results, September 19, 2009

IR 970318; Guide Damage - Lost Parts, September 24, 2009

IR 971126; Update on Lost Parts From 1D LSIV, September 24, 2009

WO 953092-01; IM Perform Calibration on 1VS-VP001, December 22, 2008 Prompt Evaluation

965440; 1D Cold Leg Stop Valve Torqued Out and Would Not Close, Revision 15

Prompt Evaluation

970878; Body to bonnet Alignment Issues, Revision 14

Section 1R13: Maintenance Risk Assessments and Emergent Work Evaluation Special Procedure

SPP-09-002; Maintenance Repairs of 2FC8765, Revision 1

IR 893197; 1A DG Starting Air Line Filter Broken, March 15, 2009

IR 921122; Equipment Out of Expanded Tolerance, May 18, 2009

IR 921982; Found Temperature Pressure Switch Out of Tolerance, May 03, 2005

IR 924129; DG Pressure Switch Found out of "ET", May 26, 2009

IR 939971; Failed PMT 1B DG 1A Starting Air Compressor, July 08, 2009

IR 942070; 1DG11MA Came Apart After 1A DG Start Unplanned LCOAR 1BOL 8.1, July 15, 2009

IR 942556; NOS ID: 1A DG Control Air Filter Tightness, July 16, 2009

Section 1R15: Operability Evaluations (Quarterly) Drawing No. 6E-2-4030EF84; Schematic Diagram Reactor Protection Semi-Auto Testing Part 3 Train B, Revision E Drawing No. 6E-204030EF94; Schematic Diagram Reactor Protection Semi-Auto Testing Part 3 Train B, Revision E

Byron Station Unit 2 Support Drawing No. M-2MS01058V - Sheet 2, Revision C

Calculation 18.6.3.3; Embed Plate Field Problems, Section 28, Revision 0

WCAP-10271 Supplement 1-P-A; Evaluation of Surveillance Frequencies and Out-of-Service Times for the reactor Protection Instrumentation System, May 1986 Byron and Braidwood Station Units 1 and 2 Application for Amendment, August 5, 1992

EC 376082 006; OP EVAL 07-008, UHS Capability with Failure of SX Fans, June 29, 2009

EC 376331, 2BOSR 3.1.5-1; Proceduralized TCC to Install Temporary Jumper in Parallel with Train 2B SSPS Mode Selector Switch Contacts 5-6 to Prevent Unnecessary Reactor Trip During Train 2A SSPS Testing, Revision 0.27 Interim 09-2-043 Operability Evaluation 09-004, "Support 1RY06121S is Not Qualified for Design Basis Loads", Revision 0

Regulatory Guide 1.84, "Design and Fabrication Code Case Acceptability ASME Section III

Division 1", Revision 26

Procedure

NES-MS-03.2, "Evaluation of Discrepant Piping and Support Systems", Revision 6

Section 1R18: Plant Modifications 50.59 Review; Temporarily Change the Function of 6" Gate Valve 2AF017A from Normally Closed to Locked Open to Maintain Operability of Essential Service Water Suction Supply to the

2A Auxiliary Feedwater Pump, Revision 0

Attachment OTDM 2009-008; Determine Appropriate Timing and Actions to be Taken to Restore 2AF017A to Operable Status, July 24, 2009

MOV Post Test Data Review Worksheet; Valve

BYR-2AF017A, July 22, 2009

EC 376290; Change the Function of 6: Gate Valve 2AF017A From Normally Closed to Locked Open Due to Valve Stroke Time Failure, July 16, 2009

IR 942048; 2AF017A Shows Dual Indication When Stroked Open, July 15, 20092BOSR

0.5-3.AF.1-1; Unit 2 ASME Surveillance Requirements for the A Train Auxiliary Feedwater SX Supply Valves, Revision 8

Work Order

1178173-02 Corrective Action Documents As a Result of NRC Inspection

IR 950297; NRC Identified No Control Mechanism on Operator Aid label, August 06, 2009

Section 1R19: Post Maintenance Testing (Quarterly)

WO 0836112; CM Replace 0SX007 in B1R16P, July 17, 2009

WO 1013413; 1RH607 Flange Gasket Leak (Boric Acid), September 24, 2009

WO 1124223 01; 1RH01PA Comprehensive IST Required for Residual Heat Removal Pump, September 25, 2009

WO 1126538 01; 1RH01PB Comprehensive IST Required for Residual Heat Removal Pump, September 25, 2009

WO 1125846, 1B Diesel Generator SI Signal Override Test, September 24, 2009

WO 1132933 02; IST Stroke Time for 1FW039C Close to Tech Spec Limit, November 05, 2008

WO 1169280 02; Replace/Upgrade 2A CV Pump Deflector Ring Setscrews, August 11, 2009

BOP

CV-19; Switching Charging Pumps, Revision 16

IR 820588; Pump Inboard Seal Leak, September 22, 2008

IR 940123;

CAT 157913-2 Requires a Conditional Release for

WO 1132933, July 09, 2009

IR 941206; Dry Boron on Mechanical Seals, July 13, 2009

IR 950830; 1FW039C Stroke Time Margin Issue (WO 1132933)

CID 157913-2, August 07, 2009

IR 951734; 2SX197A Valve Hard To Turn, August 11, 2009

IR 962821; Torque Switch Fails Inspection, September 09, 2009

IR 963054; Bolting Issues with Mounting the 0SX007 Actuator, September 09, 2009

1BOSR 8.1.17-2; Unit One 1B Diesel Generator SI Signal Override Test - 18 Month, Revision 12 1BOSR 8.1.17-2; Unit One 1B Diesel Generator SI Signal Override Test - 18 Month, Revision 13

Unit 2 Operator Log, September 23, 2009

MA-AA-716-001; Quality Material/Components Control and Identification/Segregation of Non-Conforming Items, Revision 3

Corrective Action Documents As a Result of NRC Inspection

IR 952224; NRC Observation Item on 2A CV Pump, August 11, 2009

IR 952231; Boron on 2A CV Pump Inboard Seal Area, August 11, 2009

IR 952233; NRC Observation Item on 2A CV Pump, August 11, 2009

IR 969121; NRC Identified Leak on 1RH607 - Active Dripping Stem Leak, September 22, 2009

IR 970108; A NRC Inspector Found Emergency Light without Indication, September 24, 2009

IR 971348; Engineering Recommendation to Tighten Bolting, September 22, 2009

IR 971351; Engineering Recommendation to Tighten Bolting, September 22, 2009

Attachment

Section 1R20: Refueling and Outage Activities (Quarterly) Selected B1R16 Outage Status, September 21, 2009 thru September 25, 2009 Selected B1R16 Outage News, September 21, 2009 thru September 25, 2009

IR 971126; Update on Lost Parts from 1D LSIV, September 24, 2009

IR 971743; Results of B1R16 1D LSIV FM Recovery Plan, September 28, 2009

Corrective Action Documents As a Result of NRC Inspection

IR 950853; NRC Plant Walkdown Identified Issues, August 07, 2009

IR 966452; NRC Identified Leaks in Unit 1 Containment, September 17, 2009

IR 966499; NRC Identified Leak on 1FC012 Body to Bonnet Dry Boric Acid, September 17, 2009

IR 968841; Extra Step-Off Pad in Place in 1A RH Pump Room, September 22, 2009

IR 969131; NRC Walkdown Identifies Various Unit 1 Issues, September 22, 2009

IR 970260; Inappropriate Worker Practices During Nozzle Cover Removal, September 24, 2009

IR 971348; Engineering Recommendation to Tighten Bolting, September 22, 2009

IR 971351; Engineering Recommendation to Tighten Bolting, September 28, 2008 Work Order

1271338 03; NRC Identified Leak 1RH607 - Active Stem Leak Visual No Leakage and Verify Valve Strokes, September 28, 2009

Section 1R22: Surveillance Testing (Quarterly) 0BOSR

FP-A3; 0A and 0B Fire Pump Annual Alarm Test, Revision 10 1BOSR 6.1.1-16; Unit 1 Primary Containment Type C Local Leakage Rate Tests and IST Tests of Service Air System, Revision 6

2BOSR 3.1.5-1; Train A Solid State Protection System Surveillance, August 21, 2009

WO 1123842 01; 111 "A" Train 125V Battery Bank Service Test, September 15, 2009

WO 973016 02; Replace Stem on 0SX161B Non-Safety with Safety Related, July 28, 2009 WO Task

973016 11; OP Visual (Non-ISI), July 31, 2009 WO Task

973016 12; OP Functional Test Verify Valve Stroke 0SX161B, July 31, 2009 WO Task

973016 14; OP Visual of New Vent Pipe and Welds for Leaks at NOP, August 02, 2009

WO Task

973016 15; OPS PMT - Verify Flow at Flume, August 01, 2009

WO 973016 19; Replace Steam on 0SX161B Non Safety with Safety Related, July 29, 2009

Corrective Action Documents As a Result of NRC Inspection

IR 945071; NRC Identified Error in Report of Maximum RCS Leakage, July 21, 2009 2OS1:

Access Control to Radiologically Significant Areas

IR 966917; Worker Entered HRA without ED; dated September 18, 2009 Event-Issue Report Format; Worker Entered HRA ; dated September 19, 2009

IR 967204; Unplanned Electronic Dosimeter Dose Rate alarm, dated September 19, 2009

IR 967199; LHRA Key Doesn't Match LHRA Door; dated September 19, 2009

IR 966696; High Radiation turnstile Left Unlocked; dated September 19, 2009

IR 967479; TELEX Headset Communication System was Unavailable; dated September 20, 2009

IR 966696; High Radiation Turnstile Left Unlocked; dated September 18, 2009

IR 970260; Inappropriate Worker Practices during Nozzle Cover Removal; dated September 25, 2009

Attachment

IR 969571; NRC Identified Containment Housekeeping Needs Improvement; dated September 23, 2009

IR 965005; B1R16LL - Forced Oxidation Radiological Postings; dated

September 14, 2009

RWP-10010519; Unit-1 LSIV Repair Work: All Activities; Revision No. 1

RWP-10010521; Unit-1 LSIV Interference, Scaffold, Insulation and Support Activities;

Revision No. 0

RWP-10009695; Reactor Head Disassemble - Re-Assemble - All Activities; Revision No. 0

RWP-10009715; Unit-1 Shielding Activities; Revision No. 0

RWP-10009713; Outage Scaffolds Activities; Revision No. 0

RWP-10009688; Air Operated Valves (AOV): All activities; Revision No. 0

CC-AA-401; Temporary Shielding Permit, Revision No. 8

RP-AA-460; Controls for High and Locked High Radiation Areas; Revision No. 19

RP-AA-460-001; Controls for Very High Radiation Areas; Revision No. 2

RP-AA-462-1002; Radiological Risk Assessment for Portable X-Ray Radiography; Revision No.1

RP-AA-462-1001; Control for Portable X-Ray Radiography; Revision No. 1

RP-AA-203; Exposure Control and Authorization; Revision No. 3

RP-AA-203-1001; Personnel Exposure Investigations; Revision No. 0

RP-AA-462; Controls for Radiographic Operations; Revision No. 7

RP-AA-460-002; Additional High Radiation Exposure Control; Revision No. 0

CC-Aa-401; Installation and Control of Temporary Shielding and Shielding Components;

Revision No. 8

2OS2: (ALARA) Planning and Controls (71121.02)

RP-AA-401-1001; On Line Dose Performance Threshold Reporting Guidance; Revision No.2

RP-AA-401; Operational ALARA Planning and Control; Revision No. 9

IR 967762;

RWP 10010811 Locked Out on Dose; Dated September 21, 2009

IR 969564; Worker Exceeded Dosimeter Rate Alarm Set Point; dated September 23, 2009

IR 968956; B1R16 - Loss of Video Monitoring in Containment; dated

September 23, 2009

RP-AA-401; Attachment 3; ALARA Briefing Checklist on Emergent 1S18948B Gasket Replacement; dated September 22, 2009

1RC8002D Breach Sequence Plan Briefing Sheet Byron Station B1R16 Exposure Total Goal 57 Rem

RP-AA-401; Attachment 3; MSIP Preps Including Removal of CC Piping in Reactor Vessel; September 24, 2009

IR 969456; Work Performed on RWP1009696 without an ALARA Briefing; dated September 23, 2009

IR 967223; Station ALARA Committee Meeting Results; dated September 18, 2009

Section 2PS2: Radioactive Material Processing and Transportation Radiation Protection Increased Frequency Audit Report;

NOSA-BYR-08-13; September 2, 2008 Radiation Protection Report;

NOSA-BYR-07-06; September 27, 2007

Functional Area Self-Assessment;

842790-03; Radioactive Material Processing and Transportation; May 5, 2009

RW-AA-100; Process Control Program for Radioactive Wastes; Revision 7

RP-AA-605; 10 CFR Part 61 Program; Revision 2

Attachment

RP-AP-605; 10 CFR Part 61 Waste Stream Sampling, Analysis, and Trending for Shifts in Scaling Factors; Revision 0

RP-AA-600; Radioactive Material/Waste Shipments; Revision 10

RP-AA-600-1001; Exclusive Use and Emergency Response Information; Revision 5

RP-AA-600-1003; Radioactive Waste Shipments to Barnwell and the Defense Consolidation Facility (DCF); Revision 6

RP-AA-600-1005; Radioactive Material and Non Disposal Site Waste Shipments; Revision 11

RP-AA-601; Surveying Radioactive Material Shipments; Revision 10

RP-AA-602; Packaging of Radioactive Material Shipments; Revision 12

RP-AA-603; Inspection and Loading of Radioactive Shipments; Revision 4

RP-AA-603-1001; Inspection and Loading of Radioactive Material/Waste Shipments; Revision 2

TQ-AA-126; Radioactive Shipping Training; Revision 3

IR 766507; Chemistry/Radwaste Documents Incomplete or Inaccurate; April 23, 2008

IR 765807; NOS Identified Radioactive Material Shipping Near Miss; April 15, 2008

IR 884052; Non-Conforming Waste Found be Vendor in Radwaste Shipment; February 23, 2009

IR 928393; Non-Conforming Metal Shipped to Bear Creek Processing; June 3, 2009

Radwaste Shipment;

RWS-07-014; November 28, 2007

Radwaste Shipment;

RWS-07-015; December 5, 2007 Radwaste Shipment;

RWS-07-016; December 12, 2007 Radwaste Shipment;

RWS-08-004; March 11, 2008

Radwaste Shipment;

RWS-08-006; March 17, 2008

Section 4OA1: Performance Indicator Verification

LS-AA-2090; Monthly Data Elements for NRC Reactor Coolant System (RCS) Specific Activity; April 2008 through June 2009

LS-AA-2140; Monthly Data Elements for NRC Occupational Exposure Control Effectiveness; April 2008 through June 2009

LS-AA-2150; Monthly Data Elements for RETS/ODCM Radiological Effluent Occurrences;

April 2008 through June 2009

Unit 1 & 2 Monthly RCS Leak Rate Tracking Data Sheet, June 2008 - June 2009

Corrective Action Documents As a Result of NRC Inspection

IR 945071; NRC Identified Error in Report of Maximum RCS Leak Rate, July 21, 2009

Section 4OA2: Identification and Resolution of Problems (71152)

IR 810117; Unit 1 LM Indicates Potential Source of Noise as Near 1RC8002D, August 22, 2008

IR 805756; Rattling Noises Heard on Five Loose Parts Monitors, August 11, 2008

Section 4OA5: Other Activities

Sheet M-61; Diagram of Safety Injection, Revisions AM, AI, AR, AU, AW, and V Sheet M-62; Diagram of Residual Heat Removal, Revision BC

1RH02 Sheet 1; Residual Heat Removal System Isometric, Revision A 1RH02 Sheets 2and 3; Residual Heat Removal System Isometric, Revision A 1RH02 Sheets 4 and 5; Residual Heat Removal System Isometric, Revision B

1RH02 Sheets 6 - 10; Residual Heat Removal System Isometric, Revision A

RH-3, 4, and 5; Large Bore Isometric Residual Heat Removal, Revision 14

Attachment

RH-6; Large Bore Isometric Residual Heat Removal, Revision 7

RH-7; Large Bore Isometric Residual Heat Removal, Revision 12

ISI 3; Large Bore Isometric Safety Injection, Revision 5G ISI 7; Large Bore Isometric Safety Injection, Revision 8 BOP

RH-3; Fill and Vent of the Residual Heat Removal System, Revision 33

EC 371411; Generic Letter 08-01, Gas Accumulation in ECCS, CS, and DH Systems Byron Residual Heat Removal System, Revision 1

EC 371412; Generic Letter 08-01, Gas Accumulation in ECCS, CS, and DH Systems Byron Safety Injection System, Revision 1

IR 968341; Void in RWST Header after 1B RH Dynamic Fill, September 22, 2009

IR 969331; Small Gas Void Discovered Upstream of 2SI8818A, September 23, 2009

IR 969475; Small Gas Void Discovered Downstream of 2SI8809B, September 23, 2009

IR 793279; Perform and Document Extent of Condition Review of VC and CC, June 04, 2009

Byron Campaign 1 Cask 1 Basket Layout and Load Assembly List Byron Campaign 1 Cask 2 Basket Layout and Load Assembly List Byron Campaign 1 Cask 3 Basket Layout and Load Assembly List Byron Campaign 1 Cask 4 Basket Layout and Load Assembly List Byron Station Fuel Failure History Leak Testing Specialist, Visual Acuity Record; July 11, 2008 50.59 Evaluation 6G-09-003;

EC 367123 and UFSAR Change No.13-005; July 17, 2009 50.54(q) Evaluation;

EP-AA-120-1001; Radiological E Plan Annex for Byron; Revision 4

50.59 Review Screening 6E-08-032; Engineering Change

367118 - ISFSI Pad

50.59 Review Screening 6E-08-054; Engineering Change

367119 - ISFSI Haul Path

50.59 Review Screening 6E-08-167; Engineering Change

367120 - Fuel Handling Building changes for ISFSI 50.59 Review Screening 6E-09-008; Fuel Handling Building Crane Upgrade; May 1, 2009 50.59 Review Screening 6E-09-008; Engineering Change

367123 - Fuel Handling Building Crane Upgrade to Single Failure Proof; March 19, 2009

50.59 Review Screening 6E-09-008; Engineering Change

367123 - ISFSI Pad

2.212 Evaluation Report; Byron Nuclear Power Station Units 1 and 2 10

CFR 72.212 Report; Revision 0

IR 654815; Cracks Identified in Fuel Building Overhead Crane End-Ties; July 20, 2007

IR 858012; Issues with Estimated Does from ISFSI Pad; December 18, 2008

IR 874233; New FHB Crane Trolley 0HC03G Clearance Issues; January 30, 2009

IR 889555; NOS Identifies Deficiency at Holtec for Dry Cask Storage; March 6, 2009

IR 893490; ISFSI Spacer Dimensions for Fuel with No Inserts; March 16, 2009

IR 897253; Dry Cask Storage Supplier Equipment Problems; March 25, 2009

IR 897300; TRM 3.9.D Applicability for Cask Loading Area in SFP; March 25, 2009

IR 897633; Initial Dry Cask Storage Seal Weld Demonstration; March 25, 2009

IR 898005; Fuel Handling Crane Load Test; March 26, 2009

IR 898217; Fuel Handling Crane Test Slings; March 26, 2009

IR 912885; NRC Question Regarding Design Analysis No. 7.16.14-BYR08-113; April 28, 2009

IR 912892; NRC Question Regarding Design Analysis No. 36272-17; April 28, 2009

IR 912895; NRC Question Regarding Weight of Existing FHB Trolley; April 28, 2009

IR 912911; NRC Question Regarding Upgraded FHB Crane Material; April 28, 2009

IR 918923; NRC Question Regarding Calculation No 8.1.8; May 12, 2009

IR 921359; Main and Aux Hoists Not Working; May 19, 2009

IR 921960; Calc 8.1.9 Crane Girder Analysis and Design; May 21, 2009

IR 933939; NRC Question Regarding Seismic Acceleration Factors; June 22, 2009

IR 934131; Shipping Cask Area Walls Not in Seismic Design of SFP; June 23, 2009

IR 934467; Errors in Vendor Calculation for FHB Crane Seismic Restraint; June 23, 2009

Attachment

IR 945583; NRC Question Regarding Design Analysis No. 36272-12; March 26, 2009

IR 945662; NRC Question Regarding 50.59 Screening for

EC 367123; March 27, 2009

IR 957014; Compliance with

NOG-1 Rules for Single-Failure Proof Cranes; August 24, 2009

IR 957919; NRC Question on Design analysis No. 8.1.2-BYR08-114; August 26, 2009

IR 957928; NRC Question on Design analysis No. 2.4.3-BYR08-125; August 26, 2009

IR 957935; NRC Question on Design analysis No. 2.4.3-BYR08-070; August 26, 2009

IR 966184; Compliance with

NOG-1 Rules for Single Failure Proof Cranes; September 17, 2009

Analysis No. 2.4.3-BYR08-032; Non-Mechanistic Tip of the

HI-Storm 100S, Version B;

Revision 0 Appendix J of Supplement No. 5 to

NUREG-0876; Safety Evaluation Report Related to the Operation of Byron Station, Units 1 and 2; October 1984

Assembly in Fuel Handling Building Decontamination Pit Area and Track Way; Revision 0

Assessment on Issues Regarding Field Load Testing for Single Failure Proof Crane Upgrades;

January 1, 2009 Byron Station 1 and 2 UFSAR, Revision 12 Calculation No. 2.4.3-BYR08-027; Structural Analysis of ISFSI Pads at Byron and Braidwood Calculation BYR08-024; Dry Cask Storage Project - Fire Radiant Heat and Explosion Overpressure Analysis; Revision 0

Calculation 2.4.3-BYR08-070; Dynamic Analysis of

HI-STORM /

HI-TRAC Stack Up; Revisions 0, 1, 2 Calculation 2.4.3-BYR08-125; Dynamic Analysis of

HI-TRAC/VCASP Stack Up;

Calculation BYR08-126; Dry Storage Fuel and Component Characterization;

February 23, 2009

Calculation BYR08-127; Byron Cask Loader Database Population; March 2, 2009

Calculation BYR08-135; Cask Handling Weight and Cask Handling Dimensions for Byron and Braidwood and LaSalle; Revision 1 Calculation 7.16.14-BYR08-113; Removable Access Platform at EL. 426'-10 1/4" Over Fuel Handling Building Decontamination Pit Area; Revision 0

Calculation 8.1.2-BYR08-114; Evaluation of Floor Slab at El 401'-0" for VCASP

HI-STORM

Stack Up Calculation 8.1.8-BYR09-021; Fuel Handling Building Roof and Crane Column Design (Column X-21); Revision 0

Calculation 8.1.9-BYR09-022; Fuel Handling Building Crane Girder Analysis; Revision 0

Calculation 8.1.12-BYR08-130; Design of Fuel Handling Building

HI-TRAC-VCASP Steel Support Framing at El. 401'-0"; Revision 0

Calculation 8.1.12-BYR09-054; Evaluation of Spent Fuel Pool Structure for Loads from

HI-TRAC Placed in Cask Loading Area; Revision 0 Calculation 36272-02; Exelon/Byron and Braidwood Hoist/Reeving Equipment Calculation; Revisions 2, 6, 8

Calculation 36272-12; Exelon/Byron and Braidwood Single Failure Proof Trolley Seismic Analysis; Revisions 5, 9 Calculation 36272-13; Exelon/Byron and Braidwood Single Failure Proof Trolley Critical Weld Calculations; Revisions 3, 4

Calculation 36272-17; Exelon/Byron and Braidwood Single Failure Proof Trolley Misc. Items Seismic Calculations; Revisions 3, 9, 11

Calculation 36272-31; Exelon/Byron and Braidwood - Bumper Calculation; Revision 1

Calculation 36272-35; Exelon/Byron and Braidwood - Girder Bending Moment and Reaction Force Comparison; Revision 3 Calculation

HI-2012797; Structural Analysis of the

HI-TRAC Lift Link; Revision 2

Calculation

HI-2083894; Non-Mechanistic Tip of the

HI-Storm 100S, Version B; Revision 3

Calculation

HI-2083901; Structural Analysis of ISFSI Pad at Byron; Revision 3

Attachment Calculation

HI-2084113; Dose Versus Distance from a

HI-STORM 100S Version B Containing the

MPC-32; Revision 1

Calculation

HI-2084120;

HI-Storm CoC Radiation Protection Program Dose Rate Limits; Revision 0 Calculation

HI-2094252; Structural Analysis of 125-Ton

HI-TRAC Lift Yoke; Revision 0

Calculation

HI-992234; Stress Analysis of MPC Lift Cleat; Revision 3

Calculation

HI-992272; Calculation Package for Cask Miscellaneous Items; Revision 10

Certificate of Compliance No. 1014; Amendment 3

Certificate of Conformance; Helium; April 22, 2009 Design Analysis

CC-AA-309-1001; Dry Cask Storage Project - Fire Hazard Analysis Report; Revision 4

Drawing No. 2511; MPC Cleat (Ancillary No. 209), Revision 13

Drawing No. 2602,

HI-STORM Lift Bracket Ancillary No. 107, 9

Drawing No. 2643; HI STAR/HI-TRAC Lift Link Assembly Ancillary No. 701; Revision 9 Drawing No. 3768; 125 Ton

HI-TRAC-125D Trunnion and Shell Assembly; Revision 7 Drawing No. 5894;

HI-TRAC 125 Ton Transfer Cask Lift Yoke Ancillary No. 702; Revision 3

Procedure,

EP-AA-1002; Radiological Emergency Plan Annex for Byron Station; Revision 24

Engineering Change

367120; Dry Cask Storage Project Fuel Handling Building Upgrades;

Revision 0 Engineering Change

367123; Dry Cask Storage Project-FHB Crane Upgrade to Single Failure Proof Crane-0HC03G; Revision 0

Exelon Generation Company Quality Assurance Program Topical Report

NO-AA-10, Revision 83, April 6, 2009

General Welding Standard:

GWS-1, Revision 4

General Welding Standard:

GWS-1, Revision 4

HI-STORM (Overpack), Component Completion Record, No.

DOC-1024-296R0, January 9, 2009

HI-STORM 100 Dry Cask Storage System Introduction 2009

Holtec International; Final Safety Analysis Report for the

HI-STORM 100 Cask System;

HI-2002444, Revision 5

Holtec Letter; Conversion of

HI-STORM 100 CoC (Amendment 3) Backfill Limits;

February 9, 2009

HSP-335;

HI-STORM Lifting Bracket Load and Functional Test; Revision 1

Inspection Report;

IN 139-7; MMH Fuel Handling Building Crane Inspection Report;

April 27, 2009

Licensee's Training Document; Exelon Learning History

Licensee's Training Document; LMS Supervisor Matrix Report

LS-BY-105; Attachment 5 - 10

CFR 72.48 Qualification Form Holtec Dry Cask Storage System;

Revision 10

Manual: P&H Document 36272-28, "Operation and Maintenance Manual" Revision 2

MPC-32, Component Completion Record No.

DOC-1023-089R0; October 8, 2008

MPC-32, Component Completion Record No.

DOC-1023-089R0; October 8, 2008 NDE Level II Personnel VT and PT Certificates

P & H Document

CN-36272-06; Safety Analysis Report for P and H Supersafe Single Failure Proof Trolley Exelon Fuel Handling Crane; March 4, 2009

P & H Document

CN-36272-09;

NOG-1 Compliance Matrix Byron, Braidwood and LaSalle Fuel Handling and Reactor Building Cranes; March 11, 2009 Procedure Approval Form;

AD-AA101-F-01;

GQP-9.2 Revision Byron Procedure Approval Form; Revision 1

Procedure

Approval Form;

AD-AA101-F-01;

MSLT-DSC Revision 0 Byron Procedure Approval Form; Revision 1

Attachment Procedure

BMP 3000-1; Control of the Movement of Heavy Loads; Revision 18 Procedure

BFP-FH-20T1; Fuel Building Operating Zones for Heavy Loads; Revision 4

Procedure

BFP

FH-64; Transporter Operations; Revision 2 Procedure BFP

FH-65; Spent Fuel Cask Site Transportation; Revision 1, 2 Procedure BFP

FH-71; MPC Processing; Revision 1

Procedure

BFP

FH-72; Hi-Storm Processing; Revision 0

Procedure

BFP

FH-74; Helium Cooldown System Operation and MPC Reflood; Revision 0

Procedure

BFP

FH-76; Transporter Undocumented Visual Inspection; Revision 1

Procedure

BFP

FH-77; MPC Processes; Revision 0 Procedure BFP

FH-78; Vacuum Drying System Operation; Revision 0 Procedure BFP

FH-79; MPC Alternate Cooling; Revision 0

Procedure

BFP

FH-80; Haul Path and ISFSI Dry Run Operations; Revision 0

Procedure

BFP

FH-82; MPC Unloading Operations; Revision 0

Procedure

BFP-FH-71; MPC Processing; Revision 1 Procedure

CC-AA-501-1026; Purging Techniques; Revision 0 Procedure

FH-64; Transporter Operations; Revision 0

Procedure

FH-65; Spent Fuel Cask Site Transportation; Revision 0

Procedure

FH-67; Trackmobile Undocumented Visual Inspection; Revision 0

Procedure

FH-74; Helium Cooldown System Operation and MPC Reflood; Revision 0 Procedure

FH-76; Transporter Undocumented Visual Inspection; Revision 0 Procedure

FH-80; Haul Path and ISFSI Dry Run Operations; Revision 0

Procedure

GQP-9.0; Training, Qualification, Examination and Certification of NDE, Inspection and Testing Personnel; Revision 7

Procedure

GQP-9.2; High Temperature Liquid Penetrant Examination and Acceptance Standards for Welds, Base Material, and Cladding; Revision 3 Procedure

GQP-9.6 Supplement; Visual Examination of Welds Procedure Supplement; Revision 8

Procedure

GQP-9.6; Visual Examination of Welds; Revision 8

Procedure

MA-AA-716-022; Control of Heavy Loads Program; Revision 4

Procedure

MMH 36272-16; Fuel Handling Building Site Acceptance Test Procedure; Revision 6 Procedure

MMH 36272-34; Fuel Handling Building Addendum Site Acceptance Test Procedure Zone Limiting Switches; Revision 0

Procedure

MSLT-DSC-Exelon; Helium Mass Spectrometer Leak Test Procedure;

Procedure

NF-AA-310; Move Sheet - 2009 ISFSI Campaign Cask 1; June 16, 2009

Procedure

NF-AP-622; Fuel Selection and Documentation for Dry Cask Storage Loading at Byron and Braidwood; Revision 0 Procedure 0BMSR

HC-3; Fuel Handling Building Overhead Traveling Bridge Crane Monthly/Yearly Inspection; Revision 6

Procedure

OU-AP-204; Fuel Movement in the Spent Fuel Pool for Byron and Braidwood;

Revision 8

Procedure

PI-CNSTR-T-OP-220; Closure Welding of Holtec Multi-Purpose Canisters at Exelon Facilities; Revision 2 Procedure

PI-CNSTR-T-OP-220; Closure Welding of Holtec Multi-Purpose Canister at Exelon Facilities; Revision 1

Procedure

Quality Report;

PQR 046; Revision 3

Procedure

Quality Report;

PQR 062; Revision 3

Procedure

Quality Report;

PQR 063; Revision 3 Procedure Quality Report;

PQR 600; Revision 4 Procedure

RP-AA-401; ALARA Plan; Revision 9

Procedure

RP-By1001; Remote Monitoring System Technology; Revision 0

Procedure

RP-BY-304-1002; Hi-Storm Radiation Survey; Revision 2

Attachment Procedure

RP-BY-304-1003; ISFSI Radiation Survey; Revision 1

PS-1211; Purchase Specification for the MPC Lift Sling; 5

Radiation Protection Survey No.

RP-BY-304-1001;

HI-TRAC Radiation Survey; Revision 1 Radiation Protection Survey No.

RP-BY-304-1002;

HI-STORM Radiation Survey;

Radiation Protection Survey No.

RP-BY-304-1003; Independent Spent Fuel Storage Installation Radiation Survey; Revision 1

RWP 10010025; Dry Cask Storage Support Activities; Revision 0

RWP 10010822;

RP-AA-401; Dry Cask Storage Activities - All disciplines; Revision 9

Safety Analysis Report, P&H Single Failure Proof Trolley, Exelon Fuel Handling Crane; Revision 0 Safety Evaluation Report (SER); Docket No. 72-1014 applicable to CoC 1014, Sherwin Incorporated NDE Chemical Certifications, December 20, 2004 (re-signed May 25, 2006)

Sherwin Incorporated NDE Chemical Certifications; March 30, 2007 Sherwin Incorporated NDE Chemical Certifications; November 1, 2007 Sherwin Incorporated NDE Personnel VT Certificate; October 13, 2008

Specification; Byron, LaSalle and Braidwood Nuclear Stations Independent Spent Fuel Storage Installation Single Failure Proof Crane Up Grade TS;

Training Matrix Report June 12, 2009 Training Module; Hi-Storm 100 Dry Cask Storage System Introduction; 2009 Training Module; FHAN25700; Overview Training Module; FHAN25701; Receipt Inspections Training Module; FHAN25702;

HI-TRAC Movement and MPC Transfer Training Module; FHAN25704; MPC Processing

TWE-DCS-BYR-001; Byron Fuel Failure Assessment; Revision 0 Vendor Document Review Form:

RM-AA-F01; January 6, 2009 Visual Examination Report; September 2, 2008

Welder Maintenance Log; PCI Energy Services Welder Operator Performance Qualification; PCI Energy Services Welder Performance Qualification; PCI Energy Services Welding Control Procedure;

WCP-3; Revision 9 Welding Control Procedure;

WCP-5; Revision 5

Welding Control Procedure;

WCP-8; Revision 9

Welding Procedure Specification; WPS 8MC-GTAW; Revision 11

Welding Procedure Specification; WPS 8MN-GTAW; Revision 0

Weldstar Certificate of Compliance; Weld Material; April 8, 2008 Weldstar Certificate of Compliance; Weld Material; July 2, 2008 Weldstar Certificate of Compliance; Weld Material; May 19, 2008

Attachment