Text

November 3, 2010

Mr. Michael J. Pacilio 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 05000454/2010004; 05000455/2010004; 07200068/2010001

Dear Mr. Pacillo:

On September 30, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Byron Station, Units 1 and 2. The enclosed report documents the results of this inspection, which were discussed on October 8, 2010, with the Mr. Brad Adams, 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, the NRC has determined that one Severity Level IV violation occurred and one NRC-identified finding of very low safety significance was identified. Both of these 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 2.3.2 of the NRC Enforcement Policy. If you contest the subject or severity of the 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 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.

M. Pacilio -2-

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 System (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/ Eric R. Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455;72-068 License Nos. NPF-37; NPF-66

Enclosure:

Inspection Report 05000454/2010004; 05000455/2010004; 07200068/2010001

w/Attachment:

Supplemental Information cc w/encl: Distribution via ListServ Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos: 05000454; 05000455; 07200068 License Nos: NPF-37; NPF-66 Report No: 05000454/2010004; 05000455/2010004; 07200068/2010001 Licensee: Exelon Generation Company, LLC Facility: Byron Station, Units 1 and 2 Location: Byron, IL Dates: July 01, 2010 through September 30, 2010 Inspectors: B. Bartlett, Senior Resident Inspector J. Robbins, Resident Inspector R. Ng, Project Engineer M. Learn, Reactor Engineer J. Cassidy, Senior Health Physicist R. Jickling, Senior Emergency Preparedness Inspector C. Thompson, Resident Inspector, Illinois Department of Emergency Management Approved by: E. Duncan, Chief Branch 3 Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS

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

REPORT DETAILS

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

REACTOR SAFETY

.................................................................................... 31R04Equipment Alignment (71111.04) ................................................................ 31R05Fire Protection (71111.05) ........................................................................... 41R07Annual Heat Sink Performance (71111.07) ................................................. 51R11Licensed Operator Requalification Program (71111.11) ............................. 61R12Maintenance Effectiveness (71111.12) ....................................................... 61R13 Maintenance Risk Assessments and Emergent Work Control (71111.13) .. 71R15Operability Evaluations (71111.15) ............................................................. 81R18Plant Modifications (71111.18) .................................................................... 81R19Post-Maintenance Testing (71111.19) ........................................................ 91R22Surveillance Testing (71111.22) ................................................................ 101EP2Alert and Notification System Evaluation (71114.02) ................................ 111EP3Emergency Response Organization Augmentation Testing (71114.03) ... 121EP5Correction of Emergency Preparedness Weaknesses and Deficiencies (71114.05) ................................................................................................. 121EP6Drill Evaluation (71114.06)

RADIATION SAFETY

................................................................................ 132RS5Radiation Monitoring Instrumentation (71124.05)

OTHER ACTIVITIES

................................................................................. 174OA1Performance Indicator Verification (71151) ............................................... 174OA2Identification and Resolution of Problems (71152) .................................... 204OA3Follow-up of Events and Notices of Enforcement Discretion (71153) ....... 214OA5Other Activities .......................................................................................... 224OA7 Licensee Identified Violations .................................................................... 32

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

B. Adams, Plant Manager

K. Anderson, Radiation Protection

A. Daniels, Nuclear Oversight

D. Drawbaugh, Emergency Preparedness Manager

C. Gayheart, Operations Director

B. Kartheiser, Emergency Preparedness Coordinator

J. Langan, Licensing Engineer

S. Merrill, Corporate Emergency Preparedness

J. Reed, Radiation Protection

D. Spitizer, Regulatory Assurance

D. Enright, Site Vice President

B. Askren, Security Director

D. Gudger, Regulatory Assurance Manager

T. Hulbert, Regulatory assurance NRC Coordinator

P. Johnson, Lead NOS Assessor

S. Kerr, Chemistry Manager

R. Lloyd, Performance Improvement Manager

T. Leaf, Operations SOS

J. Feimster, Maintenance and Technical Training Manager

B. Spahr, Maintenance Director

E. Hernandez, Engineering Director

B. Barton, Radiation Protection Manager Nuclear Regulatory Commission

E. Duncan, Chief, Reactor Projects Branch 3

R. Skokowski, Chief, Plant Support Branch

J. Robbins, Resident Inspector

Attachment

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened

URI Failure to Perform Adequate Evaluation for Crane Upgrade (Section 40A5)

Relying on the Use of Friction as a Restraining Force when

the HI-TRAC is Placed on top of the HI-STORM

(Section 40A5) 07200068/2010001-01 NCV Failure to Design the ISFSI Pad to Adequately Support the Static and Dynamic Loads of Stored Casks (Section 40A5)

Closed

05000454/2010004-01

05000455/FIN-2010004-01

NCV Failure to Perform Adequate Evaluation for Crane Upgrade (Section 4OA5) 07200068/2010001-01 NCV Failure to Design the ISFSI Pad to Adequately Support the Static and Dynamic Loads of Stored Casks (Section 4OA5)

05000454/2009004-04

05000455/FIN-2009004-04

URI Use of Friction in Design of FHB Crane to Single Failure Proof (Section 4OA7)

05000454/2009004-05

05000455/FIN-2009004-05 URI Unresolved Technical Concerns on Design of Seismic Restraint on FHB Crane Trolley (Section 4OA5)

05000454/2009009-01

05000455/2009009-01

200068/2009001-01 URI Pad Structural Evaluation Revisions to Address Partial Sequential Loading (Section 4OA5)

05000454/2009009-02

05000455/2009009-02

200068/2009001-02 URI Use of NUREG/CR6865 Results in Lieu of Dynamic Analysis (Section 4OA7)

05000455/LER-2009-001-01 LER Late Entry Into TS Condition Associated with Reactor Coolant System Leakage Characterization Resulting in a condition Prohibited by TSS (Section 4OA3)

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.

Section 1R04: Equipment Alignment Quarterly

- BOP

SX-3; Essential Service Water Make-up Pump Startup, Revision 26 - Drawing M-42; Diagram of Essential Service Water, Sheet 7, Revision AE - Drawing M-42; Diagram of Essential Service Water, Sheet 6, Revision BA - Drawing M-37; Diagram of Auxiliary Feedwater, Revision AY

- Drawing M-129; Diagram of Containment Spray, Rev. AK - Drawing M-137; Diagram of Residual Heat Removal, Rev. BG

Section 1R05: Fire Protection (Quarterly) - Pre-Fire Plan;

FZ11.3-0 North. Auxiliary Building 364'-0" Elevation General Area - North - Pre-Fire Plan; FZ11.5-0 North, Auxiliary Building 401'-0" Elevation General Area - North Section 1R07A:

Heat Sink Performance (Annual) -

IR 1106306; Move Up

GL 89-13 Inspection Date of 1A SI Pump Lube Oil HX, August 26, 2010 -

IR 1105710; As Found inspection results of 1B Safety Injection Pump Lube Oil Cooler; August 25, 2010 -

WO 01216874; Inspect heat Exchanger 1SI01SB per Generic Letter 89-13

Section 1R11: Licensed Operator Requalification Program

- Cycle 10-4 Out of the Box; Multiple Rod Drops and Loss of All AC Power, Revision 1

Section 1R12: Maintenance Effectiveness (Quarterly) -

IR 0842111; MSPI Low Margin - SX Pumps, November 07, 2008 -

IR 1007516; 1SX010 Did Not Fully Stroke During Testing, December 18, 2009

-

IR 1008317; 1SX010 MOV Limits Exceeded During Trend Testing, December 21, 2009

-

IR 1009038; Adverse Trend in M-Rule for

SX-5, December 23, 2009 -

IR 1061727; Poor Decision Making, April 26, 2010 - Maintenance Rule Monthly Evaluation for Pressurizer System, June 2010

- Maintenance Rule Monthly Evaluation for Low Voltage System, June 2010

IR 948139; Annual CCA on Equipment Reliability Issues, July 31, 2009 -

IR 963571; NOS ID: Six PZR HTR BKR Trips in Last 3 Months, September 10, 2009

-

IR 1081687; Breaker 1RY03EA-A1A Found in Tripped Position, June 17, 2010 -

IR 1081695; Breaker 2RY03EA-B3A Found in Tripped Position, June 17, 2010 -

IR 1092696; Pressurizer Heater Breaker Found Tripped Open, July 21, 2010

-

IR 989693-02; Apparent Cause Evaluation for Pressurizer Heater Breaker Still Tripping, December 30, 2009 -

IR 1001629-02; Common Cause Analysis to review Auxiliary Power System of Maintenance Rule Function Failures and Critical Component Failure for Common Failure Modes, January 6, 2010

Attachment - SX System Health Report; July 01, 2010 - September 30, 2010 - Unit 1 Component Cooling System Health Reports, 3rd Quarter 2010 - Unit 0 Component Cooling System Health Reports, 3rd Quarter 2010 -

IR 928827; Thermal Barrier CC Return Flow Low, June 8, 2009 -

IR 951336; How to Fill CC Surge Tanks and Engage Margin Management Too, August 10, 2009 -

IR 951684; Unit 1 CC Surge Tank Level Indication / Alarm Spiking, August 10, 2009

-

IR 954443: Unit 1 CC Surge Tank Level Indication Still Spiking, August 17, 2009

-

IR 962777; Unit 1 CC Surge Tank Level High Alarm not lit with SER Showing Alarm, September 9, 2010 -

IR 989561; 1CC053 Tripped and Will Not Reset, November 5, 2010

- IR 1CC9460B Valve Handle Broken, November 16, 2010

-

IR 1002196; Adverse Trend on 1CC01PB Differential Pressure, December 7, 2009

-

IR 1004884; Unit 1 CC Surge Tank Level Spike, December 13, 2009

Corrective Action Documents As a Result of NRC Inspection

IR 1096173; Discussion Results with NRC Regarding LV/RY Issues, July 30, 2010

Section 1R13: Maintenance Risk Assessments and Emergent Work Control (Quarterly) - Issue Resolution Documentation Form 2010-10; Determine When Byron Unit 2 Leaking Pressurizer Safety Relief Valve (PSRV) Should Be Replaced, Revision 6 -

WC-AA-101; On-Line Work Control Process, Rev. 17

- Draft Risk Assessment for Week of March 01, 2010 - Risk Assessment for Week of September 20, 2010, Rev. 1 - Risk Assessment for Week of September 20, 2010, Rev. 2

- Risk Assessment for Week of September 20, 2010, Rev. 3

- Risk Assessment for Week of September 20, 2010, Rev. 4

-

IR 1116288; Remove the Oil Filter Housing for Use in Unit 1 Feedwater Pump, September 22, 2010 -

IR 1116305; Runback of Byron Station Unit 1 due to 1A Feedwater Pump Trip, September 22, 2010 -

IR 1116458; 1A Feedwater Pump Oil Leak Impact on Adjacent Equipment, September 22, 2010 -

IR 1117036; Application of Proper Technical Human Performance Missed Opportunity, September 23, 2010 -

IR 1114580; Review of

OE 31887 for Applicability at Byron, September 19, 2010

-

IR 1115492; Unit 1 Reactor Trip, September 20, 2010

-

IR 1115504; B Train Feedwater Injection Signal, September 20, 2010

-

IR 1115574; Unit 1 Reactor Trip - Train B SSPS Failure, September 20, 2010 -

IR 1064124; Relief Valve in Need of Repair, May 1, 2010 -

IR 1079917; Pressurizer Safety Relief Valve Temperature Indicator Reading Higher, June 13, 2010 -

IR 1080512; Received Unexpected Pressurizer Safety Relief Discharge Temperature High Alarm, June 15, 2010 -

IR 1080965; Pressurizer Safety Relief Discharge Temperature High Alarm Not Working, June 16, 2010 -

IR 1081634; 2A Pressurizer Safety Valve Leaking, June 17, 2010

-

IR 1085536; 2RY8010A Indicating a Leak-by, June 29, 2010

-

IR 1085735; 2A Pressurizer Safety - Emergent Clearance Order C&T Level 4, June 29, 2010

Attachment -

IR 1115247; 2RY8010A Monitoring Update / Lessons Learned, September 20, 2010 -

IR 1117749; Pressurizer Safety 2RY8010A Temperature Spike, September 29, 2010

-

IR 1011385; Unit 1 CC Surge Tank Auto Make-Up for 1 Second Only, January 1, 2010

Section 1R15: Operability Evaluations (Quarterly) -

IR 1073466; Buzzing Noise and Abnormal Indication During ESF Start, May 26, 2010 -

IR 1093487; Fan Motor Bearing-To-Shaft Fit May Be Beyond STND Tolerance, July 22, 2010 -

EC 380260; OP Evaluation 10-002, Train 1B ESF Relay K611 Degraded, June 01, 2010 -

EC 380861; OP Evaluation 10-003, ECCS Pump Cubicle Cooler Fan Shaft Bearing Interference Fit out of Tolerance, Modified July 28, 2010 -

IR 1088474, Potential Design Vulnerability of Auxiliary Feedwater System, July 7, 2010

-

EC 381435, Operability Evaluation of Potential Design Vulnerability of Auxiliary Feedwater System - 0BOSR 8.3.2-1; Diesel Generator Oil Sample Surveillance, August 18, 2010

- BYR96-126; Design Analysis for Diesel Oil Storage Tank Level Setpoints, Rev. 2B

-

ATD-0196; Calculation for Unusable Volume in Diesel Oil Storage Tanks and Day Tanks, Rev. 4

Corrective Action Documents As a Result of NRC Inspection

- NRC Identified Discrepancy in Fire Protection Report, July 15, 2010

Section 1R18: Temporary Modifications

-

EC 380139, Install a Temporary Pump in the Unit 1 SX Room Sump, May 14, 2010 -

IR 1119037, NRC Inspector identifies WE Piping support brackets not tight, September 28, 2010

Section 1R19: Post Maintenance Testing

- Work Order

1072104-01; Replace Charger Control Card; July 26, 2010 - Work Order

1072104-02; OP PMT - Verify Proper Output Voltage and Float Current, July 27, 2010 - Work Order

1207848-01; Battery Charger 18M Surveillance, July 27, 2010 - Work Order

1351299-01; SX Makeup Pump 0B Monthly Operability Surveillance; July 29, 2010 - 2BOSR 5.2.5-1, ECCS Subsystem Automatic Valve Actuation Test, Revision 5 - 2BOSR 0.5-2.SI.2-2.1, Unit Two 2SI8802A, 2SI8806, 2SI8809A-Stroke Test and Position Verification Test, Revision 11 -

IR 1090058, Auxiliary Feedwater Valve 2AF006A leaking by and will not move, July 12, 2010 -

WO 1290990; Install Engineering Change

378101 Diesel Oil Storage Tank Level Switches, Rev. 0 -

WO 1351433; 1B Diesel Generator Operability Surveillance, June 1, 2010

-

WO 1282202; 1B Diesel Generator Operability Surveillance, July 28, 2010

- 1BOSR 8.1.2-2 Unit 1 B Monthly/Quarterly Surveillance, June 30, 2010 -

WO 1348744; Install new United Electric J120-453, EC380503, August 6, 2010 -

WO 1348746; Install new United Electric J120-453, EC380503, August 6, 2010

Attachment Corrective Action Documents As a Result of NRC Inspection

-

IR 1095767; NRC Questions Some Work Practices in RSH, July 29, 2010

-

IR 1095748; Petcock Valve Bent and Loose, July 29, 2010

Section 1R22: Surveillance Testing (Quarterly) - 1BOSR 0.5-3.SX.1-2, Unit 1 Test of the 1B Essential Service Water Miscellaneous System Valve, Revision 5 - 2BOSR 0.5-3.AF.1-1, Unit 2

ASME Surveillance Requirements for the A Train Auxiliary Feedwater SX Supply Valves, Revision 9 - 0BOSR 7.9.6-1, Essential Service Water Makeup Pump 0A Monthly Operability Surveillance, Revision 26 - 2BOSR 6.6.2-1, Unit 2 Reactor Containment Fan Cooler Monthly Surveillance, Revision 24 - 2BOSR 6.3.5-2, Unit 2 Chilled Water Containment Isolation Valve Stroke Test, Revision 4

Corrective Action Documents As a Result of NRC Inspection

-

IR 1096305; NRC Concern - Gasket Not Seated in Damper Access Door, July 30, 2010

-

IR 1096322; NRC Concern - 1DG5152B Thread Engagement, July 30, 2010 -

IR 1097538; Security Diesel Fire Dampers Need Cleaning, August 03, 2010 -

IR 1097549; NRC Identified Leaks on Discharge Boot on the 0DG01K, August 03, 2010

Section 1EP2: Alert and Notification (ANS) Evaluation - Offsite Emergency Plan Alert and Notification System Addendum for the Byron Nuclear Power Station; November 2009 -

EP-AA-1000; Exelon Nuclear Standardized Radiological Emergency Plan Section E; Revision 20 -

EP-AA-1002; Exelon Nuclear Radiological Emergency Plan Annex for Byron Station, Section 4; Revision 26 - Exelon Nuclear Siren Operations Manual; December 14, 2009 - Byron Plant Warning System Annual Maintenance & Operational Reports; June 9, 2010

- Byron Plant Warning System Annual Maintenance & Operational Reports; July 6, 2009

- Byron Siren Daily Operability Reports; January 1, 2009 - June 30, 2010

- Byron Monthly Siren Availability Reports; June 2008 - June 2010 - Exelon Semi Annual Siren Reports; June 30, 2009 and December 31, 2009 -

IR 00808612; Bryon Alert Notification System Reached an Outage of 25%; August 19, 2008

Section 1EP3: Emergency Response Organization Augmentation Testing -

EP-AA-1000; Exelon Nuclear Standardized Radiological Emergency Plan, Sections B and N; Revision 20 -

EP-AA-1002; Exelon Nuclear Radiological Emergency Plan Annex for Byron Station, Section 2; Revision 26 -

EP-AA-112; Emergency Response Organization (ERO)/Emergency Response Facility (ERF) Activation and Operation; Revision 14EP-AA-122-1001; Drill & Exercise Scheduling, Development, and Conduct; Revision 11 -

EP-AA-121; Emergency Response Facilities and Equipment Readiness; Revision 9

- 0BOSR

CQ-1; Test of the Employee Alarm System; Revision 4

-

OP-AA-102-104; On Site Warning System Compensatory Actions; June 11, 2010

-

OP-AA-115-101; List of Inaudible Public Address System Locations; June 11, 2010

Attachment -

TQ-AA-113; ERO Training and Qualification; Revision 16 - Emergency Response Organization Call-Out Roster; July 7, 2010

- Quarterly Unannounced Off-hours Call-In Augmentation Drill Reports; April 9, 2009 - May 18, 2010 - ERO Drive-In Drill Reports; December 12, 2008 and January 7, 2009

- EP Information 2010-07; Byron EP Information Newsletter; July 2010

- 2008 Drill Findings and Assembly and Accountability Report, Revision 1; July 7, 2009

- 2009 Byron Pre-Exercise with Assembly and Accountability Report; June 17, 2009

-

IR 1090669; NRC Review of Plant PA and Alarm System; July 14, 2010 -

IR 1089102; Plant Page Deficiencies Creating Unsafe Work Environments; July 9, 2010 -

IR 1070455; TSC Operations Director Did Not Respond for Call-In Drill; May 18, 2010

-

IR 1058355; NRC Concern Regarding Call-In Drills Exclusion of Personnel; April 19, 2010 -

IR 1056174; On Site Warning Systems Not Being Maintained as Required; April 13, 2010

Section 1EP5: Correction of Emergency Preparedness Weaknesses and Deficiencies -

NOSA-BYR-10-03; Emergency Preparedness (50.54(t)) Audit Report; April 21, 2010 -

NOSA-BYR-10-03; Objective Evidence Report EP Functional Area Audit, P2I-1; April 16, 2010 -

NOSA-BYR-09-04; Emergency Preparedness (50.54(t)) Audit Report; May 6, 2009

-

NOSA-BYR-09-04; Objective Evidence Report EP Functional Area Audit, P2I-1; May 1, 2009 - CIAR

1005570-02; Byron Emergency Preparedness Program Inspection Readiness Assessment; June 4, 2010 -

IR 1089102; Plant Page Deficiencies; July 9, 2010

-

IR 1083437; NOS ID Emergency Preparedness Rated Yellow; December 22, 2009

-

IR 1075788; TSC Fan Problem; June 1, 2010 -

IR 0996594; NOS ID Issues Regarding ACE Cause and Actions; November 20, 2009 -

IR 0932440; Preliminary Results for Byron's EP Pre-Exercise; June 17, 2009

Section 2RS5: Radiation Monitoring Instrumentation (71124.05) -

RP-AA-700; Controls for Radiation Protection Instrumentation; Revision 2 -

BRP 5820-14; Process Radiation Monitoring System Alert/High Alarm Setpoints; Revision 37 - Calibration of the Canberra FASTSCAN B2 WBC System at the Byron Station; June 12, 2009

- Certificate of Calibration; Certificate No.

0010575067; MGP

AMP 100; Asset No.

078646; January 15, 2010 -

BRP 5823-39; Operation of the Merlin Gerin

AMP-100; Revision 12 -

RP-AA-700-1401; Operation and Calibration of Eberline Model Pm-7 Personnel Contamination Monitor; Revision 0 -

RP-AA-700-1401; Attachment 3; Calibration Data Sheet; Portal Monitor Instrument No. 180; January 29, 2010 -

RP-BY-721; Operation and Calibration of the Canberra Argos-5AB Zeus Personnel Contamination Monitor; Revision 1 -

RP-BY-721; Attachment 1; Argos-5 Calibration Data Sheet; Monitor No. 164; April 5, 2010 - Argos and GEM Monitors Operation Manual; Canberra Industries; Revision 00

-

BRP-5822-11; Calibration of Nuclear Enterprises Small Articles Monitor (SAM); Revision 16

-

BRP-5822-11; Attachment B; SAM Calibration Data Sheet; Monitor Serial Number 427; May 20, 2010 -

RP-AA-70-1100; Operation of the Eberline

RO-2/2A/20, Bicron

RSO 50E; Revision 0 - Certificate of Calibration; Certificate No.

0010572975; Eberline

RO-20; Asset No.

078110; January 29, 2010

Attachment - Certificate of Calibration; Certificate No. 00105715555; Bicron

RSO-50E; Asset No.

077678; June 23,2010 -

BRP-5821-4; Operation of the Eberline

AMS-3 Beta Air Monitor; Revision 7 - Test Report; Beta Continuous Air Monitor; AMS3; Serial Number 1265; February 25, 2010 -

BRP 5825-3; Operation and Use of the J.L. Shepherd Model 89 Gamma Calibrator; Revision 13 -

RP-BY-700-1001; Instrument Calibration and Source Check Settings; Revision 30

- Functional Area Self-Assessment; Assignment Number

1006770-03; Radiation Instrumentation per

IP 71124.05; June 11, 2010 - Functional Area Self-Assessment; Assignment Number

AR 929091-02; Power Labs Instrument Calibration Facility Process; February 25, 2010 -

IR 999376; IPM No. 381 Tagged OOS Due to Low Flow - Mylar Tear; November 30, 2009

-

AR 1009820;

PM-7 No. 373 is Experiencing Many False Alarms; December 28, 2009

-

AR 1039346; Vendor Calibration Data Sheets Had Incorrect Data Point; March 05, 2010 -

AR 1071645; Annual Out of Tolerance Review for Portable RP Instruments; May 20, 2010 -

AR 1083633; Power Labs Cal of Ion Chamber; Not within 10 percent of Standard; June 23, 2010 -

BIP 2500-137; Calibration of Steam Jet Air Ejector (SJAE)/Gland Steam Exhaust Radiation Monitor (PR); Revision 7 - Work Order

01079638 01; STM Jet Air Ejector/Gland Steam Exhaust Rad Mon Loop 1PR-027; August 27, 2009 - BISR 11.b,5-200; Surveillance Calibration of Auxiliary Building Vent Stack Effluent (PIGG) Radiation Monitor (PR); Revision 3 - Work Order

01116156 01; Cal of Rad Monitor 1PR28J; May 06, 2009

- BISR 11.a.5-200; Surveillance Calibration of Liquid Effluent Radiation Monitor (PR); Revision 0 - Work Order

01055110 01; Perform Calibration of 0PR01J; March 04, 2009 - BISR 3.3.2-207l Surveillance Calibration of High Range Containment Radiation Monitor (AR); Revision 9 - Work Order

01165961 01; Cal of High Range Containment Radiation Monitor; March 15, 2010

-

862747; Assign 16, Evaluate Revision to EP Demonstration Criteria; March 20, 2009

Corrective Action Documents As a Result of NRC Inspection - Technical Basis for Main Steamline Area Radiation Monitor, July 16, 2010

Section 4OA1: Performance Indicator Verification -

LS-AA-2110; Monthly Data Elements for NRC ERO Drill Participation; September 2009 - March 2010 -

LS-AA-2120; Monthly Data Elements for NRC Drill/Exercise Performance; July 2009 - March 2010 -

LS-AA-2130; Monthly Data Elements for NRC Alert and Notification System Reliability; July 2009 - March 2010 - Byron Monthly Siren Availability Reports; July 2009 - March 2010 -

IR 1089356; LORT DEP Failure - EP EAL Missed; July 9, 2010

-

IR 1056216; Plant Page System Failed Partial Surveillance; April 13, 2010

-

IR 1050496; Table Top Drill EAL Call Scenario Problem; March 31, 2010 -

IR 0996470; Training-Emergency Planning DEP Failure during LORT; November 20, 2009 - Monthly Data Elements for NRC Reactor Coolant System (RCS) Leakage, July 2009 to June 2010 - Monthly Data Elements for NRC Safety System Functional Failure, April 2009 to June 2010

Attachment - Procedure 2BOSR 4.13.1-1; RCS Water Inventory Balance 72 Hour Surveillance, February 16, 2010

Section 4OA2: Problem Identification and Resolution -

IR 1092137; Aluminum Not Incorporated in Chemical Effects Calculation, July 19, 2010 -

IR 1093900; Fan Motor Bearing to Shaft Fit Out of Tolerance, July 23, 2010

-

IR 1092694; 2VA02CB-M Criteria Not Met for Outboard Shaft Measurements, July 21, 2010

-

IR 1093816; Leaking Water Into Unit 1 Penetration Area, July 23, 2010 -

IR 1093820; Leaking Water Into Unit 2 Penetration Area, July 23, 2010 -

IR 1096574; ESF Cubicle Fan Breaker Off, 2AP22E-A4, July 31, 2010

-

IR 1115732; Found Unit 2

AF 13D Piping Very Hot, September 21, 2010

-

IR 1098457, Unplanned LCOAR Entry for Unit 1 Diesel Fuel Oil Storage Tanks, August 5, 2010 - Design Analysis Number 19-T-5, Diesel Generator Loading During LOOP/LOCA - Byron Units 1 and 2, Revision 6 - Design Analysis Number DGD09301, Time Dependent Loading and Fuel Consumption for EDGs Following LOOP/LOCA, Revision 6 - Design Analysis Number DGD09301, Time Dependent Loading and Fuel Consumption for EDGs Following LOOP/LOCA, Revision 6C -

EC 381086, Evaluation to Assist in Determining Reportability of 1B EDG Diesel Oil Storage Tank (DOST) Level Indication Shift In The Non-conservative Direction (IR 1098457) - Exelon Nuclear Procurement Engineering Standard

PES-P-006, Diesel Fuel Oil, Revision 6

Corrective Action Documents As a Result of NRC Inspection -

IR 1092193; Concern with Operating VA Supply/Exhaust Fans, July 19, 2010

-

IR 1115427; MCR Door 0DSSD171 Periodically Fails to Automatically Latch, September 20, 2010

Section 4OA5: Other Activities -

NRC Form 748; National Source Tracking Transaction Report; Byron Station; 1/25/2010

ISFSI Inspection

Calculations: - 2.4.3-BYR08-027; Structural Analysis of the ISFSI Pads at Byron and Braidwood; Revision 3

- 2.4.3-BYR08-070; Dynamic Analysis of

HI-STORM /

HI-TRAC Stack Up; Revision 2

- 2.4.3-BYR10-095; Seismic Stability of

HI-STORM 100 Casks on Byron ISFSI Pad Using Classical Non-Linear Dynamics Model with Soil-Structural Interaction; Revision 1 - 36272-02; Exelon/Byron & Braidwood Hoist/Reeving Equipment Calculation; Revisions 11, 16 - 36272-12; Exelon/Byron & Braidwood Single Failure Proof Trolley Seismic Analysis;

Revisions 15, 18 - 36272-13; Exelon/Byron & Braidwood Single Failure Proof Trolley Critical Weld Calculations; Revision 13 - 36272-17; Exelon/Byron & Braidwood Single Failure Proof Trolley Misc. Items Seismic Calculations; Revisions 16, 23 - 4.1.1-BYR10-093; Synthetic Time Histories Consistent With the SSE Response Spectra for Fuel Handling Building Floor Elevation 401'-0"; Revision 0

Attachment - 4.1.4-BYR10-070; Fuel Handling building Single Failure Proof Crane - Coupled Building and Crane ANSYS analysis; Revision 0 - 8.1.20-BYR10-074; Fuel Handling building Single Failure Proof Crane - Shear Wall Analysis; Revision 0 - 8.1.2-BYR10-075; Base Mat Analysis Due to Loads From Single Failure Proof Crane;

Revision 0 - 8.1.6-BYR10-073; Fuel Handling building Single Failure Proof Crane -Roof Framing Member Analysis; Revision 0 - 8.1.8-BYR10-072; Fuel Handling building Single Failure Proof Crane - Crane column and Roof Column Analysis; Revision 0 - 8.1.8-BYR10-102; Fuel Handling building Single Failure Proof Crane - Structural Member Connection Analysis; Revision 0 - 8.1.9-BYR10-071; Fuel Handling building Single Failure Proof Crane - Crane Girder Analysis; Revision 0 - 8.1.9-BYR10-101; Fuel Handling building Single Failure Proof Crane - Crane Runway Rail clips Design; Revision 0 - BYR08-024; Dry Cask Storage Project - Fire Radiant Heat and Explosion Overpressure Analysis; Revision 0 - BYR08-025; Dry Cask Storage Project - Fire Hazards Analysis Report; Revision 0 - BYR08-126' Byron 1 Cycles 1 to 14 and Byron 2 Cycles 1 to 13 Dry Storage Fuel and component Characterization; Revision 0 - BYR08-127; Byron 1 Cycles 1 to 14 and Byron 2 Cycles 1 to 13 Cask Loader Database Population; Revision 0 - BYR09-056; Tornado Evaluation for Byron, Braidwood, and LaSalle Nuclear Generating Station Dry Cask Storage Projects, Revision 1 - BYR10-076; Structural Evaluations Associated with the Cask Stack-up Restraint System; Revision 1 -

HI-992284; Miscellaneous Thermal-Hydraulic Calculations for

HI-STAR and

HI-STORM; Revision 1 - Holtec Document

1678059; NRC Pad Concerns; August 17, 2010

Issue reports: -

IR 110370; Near Miss - Dry Cask Storage; August 11, 2010 -

IR 893490; ISFSI Spacer Dimension for Fuel with No Inserts; February 24, 2010

-

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 957014; Compliance with

NOG-1 rules for Single Failure Proof cranes; August 24, 2009

-

IR 966184; Compliance with

NOG-1 rules for Single Failure Proof cranes; September 1, 2009

-

IR 981962; FHB Crane Modification Drawing Error; October 20, 2009

-

IR 1004502; Vendor Product review Process Weaknesses; December 11, 2009 -

IR 1027260; Engineering Review for Single Failure Proof Crane; February 8, 2010 -

IR 1049402; Restraint System Needed for ISFSI Stack-up Configuration; March 29, 2010

-

IR 1095194; Question of Need for Seismic Protection on Draindown Tank; July 27, 2010

-

IR 1095578; Hoist Upper Travel Interlocks Locks Out SFPBC Hoist; July 29, 2010

-

IR 1095887; ISFSI Project May Alarm FHB Area Rad Monitors; July 28, 2010

-

IR 1098384; ISFSI Observations During DRY Run; July 30, 2010 -

IR 1100062; FHB Crane Bridge and FHB Structure Calcs Need Revision; August 10, 2010 -

IR 1105405; ISFSI Seismic Restraint Shoe Adjustment Screw Engineering; August 19, 2010

Attachment Corrective Action Documents As a Result of NRC Inspection

-

IR 1031363; NRC Questions on Byron Specific Stackup Calculation; February 16, 2010 -

IR 1031363; NRC Questions on Byron Specific Stackup Calculations; February 12, 2010 -

IR 1099897; NRC Inspectors Identified Errors in FHB Crane Design Analysis; August 10, 2010

-

IR 1102835; NRC Concerns with Byron ISFSI pad Structural Qualifications; August 18, 2010

-

IR 1106006; NRC Identified Procedure Improvement; August 24, 2010

-

IR 1098537; NRC Identified Potential Errors in FHB Crane Analysis; August 5, 2010

Drawings: - Drawing Number 5490; Dry Cask Storage Project Cask Storage Pad

CFR 72.48 Screenings / Evaluations: - Byron 72.48 Number 1; 72.212 Evaluation Report Change; Revision 0 - Holtec 72.48 Number 890;

HI-TRAC 125D Design Change; Revision 0

Procedures: -

BAP 1210-1T1; Byron Station Plant Review Report - TRM Change 09-010; June 26, 2009 - BFP

FH-35; Contingency Fuel Handling Building Crane Operations; Revision 0 - BFP

FH-64; Transporter Operations; Revision 4 - BFP

FH-65; Spent Fuel Cask Site Transportation; Revision 6 - BFP

FH-68;

HI-TRAC Preparation; Revision 2 - BFP

FH-69;

HI-TRAC Movement within the Fuel Building; Revision 4 - BFP

FH-70;

HI-TRAC Loading Operations; Revision 1 - BFP

FH-72;

HI-STORM Processing; Revision 0 - BFP

FH-74; Helium Cool down; Revision 0 - BFP

FH-76; Transporter Undocumented Visual Inspection Revision 2 - BFP

FH-78; Vacuum Drying System Operation; Revision 2 - BFP Fh-80; Haul Path and ISFSI Dry Run Operations; Revision 0 - BFP

FH-84;

HI-TRAC Operations within the Fuel Handling Building; Revision 0 -

BFP-FH-20; Operation of Fuel Handling Building Crane; Revision 24 -

BFP-FH-34; Water Transfer of the Spent Fuel, Wet Cask Pit or Transfer Canal; Revision 6 -

LS-BY-105; 72.48 Review Process for Dry Cask Storage; Revision 1 -

MMH 36272-41; Exelon Byron FHB Single Proof Trolley Site Acceptance Test Procedure; October 27, 2009 -

MMH 36727-16; Exelon Byron FHB Single Failure Proof Trolley Site Acceptance Test Procedure; March 20, 2009 -

NF-AA-309; PWR Move Sheet for Dry Cask Movement; July 22, 2010 -

NF-AP-622; Fuel Selection and Documentation for Dry Cask Storage; Revision 22 -

OU-AP-204; Fuel Movement in the Spent Fuel Pool for Byron and Braidwood; Revision 9 -

OU-AP-216; Operation of the Spent Fuel Pool Bridge Crane; Revision 2 -

OU-AP-229; Operation of the Spent Fuel Pool Sluice Gates for Byron and Braidwood;

Revision 2

Other Documents: - Byron Nuclear Power Station Unit 1 and 2 10

CFR 72.212 Evaluation Report; Revision 0 - Byron Nuclear Power Station Unit 1 and 2 10

CFR 72.212 Evaluation Report; Revision 1

Attachment - Byron Stations Quality Assurance Topical Report - Fuel Handler Qualification and Training Matrix; April 7, 2010

- MPC Leak Testing Documentation; December 17, 2009 - Spent Fuel Pool Boron Sample Results; July 27, 2010 -

WO 1166091;

HI-STORM and MPC Pre-Use Inspection; November 19, 2008

Attachment

LIST OF ACRONYMS

USED [[]]

AC Alternating Current

ADAMS Agencywide Document Access Management System

AF Auxiliary Feedwater

ALA [[]]

RA As-Low-As-Is-Reasonably-Achievable

ARM Area Radiation Monitor

AS [[]]

CE American Society of Civil Engineers

ASME American Society of Mechanical Engineers

CAM Continuous Air Monitor CAP Corrective Action Program

CE [[]]

DE Committed Effective Dose Equivalent

CFR Code of Federal Regulations

CoC Certificate of Compliance

DBD Design Basis Document

DNMS Division of Nuclear Materials Safety

DG Diesel Generator

d/p Differential Pressure

DRP Division of Reactor Projects

DRS Division of Reactor Safety

DSF [[]]

ST Division of Spent Fuel Storage and Transportation

EC [[]]

CS Emergency Core Cooling System

ED Electronic Dosimeter

FHB Fuel Handling Building

FSAR Final Safety Analysis Report

HPGE High Purity Germanium I&C Instrumentation and Controls

IE [[]]

EE Institute of Electrical & Electronic Engineers

IMC Inspection Manual Chapter

IP Inspection Procedure

IR Issue Report

ISF [[]]

SI Independent Spent Fuel Storage Installation

ISI Inservice Inspection

IV Independent Verification

LCO Limiting Condition for Operation

LER Licensee Event Report

LHRA Locked High Radiation Area LLC Limited Liability Corporation

LO [[]]

CA Loss of Coolant Accident

LO [[]]

OP Loss of Off-site Power

LPCI Low Pressure Coolant Injection

MCID Materials Control

ISFSI and Decommissioning

MPC Multi-Purpose Canister

mrem Millirem

MR [[]]

FF Maintenance Rule Functional Failure

msec Millisecond

MSIV Main Steam Isolation Valve

MSL Mean Sea Level NCV Non-Cited Violation

Attachment

NEI Nuclear Energy Institute

NFPA National Fire Protection Association

NIOSH National Institute of Safety & Health

NRC [[]]

U.S. Nuclear Regulatory Commission

PARS Publicly Available Records System

PC [[]]

IS Primary Containment Isolation System

PI Performance Indicator

PI&R Problem Identification and Resolution

PM Planned or Preventative Maintenance

PMT Post-Maintenance Testing psid Pounds Per Square Inch Differential

psig Pounds Per Square Inch Gauge

QA Quality Assurance

RCA Radiologically Controlled Area

RCIC Reactor Core Isolation Cooling RH Residual Heat Removal

RP Radiation Protection

RPS Radiation Protection Specialist

RPS Reactor Protection System

RPV Reactor Pressure Vessel RWP Radiation Work Permit

scf Standard Cubic Feet

SDP Significance Determination Process

SFP Spent Fuel Pool

SRV Safety Relief Valve

SSC Systems, Structures, and Components SSI Soil Structure Interaction

SW Service Water

TAR Technical Assistance Request

TLD Thermoluminescent Dosimeters

TS Technical Specification

UFS [[]]

AR Updated Final Safety Analysis Report

URI Unresolved Item

WBC Whole Body Count

WO Work Order

M. Pacilio -2-

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 System (

PARS ) component of

NRC 's document system (

ADAMS ).

ADAMS is accessible from the

NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Sincerely,

/RA/ Eric R. Duncan, Chief Branch 3

Division of Reactor Projects Docket Nos. 50-454; 50-455;72-068

License Nos.

NPF -37;

NPF-66

Enclosure: Inspection Report 05000454/2010004; 05000455/2010004; 07200068/2010001 w/Attachment: Supplemental Information cc w/encl: Distribution via ListServ

DOCUME [[]]

NT [[]]

NAME G:\

DRPIII \BYRO\Byron 2010 004.docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy

OFFICE [[]]

RIII [[]]

NAME [[]]

MT horpe-Kavanaugh:dtp

ED uncan

DATE 11/03/10 11/03/10

OFFICI AL

RECORD [[]]