Text

October 30, 2009

Mr. Charles Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2 NRC INTEGRATED INSPECTION REPORT 05000373/2009004; 05000374/2009004

Dear Mr. Pardee:

On September 30, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your LaSalle County Station, Units 1 and 2. The enclosed inspection report documents the inspection results, which were discussed on October 16, 2009, with the Site Vice President, Mr. Dave Wozniak, and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, three findings of very low safety significance were identified. Two of the findings were associated with violations of NRC requirements. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section VI.A.1 of the NRC Enforcement Policy because of the very low safety significance of the violations and because they are entered into your corrective action program (CAP). Additionally, a licensee identified violation which was determined to be of very low safety significance is listed in this report. If you contest the subject or severity of an NCV, 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 LaSalle County 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 LaSalle County Station. The information that you provide will be considered in accordance with Inspection Manual Chapter 0305. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/

Kenneth Riemer, Chief Branch 2 Division of Reactor Projects

Docket Nos. 50-373; 50-374 License Nos. NPF-11; NPF-18

Enclosure:

Inspection Report 05000373/2009004; 05000374/2009004

w/Attachment:

Supplemental Information cc w/encl: Distribution via ListServ Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket Nos: 05000373; 05000374 License Nos: NPF-11; NPF-18 Report No: 05000373/2009004; 05000374/2009004 Licensee: Exelon Generation Company, LLC Facility: LaSalle County Station, Units 1 and 2 Location: Marseilles, IL Dates: July 1, 2009, through September 30, 2009 Inspectors: G. Roach, Senior Resident Inspector F. Ramírez, Resident Inspector M. Mitchell, Region III Health Physics Inspector M. Learn, Region III Branch 2 Reactor Engineer S. Bakhsh, Region III Reactor Inspector J. Bozga, Region III Reactor Inspector V. Meghani, Region III Reactor Inspector J. Neurauter, Region III Reactor Inspector R. Temps, Safety Inspector, Office of Nuclear Materials Safety and Safeguards J. Yesinowski, Illinois Dept. of Emergency Management Approved by: Kenneth Riemer, Chief Branch 2 Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS

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

REPORT DETAILS

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

REACTOR SAFETY

.......................................................................................................3

1R01 Adverse Weather Protection

Main article: IP 71111.01

.....................................................3

1R04 Equipment Alignment

Main article: IP 71111.04

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

1R05 Fire Protection

Main article: IP 71111.05

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

1R07 Annual Heat Sink Performance

Main article: IP 71111.07

.................................................6

1R11 Licensed Operator Requalification Program

Main article: IP 71111.11

.............................6

1R12 Maintenance Effectiveness

Main article: IP 71111.12

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

1R13 Maintenance Risk Assessments and Emergent Work Control

Main article: IP 71111.13

..8

1R15 Operability Evaluations

Main article: IP 71111.15

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

1R19 Post-Maintenance Testing

Main article: IP 71111.19

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

1R22 Surveillance Testing

Main article: IP 71111.22

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

1EP6 Drill Evaluation

Main article: IP 71114.06

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

RADIATION SAFETY

...................................................................................................14 2OS1 Access Control to Radiologically Significant Areas (71121.01).................14

OTHER ACTIVITIES

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

4OA1 Performance Indicator Verification

Main article: IP 71151

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

4OA2 Identification and Resolution of Problems

Main article: IP 71152

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

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

Main article: IP 71153

.......21

4OA5 Other Activities..........................................................................................23 4OA6

Management Meetings..............................................................................25 4OA7 Licensee-Identified Violations....................................................................25

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

D. Wozniak, Site Vice President

D. Rhoades, Plant Manager

K. Aleshire, Exelon EP Programs Manager

D. Amezaga, GL 89-13 Program Owner

J. Bashor, Site Engineering Director

L. Blunk, Operations Training Manager

D. Carpenter, Senior ISFSI Project Manager

H. Do, Corporate ISI Manager

P. Endress, Design Engineer

J.C. Feeney, NOS Lead Assessor

F. Gogliotti, System Engineering Senior Manager

D. Henly, Design Engineer

W. Hilton, Engineering Supervisor - Mechanical/Structural

K. Ihnen, Nuclear Oversight Manager

A. Kochis, ISI Engineer

R. Leasure, Radiation Protection Manager

K. Taber, Operations Director

B. Maze, ISFSI Project Manager

J. Meyer, Exelon Nuclear Oversight Inspector

J. Miller, NDE Level III

B. Rash, Maintenance Director

J. Rommel, Design Engineering Senior Manager

K. Rusley, Emergency Preparedness Manager

J. Shields, ISI Program Supervisor

S. Shields, Regulatory Assurance

T. Simpkin, Regulatory Assurance Manager

H. Vinyard, Work Management Director

J. Vegara, Regulatory Assurance

W. Trafton, Shift Operations Superintendent

J. White, Site Training Director

G. Wilhelmsen, Design Manager

S. Wilkinson, Chemistry Manager

C. Wilson, Station Security Manager Nuclear Regulatory Commission

K. Riemer, Chief, Reactor Projects Branch 2

Attachment

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened

05000373/2009004-01;

05000374/2009004-01 NCV Failure to declare SBLC system inoperable during surveillance testing

05000374/2009004-02 NCV Failure to make required non-emergency 50.72 notification to NRC following loss of shutdown cooling

05000374/2009004-03 FIN Reactor scram during turbine testing

Closed

05000373/2009004-01;

05000374/FIN-2009004-01 NCV Failure to declare SBLC system inoperable during surveillance testing

05000374/FIN-2009004-02 NCV Failure to make required non-emergency 50.72 notification to NRC following loss of shutdown cooling

05000374/FIN-2009004-03 FIN Reactor scram during turbine testing

05000373/LER-2009-002-00 LER Loss of shutdown cooling due to spurious closure of the shutdown cooling suction isolation valve

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.

1R01 Adverse Weather Protection (71111.01) Issue Reports: -

856960; New Dry Cask Haul Path Affects Site Flooding Zones; 12/16/2008 Working Documents: -

EC 373566; Evaluation of the Expected Flooding Level Due to the New Dry Cask Haul Path; 3/25/2009 Drawings: - S-1720; ISFSI Haul Path Location Plan; Rev. 0 Miscellaneous: -

LSCS-UFSAR 2.4; Hydrologic Engineering; Rev. 14 1R04 Equipment Alignment (71111.04)

Procedures: -

LOP-RI-01E; Unit 1 Reactor Core Isolation Cooling System Electrical Checklist: Rev. 11 -

LOP-RI-01M; Unit 1 Reactor Core Isolation Cooling System Mechanical Checklist: Rev. 19 Issue Reports: -

950159; 1B WS Pump Needs OTBD Packing Adjusted; 8/6/2009 Working Documents: -

LOP-DG-01E; Unit 1 A Diesel Generator Electrical Checklist; 8/22/1997

-

LOP-DG-01M; Unit 1 A Diesel Generator mechanical Checklist; 6/12/2003 -

LOP-RH-2BM; Unit 2B Residual Heat Removal System Mechanical Checklist; 3/3/2008 -

LOP-RH-2CM; Unit 2 C Residual Heat Removal System Mechanical Checklist; 3/3/2008

-

LOP-WS-01M; Unit 1 Service Water System Mechanical Checklist; 4/23/2007 Miscellaneous: - Work Week

200928;7/6-7/12/2009

Attachment 1R05 Fire Protection (71111.05) Issue Reports: -

927960; Neil Fire Protection System Testing; 6/4/2009 -

947561; NRC ID'd: Housekeeping Issues with U2

RB 673'; 7/30/2009 Miscellaneous: - 2I4 Fire Pre-Att.; Information Sheet for Rx Bldg. 673' Elev. LPCS/RCIC Pump Cubicle; 2/2/2006 - 5B7 Fire pre-att.; Information Sheet for Turbine Building Unit 1 Hydrogen Seal Oil Skid 731'0"; 2/2/2006 -

LSCS-FPR Table H.3-2; Combustible Loading and Extinguishing Capability; Rev. 3 1R07 Annual Heat Sink Performance (71111.07)

Issue Reports: -

969442; New 2A DG Cooler End Cover Coating Issue; 9/23/2009 Procedures: -

ER-AA-330-008; Exelon Service Level I, and Safety-related (Service Level III) Protective Coatings; Rev. 6 -

ER-AA-340-1002; Service Water Heat Exchanger Inspection Guide; Rev. 4 Work Documents: - HX 2DG01A/ER-AA-340-1002; HX Inspection Report: 2A DG Cooler; 9/28/2009 -

EC 372326; 0DG Thermal Performance Margin with Tubes Blocked; 10/20/2008 - Ver. 44 9-21-09 1015; 2A DG Window for 9-28-09 week; 9/21/2009 Calculations: - 97-195 /

EC 334017; Thermal Model of ComEd/LaSalle Station Unit 0, 1, and 2 Diesel Generator Jacket Water Coolers; Rev. A Miscellaneous: -

GL 89-13; Program Basis Document: Heat Exchanger Visual Inspection Acceptance Criteria (VIAC); Rev. 6 -

IR 597664; Apparent Cause Evaluation: 2A DG Heat Exchanger Coating Failure; 3/1/2007

1R11 Licensed Operator Requalification Program (71111.11)

Miscellaneous: - Simulator training scenario 3rd quarter 2009 1R12 Maintenance Effectiveness (71111.12)

Procedures: -

MA-AA-723-301; Periodic Inspection of Limitorque Model SMB/SB/SBD-000 Through 5 Motor Operated Valves; Rev. 5 -

LES-EQ-102; Testing of Environmentally Qualified Motors; Rev. 9 -

LMS-GM-01; HBC Valve Actuator Grease Inspection and Lubrication Application; Rev. 14

Attachment Issue Reports: -

687445; 2E51-C003 Pump Mechanical Seal Leak; 10/21/2007

-

689882; Instrument Out of Tolerance Review for RI System; 10/26/2007 -

723020; High Vibes/Low Disch Press on RCIC Water Leg Pump; 1/16/2008 -

946225; Unit 1 RCIC Water Leg Pump Discharge Pressure Reading Low; 7/27/2009

-

947308; Control Room Alarm C RHR Low Pressure; 7/29/2009

-

947379; Oil Leak on 2B/C RHR Water Leg Pump Housing Nipple; 7/30/2009

-

950941; Unexpected MCR Alarm.

2C RHR Discharge Pressure Low; 8/7/2009

-

951144; U2 Div II Waterleg Pump Oil Leakage Higher then Previous IR; 8/9/2009 -

951171; Contingency WO for Div 3 WLP & Use for Unit 2 Div 2; 8/9/2009 -

952661; Need Contingency WO for Unit 2 b/c RHR Water Leg Pump; 8/12/2009

-

957133; Water Leg Pump Impeller Diameter Inconsistencies; 8/25/2009

-

961952; Flange Thickness of Spare/Replacement Water leg Pumps; 9/9/2009

-

962839; Serial # of ECCS & RCIC Water Leg Pumps; 9/9/2009 -

965914; Grease Sample Quality from MOV Actuator Degraded; 9/16/2009 Work Documents: -

WO 1083707; 2E22C003 HPCS Water Leg Pump Reservoir; 5/08/2009 Miscellaneous: - ; U1 Safety-related MOV Listing; 2009 - ; U2 Safety-related MOV Listing; 2009 - VM J-0687; Vendor Equipment Technical Information Program (VETIP) Limitorque - Valve Operators; 5/14/1998 1R13 Maintenance Risk Assessments and Emergent Work Control (71111.13) Procedures: -

LOP-RR-08; Changing Reactor Recirc Pump Speed from Fast to Slow Speed; Rev. 34 -

OP-AA-108-111; Att. 1: Adverse Condition Monitoring and Contingency Plan for Unit 1 RR Pump Seal Degradation (Rev 5); Rev. 4 Issue Reports: -

938723; 1 B RR Pump Seal Cavity #2 Pressure Spike; 7/4/2009

-

939611; Need to Validate Alarm Condition for 1B RR PMP Seal Trouble; 7/8/2009 -

939756; 1B RR Seal Leakage Input Complex TS Plan Documentation; 7/8/2009 -

940604; AR Subj: After Autopsy of 1B RR Pump Seal Send Offsite for Analysis;7/15/2009

-

943453; 1B RR Pump Seal Cover Carbon Bushing Minor Damage; 7/19/2009

-

943476; 1B33-C001B Replace Pump Seal Leakage Cover in L1R13; 7/19/2009

-

944354; Increased Vibration During Slow Speed Operation; 7/21/2009

-

946713; NRC Question on RI Availablity; 7/28/2009 -

946742; NRC Identified Steam Leak from U1 MDRFP; 7/28/2009 -

946791; NRC Resident Concerns; 7/28/2009

-

946792; Small Fishing Boat Sunk in the LaSalle Lake; 7/28/2009

-

948168; 1B RR Pump Seal Degradation; 7/31/2009

-

948388; 1B RR Pump Upper thrust Bearing Hi temperature PPC Alarm -

949535; Flowserve Preliminary L1M19 Autopsy of 1B RR Pump Seal; 8/4/2009 -

949537; Recommendations from Flowserve Regarding RR Seal Replacement; 8/4/2009 Work Documents: - Protected Equipment List, 2A DG Work Window; 9/28/2009

Attachment Drawings and Graphs: - 1B Reactor Recirculation Pump Seal (L1C13), Cavity 1 & 2 Seal Pressure; 2/28/2008 - 8/27/2009 - Unit 1 B Reactor Recirc #2 Seal Pressure; 7/31/2009 Miscellaneous: - Adverse Condition Monitoring and Contingency Plan for Unit 1 RR Pump Seal Degradation; 6/26/2009 - Email from Jeffrey Miller: 1 B RR Seal & DWEDS Detailed information; 7/8/2009

- LaSalle Operations Log; 7/28 - 7/29/2009 - Licensee Presentation: LaSalle Unit 1 1B RR Pump Seal Degradation; 7/7/2009 - Work Week

200931; 7/27 - 8/2/2009

- INPO

TR9-66; Topical Report: Reactor Recirculation and Coolant Pump Seal-Related Events; 6/2009 -

IR 931985-02; Issue Resolution Documentation for whether U1 should Shutdown to Replace 1B RR Pump Seal; 6/25/2009 -

IR 946327; Complex Troubleshooting Data Sheet for Unit 1, Mode 1, RCIC Min Flow Valve Cycled Excessively during

LOS-RI-Q5; 7/27/2009 1R15 Operability Evaluations (71111.15) Procedures: -

ER-AA-330-009; Pressure Testing Following Replacements with Core Criticality at BWRs: Alternate Requirements for Small Items; Rev. 5 -

HU-AA-104-101; Procedure Use and Adherence; Rev. 3

-

LOP-RH-07; Shutdown Cooling System Startup, Operation and Transfer; Rev. 58

-

LOP-RH-08; Shutdown Cooling System Shutdown; Rev. 33

-

LOS-DG-SR2; 0 Diesel generator Action Statement Operability Test; Rev. 20 -

LOS-DO-SR2; Diesel Fuel Oil Analysis Verification (New Fuel Oil); Rev. 13 -

LTS-900-8; Operation of High/Low Pressure Water Leak Rate Test Rig; Rev. 17 Issue Reports: -

943767; PMT for ASME Code Class 1 Bolted Repairs after L1M19; 7/20/2009

-

943883; Spurious Isolation of RHR SDC Inboard Isolation; 7/20/2009 -

961947; New Diesel Fuel Oil Water & Sediment Analysis; 9/4/2009 Work Documents: - DG99-000135; Conduct of ASME Section XI Pressure Testing Following Replacements with Core Criticality at Boiling Water Reactors; 2/19/1999 - LAS03.G03; ISI Program Plan Third Ten-Year Inspection Interval; Rev. 0

-

LOS-DO-SR2; Diesel Fuel Oil Analysis Verification; Rev. 13 -

PM 96111-01; Data Package Lab Analysis Report by Analysts Inc., for

LOS-DO-SR2 Diesel Fuel Oil Att. A (New Fuel Oil); 9/4/2009 -

PM 96111-02; Data Package Lab Analysis Report by Analysts Inc., for

LOS-DO-SR2 Diesel Fuel Oil Att. B (New Fuel Oil Within 31 Day); 9/4/2009 - TCCP # 1-PO23-09; Checklist for Unit 1 Bypass SDC High Flow and RPV High Pressure Isolation (LOP-RH-08); 7/20/2009 Drawings: - M-93; P & ID Nuclear Boiler & Reactor Recirculating System; Rev. AV

Attachment Miscellaneous: - Amendment 147/133; Programs and Manuals - Diesel Fuel Oil Testing Program (5.5.10); - ASTM D 2709 - 96; Standard Test Method for Water and Sediment in Middle Distillate Fuels by Centrifuge; 1999 - ASTM D 4176 - 93; Standard Test Method for Free Water and Particulate Contamination in Distillate Fuels (Visual Inspection Procedures); 1997 -

EC 376246; Establish Revised Reference Value and Acceptance Criteria for IST Biennial Comprehensive Pump Testing for 1E12-C300D; Rev. 0 -

IR 943883; Equipment Prompt Investigation Report for Spurious Isolation of RHR SDC Inboard Isolation; 7/20/2009 1R19 Post-Maintenance Testing (71111.19)

Procedures: -

LGP-1-1; Normal Unit Startup; Rev. 86

-

LIS-EH-203; Unit 2 Turbine Bypass System Response Time Test and Level 8 Trip Test; Rev. 13 -

LOP-NB-02; Operations with the Potential to Drain the Reactor Vessel; Rev. 10

-

LOP-RR-02; Draining, Filling, and Pressure Testing an Isolated Reactor Recirc Loop; Rev. 20

-

LOP-RH-24; Temporary Fill for A, B & C RHR System Discharge Lines; Rev. 9 -

LOS-RH-Q1; RHR (LPCI) and RHR Service Water Pump and Valve Inservice Test for Modes 1,2,3,4 and 5; Rev. 71 -

LOS-TG-M4; Turbine Bypass Valve Surveillance; Rev. 5

-

LOS-TX-Q1; Diesel Generator 0Dg09K Quarterly Test; Rev. 12

-

LOS-VC-SR1; Auxiliary Electric Equipment Room HVAC Pressurization Surveillance; Rev. 2 Issue Reports: -

946225; Unit 1 RCIC Water Leg Pump Discharge Pressure Reading Low; 7/27/2009 -

947308; Control Room Alarm C RHR Low Pressure; 7/29/2009 -

947379; Oil Leak on 2B/C RHR Water Leg Pump Housing Nipple; 7/30/2009

-

947561; NRC Id'd: Housekeeping Issues with U2

RB 673'; 7/30/2009

-

963844; 231B-7 ASCO Transfer Switch Failed During

LOS-TX-Q1 Work Documents: -

LOS-RH-M1; Tech Spec Surveillance - Unit 2 RHR C Att. 2C; 7/31/2009 -

LOS-RH-Q1; Tech Spec Surveillance - 2C RHR Pump Att. 2C; 7/28/2009

-

LOS-RH-Q1; Unit 2 C RHR System Operability and Inservice Test Checklist; Rev. 71 -

LOS-VC-SR1, Att. B,D,E; Checklist for Auxiliary Electric Equipment Room HVAC Pressurization Surveillance; 7/17/2009 -

WO 1089556;

LES-RH-206 ATT C Min Flow Time Delay Relay Test; 5/12/2009 Drawings: - M-93; P & ID Nuclear Boiler & Reactor Recirculating System; Rev. AX Miscellaneous: - ;LaSalle Operations Log; 7/29 - 7/30/2009

Attachment 1R22 Surveillance Testing (71111.22)

Procedures: -

LOP-NB-03; Troubleshooting Drywell Leakage; Rev. 1 -

LOS-DG-M3; 1B(2B) Diesel Generator Operability Test; Rev. 71 -

LOS-HP-Q1; HPCS System Inservice test; Rev. 63

-

LOS-RH-Q1; RHR (LPCI) and RHR Service Water Pump and Valve Inservice Test for Models 1,2,3,4 and 5; Rev. 71 -

LOS-SC-Q1; SBLC Pump Operability/Inservice Test and Explosive Valve Continuity Check; Rev. 28 -

LRP-5821-53; 1(2)PL15J Primary Containment Panel Particulate and Nobel Gas Monitor Performance Check; Rev. 1 -

OP-LA-101-111-1002; LaSalle Operations Philosophy Handbook; Rev. 23

-

WC-AA-101; On-Line Work Control Process; Rev. 16 Issue Reports: -

946200; NOS ID: Clearance Order Electronic Sign on Not Used; 7/27/2009 -

946203; RCIC Overspeed Connector Needs Repaired; 7/27/2009

-

946225; Unit 1 RCIC Water Leg Pump Discharge Pressure Reading Low; 7/27/2009

-

946303; RCIC Suction Pressure Gauge Disagreement; 7/27/2009

-

946304; RCIC Suction Pressure Gauge Disagreement; 7/27/2009 -

946327; Unit 1 RCIC Min Flow Valve Cycling; 7/27/2009 -

946814; Unit 1 RCIC Barometric Condenser Vac. Tank Low Level Alarm; 7/28/2009

-

946900; Unexpected Alarm on RCIC Barometric Vacuum Tank Level Low; 7/28/2009

-

948170; NRC Identified: No Emergency Restoration ATT For

LOS-SC-Q1

-

951498;

LOS-DG-M3 As-Found 1VY02A Flow Low; 8/10/2009

-

952624; OP_LA_101-111-1002 Needs Revision for Consistency with PRA; 8/12/2009 -

953484; NRC Question: SBLC Availability During Surveillance; 8/14/2009 -

955588; NRC Question on ARI Initiation During U2 Scram; 8/20/2009

-

960793; NRC Concern: Maintenance of SBLC Operability Status During L; 9/2/2009

-

965578; 345 KV Line 0104 Trip; 9/16/2009

-

966125; Panel 2PL75J - High Particulate Channel Activity;9/17/2009 -

967365; 2PL75J Rad Monitor Alarm; 9/19/2009 -

968370; Hi Rad Alarm From 2PL75J; 9/222/2009

-

968524; Request Set Point Change for 2PL75J Part Channel; 9/22/2009

-

971089; 2PL15J Particulate Channel Alarms; 9/27/2009 Working Documents: -

DCR 991595; Design Analysis Approval: Change

NED-I-EIC-0158 to Derive Allowable Values and Expanded Tolerances; 9/19/2000 -

EC 360691; CSCS Cooling Water Flow Margins for Operability of the ECCS Cubicle Room Coolers and DG Coolers; Rev. 0 -

LOS-2009-35; Procedure Change Request

LOS-DG-M3; 8/10/2009

-

LOS-DG-SR7; Division 3 Cooling Water System Test Procedure Checklist; 8/10/2009 -

WO 1228244;

LOS-SC-Q1 U2 A SBLC "Biennial Comprehensive Test" Att. 2A; 7/31/2009 -

WO 1231552;

LOS-RI-Q5 U1 RCIC Cold-Quick Start, Att. 1A; 7/24/2009

-

WO 1239276;

LOS-RH-Q1 2A RHR WS Operability & Inservice Test (Biennial); 8/24/2009

-

WO 1243592;

LOS-HP-Q1 U2 HPCS Comprehensive Pump Test Att 2A (Wk 12); 9/9/2009

-

WO 1249644;

LOS-DG-M3 1B DG Idle Start Att. 1B-Idle; 8/10/2009

Attachment Calculations: - A.47;LaSalle HRA Notebook: Operator Fails to Initiate SLC Early; 7/12/2007 Graphs: - 2PL75JPART; Year to Date 2PL75J Particulate Containment Monitoring Log for Various Isotopes; 9/2009 Miscellaneous: - LaSalle DLoop ATWS Event Tree; 8/21/2009

- LaSalle News Flash from Dave Rhoades, Plant Manager: Unsecured High Rad Boundary Reinforces Need to Focus on Human Performance; 8/24/2009 - LaSalle Operations Log; 7/26 - 7/27/2009 - LaSalle Operations Log; 7/31/2009

- LaSalle Operations Log; 9/14 - 9/23/2009

- LaSalle Operations Log; 9/16/2009

- Review of Surveillances for Week of August 17, 2009 for Availability Maintained with Operator Actions; 8/17-8/23/2009 - Standby Liquid Control (SC) Activities/Notes;

- Amendment 147/133; Reactivity Control Systems; Standby Liquid Control (SLC) System; - B 3.1.7-1; Reactivity Control Systems; Standby Liquid Control (SLC) System; Rev.0 - C467060024-7435-3/21/2008; LaSalle Event Tree Notebook; Reactivity Control with SBLC and RPV Level Control; 3/21/2008 -

IR 946327; Engineering Summary (informal) of RCIC Min Flow Valve Excessive Cycling Issue; date unknown -

LSCS-UFSAR 15.8; Anticipated Transients without Scram (ATWS); Rev. 13

-

LSCS-UFSAR 15.8.1; References List for Anticipated Transients without Scram (ATWS); Rev. 16 -

LSCS-UFSAR 9.3; Standby Liquid Control System; Rev. 13 - Part 9900; Technical Guidance, Operability Determinations Process; 4/16/2008

- RM

LS-MISC-05; Input to Operations for

OP-LA-101-111-01002, LaSalle Operations Philosophy Handbook; Rev. 0 1EP6 Drill Evaluation (71114.06) - EP Drill Package; Third Quarter, 2009 2OS1 Access Control to Radiologically Significant Areas (71121.01) Procedures: -

RP-AA-220; Bioassay Program; Revision 5

-

RP-AA-221; Whole Body Count Data Review; Revision 1

-

RP-AA-390; Spent Fuel Pool Material Control; Revision 3 -

RP-AA-400; ALARA Program; Revision 5 -

RP-AA-401; Operational ALARA Planning and Controls; Revision 9

-

RWP 10009373; L2R12 Drywell Emergent Work; Revision 0

-

RWP 10009396; L2R12 Emergent Under Vessel Nuclear Instrumentation; Revision 0

-

RWP 10009402; L2R12; Emergent Work in the Reactor Building; Revision 0 -

RWP 10009447; L1R12 Turbine Building Emergent Work Activities; Revision 0

Attachment Issue Reports: -

848246; Check-In Self-Assessment:

Lead Shielding Program; 5/21/2009

-

861378-02; Check-In Self-Assessment:

Dose Timekeeping;

6/26/2009 -

848240; Check-In Self-Assessment:

Access Control to Radiologically Significant Areas and ALARA Planning and Controls;

7/21/2009 -

874282; Secured High Radiation Area Unlocked;

1/30/2009

-

897924; Unexpected Airborne Air Sample;

3/26/2009

-

907825; Contamination Discovered Outside of a Posted Contaminated Area;

4/15/2009

-

921607; New High Radiation Area Posted;

5/19/2009 -

924020; New High Radiation Area Posted; 5/26/2009 -

925044; Airborne Radiation Area Radwaste Exhaust Filter Room;

5/21/2009

-

941362; Un-necessary Dose Received Recovering Seal Parts;

7/8/2009

-

945167; Mechanical Maintenance Technician Entered High Radiation Area Under Wrong Radiation Work Permit;

7/23/2009 -

948525; Hot Spot Controlled as Administrative High Radiation Area;

8/1/2009 -

950325; Secured High Radiation Area Not Secured;

8/6/2009

-

951830; Potential Adverse Trend in Radiation Worker Practices;

8/11/2009

-

952854; NOS Identified:

Radworker Performance Issue Review;

8/13/2009

-

956955; High Radiation Area Found Not Secured;

8/24/2009 Miscellaneous: - L2R12 Refueling Outage Report 4OA1 Performance Indicator Verification (71151)

Issue Reports: -

798767; Discrepancies in Design Analysis

CE-LS-003; 7/21/2008

-

800332; U-1 HPCS Pump Excessive Squealing Noise Upon Startup; 7/25/2008 -

804192; 1B RHR Pump Seal Cooler Flowrate < 12.5 GPM; 8/5/2008 -

809466; SSPI Monthly Goals are in Variance; 8/21/2008

-

840907; NRC Identified Error in MSPI Unavailability Reporting; 11/5/2008

-

883847; Retorque Packing for the 2E12-F068B; 2/23/2009

-

915437; Replace the Stem Nut for the 1E12-F068A Next PVT Interval; 5/4/2009 -

915428; Retorque Packing for the 1E12-F068A; 5/4/2009 -

932256; 1A DG MVAR Swings; 6/17/2009

-

932269; 1A DG KVAR Anomaly; 6/17/2009

-

932469; 1A DG Voltage Regulator Pot R3 Resistance Variations; 6/18/2009

-

957705; Identified Historical Error in MSPI Unavailability; 8/26/2009 Miscellaneous: - RM

SA-1561; LaSalle MSPI Basis Document; Rev. 6 - RM

SA-1561; LaSalle MSPI Basis Document; Rev. 7

Attachment 4OA2 Identification and Resolution of Problems (71152)

Procedures: -

OP-AA-102-103; Operator Work-Around Program; Rev. 2 Issue Reports: -

943883; Spurious Isolation of RHR SDC Inboard Isolation; 7/20/2009

-

946040; Potential Operator Challenge: U-2 CRD Accumulator 54-43;7/27/2009

-

953852; Alterex Temperature Rose Following the Unit 2 Scram; 8/16/2009

-

957667; DEHC Alarm Issues; 8/26/2009

-

957967; Fire Alarm - 2FP10J Trouble; 8/26/2009 -

958057; Responded to an Alarm on the 1PL-15J; 8/27/2009 -

958171; NOS ID: Operator Burden Program Implementation; 8/27/2009

-

923329; CRD FCV Placed in Manual From Auto For Rod Exercising; 5/23/2009

-

902423; Operator Work Around Board Meeting Results; 4/3/2009

-

917852; LD RWCU Rooms Differential Temperature High Alarm; 5/10/2009 -

891117; U-2 CRD FCV Controller; 3/10/2009 -

934253; Observed Increase in U1 Offgas Pre-Treat Activities; 6/23/2009 Issue Reports Resulting from NRC/IEMA Inspection: -

936955; High Radiation Area Found Not Secured; 8/24/2009

-

939469; NRC Question after Walkdown for Flooding; 7/7/2009 -

940506; IDNS Identified Housekeeping Issue; 7/10/2009 -

940813; NRC Resident Inspector Observation; 7/10/2009

-

941336; IEMA Concern; 7/13/2009

-

942791; IEMA Identified 6 Potential Flooding Hazard in U2 RCIC Room; 7/16/2009

-

946742; NRC Identified Steam Leak from U1 MDRFP; 7/28/2009

-

946791; NRC Resident Concerns; 7/28/2009 -

947561; NRC ID'D: Housekeeping Issues with U2

RB 673'; 7/30/2009 -

948170; NRC Identified: No Emergency Restoration ATT For

LOS-SC-Q1; 7/31/2009

-

949458; NRC Observation: 1C41-R002 temperature Indication; 8/4/2009

-

951501; NRC Resident Question Regarding Hot Weather Alert; 8/10/2009

-

953484; NRC Question: SBLC Availability During Surveillance; 8/14/2009 -

955588; NRC Question on ARI Initiation During U2 Scram; 8/20/2009 -

956811; NRC Identified: Miscommunication on Work in Progress; 8/24/2009

-

957475; NRC Identified - Groundwater Leak in U2 Div 1 CSCS Pump Room; 8/25/2009

-

960793; NRC Concern: Maintenance of SBLC Operability Status During L; 9/2/2009 Miscellaneous: - Agenda20090915.doc; Operator Workaround Board Meeting Agenda; 9/15/2009 -

EN 45025; Event Notifications Residual Heat Removal (RHR) Pump Tripped While in Operation for Shutdown Cooling; 4/28/2009 - NCV ML083190078; (PIM) Failure to Report a Reportable Condition; 12/31/2008

- Operator Burden Report - Operator Burden Aggregate Assessment Form; 8/9/2009

Attachment 4OA3 Follow-Up of Events and Notices of Enforcement Discretion (71153) Procedures: -

LOP-EH-11; EHC Workstation Alarm Response and Other Information; Rev. 8 -

LOR-2H13-P601-A308; Reactor Vessel Water Level 2 Lo-Lo; Rev. 3 -

LOR-2H13-P603-B107; Div II ARI Logic Initiated; Rev. 3

-

LOR-2H13-P603-B401; Division 1 RX Vessel Water Level 2 Lo-Lo; Rev. 4 Issue Reports: -

923112; NOS ID: Unit One Scram Documentation; 5/22/2009

-

951150; U-2 DEHC Alarm; 8/9/2009 -

953784; U-2 Automatic Scram from Full Power; 8/15/2009 -

953806; Relief Valve 2C11-F460B Lifted Following the Unit 2 Scram; 8/15/2009

-

953837; S and U SRV's Opened During the Scram; 8/16/2009

-

953845; 2A TDRFP Tripped Twice on Overspeed Following Scram on Unit; 8/16/2009

-

953854; 2FW036A and B had to be Closed Following the Unit 2 Scram; 8/16/2009 -

953861; U2 RT Isolation on U2 Scram; 8/16/2009 -

953872; Unit 2 RT Isolated on Delta Flow; 8/16/2009 Event Notification: - 45265; Unit 2 Automatic Scram Due to Turbine Trip; 8/15/2009 Engineering Changes: -

EC 347737; Upgrade Wide Range Reactor Level Indication to Mitigate Ringing; 3/1/2005 Drawings: - 1E-2-4205AB; Schematic Diagram Reactor Recirculation System "RR" (B33) Part 2; Rev. T - 1E-2-4207CA; Schematic Diagram Alternate Rod Insertion SYS RD (C22) Pt. 6; Rev. C

- 1E-2-4207CD; Schematic Diagram Alternate Rod Insertion System "RD" (C22) Part 9; Rev. D - 1E-2-4232AJ; Schematic Diagram Primary Containment & Reactor Vessel Isolation Alarm 1E-2-4205AM; Schematic Diagram Reactor Recirculation System "RR" (B33) Part 12; Rev. V - System PC (B21H) Part 9; Rev. M

- 1E-2-4232AV; Schematic Diagram Primary Containment & Reactor Vessel Isolation Sys. PC (B21H) Part 21; Rev. D - M-139; P&ID Nuclear Boiler & Reactor Recirculation System; Revs. AR, AI Graphs and Charts: - One Two-Variable Trend: RX Water Level WR Level and RX Pressure WR; 6/15/2009, 22:46

- One Two-Variable Trend: RX Water Level WR Level and RX Pressure WR; 6/15/2009, 22:51

- Two Two-Trend: RX Water Level, RX Pressure; 8/19/2009

- Unit 2 RX Water Level WR Level; 8/17/2009 Miscellaneous: - Control Room Operator Log; 8/15/2009 - U2 Sequence Events Recorder; 8/15/2009

- U1 ARI Div 2 Init; Scram Post Transient Review Concerns to Address; 5/21/20090

Attachment 4OA3 Follow-Up of Events and Notices of Enforcement Discretion (71153)

Procedures: -

MSLT-MPC-HOLTEC; Helium Mass Spectrometer Leak Test Procedure; Revs. 2 and 3 Issue Reports: -

949081; Insufficient Control of Design Analysis; 8/3/2009

-

950425; Reactor Building Crane Seismic Calculation Error; 8/6/2009

-

950435; Reactor Building Crane Weld Calculation Error; 8/6/2009