Text

February 10, 2010

EA-06-178 Mr. Larry Meyer Site Vice-President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241

SUBJECT: POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, NRC INTEGRATED INSPECTION REPORT 05000266/2009005; 05000301/2009005 AND STATUS OF CONFIRMATORY ORDER EA-06-178

Dear Mr. Meyer:

On December 31, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed a baseline inspection at your Point Beach Nuclear Plant, Units 1 and 2. The enclosed report documents the inspection results, which were discussed on January 6, 2010, with Mr. C. Trezise and members of your staff. The report also documents the status of Confirmatory Order EA-06-178, as it relates to your Point Beach Nuclear Plant. 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 your personnel. Based on the results of this inspection, two NRC-identified and three self-revealed findings of very low safety significance were identified. Of these findings, four involved a violation 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 these issues as Non-Cited Violations (NCVs) in accordance with Section VI.A.1 of the NRC Enforcement Policy. 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 Point Beach Nuclear Plant. 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 Office at the Point Beach Nuclear Plant.

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 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/

Michael Kunowski, Chief Branch 5 Division of Reactor Projects

Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27

Enclosure:

IR 05000266/2009005; 05000301/2009005

w/Attachment:

Supplemental Information cc w/encl: Distribution via ListServe

Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos: 50-266; 50-301 License Nos: DPR-24; DPR-27 Report No: 05000266/2009005; 05000301/2009005 Licensee: NextEra Energy Point Beach, LLC Facility: Point Beach Nuclear Plant, Units 1 and 2 Location: Two Rivers, WI Dates: October 1, 2009, through December 31, 2009 Inspectors: S. Burton, Senior Resident Inspector R. Ruiz, Senior Resident Inspector (Acting)

M. Thorpe-Kavanaugh, Resident Inspector (Acting)

J. Jandovitz, Project Engineer J. Cassidy, Senior Health Physicist ` R. Jickling, Senior Emergency Preparedness Inspector D. Jones, Reactor Inspector D. McNeil, Senior Operations Engineer R. Edwards, Reactor Engineer J. Gilliam, Reactor Engineer E. Sanchez-Santiago, Reactor Engineer N. Feliz Adorno, Reactor Engineer

Approved by: M. Kunowski, Chief Branch 5 Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS

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

REPORT DETAILS

.......................................................................................................................5 Summary of Plant Status...........................................................................................................5

REACTOR SAFETY

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

1R01 Adverse Weather Protection

Main article: IP 71111.01

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

1R04 Equipment Alignment

Main article: IP 71111.04

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

1R05 Fire Protection

Main article: IP 71111.05

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

1R06 Flooding

Main article: IP 71111.06

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

1R08 Inservice Inspection (ISI) Activities

Main article: IP 71111.08P

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

1R11 Licensed Operator Requalification Program

Main article: IP 71111.11

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

1R12 Maintenance Effectiveness

Main article: IP 71111.12

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

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

........16

1R15 Operability Evaluations

Main article: IP 71111.15

....................................................................16

1R18 Plant Modifications

Main article: IP 71111.18

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

1R19 Post-Maintenance Testing

Main article: IP 71111.19

...............................................................25

1R20 Outage Activities

Main article: IP 71111.20

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

1R22 Surveillance Testing

Main article: IP 71111.22

........................................................................29

1EP2 Alert and Notification System (ANS) Evaluation

Main article: IP 71114.02

..............................30

1EP3 Emergency Response Organization Augmentation Testing

Main article: IP 71114.03

............30

1EP4 Emergency Action Level and Emergency Plan Changes

Main article: IP 71114.04

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

1EP5 Correction of EP Weaknesses and Deficiencies

Main article: IP 71114.05

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

RADIATION SAFETY

...................................................................................................32 2OS1 Access Control to Radiologically Significant Areas (71121.01).........................32 2OS2 ALARA Planning and Controls (71121.02)........................................................37

OTHER ACTIVITIES

....................................................................................................38

4OA1 PI Verification

Main article: IP 71151

.......................................................................................38

4OA2 Identification and Resolution of Problems

Main article: IP 71152

............................................41

4OA5 Other Activities...................................................................................................43 4OA6

Management Meetings......................................................................................53

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

S. Aerts, Accounting Manager (NSCIT Leader)

B. Castiglia, Performance Improvement Manager

J. Costedio, Nuclear Licensing Manager/Regulatory Affairs Manager

R. Farrell, Radiation Protection Manager

R. Freeman, Emergency Preparedness Manager

R. Harrsch, Operations Site Director

L. Hawkeye, Engineering PI Manager

C. Hill, Work Control Center Manager

P. Holzman, GL 89-13 Program Engineer

L. Meyer, Site Vice-President

J. Schroeder, SW System Engineer

C. Trezise, Engineering Director/Acting Site Vice-President

T. Vehec, Plant Manager

G. Vickery, Work Management Manager Nuclear Regulatory Commission

M. Kunowski, Chief, Division of Reactor Projects, Branch 5

J. Poole, Point Beach Project Manager, Office of Nuclear Reactor Regulations

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened

05000266/2009005-01;

05000301/2009005-01 FIN Failure to Meet GL 89-13 Program for Mussel Control (Section 1R12.1)

05000301/2009005-02 NCV Failure to Ensure Adequate Control of Foreign Material in Safety-Related Systems (Section 1R15.1)

05000301/2009005-03 NCV Failure to Update Safe Load Path Manual to Include Safety-Related Cable Locations (Section 1R18.1)

05000266/2009005-04;

05000301/2009005-04 URI Potential Failure to Adequately Evaluate Seismic II/I Concerns for Units 1 and 2 'B' Containment Sump Strainers (Section 1R18.2)

05000301/2009005-05 NCV Momentary Loss of Unit 2 Reactor Vessel Level Indication in the Control Room (Section 1R20.1)

05000266/2009005-06;

05000301/2009005-06 NCV Failure to Maintain Proper Control of Radioactive Material Within the Radiologically Controlled Area (Section 4OA5.1)

Attachment

Closed

05000266/2009005-01;

05000301/FIN-2009005-01 FIN Failure to Meet GL 89-13 Program Requirement for Mussel Control (Section 1R12.1)

05000301/FIN-2009005-02 NCV Failure to Ensure Adequate Control of Foreign Material in Safety-Related Systems (Section 1R15.1)

05000301/FIN-2009005-03 NCV Failure to Update Safe Load Path Manual to Include Safety-Related Cable Locations (Section 1R18.1)

05000301/FIN-2009005-05 NCV Momentary Loss of Unit 2 Reactor Vessel Level Indication in the Control Room (Section 1R20.1)

05000266/2009004-01;

05000301/FIN-2009004-01 URI Failure to Control Radioactive Material Within the Radiologically Controlled Area Resulting in Unnecessary

Dose to Worker (Section 4OA5.1)

05000266/2009005-06;

05000301/FIN-2009005-06 NCV Failure to Maintain Proper Control of Radioactive Material Within the Radiologically Controlled Area (Section 4OA5.1)

05000266/2006013-05;

05000301/2006013-05 AV Confirmatory Order EA-06-178 (Section 4OA5.4)

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 IR. 1R01 Adverse Weather Protection -

AR 00509533; O&MR 379; Revision 1 Freezing Of Instrumentation Piping -

AR 00509586; Reduced Pump Seal Life Because Of Improper Venting -

AR 01075828; PAB HV Steam Exhaust Stack Drain Line Is Frozen -

AR 01140416; Ice In Sealtite For Many Security Components

-

AR 01140633; Beach Drains Frozen

-

AR 01141214; Ice On Floor In Unit 1 Facade

-

AR 01141395;

EC 12789 Facade Freeze Upgrade DRB Action items -

AR 01141687; Verify Cold Weather Preps Remains In A Working Stat -

AR 01142302; U2 Facade Sump Piping Heat Trace Alarms

-

AR 01142711; Inadequate 2X04 Cable Drip Tray Causes Ice Buildup In Facade

-

AR 01142806; Changes To

OI 106 To Incorporate

EC 12789 Facade Freeze Mod

-

AR 01143674; Faulted MUX Causing MET Tower Data To Be Frozen -

AR 01143775; Frozen Drain Line In Unit 2 Facade -

AR 01146740; Cold Weather Checks UNSAT - Heat Lamp GFI Tripped

-

AR 01148041; Heat Trace Drawing Needs Updating

-

AR 01148221; Facade Heat Trace Panel reliability Unsatisfactory

-

AR 01148314; Heat Trace Drawing Needs Updating/More Information

-

AR 00149677; Massive Formation Of Ice Has Collected On Cable Tray In Southwest Corner Of Unit -

AR 01154068; Heat Trace For

RS-SA-003 Installed Incorrectly

-

AR 01155627;

PC 49.5 Cold Weather Checklist, WH4 Heaters Broke

-

AR 01155718; Heat Trace Not Installed Per Manufacturer Recommendations

-

AR 01155829; Cold Weather Preps -

AR 01156747; Cold Weather Preps May Not Get Completed As Scheduled -

AR 01156940; Facade Freeze Tent

-

AR 01156958; HV Piping Leak Downstream Of

HV-990

-

AR 01157478; CWPH MOD

EC 11174 Requires Cold Weather Procedure Update

-

AR 01158201; Cold Weather Issue - Primary And Backup Circuit In Alarm

-

AR 01158202; Cold Weather Issue - Primary And Backup Circuit In Alarm -

AR 01158203; Cold Weather Issue - Vent To Atmosphere For RWST -

AR 01158938; Cold Weather Readiness System Engineering Reviews

-

AR 01159535; BDE May Need Cold Weather Shutdown

-

AR 01154813; Facade Freeze Protection Work Not Ready

-

AR 01154683; Section Of Facade Heat Tracing Is Missing -

AR 01155829; Cold Weather Preps -

ICI 32; Facade Freeze Control Panel Settings; Revision 1

- IE Bulletin 79-24; Frozen Lines; September 27, 1979

-

ISA-S67.02; Nuclear Safety-Related Instrument Sensing Line Piping And Tubing Standards For Use In Nuclear Power Plants -

OP-AA-102-1002; Seasonal Readiness; Revision 0 - OM 3.39; Degraded Equipment / Adverse Condition Monitoring Procedure; Revision 2

Attachment - 0-SOP

HT-1B01; Unit 1 Non-Vital Train A Heat Trace Panels; Revision 0 - OM 3.9; Watchstation Status Checks And Watchstander Turnover Guides; Revision 15

-

OI 106; Facade Freeze Protection; Revision 26 -

OP-AA-102-1002; Seasonal Readiness; Revision 0 -

PC 49; Cold Weather Preparations; Revision 7

-

PC 49 Part 5; Cold Weather Checklist:

Outside Areas And Miscellaneous; Revision 25

- WO #353856-07; Install 2FF-07-02C Heat Trace Cable On

RS-SA-003 And Test

- WO #366472; 2VNTB-04802A Damper Not Fully Closing

- Drawing

019193; Electrical Layout Facade Area E-142; Unit 1 - Drawing 55805; Wiring Diagram Heat Tracing Panel "AH"; Auxiliary Building; Units 1 And 2 - Drawing

325073; Facade Freeze Protection Control Panel 1FFCP-02B; Secondary Distribution Breaker Panelboard 1FFDP-02-5; Unit 1 - Generic Letter 88-20; Supplement 5; Individual Plant Examination Of External Events For Severe Accident Vulnerabilities 1R04 Equipment Alignment - 2-SOP-RH-002; Residual Heat Removal System Operation; Revision 3 - CL 7A; Safety Injection System Checklist Unit 2; Revision 30

- CL 7B; Safety Injection System Checklist Unit 2; Revision 27

-

IT 04F; 2P-10A LHSI Pump Profile Test Mode 6 High Cavity Water Level Unit 2; Revision 4 - O-TS-EP-001; Weekly Power Availability Verification; Revision 11 - OP 7A; Placing Residual Heat Removal System In Operation; Revision 45

- Drawing

ISI-2122; Residual Heat Removal Suction From Loop "A"; Unit 2

- Drawing

ISI-2123; Residual Heat Removal Suction Header; Unit 2

- Drawing

ISI-2125; Residual Heat Removal To Loop "B"; Unit 2

- Drawing

ISI-2204; Residual Heat Removal Heat Exchangers

HX-11A And

HX-11B; Unit 2 - Drawing

ISI-2228; Residual Heat Removal Pump Discharge; Unit 2 - Drawing

ISI-2231; Residual Heat Removal Heat Exchanger Bypass; Unit 2

- Drawing

ISI-PRI-2131; Residual Heat Removal To RPV; Unit 2

- Valve And Component Map; Pipeway 3; EL 8" PAB; Revision 0

- Valve And Component Map; Unit 2 RHR Heat Exchanger Cubicle; EL 5' PAB; Revision 4 - Valve And Component Map; Pipeway 3; Hallway Outside; EL 8' PAB; Revision 2 - Valve And Component Map; U2C - 46'; Revision 2

- Valve And Component Map; Unit 2 Containment; 10' And 21' Elevation; Revision 2 - Valve And Component Map; U2 A S/G Handhole Level; Area 2C-8; Revision 2

- Valve And Component Map; Unit 2 Containment "A" 10' Platform; Revision 3 1R05 Fire Protection - FEP 4.0; Fire Emergency Plan; Revision 5 - FEP 4.20; Site; Revision 7

- FEP 4.26; North Service Building; Revision 3

- FHAR FZ245; Fire Area A01-E; Electrical Equipment Room - Unit 1; Fire Zone Data

- FHAR FZ775; Fire Area A71; G-04 Diesel Room; Fire Zone Data - FOP 1.1; Brigade Training; Revision 9 - NP 1.9.14; Fire Protection Organization; Revision 10

-

PC 74; Conducting And Evaluating Fire Drills; Revision 10

- Drawing

290590; Fire Protection For Turbine Building, Auxiliary Building And Containment; Elevation 44' - 0" - Shift Staffing Report; Station Log; Mid-Shift; December 10, 2009

Attachment 1R06 Flood Protection Measures -

AOP-9A; Service Water System Malfunction; Revision 24 - FSAR Appendix A.7; Plant Internal Flooding - NP 8.4.17; PBNP Flooding Barrier Control; Revision 10 1R08 Inservice Inspection Activities -

AR 01142750; U2R30 Inservice Inspection -

AR 01160164; Delays In RPV Examinations

-

AR 01153595; EPRI Issued Document For Dissimilar Metal Weld UT Exams

-

AR 01144460;

WCAP-15666-A (Reactor Coolant Pump Flywheel Examinations) -

AR 01125657; OE26445 - Nondestructive Examination Results Affect Core -

NDE-163; Manual Ultrasonic Examination Of Ferritic Pressure Vessel Welds Greater Than 2 Inches In Thickness; Revision 14 -

NDE-109; Manual Ultrasonic Examination Using Longitudinal-Wave Straight-Beam Techniques; Revision 8 -

NDE-171; Manual Ultrasonic Examination Of Nozzle Inside Radius Sections; Revision 13 -

NDE-451; Visible Dye Penetrant Examination Temperature Applications 45°F

TO 125°F; Revision 25 -

NDE-753; Visual Examination (VT-2) Leakage Detection Of Nuclear Power Plant Components; Revision 15 -

NDE-757; Visual Examination For Leakage Of Pressure Vessel Penetrations; Revision 7 - AM 3-31; Alloy 600 Management Program; Revision 4

- Work Order Package

00352519; Replacement Of An ASME Section III, Class 1, RCS

To P-10A/B Residual Heat Removal Pump Suction Header Drain Valve 2RH-D-9

- Work Order Package

00352831; Replacement Of An ASME Section III, Class 1, Excess Letdown Heat Exchanger 2HX-4 Outlet Drain Valve 2CV-D-11

1R11 Licensed Operator Requalification Program - OP 1B; Reactor Startup; Revision 60 - OP 1C; Startup To Power Operation Unit 2; Revision 15

- Results Of Licensed Operator Annual Operating Tests; 2009 1R12 Maintenance Rule Implementation - AM 3-4; Implementation Of The Maintenance Rule At PBNP; Revision 7 -

AR 01157305; Delayed Inspection Raises

GL 89-13 Program And CCW Questions

-

AR 01159196; 2HX-015D Containment Fan Coolers Blocked With Mussels

-

NAP-407; Equipment Reliability; Revision 5

- NP 7.7.4; Scope And Risk Significant Determination For The Maintenance Rule; Revision 17

- NP 7.7.5; Maintenance Rule Monitoring; Revision 21 - NP 7.7.7; Maintenance Rule Periodic Evaluation; Revision 4 - SEM 4.2; Component Maintenance Program Guideline; Revision 4

- Evaluation Of Exceeding The Assumed Value For Partially Blocked Flowpaths For The Inspection Of Containment Fan Cooler 2HX-015A (EC14792)

- Evaluation Of Exceeding The Assumed Value For Partially Blocked Flowpaths For The

Inspection Of Containment Fan Cooler 2HX-015C And 2HX-015D (EC14793) - Point Beach GT System Corrective Action Plan; Revision 0 and 1

- Point Beach

SE-0401 Action Tracking Data; Gas Turbine AR/CAPs Attachment - Point Beach Gas Turbine System Health Report - Third Quarter 2009 - Point Beach Third Quarter System Matrix; July 1 - September 30, 2009 - Point Beach Fourth Quarter System Matrix; October 1 - December 31, 2009 - Point Beach Smart System Status Report; Gas Turbine System; December 15, 2007 - Point Beach Smart System Status Report; Gas Turbine System; January 17, 2008 - Point Beach Smart System Status Report; Gas Turbine System; February 28, 2008 - Point Beach Smart System Status Report; Gas Turbine System; May 2, 2008

- Point Beach Smart System Status Report; Gas Turbine System; August 1, 2008 - Point Beach Smart System Status Report; Gas Turbine System; January 1, 2009 - Point Beach Smart System Status Report; Gas Turbine System; February 23, 2009 - Point Beach Nuclear Plant Maintenance Rule (a)(1) Action Plan Timeline Data

- Point Beach Nuclear Plant Maintenance Rule Unavailability Data Sheet;

June 1, 2009 - November 1, 2009

-

GL 89-13 Program Document; Revision 8 - Procedure AM 3-19; Biofouling Control Program; Revision 4 - Procedure

OI 155; Chemical Treatment of Service Water for Mussels; Revision 27

- Calculation 2002-0008; CCW HX Plugging Limit; Revision 3

-

AR 01158115; Unexpected TSAC Entry due to low accident cooler SW flow

-

AR 01158344; 2HX-12D CC HX Found to be Approximately 66% blocked -

AR 01159196; 2HS-1015D Containment Fan Cooler Blocked with Mussels -

AR 01159293; Significant Number of Blocked Tubes on 2HX-15C CFC

-

AR 01159787;

HX-12C CCW HX Exceeds Allowed Blocked Tubes

-

AR 01159890; Tubes Blocked in 2HX-12D

-

AR 01160350; U2 "A" CFC Exceeded Plugging Limits per Calculation 2002-0003

- EC14794; Evaluation of the Effect of the Blocked Flowpaths Found during the Inspection of

HX-12C and 2HX-12D; December 10, 2009 -

HX-12C BIO/SILT Fouling Inspection Program Form, Inspection dated October 27, 2009

-

HX-12D BIO/SILT Fouling Inspection Program Form, Inspection dated October 28, 2009

-

HX-15C-6 BIO/SILT Fouling Inspection Program Form, Inspection dated October 22, 2009 1R13 Maintenance Risk Assessments and Emergent Work Control -

AR 01161450; Availability Of AFW Piping For Mode 5 Steam Generator Availability -

AR 01161450; Availability Of AFW Piping For Mode 5 Steam Generator Availability

-

IN 95-35; Degraded Ability Of Steam Generators To Remove Decay Heat By Natural Circulation

-

NP 10.3.6; Shutdown Safety Review And Safety Assessment; Revision 30

- Control Room Log Entries Report; November 15 - 17, 2009 - Drawing 25494-200-M0K-0000-06061; Weld Map For

FE-4036 Assembly - Drawing

342215; ISI Isometric Auxiliary Feedwater To Steam Generator "B" - Drawing

342217; ISI Isometric Auxiliary Feedwater To Steam Generator "A" 1R15 Operability Evaluations -

AR 01147224; Spent Fuel Pool Cooling Pump Was Rendered Non-Functional -

AR 01148036; P-12B Spent Fuel Pool Pump's RV Not Indicative Of True Performance -

AR 01156117; EPU Spent Fuel Pool Cooling Calculation Issues

-

AR 01159196; 2HX-015D Containment Fan Coolers Blocked With Mussels

-

AR 01160033; Apparent SW Leak; Unit 2 CFC

HX-015A1-A4 Coils

-

AR 01161636; New AFW Line In Contact With SW Pipe

-

AR 01160007; Evidence Of Leakage From HX15A1-4

Attachment -

AR 01160262; 1HX-15C CFC Flow Out Of Limit Low Per

TS-33 -

AR 01160350; U2 "A" CFC Exceeded Plugging Limits Per Calculation 2002-0003

-

AR 01160443; Found Washer Between Gasket And Flange Face On 2HX-15A3 -

AR 01162022; Spent Fuel Pool Cooling System Incorrectly Classified -

AR 1159784; Spent Fuel Pool Pump Suction Isolation Valve Stem Contacting Adjacent Pipe Insulation

-

AR 1160262; 1HX-15C CFC Flow Out Of Limit Low Per

TS-33

- CL 5C; Spent Fuel Pool Cooling And Refueling Water Circulating Pump Normal Operation Valve Lineup -

DG-M09; Design Requirements For Piping Stress Analysis; Revision 2 -

EN-AA-203-1001; Operability Determinations/Functionality Assessments; Revision 1

- NP 8.4.10; Exclusion Of Foreign Material From Plant Components And Systems;

Revisions 7 and 24

-

TS 33; Containment Accident Recirculation Fan-Cooler Units (Monthly); Unit 1; Revision 31 - Causal Evaluation; 2SI-897B Failed To Operate (AR

1158812, AR1158797/WO 379810);

October 22, 2009

- Drawing

018993; Auxiliary Cooling System; Unit 1; Revision 44

- Drawing

018995; P&ID Service Water; Unit 1

- Point Beach Nuclear Plant A-46 Final Report; Introduction And Seismic Verification

Methodology; Revision 1 - Point Beach Nuclear Plant A-46 Final Report; Appendix A; Seismic Design For Structures and Equipment 1R18 Plant Modifications - 07 Calculation 2009-0022; Air Entrainment for Containment Sump Screens; 2009 -

AR 01122278; Safe Load Paths For Turbine Building Crane -

AR 01145715; SLP 3 Revision 11 For Precautions Needed Over U2 Truck Bay -

CA 0112278; Safe Load Paths For Turbine Building Crane

- 10

CFR 50.59/72.48 Screening For

CA 0112278; Safe Load Paths For Turbine Building Crane

-

AR 01159514; 5B FWTR Heater Contacted And Damaged Component

-

AR 01162492;

ACE 01157505 Failed To Meet Minimum Requirements -

EC 11542; Unit 2 Main Generator Circuit Breaker Addition - 10

CFR 50.59 Evaluation of

EC 11542; Unit 2 Main generator Circuit Breaker Addition

-

EC 12601; Additional Sump Strainer Modules - Unit 2; October 1, 2009

-

EC 13601;

GSI-191 RCP, S/G, and RCS Loops Piping Insulation Replacement - Unit 2; February 11, 2008 -

EC 14790; Validation of SSCs above the Unit 1 Sump B Suction Strainers; November 15, 2009 -

EN-AA-203-1001; Operability Determinations/Functionality Assessments; October 8, 2009

- FSAR Appendix A.3; Control Of Heavy Loads

- MDB 3.2.5 1B30; 480 V AC Motor Control Centers; Unit 1; Revision 2

- MDB 3.2.6 2B30; 480 V AC Motor Control Centers; Unit 2; Revision 1 -

OI 35B; Electrical Equipment General Information; Revision 14 - PASS

002452; Electrical Raceways - Unit 2 Containment 8ft; November 4, 2009

- PBNP Engineering Planning And Management Cable Schedule Data; Train "A" Cables

- PBNP U2R30 Draft Schedule (Fall 2009); September 2, 2009

- PBNP U2R30 Production Schedule; 72-Hour Look Ahead; October 18, 2009

-

SCR 2009-0127-01;

GSI-191 RCP, S/G, and RCS Loops Piping Insulation Replacement -

Unit 2; September 8, 2009 -

SFS-PB2-GA-00; Sure-Flow Strainer Recirc Sump System Layout; February 18, 2009

Attachment -

SFS-PB2-GA-01; Sure-Flow Strainer General Notes; March 3, 2009 - SLP 3; Turbine Building Main Crane; Revisions 11 And 12-Draft A

- Bechtel Power Corporation Correspondence; Interim Load Paths For Safety-Related Handling

Devices; October 8, 1981 - Drawing 19739; Lighting Schedule Panel 7L; Revision 22

- Drawing

080034; P&ID Service Water; Unit 1; Revision 65

- Drawing 6704-E-151001; Diesel Generator Building Yard Area Grading Plan; Revision 4

- Drawing 6704-E-353403; Yard Area Diesel Generator Duct Bank Plan; Revision 5

- Drawing 82607-G1.0; Old FWH 5A And 5B Removal; Revision 1 - Drawing M-2007; Equipment Location - Plan; Ground Floor North; Revision 19 - Hatch Area Study Design; Truck Bay, Gantry Track, Door Position And Opening, A/B Train Duct Banks

- Hatch Area Study With FWHTR Design; Truck Bay, Gantry Track, Door Position And Opening,

A/B Train Duct Banks Feedwater Heater With Plates - Hatch Area Study With Plates Design; Truck Bay, Gantry Track, Door Position And Opening,

A/B Train Duct Banks With Plates 1R19 Post-Maintenance Testing -

AR 01159648; 2P-010B, Residual Heat Removal Pump Oiler Level Consumption -

AR 01160385; Bechtel Identification Of Precursors To EPC Contract -

AR 01160661; Failed Radiographs On Welds For EC11683 -

AR 01161009; Failure Investigation Process Established Due To Repetitive Failure During Radiographic Testing Of AFW Welds Associated With

EC 133400

-

AR 01161191; Bechtel Corrective Action Report Not Written As Required

-

AR 01159839; Some Vent Valves Not Identified On Isometric Drawings (NRC-Identified)

-

AR 01159862; Acceptance Criteria For Gas Voids May Be Incomplete (NRC-Identified) -

AR 01159937; Sump Strainer Ii/I Seismic Documentation Incomplete (NRC-Identified) -

AR 01163219; Lack Of Documentation To Support A Decision Of 2/1 Acceptability (NRC-Identified) -

AR 01160941; No Requirement To Document Seismic II/I Evaluations; (NRC-Identified)

-

AR 01158870; Found Badly Burned Contacts On 2B52-429K For Compressor K-4B -

AR 01159029; G-02 Foreign Material -

AR 01159056; Found G-02 Emergency Diesel Generator Start Lockout Relay 2 Out Of Specification

-

AR 01159161; 40 T Relay In G-02 Found Out Of Specification

-

AR 01159187; Mis-Communication During Work Activity

-

AR 01159410; Z-013 Main Hoist Has A Pinched Cable -

AR 01159721; Oil Addition To 2P-10B RHR Pump -

AR 01159843; Thermal Overloads Found Tripped On 2B52-329K

-

AR 01159845; Minor Procedural Issues Encountered During G-02 PMT

-

AR 01159960; 2P-010B Oiler Adjustment Mechanism Setup Improperly

-

AR 01160179; 2P-10A RHR Pump Oiler May Be Incorrectly Installed -

AR 01160366; Low Flow Indication In

OI 136A RHR "A" Train F & V -

AR 01160551; Inconsistent RHR Flow Limitations In Various Procedures

-

AR 01160557; Discrepancies Found During NRC Observed

IT-04A RHR Test

-

AR 01160749;

SLP-1 And -2 Conflict With OSHA Required Crane Checks

-

AR 01161191; No Corrective Action Report Has Been Written To Document Trend Of Failed Welds -

AR 01161192; Contrary to Requirement A 3-Inch Elbow Between Welds 44Q And 44M On

The Auxiliary Feed Water Project Was Cut Out Due To Being Deficient Attachment -

AR 01161222; Site Evaluation Of NRC Information Notice 2009-20 -

AR 01161691; Main generator Rotor(s) Weight Exceeds TB Crane (Z-14) Capacity

-

AR 01161694; New Generator Rotor Weight Exceeds TB Crane (Z-14) Capacity -

AR 01161706; ASME B30.2 Code Year For Wire Rope Inspections -

AR 01161946;

ACE 1160527 Not Accepted In A timely Manner

-

AR 01162048; Load Block Leveler And White Substance On Wire Rope On Z-015

-

AR 01162940; Work Orders Not Yet Completed From RCE

-

IT 04A; RHR Pump And Valve Tests In DHR Mode (Cold Shutdown); Unit 2; Revision 26

-

PI-AA-100-1002; Guideline For Failure Investigation Process; Revision 0 - 2-SOP-RH-002; Residual Heat Removal System Operation; Revision 3 - TS 3.7.5; Auxiliary Feedwater

-

TS 82; Emergency Diesel Generator G-02 Monthly; Revision 77

-

WO 376979; Replace Wire Rope On the Polar Crane; Unit 2

- Drawing 25494-200-M0K-0000-06061; Weld Map For

FE-4036 Assembly; Revision 4 - Drawing 25494-200-M0K-0000-06062; Weld Map For 2FE-04036 Spool; Revision 1 - Drawing 25494-200-M0K-0000-06063; Weld Map For 2FE-4037 Assembly; Revision 6

- Drawing 25494-200-M0K-0000-06064; Weld Map For 2FE-4037 Spool; Revision 1

- Master Weld Log - Job No. 25494; Weld Map For 2FE-4037 Spool

- Point Beach Daily Quality Summary; November 12, 2009 - Point Beach U2R30 Outage Schedule; Polar Crane Cable Repair Data; October 25-26, 2009 - Polar Crane 2Z-013 Estimated Wire Rope Stretch Data

- Trico Manufacturing Corp; Technical Information Sheet; Effects Of Aeration On Constant Level Oilers

- Trico Manufacturing Corp; Technical Information Sheet; Affects Of Air Movement On Opto-Matic Oilers - Trico Manufacturing Corp; Technical Information Sheet; Glass, LS, Or SS Opto-Matic Oilers

Instructions Before Installing

- Trico Manufacturing Corp; Technical Information Sheet; Opto-Matic Installation

- Trico Manufacturing Corp; Technical Information Sheet; Preventing Excessive Lubrication In Oil Sump Applications - Weld Failure Casual Evaluation; Aux Feed/Containment Spray Weld Failures;

November 14, 2009 1R20 Refueling And Other Outage Activities -

AOP-2B; Unit 2; Feedwater System Malfunction; Revision 15 -

AR 01158914; Reactor Vessel Level Indication Wide Range Calculations On Hold

-

AR 01160451; Add Transmitter Valving To I&C Pre-Outage Training -

AR 01161576; Unit 2 Reactor Heat Removal Components Will Exceed 125 Percent -

AR 01161998; Revise 535A To Better Document Full Stroke Manual Exercise Of 2RH-715C

-

AR 01162196; Inservice

Testing Program Acceptance Criteria

-

AR 01162379; Unit 2, 2CC-738A Valve Did Not Go Full Shut

- ASTM Designation; A 193/A 193M-93a; Standard Specification For Alloy-Steel And Stainless

Steel Bolting Materials For High-Temperature Service - ASTM Designation; B 16/B 16M-00; Standard Specification For Free-Cutting Brass Rod, Bar And Shapes For Use In Screw Machines-EC 14895; 2RH-716A - Yoke Bushing Nut Bolt Installation

-

AR 01159071; Unable To Complete 21CP 04.024 Due To Mode Change

-

AR 01159076; Unexpected Unit 2 Reactor Vessel High Alarm -

AR 01161058; PMT for

RC-537 Not Performed According To Work Order Task -

AR 01161630; Cut Reinforcing Bar In AFW Pump Room Wall Attachment -

AR 01161966; P-31B Discharge Elbow Support Degraded -

AR 01161994; Testing Of SG Atmospherics Prior To Mode 4

-

AR 01162014; Issue With SG Atmospheric Testing In

OP-1A -

AR 01162073; Duct Tape On 2MS-02020 Yoke And Gland Follower -

AR 01162088; 2MS-2015 Atmospheric Dump Stroke Time Exceeded IST Limit

-

AR 91162106; 2FD-2608

HX-22B MSR BTV Stuck In Mid Position

-

AR 01162110; 2AF-4006 Closed Light Continuity Not As Required

-

AR 01162119; Lone Wire Laying On Floor Below Apron Section of 2C03

-

AR 01162139;

MOB-276 Tripping -

AR 01162146; Valve Contractor Missing Step Sign Offs -

AR 01162166; 2C-03 Control Board Indication Deficiencies

-

AR 01162202; Mode Change Hold Process Improvement Suggestions

-

AR 01162223; U2 Purge Spool Pieces Restrict Access To Valves

-

AR 01162253; BALCM - Dried Boric Acid Found On Packing Gland - 2SI-V-09 -

AR 01162316; Additive Valve Position Out-Of-Tolerance For GV 4 -

AR 01162353; Feed Pump Seal Inlet Valve Frozen/Doesn't Move

-

AR 01162379; Unit 2 2CC-738A Valve Did Not Go Full Shut

-

AR 01163155; Ground Water Drain Line Dripping On U1F 6.5" Floor

-

AR 01163605; Wrong Valves For Tubing And Valve Replacement For K-2b -

AR 01153633; 2Z-104B Needs Replacement - CL 1B; Containment Barrier Checklist; Unit 2; Revision 58

- CL 2B; Mode 6 To Mode 5 Checklist; Revision 11

- CL 2C; Mode 5 to Mode 4 Checklist; Revision 15

- CL 2E; Mode 3 To Mode 2 Checklist; Revision 16

-

CL 20; Post Outage Containment Closeout Inspection; Revision 19 -

CR 99-2241; Need To Evaluate Implementation Of The Service Water Model To Ensure

Assumptions Are Valid

-

EC 0014645; D-08 Battery Charger Temp Power From Alternate Source

-

FP-E-MOD-02; Engineering Change Control; Revision 6

-

FP-E-RTC-02; Equipment Classification - Q List; Revision 4 -

IT 06; Containment Spray Pumps And Valves (Quarterly) Unit 2; Revision 61 -

IT 45; Safety Injection Valves (Quarterly) Unit 2; Revision 51

-

IT 45B; SI Valves (Shutdown) Unit 2; Revision 4

-

IT 395; Safety Injection Valves (Annual) Unit 2; Revision 12

- NP 4.2.19; Entry requirements Into Various Radiologically Controlled Areas; Revision 16

-

IWA-4000; Repair/Replacement Activities -

IWA-5000; System Pressure Tests -

IWB-5000; System Pressure Tests

-

MR 97-102; RC Piping Overpressurization Relief - Unit 1; Final Design Description;

October 22, 1997

-

OI 53; Positioning Of The Fuel Transfer Cart; Revision 12 - OP 1A; Cold Shutdown To Hot Standby; Revision 99 - OP 1B; Reactor Startup; Revision 61

- OP 1C; Startup To Power Operation; Unit 2; Revision 16

- OP5A; Reactor Coolant Volume Control; Revision 42

- 10

CFR 50.99/72.48 Screening For

MR 97-102; RC Piping Overpressurization Relief - Unit 1

- RESP 4.1; BOL Physics Tests; Revision 24 - TRHB 10.2; Primary Systems Descriptions:

Reactor Coolant System; Revision 9 -

WO 00378956; 2RH-716A Yoke Bushing Nut Bolt Installation

- 10

CFR 50.59/72.48 Screening of

WO 00378956; 2RH-716A Yoke Bushing Nut Bolt Installation Attachment - 2-PT-RCS-1; Reactor Coolant System Pressure Test - Inside/Outside Containment; Unit 2;

Revision 3

- 21CP 04.023-1; Reactor Vessel Level Outage Calibration; Revision 7 - Calculation 2003-0057; Evaluation Of Service Water System Debris Transport To Auxiliary

Feedwater

- Control Room Log Entries Data; October 19-20, 2009

- Drawing

018941; Fuel Transfer Arrangement System 2224; Revision 6

- Drawing

018977; Auxiliary Coolant System; Unit 2

- Drawing

152353; Auxiliary Cooling System; Residual Heat Exchanger; Discharge To

Valve 720 To Loop B To Valve 742 To

MOV 871

AC 601R-G; Unit 2 - Equipment Specification

677020; Fuel Transfer System; Revision 0

- NRC Generic Letter 88-17; Loss Of Decay Heat Removal 10

CFR 50.54(f); October 17, 1988

- Operations PCRA Backlog Scrub Data; December 23, 2009

- Point Beach

AT-0246 Outage Action Request Mode Change Restraints Data;

December 3, 2009 - Pro-Line Water Screen Services, Inc.; Installation Of Lower Boot Flapper Seal And Main

Frame To Non-Metallic Basket Seals; September 12, 2001

- Rex Chainbelt Inc.; Conveyor And Process Equipment Division Service Manual; June 1965

- Unified Screw Threads Data; Table 3a - Coarse-Thread Series, UNC And UNRC - Basic

Dimensions; Table 3b - Fine-Thread Series, UNF And UNRF - Basic Dimensions

1R22 Surveillance Testing -

AR 00151138; OSHA Required Crane Inspection Not Performed -

AR 01158712; Possible Discrepancies Noted During 2Z-13 Visual Inspection

-

AR 01158730; 2Z-013 Visually Indeterminable Lateral Support Connections

-

AR 01158949; 2Z-013 Polar Crane Inspection Weaknesses -

AR 01159254; 2Z-013 Polar Crane Inspection Weaknesses -

AR 01159410; Z-013 Main Hoist Has A Pinched Cable

- ANSI

B30.2.0 - 1976; Overhead And Gantry Cranes (Top Running Bridge, Multiple Girder)

- ASME B30.2-2001; Overhead And Gantry Cranes (Top Running Bridge, Single Or Multiple Girder, Top Running Trolley Hoist) - ASME B30.2-2005; Overhead And Gantry Cranes (Top Running Bridge, Single Or Multiple

Girder, Top Running Trolley Hoist)

- ASME OM

CODE-1995; Code For Operation And Maintenance Of Nuclear Power Plants

-

AR 01158563; Unit 2 Containment Polar Crane Trolley Failure To Move

-

AR 01158730; 2Z-013 - Visually Indeterminable Lateral Support Connection

-

AR 01158746; Unit 2 Z-13 Crane #1 Controller Bridge Control Broken -

AR 01158788; 2RMP 9118-1 Emergent Issuance -

AR 01159790; Polar Crane Stopped Working

-

AR 01159794; Potential Improvement To

PBV-9240

-

AR 01160749;

SLP-1 And -2 Conflict With OSHA Required Crane Checks

-

AR 01160844; Outdated Daily Crane Inspection Form Used -

AR 01162152; 12L-25 Lighting Panel Breaker Found Tripped -

AR 01162165; AR Not Initiated For Adverse Condition

-

AR 01162167; DC Ground Found During ORT 3A

-

AR 01162172; D-09 AC Input Breaker Tripped

-

AR 01162173; Sliders Found Open During

RF-445

-

AR 01162177; G-01 Alarms Received During ORT 3A -

AR 01162205; Use Of CAPs Not Reinforced In ORT 3A -

AR 01162206;

SA-51 Interstage Bleed On K-3B SA Compressor Does Not Work Attachment -

AR 01162212; Unexpected Alarm, 2C20A 2-2, D-01/D-03 DC Bus Under Voltage -

AR 01162222; Full Shut 2MS-5958 Indicates 12% Open Locally During

ORT-54

-

AR 01162638; 2DT-2081 Gasket Failure -

AR 01162668; 2P029T Oil Sample Contained Water -

AR 01162712; 2MS-2082 Trip Valve Leakage Observed During

IT 09A

-

AR 01162728;

TS-81 G-01 EDG Testing While 2P-29 TDAFW Pump OOS

-

AR 01162762; OBD Completion Did Not Reverse Changes To Procedure

-

CMP 11.1; Component Maintenance Program; Revision 0

- FSAR Appendix A.3; Control Of Heavy Loads -

IT 09A; Cold Start Of Turbine-Driven Auxiliary Feed Pump And Valve Test (Quarterly) Unit 2;

Revision 49

- ORT 3A; Safety Injection Actuation With Loss Of Engineered Safeguards AC (Train A)

- NRC Correspondence To Wisconsin Electric Power Company; February 1, 1982

-

NUREG-0612; Control Of Heavy Loads At Nuclear Power Plants - 2RMP 9118-1; Containment Building Crane OSHA Operability Inspections; Revision 5 -

SLP 10; Load Weight Listings And Rigging Figures; Revision 22

-

WO 359117; Wire Rope Inspection

- ALPS Wire Rope Corporation; Certificate Of Conformance; October 25, 2009

- Control Room Log Entries Data; TDAFW Test; December 4 - 11, 2009 - Drawing

275460; Auxiliary Feedwater System Units 1 and 2 - Point Beach Nuclear Plant Wire Rope Inspection Criteria Instructions

- Priority Work Schedule Data; September 10, 2009 1EP2 Alert and Notification Evaluation - ENS Notification 45553; Notification Due To A Single Emergency Siren Actuation;

December 9, 2009 - EPMP 6.0; Alert And Notification System; Revision 9 - FEMA Prompt Alert And Notification System Approval Letter And Design Report;

December 7, 1987

- PBNP ANS Maintenance Records; October 2007 - November 2009

-

AR 01162916; Power Outages Caused Sever Sirens Out-of-Service Due To Weather -

AR 01160553; Replaced Siren P-013 Antenna -

AR 01130759; Siren Test Postponed Due To Severe Weather 1EP3 Emergency Response Organization Augmentation Testing - EP 5.0; Organizational Control Of Emergencies; Revision 52 - EPIP 1.1; ERO Notification; Revision 56

- EPG 1.0; Point Beach Nuclear Plant Shift Augmentation Drill Guideline; Revision 13 - EPMP 7.0; Emergency Response Organization Notification System; Revision 6 - PBN EP TP; Emergency Preparedness Training Program Description; Revision 8

- Emergency Response Organization Training Drill Team Roster; December 3, 2009

- LMS ERO Qualification Status Verification; December 10, 2009

-

NPM 2008-0130; March 27, Quarterly ERO Augmentation Drills;

May 2, 2008 - September 17, 2009 -

AR 01162982; Augmentation Drills Taking Credit For 30-Minute Chemistry Technician With On-shift Chemistry Technician -

AR 01162977; Augmentation Drill Start Time Questioned During NRC Inspection

-

AR 01162972; Loss Of Dialogics ERO Notification System Capabilities

-

AR 01155763; EP ERO Expectations For Wearing A Pager Attachment -

AR 01153790; July 28, 2009 Drill Dose Assessment Challenge -

AR 01156706; September 17, 2009 Augmentation Drill Two Responders Greater Than 30 Minutes And One Responder Greater Than 60 Minutes -

AR 01151489; June 16, 2009 ERO Augmentation Drill Two Responders Greater Than 30 Minutes 1EP4 Emergency Action Level And Emergency Plan Changes - EP 2.0; Emergency Plan Acronyms And Definitions; 41 and 42 - EP 6.0; Emergency Measures; 50, 51, and 52

- EPIP 1.2.1; Emergency Action Level Technical Basis; 3 - 10

CFR 50.54(q) Reviews For Emergency Plan And EAL Revisions 1EP5 Correction Of Emergency Preparedness Weaknesses And Deficiencies - Focused Self-Assessment Report

PBSA-EP-09-03; Point Beach Emergency Preparedness Pre-NRC Inspection; November 3, 2009 - Point Beach Toxic Gas Unusual Event July 3, 2008 Report; July 14, 2008 - Point Beach Security Unusual Event April 8, 2008 Report; May 7, 2008 - Point Beach Loss Of Off-Site Power Unusual Event January 15, 2008 Report; February 26, 2008 - PBNP 09-026; Emergency Preparedness Audit; August 12, 2009

- PBNP 08-026; Emergency Preparedness Assessment; August 12, 2008 - PBNP 08-011; Emergency Preparedness Assessment; May 3, 2008 -

AR 01151074; EPlan Organization Chart Different Than Site Organization Chart

-

AR 01149526; Radiation Protection Leader Position Drops Below Three Deep

-

AR 01136999; Self-Assessment DEP Data Discrepancy

-

AR 01131429; July 3, 2008 Evaluate Toxic Gas EAL

-

AR 01131394; July 3, 2008 Unusual Event -

AR 01121253; Transfer Of Command And Control Confusion During January 15, 2008 Unusual Event -

AR 01120314; Unusual Event January 15, 2008 ENS Notification Made At 59 Minutes 2OS1 Access Control to Radiologically Significant Areas -

RWP 00000861, Fuel Motion And Sent Fuel Pool Activities; Revision 1 - HP 2.14; Containment Keyway Personnel Access; Revision 15 - HP 2.15.1; High Level Contamination And Discrete Radioactive Particle Control; Revision 5

- HP 2.17; Very High Radiation Area Personnel Access; Revision 7

- HP 2.6; Locked And Very High Radiation Area Key Control; Revision 32

- HP 3.2; Radiological Labeling, Posting And Barricading Requirements; Revision 50

- HP 3.2.10; Secure High Radiation Area Controls; Revision 1 - HP 3.6; Alpha Monitoring Program; Revision 0 - HPIP 1.64; Control of Underwater Diving In Radiologically Hazardous Areas; Revision 7

- HPIP 2.1.1; Response Checks Of Portable Survey Instruments; Revision 11

- HPIP 3.50; Radiation Surveys; Revision 13

-

FP-RP-JPP-01; Radiation Protection Job Planning; Revision 6 - 0-SOP-FH-001; Fuel/Insert/Component Movement In the Spent Fuel Pool Or New Fuel Vault; Revision 15 - RP 1C, Refueling; Revision 65

- RP 2A; Receipt Of New Fuel Assemblies; Revision 47

Attachment -

RP-18 Part 3; Place Loaded DSC/TC Back Into The Spent Fuel Pool; Revision 3 - RESP- 2.3; Defective Removable Top Nozzle Replacement; Revision 7

- HPCAL 1.1; Radiation Protection Instrument Calibration, Repair And Response Checks; Revision 22 - NP 4.2.19; Entry Requirements Into Various Radiologically Controlled Areas; Revision 16

- NP 4.2.32; Respiratory Protection Program; Revision 7

- AR

SAR 01142742; Access Control To Radiologically Significant Areas And ALARA Planning And Controls - AR

SAR 0115197; Access Control To Radiologically Significant Areas And ALARA Planning And Controls 2OS2 As-Low-As-Is-Reasonably-Achievable Planning And Controls -

FP-WM-PLA-01; Work Order Planning Process; 5 - NP 4.2.1; ALARA Program; Revision 20

-

FP-RP-JPP-01; RP Job Planning; Revision 6 -

FP-RP-RWP-01; Radiation Work Permit; Revision 8 - Radiological Controls And Associated ALARA Files For Insulation; Work Orders

00371055,

00371056, And

00371057 - Radiological Controls And Associated ALARA Files For RCP Work; Work Orders

00356469,

00358775, And

00366298 - Radiological Controls And Associated ALARA Files For Core Barrel Move; Work Order

00365421 4OA1 Performance Indicator Verification - 2-PT-AF-2; Turbine Driven Auxiliary Feedwater System And MS Supply Pressure Test Outside

Containment - Unit 2

-

AR 01135651; AF Mod Deferral Requires MSPI Basis Document Update -

AR 01138122; PRA Change For MSPI Not Explained In Submittal File -

AR 01138400; PRA Change For MSPI Not Explained In Submittal File

-

AR 01142718; MSPI Margin Reduced Due To PRA Change

- EPG 1.1; Performance Indicator Guideline; Revision 6

- EPMP 6.0; Alert And Notification System Siren Function Data; October 2008 - September 2009 -

FG-E-MSPI-01; Mitigating System Performance Index; Revision 3 -

LI-AA-200-1000-10000; FPL Fleet Licensing Performance Indicators; Revision 00

- Mitigating Systems Performance Index (MSPI) Basis Document Data For Point Beach Nuclear

Plant; Revisions 12 And 14

- MSPI Monthly Unavailability And Verification Data; July, August, And September, 2008 - MSPI Monthly Unavailability And Verification Data; October, November, And December, 2008 - MSPI Monthly Unavailability And Verification Data; January, February, And March, 2009 - MSPI Monthly Unavailability And Verification Data; April, May, And June, 2009

- NP 5.2.16; NRC Performance Indicators; Revision 14

- NRC Occupational Exposure Performance Indicator Data; October 2008 Through

September 2009 - Alert and Notification System Performance Indicator Records; October 2008 - September 2009 - Atmospheric Effluent Radioisotopic Quantification Report; March 2009

- Atmospheric Effluent Radioisotopic Quantification Report; June 2009

- Atmospheric Effluent Radioisotopic Quantification Report; September 2009

Attachment - Drill And Exercise Performance PI Results; October 2008 - September 2009 - Drill And Exercise Performance Records; October 2008 - September 2009

- ERO Drill Participation Summaries; December 2008 - September 2009 - ERO Participation Monthly Reports; December 2008 - September 2009 - Emergency Preparedness Attendance Reports; December 2008 - September 2009

- Liquid Effluent Radioisotopic Quantification Report; March 2009

- Liquid Effluent Radioisotopic Quantification Report; June 2009

- Liquid Effluent Radioisotopic Quantification Report; September 2009

- Mitigating Systems Performance Index Derivation Report Units 1 And 2; Heat Removal

System; Third Quarter of 2008 Through Second Quarter of 2009 -

NEI 99-02; Regulatory Assessment Performance Indicator Guideline; Revision 5

-

NEI 99-02; Regulatory Assessment Performance Indicator Guideline; Revision 6;

October 2009

- NP 1.10.1; Record Keeping For NRC Licensed Operators; Revision 8 - NP 5.2.16; NRC Performance Indicators; Revision 14 - NP 5.2.17; Equipment Performance And Information Exchange (EPIX); Revision 2

-

OI 62A; Motor-Driven Auxiliary Feedwater System (P-38A And P-38B) - TRHB 11.4; Secondary Systems Descriptions:

Auxiliary Feedwater System; Revision 10 - Control Room Log Entries; July 2008 through June 2009

4OA2 Identification and Resolution of Problems -

AR 01114734; Lack Of Progress On Cable Submergence Issue -

AR 01163603; Trend Coding Of CAPS

-

AR 01138519; FM Found During Lower Core Plate Inspection

-

AR 01157789; FME Barrier Found Inside FW Heater 4A During Inspection

-

AR 01158516; Component Cooling Water Heat Exchanger FME Issues -

AR 01158573; Wrench Dropped Into Cavity -

AR 01159958; Foreign Material Found In Discharge Of 2CV-257

-

AR 01160348; FM Debris Scan Challenged RV Lower Internal Install (2R30)

-

AR 01160355; LUVS Screen Dropped In Refuel Cavity

-

AR 01160443; Found Washer Between Gasket And Flange Face On 2HX-15A3 -

AR 01160489; Foreign Material On Lower Core Plate -

AR 01160494; Trend - Submerged Electrical Cables

-

AR 01160572; Resource Needs Were Not Identified To Support FM Inspection In RMP

-

AR 01160820; U2R30 Cavity Foreign Material Controls

-

AR 01160980; SFMEA Concerns At The Spent Fuel Pool

-

AR 01161181; Untimely Reporting Of foreign Material -

AR 01161214; Z-756 Hoist Pendant Damage Causes Hoist Inoperability -

AR 01161216; FME Found While Inspecting Portion Of 2A02 Bus

-

AR 01161285; Sump Bravo Needs Fabricated FME Covers When Elbows Are Removed

-

AR 01161310; During 2ICP 02.019 Testing, We Found A Hair In

PC-949B-XA

-

AR 01161672; Bechtel Contamination Control For Valves And Pipes -

AR 01162133; Foreign Material Found In The New Output Breakers -

AR 01162169; FME Issue Of Bottle Dropped In Stabrex Tanker

-

AR 01162213; No Housing Covers Installed On FD Valve Operators

-

AR 01162509; Four Absorbent Bags Found In the Unit 2 Turbine Hall Sump

-

CMP 12.0; Equipment Failure Trending; Revision 5

-

FG-PA-CTC-01; CAP Trend Code Manual; Revision 11 -

FG-PA-DRUM-01; Department Roll Up Meeting Manual - Department Performance Trending; Revision 8

Attachment -

PBN-09-010; Point Beach Nuclear Assurance Report; System Engineering; May 26, 2009 -

REI 48.0; Reactor Engineering Trending Program; Revision 2

- Point Beach Nuclear Plant

AT-0384 Activity Trending Data; December 21, 2009 - Point Beach Nuclear Plant Drum Summary Report; First Quarter 2009 - Point Beach Nuclear Plant Drum Summary Report; Second Quarter 2009 4OA5 Other Activities -

AR 01165164;

NP-413 Policy Requirement Not Implemented - Policy

HR-AA-01; Involuntary Termination Or Other Significant Employment Actions Affecting Nuclear Division Employees; Revision 0 - Policy

SY-AA-02; Denial of Unescorted Access to FPL/FPLE Nuclear Facility; Revision 0 - FP&L NUC GET Plant Access Training 003; Revision Dated July 26, 2006

- HPIP 1.60; Calculating Shallow And Deep Dose Rates Due To Skin Contamination;

Revision 11

- NP 1.7.3; Site Specific Requirements For Access To And Termination From Point Beach Nuclear Plant; Revision 18 - NP 4.2.25; Release Of Material, Equipment And Personal Items From The Radiologically Controlled Areas; Revision 14 - Apparent Cause Evaluation -

AR 01150045; Loss Of Radioactive Material Control Inside Protected Area; Revision 1 and 2 - Chesapeake Nuclear Services Final Report, Dose Assessment For May 21, 2009 Contamination Event At The Point Beach Nuclear Plant; September 10, 2009 - Dispersed Contamination Dose Assessment Summary; July 2, 2009

- Personnel Contamination Event Report; May 21, 2009

-

DRW 110E029, Sheet 1; Auxiliary Coolant System; September 10, 2008.

-

DRW 110E035, Sheet 1; Safety Injection System; August 1, 2007 - DRW P-248; Residual Heat Removal System; December 25, 1999 - DRW P-237; SIS to Primary Coolant Cold Leg; January 22, 2004

- PO No.

00024065; Point Beach Walkdown Closure Report; November 16, 2009

-

AR 01129366; PBNP Confirmatory Order Requirements Sustainability For Adverse Employment Actions -

AR 01129462; Schedule For Incumbent Mgrs/Supv For NLA Course -

AR 01129565; 4 Individuals Not Meeting SCWE Confirmatory Order

-

AR 01129659;

EA 06-178 Confirmatory Order Inspection Finding

-

AR 01152228; Independent Assessment Of The Effectiveness Of Corrective Actions From Safety Culture Survey -

AR 01157190; Schedule PBN Personnel For SDA/LF Slots -

AR 01157534; Quick Hit Assessment

PBSA-SRC-09-04 -

AR 01162560; Security Supervisor Not Tracked For Required SCWE Training

-

AR 01162564; 7 People Required To Attend SCWE Training And Not Being Tracked

-

AR 01163410; Follow-up Issue SCWE Confirmatory Order Inspection

- FPL Nuclear Policy

NP-413; Involuntary Termination of Division Employees; Revision 5 - NMC Policy

CP 0087; Material Employment Action Review; Revision 0 - Corrective Action Effectiveness Review -AR01070153-12, April 29, 2009

- Memo from F. Flentje to J. Costedio; Verification of 2007 SCWE Confirmatory Order Actions Committed During September, 24, 2008 Public Meeting with NRC; February 14, 2009 - PARB Presentation for Non-Performance of

EFR 1070334, Adverse Employment Action Policy, November 30, 2007 - Memo from B. Deuel to Nuclear Safety Culture Improvement Team; September 30, 2009 Nuclear Safety Culture Improvement Team Meeting Minutes; September 30, 2009

Attachment - Memo from B. Deuel to Nuclear Safety Culture Improvement Team; December 2, 2009 Nuclear Safety Culture Improvement Team Meeting Minutes; December 2, 2009 - Memo from L Meyer to File; August 2009 PBNP PTAB Meeting Minutes; September 12, 2009 - Memo from L Meyer to File; February 2009 PBNP PTAB Meeting Minutes; February 23, 2009 - Point Beach Supervisor Leadership Development Program; Training Program Description; Revision 6 - Point Beach Succession Plan; January 2010

- Point Beach Knowledge Retention Program; December 2009

-

NRC 2007-0015, NMC Letter to NRC; NMC Plan to Address the Safety Culture Issues an at Point Beach Nuclear Plant; March 29, 2007 (ML070890434) -

NRC 2008-0078, FPL Energy Letter to NRC; Status of Action Plans Taken in Response to Confirmatory Order

EA-06-178; November 11, 2008 (ML083170356) -

NRC 2008-0090, FPL Energy Letter to NRC; Confirmatory Order

EA-06-178 Section

IV.6 Nuclear Safety Culture Survey Results; December 22, 2008 (ML083660387) - Point Beach Independent Assessment of Safety Culture Survey Corrective Action Effectiveness; June 28, 2009

Attachment