Download: ML092050661

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July 24, 2009

Mr. Barry Allen Site Vice President FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2, Mail Stop A-DB-3080 Oak Harbor, OH 43449-9760

SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION INTEGRATED INSPECTION REPORT 05000346/2009-003

Dear Mr. Allen:

On June 30, 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an integrated inspection at your Davis-Besse Nuclear Power Station. The enclosed inspection report documents the results of our inspection, which were discussed on July 14, 2009, with you 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, no findings of significance were identified. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/ Jamnes L. Cameron, Chief Branch 6 Division of Reactor Projects Docket No. 50-346 License No. NPF-3

Enclosure:

Inspection Report 05000346/2009-003

w/Attachment:

Supplemental Information DISTRIBUTION: See next page Letter to

SUMMARY OF FINDINGS

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

REPORT DETAILS

..................................................................................................................... 2 Summary of Plant Status.........................................................................................................

REACTOR SAFETY

..................................................................................................... 2

1R01 Adverse Weather Protection

Main article: IP 71111.01

............................................................ 2

1R04 Equipment Alignment

Main article: IP 71111.04

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

1R05 Fire Protection

Main article: IP 71111.05

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

1R06 Flooding - Internal Flooding

Main article: IP 71111.06

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

1R07 Annual Heat Sink Performance

Main article: IP 71111.07

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

1R11 Licensed Operator Requalification Program

Main article: IP 71111.11

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

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

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

1R18 Plant Modifications Permanent Plant Modifications

Main article: IP 71111.18

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

1R19 Post-Maintenance Testing

Main article: IP 71111.19

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

1R20 Outage Activities - Other Outage Activities

Main article: IP 71111.20

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

1R22 Surveillance Testing Surveillance Testing

Main article: IP 71111.22

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

1EP6 Drill Evaluation - Emergency Preparedness Drill Observation

Main article: IP 71114.06

OTHER ACTIVITIES

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

4OA1 Performance Indicator Verification

Main article: IP 71151

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

4OA2 Identification and Resolution of Problems

Main article: IP 71152

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

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

Main article: IP 71153

.............. 17 4OA5 Other Activities ................................................................................................. 19 4OA6 Management Meetings .................................................................................... 19

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

B. Allen, Site Vice President

B. Boles, Director, Site Maintenance

S. Cope, Senior Nuclear Specialist, Emergency Planning

V. Kaminskas, Director, Site Operations

D. Moul, Director, Site Engineering

C. Price, Director, Site Performance Improvement

C. Stenbergen, Superintendent Operations Training

S. Trickett, Superintendent, Radiation Protection

J. Vetter, Emergency Response Manager

G. Wolf, Regulatory Compliance Supervisor

D. Wuokko, Manager, Regulatory Compliance

LIST OF ITEMS

OPENED, CLOSED AND DISCUSSED

Opened

05000346/2009003-01 URI Loss of Switchyard J Bus

Attachment

LIST OF DOCUMENTS REVIEWED

The following is a list of documents reviewed during the inspection.

Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort.

Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report. 1R01 Adverse Weather Protection

Procedures: -

DB-OP-1300; Switchyard Management; Revision 6 -

DB-OP-2025; Davis-Besse 345 KV Switchyard Alarm Panel 25 Annunciators; Revision 6 -

DB-OP-2521; Loss of AC Bus Power Sources; Revision 13

-

DB-OP-2546; Degraded Grid; Revision 0 -

FE-EOP-113W; Nuclear Plant Operation During a System Emergency; Revision 2 -

FE-NOP-31; Davis-Besse Voltage Alarm Procedure; Revision 4 -

NOP-OP-1003; Grid Reliability Protocol; Revision 2 Other: - American Transmission System Revised and Restated Generator Interconnection and Operating Agreement with Midwest Independent Transmission System Operator and FirstEnergy Nuclear Operating Company 1R04 Equipment Alignment

Condition Reports: -

CR 07-19601; BACC: Surface rust on bolts. Containment spray pump 1 -

CR 08-41788; BACC: Slight boric acid accumulation in ctmt spray pump #2 suction line flange

-

CR 08-41831; BACC: Boric acid accumulation on containment spray pump #2 suction flange -

CR 08-47998; BACC: Boric accumulation on inboard pump shaft of containment spray pump 2 -

CR 09-59387;

BACC-Packing found on

CS 1530 by NRC inspector Procedures: -

DB-OP-6012; Decay Heat and Low Pressure Injection System Procedure; Revision 41

-

DB-OP-6013; Containment Spray System; Revision 20 -

DB-OP-6233; Auxiliary Feedwater System Operating Procedure; Revision 26 -

DB-OP-6262; Component Cooling Water System Procedure; Revision 18 -

DB-SP-3337; Containment Spray train 1 Quarterly pump and valve test; Revision 19 -

DB-SP-3338; Containment Spray train 2 Quarterly pump and valve test; Revision 19 Drawings: -

OS-4, Sheet 1; Decay Heat Removal/Low Pressure Injection System; Revision 45 -

OS-5; Containment Spray System; Revision 11 -

OS-17A, Sheet 1; Auxiliary Feedwater System; Revision 22 -

OS-17B, Sheet 1; Auxiliary Feedwater Pumps and Turbines; Revision 24

-

OS 21, Sheet 1; Component Cooling Water System; Revision 33 -

OS 21, Sheet 2; Component Cooling Water System; Revision 25 - M-034; Emergency Core Cooling System, Ctmt. Spray, & Core Flooding Systems; Revision 65

Attachment Work Orders: -

WO 200011662; CS pump #2 suction spool -

WO 200370524; CS1530-Retorque packing, MOV - Notification

600381540; Bolts are rusting on Ctmt spray pump 1; 4/29/07 - Notification

600471556; Ctmt spray suction line flange leak; 6/13/08 - Notification

600471731; Ctmt spray suction line flange leak; 6/15/08

- Notification

600477318;

BACC-Followup inspection of P56-2; 7/9/08 - Notification

600499173; Boric acid on Ctmt spray pump shaft; 10/16/08 - Notification

600543241 BACC Leak-Retorque packing of

CS 1530; 5/18/09 Other: - ISTB1, Valve Basis-Containment Spray System; Revision 07

-

SD-22A; System Description for Containment Spray; Revision 03 1R05 Fire Protection

Procedures: -

DB-FP-5; Fire Brigade; Revision 5 -

DB-OP-2529; Abnormal Procedure-Fire Procedure; Revision 5 -

NG-DB-302; DBNPS Fire Protection Program; Revision 6 -

NT-OT-7007; Fire Brigade Training; Revision 7

-

PFP-AB-318;; Diesel Generator 1-1 Room, Rooms 318 and 318UL, Fire Area K; Revision 6 -

PFP-AB-319;

Diesel Generator 1-2 Room, Rooms 319 and 319A, Fire Area J; Revision 6 -

PFP-AB-402; No. 1 Electrical Penetration Room, Room 402, Fire Area DG; Revision 4 Drawings: - A-0223F; Fire Protection General Floor Plan, Elev. 585'-0"; Revision 20

- A-0224F; Fire Protection General Floor Plan, Elev. 603'-0"; Revision 22 - A-0225F; Fire Protection General Floor Plan, Elev. 623'-0"; Revision 16

Other: - Fire Brigade Drill Evaluation; Second Quarter 2009 Day shift; 5/12/09

- EP Evaluated Exercise Debrief Report; 5/12/09 - Fire Hazard Analysis Report

1R06 Flooding

Condition Reports: -

CR 05-3342;

IN 2005-11 Internal Flooding/Spray-Down of SR Equipment

-

CR 07-24837; Decay Heat Exchanger Pit (Room 113) Floor Drain Approximately 1/4 Blocked Procedures: -

RA-EP-2880; Internal Flooding; Revision 3 Drawings: -

C-1594; Barrier Functional List; Revision 3

- M-174; Auxiliary Building Plan El 545' & Partial Plans; Revision 19 - M-175; Auxiliary Building Details, Notes and Symbols; Revision 9

Attachment Work Orders: -

200188136;

PM 5773 P89-2A Clean ECCS Room Sump -

200221300;

PM 5774 P89-3A Clean ECCS Sump 3 Pump A -

20022165;

IN 05-11, Internal Flooding and Spray Down of Components Calculations: - 15.50; Fire Suppression System Impact on Auxiliary Building Flooding; Revision 1

- 58.10; Flow Rate Due to a Crack in Make-Up Pump Discharge; Revision 3 - 58.20; Flooding in ECCS Rooms due to a Feedwater Line Break; Revision 1 - 58.20, Addendum A01; Flooding in ECCS Rooms due to a Feedwater Line Break; Revision 1 Other: - Notification

600262473; Identify Credited Floor Drains in Auxiliary Building

- Notification

600405113; Clean Floor Drains in Room 113 - Notification

600428715; Clean Floor Drains - USAR Sections

3.2.6.7.2 (Seismic Class II Fluid Systems) and 9.3.3 (Equipment and Floor Drainage Systems)

1R07 Annual Heat Sink Performance

Condition Reports: -

CR 09-59363; Eddy Current Results on #3 TPCW Heat Exchanger Procedures: -

DB-CH-6013; Station Chlorination System; Revision 27 -

DB-CH-6075; Dechlorination Skid Operations; Revision 1 Work Orders: -

200291418;

PM 6529, TPCW Eddy Current Test 1R11

Licensed Operator Requalification Program

Other: -

DB-S102, OTLC 2009-03; CAC Malfunction, API Failure, and Makeup System Leak; Revision 0 1R12

Maintenance Effectiveness

Condition Reports: -

CR 06-630; Integrated SFRCS Testing:

AF 3869 Did Not Close On Manual SFRCS Signal -

CR 06-2284; 10CFR21 Notification for Prime/Barton DP Instruments -

CR 09-52409; SFRCS Testing Log Entries Not Correct -

CR 09-59278; SFRCS Maintenance Rule Unavailability Accuracy

-

CR 09-56511; DH11 and DH12 Open in Mode 3 Inhibits SFRCS From Opening

MS 106 and

MS 107 -

CR 09-59999; Potential Safety Concern While Drawing Oil Samples From EDG Generator Bearings Attachment Procedures: -

DB-CH-04056; New Diesel Fuel Oil Analysis;

Revision 3 -

DB-MI-3211; Channel Functional Test of SFRCS Actuation Channel 1 Logic for Mode 1; Revision 15 -

DB-MI-3245; Channel Functional Test and Device Calibration of SFRCS Steam Generator Level Inputs 83C-ISLSP9A6, A7, B8 and B9 to Actuation Channel 1; Revision 9 -

DB-MM-09159; EDG and SBODG Starting Air Compressor Maintenance; Revision 2 -

DB-OP-06904; Shutdown Operations; Revision 29 -

DB-PF-3; Maintenance Rule; Revision 8 -

DB-SC-3073; Emergency Diesel Generator 2 Maintenance Surveillance; Revision 3 -

IP-A-008; Emergency Diesel Generator Room Temperature Monitoring; Revision 0

-

NOP-ER-3004; FENOC Maintenance Rule Program; Revision 1 -

NOP-LP-2001; Corrective Action Program; Revision

21 -

NOP-OP-1007; Risk Determination; Revision 5 Work Orders: - Notification

600344870; Inspect Bellows for Damage - Notification

600326832; Replace due to Excessive Number of Calibrations -

WO 200283215; Replace Relays SFRCS Train 1

-

WO 200324708;

PM 8151 Replace Switch Drawings: -

OS-41A; Emergency Diesel Generator Systems; Revision 20 -

OS-41B; Emergency Diesel Generator Air Start / Engine Air System; Revision 26 -

OS-41C; Emergency Diesel Generator Diesel Oil System; Revision 14 Other: - Maintenance Rule Unavailability Database - Maintenance Rule Program Manual; Revision 26 - M-180Q; Technical Specification for Operational Phase for Emergency Diesel Generators for Davis Besse Nuclear Power Station; Revision 1 - Plant Health Report; Fourth Quarter 2008 -

SD-3B; System Description for Emergency Diesel Generators and Station Blackout Diesel Generator; Revision 5 -

SD-10; Steam and Feedwater Line Rupture Control System Description; Revision 5 - USAR Section 7.4.1.3; Steam and Feedwater Line Rupture Control System (SFRCS)

- USAR Section 8.3.1.1.4.1; Emergency Diesel Generators

1R13

Maintenance Risk Assessments and Emergent Work Control

Condition Reports: -

CR 07-31982; Failure of Lemoyne Line CCPD Caused Entry Into Tech Spec 3.8.1.1 Action A -

CR 08-34376; Bayshore Line CCPD Failure Trending Only Condition Report

-

CR 08-32881; ER Template Incorrectly Implemented -

CR 09-56734; Rod 5-8 Position indication is erratic and causing asymmetric alarm -

CR 09-56724; Indication for PORV open status did not respond as expected -

CR 09-56725; Steam generator fill/soak/drains terminated prior to meeting chemistry specs -

CR 09-56688; CRD Group 4 rods did not transfer to AUX -

CR 09-57462; Rod B-6 (Safety Group 4) jumping 0-20% -

CR 09-57475; Steam Leak at MS762

-

CR 09-57501; Reactor startup stopped due to anticipated critical rod index less than limit Attachment -

CR 09-57699; Plant Transient During Control Valve Testing,

DB-SS-4151 -

CR 09-61025; Loss of J Bus, Catastrophic Failure of J Bus B Phase Potential Device -

CR 09-61115; Transitory Alert Emergency Classification Following Loss of J Bus -

CR 09-61038; DB Security to Critique Opportunities for Improvement On Response to Switchyard Event -

CR 09-61112;

RA-EP-01500 Procedure Requires Additional Guidance Procedures: -

DB-ME-5501; Start-Up Transformer X01 Tap Changes; Revision 2 -

DB-ME-5502; Start-Up Transformer X02 Tap Changes; Revision 2 -

DB-OP-6002; RCS Draining and Nitrogen Blanketing; Revision 16 -

DB-OP-6900; Plant Heatup; Revision 43

-

DB-OP-6901; Plant Startup; Revision 31 -

DB-OP-6904; Shutdown Operations; Revision 29 -

DB-OP-6912; Approach to Criticality; Revision 11 -

DB-SS-4151; Main Turbine Control Valve Test; Revision 8 -

NG-DB-00117; Shutdown Defense in Depth Assessment; Revision 02 -

NOP-OP-1006; Shutdown Defense in Depth; Revision 10 -

NOP-OP-1007; Risk Determination; Revision 05 Other: - Drawing

OS 56, Sheet 1; 345 KV System; Revision 7 - Event Notification 45162; Davis-Besse: Discovery of an After-the-Fact Alert Due to Catastrophic Failure of CCPD - FirstEnergy Switching Order - Davis-Besse 345 KV J-Bus; June 25, 2009; Revision 3

- Operations Evolution Order; Recovery from Turbine Control Valve Testing; April 23, 2009 - Unit Logs; Night Shift; June 25, 2009 - Weekly Maintenance Risk Summary: Week of June 22, 2009; Revision 1 and 2

1R15

Operability Evaluations

Condition Reports: -

CR 09-52766; Nuclear Fuel:

Reactor Core Axial Power Imbalance Predicted Versus Measured -

CR 09-57560; Failure of NSSDATA Program -

CR 09-57730; Incores Non-Functional Due to NAS Issues Procedures: -

DB-MI-5255; Nuclear Instrument

NI 08 (RPS CH 3) Power Range Adjustment; Revision 9 -

DB-MM-9118; EDG Governor Removal, Installation, and Adjustment; Revision 8 -

DB-NE-3230; RPS Daily Heat Balance Check; Revision 14 -

DB-NE-3231; RPS Monthly Imbalance Check; Revision 3 -

DB-NE-3233; Incore Instrument Channel Check; Revision 3

-

DB-NE-4220; Imbalance, Tilt, and Rod Index Calcs - Group 38 Alarms; Revision 0 -

DB-OP-2044; Emergency Diesel Generator 2 Alarm Panel 44 Annunciators; Revision 6 -

DB-OP-6316; Diesel Generator Operating Procedure; Revision 41 -

DB-SC-3081; Emergency Diesel Generator 2 Overspeed Trip Test; Revision 5

Attachment Work Orders: -

200343124; Incore Instrumentation Channel Check -

200354500; Imbalance, Tilt, and Rod Index Calculation -

200367012; Imbalance, Tilt, and Rod Index Calculation -

200367069; Imbalance, Tilt, and Rod Index Calculation -

200367070; Imbalance, Tilt, and Rod Index Calculation Drawings: - M-180Q-14; Schematic Diagram Engine Control; Revision N Other: - Cycle 16 Outage Log; April 21, 2009 - Operator Logs; April 21, 2009

- Operator Logs; April 22, 2009 - Operator Logs; April 23, 2009 - Operator Required Reading; Control of #2 Emergency Diesel Generator If In the Hydraulic Mode for the Governor; March 9, 2009 - System Description 3B; Emergency Diesel Generators; Revision 5 1R18

Plant Modifications

Condition Reports: -

CR 09-57699; Plant Transient During Control Valve Testing,

DB-SS-4151 -

CR 09-59382; First Stage Pressure Feedback Signal Reversed at EHC Cabinet After Implementing ECP Procedures: -

DB-SS-4151; Main Turbine Control Valve Test; Revision 9

Work Orders: -

2003367857; Transmitter Will Not Calibrate Drawings: - M-3B, Sheet 2; Main Steam and Reheat System; Revision 23 Other: - Computer Group Trend; Core and Generated Power with High Pressure Steam Chest Pressure; June 6, 2009 -

ECP 09-0394-000; Pressure Transmitter PT2374A; Revision 0 -

ECP 09-0394-001; Replace Pressure Transmitter PT2374A; Revision 0

- M-7201; Instrument Index; Revision 50 -

NEI 96-07; Guidelines for 10

CFR 50.59 Implementation; Revision 1 1R19

Post-Maintenance Testing

Condition Reports: -

CR 08-40248; DH1A Removed From #2 DH Loop Outage at T+01 Work Week -

CR 09-56424; Lower Bearing on Drive Sleeve Assembly Found Damaged

-

CR 09-56980; MS100 Failed to Open -

CR 09-57272; MS100 Main Steam Line 2 Isolation Valve Failed to Fully Open -

CR 09-57234; As Found Condition - MS100

Attachment -

CR 09-59954; SFAS Ouput Module L311 Did Not Indicate Proper Block/Releasing During Testing -

CR 09-59839; EDG 2 DA31 Side Air Motor Abutment During Idle Start -

CR 09-59860; PI2994 Slow to Respond Following Restoration of #2 EDG 2-2 Air Start Side -

CR 09-60065; Order to Troubleshoot and Repair SFAS L311 Did Not Include LCO 3.0.5 Details (NRC Identified) Drawings: - OS 2, Sheet 1; Makeup and Purification System; Revision 28 - OS 2, Sheet 3; Makeup and Purification System; Revision 30 - OS 2, Sheet 4; Makeup and Purification System; Revision 20 Procedures: -

DB-MI-3135; Response Time Test of 64B-ISPRC02B4 Reactor Coolant Loop 1 Hot Leg Wide Range Pressure SFAS Channel 1; Revision 9 -

DB-OP-6006; Makeup and Purification System; Revision 24 -

DB-PF-03272; Post Maintenance Valve Test; Revision 6 -

DB-SC-3071; Emergency Diesel Generator 2 Monthly Test; Revision 20 -

DB-SC-3110; SFAS Channel 1 Functional Test; Revision 18 -

DB-SP-3137; Decay Heat Train 2 Pump and Valve Test; Revision 21

-

DB-SP-3376; Quarterly Makeup Pump 2 Inservice Test and Inspection; Revision 11 -

DB-SP-3444; SFRCS Channel 1 Trip of MS100 and MS101; Revision 8 -

DB-SP-3445; SFRCS Channel 2 Trip of MS100 and MS101; Revision 9 -

DB-SS-4005; Main Steam Isolation Valve Air Leak Test; Revision 3

Work Orders: -

200007526;

ECP 02-197-00 - Replace Valve CC130 -

200238472; DH56 - Replace Valve -

200282723; DH1A Actuator Relube -

200265448; Replace EDG Air Reciever 1-2-1 Pressure Regulator Valve -

200364040; DH00001A Post Maintenance Test

-

200359612; Calibrate MU Pump 2 Lube Oil Pressure Switches -

200365506; FV100 Rebuild Actuator/MS100 Rebuild -

200372040; SFAS Channel 1 Output Module L311 Inoperable Other: -

ECR 05-0299-00; D117, D217 Wiring Changes; Revision 0

-

EDB-SUB049-02-006; Clearance - LP Injection 2 Valve Motor -

EWR 02-197-00; Replace Valve CC130 With an Equivalent Valve; Revision 1 - Operation Evolution Order; Drain DH Pump 2 to Replace DH56 1R20 Outage Activities Condition Reports: - 09-57462; Rod B-6 Relative Position Indication Not Working Correctly - 09-57501; Reactor Startup Stopped Due to Anticipated Critical Rod Index Less Than Limit Procedures: -

DB-OP-1101; Containment Entry; Revision 8 -

DB-OP-6301; Generator and Exciter Operating Procedure; Revision 21 -

DB-OP-6900; Plant Heatup; Revision 42

Attachment -

DB-OP-6901; Plant Startup; Revision 31 -

DB-OP-6902; Power Operations; Revision 25 -

DB-OP-6903; Plant Cooldown; Revision 32 -

DB-OP-6904; Shutdown Operations; Revision 29 -

DB-OP-6912; Approach to Criticality; Revision 11 -

DBBP-ESAF-1015; Industrial Safety Requirements for Containment Entry; Revision 14

-

NG-DB-117; Shutdown Defense In Depth Assessment; Revision 2 -

NOP-OP-1005; Shutdown Defense in Depth; Revision 10 -

NOP-OP-1007; Risk Determination; Revision 5 Other: - Plant Manager

Memorandum; Enumeration of "Infrequently Performed Tests or Evolutions;" March 23, 2009 - Shutdown Defense in Depth Report; April 2, 2009 and Revision 1 dated April 13, 2009 - Outage Control Center Shift Turnover Reports; April 4, 2009 through April 21, 2009 - Operations Evolution Order; Use of

DB-OP-6900 Series Procedures for Pressurizer Code Safety Outage; April 3, 2009 - Cycle 16 Code Safety Outage Containment Entry Plan; Not Dated - Reactivity Plan Review Package; Power Increase After Outage; April 9, 2009

Other: - Contingency Plan 4/9-1; RCS Drain to 250 Inches Pressurizer Level Without an Adequate RCS Vent Path; Revision 0 1R22 Surveillance Testing Condition Reports: -

CR 09-56991; Debris in containment (NRC Identified) -

CR 09-56964; Ctmt closeout inspection -

CR 09-56967;

OP 3013 Containment close out deficiencies -

CR 09-57167; Broken glass under 1-2 RCP -

CR 09-57203;

DB-OP-03013 Daily ctmt inspection results

-

CR 09-57208; Concern Noted by NRC during ctmt walkdown -

CR 09-57300;

DB-PA-09-02 Post-closeout ctmt debris Procedures: -

DBBP-DBTS-2; Use of Leak Rate Monitor Test Equipment; Revision 0 -

DB-OP-3013; Containment Inspection and Containment Closeout Inspection; Revision 5

-

DB-PF-3008; Containment Local Leakage Rate Tests; Revision 12 -

DB-PF-6703; Miscellaneous Operation Curves; Revision 14 -

DB-SC-3077; Emergency Diesel Generator 2 184 Day Test; Revision 17 -

DB-SP-3357; RCS Water Inventory Balance; Revision 14 Work Orders: -

200360382; Perform PF3008-142 05.500 CV5007 Other: - Operations Standing Order 09-3; Guidance for Evaluating PZR Quench Tank In-Leakage Values; Revision 0 - Containment Leakage Rate Testing Program; Revision 6

Attachment 1EP6 Drill Evaluation

Condition Reports: -

CR 09-57200; EP Drill-Issuance of emergency dosimetry for dry run -

CR 09-57267; EP Drill-No depth of experience for rad protection players in medical response -

CR 09-57299; EP Drill-Site Condition Board not understood or updated -

CR 09-57301; EP Drill-Dry run exercise: Discrepancies in EAL Reference Manual

-

CR 09-57302; EP Drill-Simulated Injured Individual did not exit protected area as required -

CR 09-57305; EP Drill-Ambulance arrival on site not communicated effectively -

CR 09-57311; EP Drill-Delayed station alarm for Site Area Emergency -

CR 09-57312; EP Drill-Evaluate use of SSN when issuing dosimetry -

CR 09-57315; EP Drill-PA Accountability Request performed without Emergency Director input -

CR 09-57318; EP Drill-Posting background radiological data with no release in progress

Other: - Davis-Besse Emergency Preparedness Integrated Drill Manual; April 14, 2009 -

NEI 99-02; Regulatory Assessment Performance Indicator Guideline; Revision 5 - Davis-Besse EP Integrated Drill CTRM Simulator Safety Brief; April 14, 2009

- March 19, 2009 Integrated Drill Lessons Learned; April 9, 2009 4OA1 Performance Indicator Verification

Other: - Select Operator Logs covering the period of April 2008 through March 2009 -

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

- Form

NOBP-LP-4012-44; Initiating Events Cornerstone Indicators; Forms for April 2008 through March 2009

4OA2 Identification and Resolution of Problems Condition Reports: -

CR 09-50977; Cross-Cutting Aspects Precursor Documentation (H.2.C) Trend

-

CR 09-52334;

DB-SA-09-015, Negative/Emerging Trend for Plant Equipment & Reliability Engineering -

CR 09-52403;

DB-SA-09-021, Site Protection IPA Negative/Emerging Trend in Human Performance -

CR 09-52478;

DB-SA-09-007, Chemistry IPA - Negative Trend in Briefing or Communication LTA -

CR 09-52485;

DB-SA-09-007: Chemistry IPA - Negative Trend - Procedure Non-Compliance Category -

CR 09-52734;

CA-SA-09-018 Opportunities From Emerging or Potential Trends -

CR 09-53068;

DB-PA-09-01 Trending of Field Observation Data Needs Improvement

-

CR 09-54569;

CR 08-46981 - AFP Time Delay Unacceptable PM Calibration Trend -

CR 09-56697; AS1934 Failed to Close From Control Room Procedures: -

NOBP-OP-12; Operator Work-Arounds, Burdens, and Control Room Deficiencies -

NOBP-LP-2010; Crest Trending Codes; Revision 8 -

NOP-LP-2001; Corrective Action Program; Revision 21

Attachment Other: - Spreadsheet of Condition Reports; From Period of Approximately September 1, 2009 through May 1, 2009 - Crest Generated List of Recurrent Trending Codes; September 1, 2009 to May 1, 2009 - Davis-Besse Fleet Oversight Quarterly Report; Fourth Quarter 2008 - Davis-Besse Fleet Oversight Quarterly Report; First Quarter 2009

-

DB-SA-09-025; Site Roll-up Integrated Performance Assessment; July 1 to December 31, 2008 -

DB-SA-09-030; Davis-Besse First Quarter Safety Culture Monitoring Assessment; March 31, 2009 -

DB-SA-032; Minor Deficiency Monitoring Semi-Annual Review; March 2009

-

ECP 08-0322-01; Temporary Power Supply to Reactor Sample Panel Fume Hood Blower Motor -

ECP 09-0114-01; Remove Breaker BE2146 Due to Water Intrusion to Allow Restoration of MCC E21A -

ECP 09-0149-001; Restores Electrical Power and Control Power to CT915 (Circ Water Loop 2 Bypass Valve) -

ECP 09-0387-01; Pinhole Leak Near CD72

- Performance Indicator D-RPO-15; Control Room Deficiencies; April 2009 - Performance Indicator D-RPO-16; Operator Workarounds; April 2009 - Performance Indicator D-RPO-17; Operator Burdens; April 2009 - Operator Work-Around/Burden - Identification Forms Database; May 22, 2009 - Operations Loss of Function List; As of May 21, 2009 4OA3 Follow-Up of Events and Notices of Enforcement Discretion Condition Reports: -

CR 09-56828; Debris Removed From LP Condenser Waterbox May Not Correlate to High DP -

CR 09-58059;

PF-04717 Circ Water System Result for Condenser - LP2 Exceeds DP Criteria -

CR 09-58333; Inadvertent Activation of Bay Township EPZ Sirens by County Radio Service Vendor -

CR 09-58714;

RA-EP-420 Does Not Contain Guidance for Reporting Siren Inadvertent Activation -

CR 09-59080; Battery !N Found Below Technical Specification Limit -

CR 09-59296; Adverse Circ Water DP Trend on LP Condenser Outer Loop

-

CR 09-59669; ODMI: Main Condenser Fouling (LP Condenser Outer Loop) Procedures: -

DB-ME-3000; Station Battery and Charger Weekly Surveillance; Revision 19 -

DBRM-RC-0001; Regulatory Reporting Requirements; Revision 3 Other: - Reactor Plant Event Notification Worksheet; April 30, 2009 - NRC Event Notification 45032; Offsite Notifications Made Due To Inadvertent Actuation of Six EPZ Sirens - Problem Solving Plan, Main Condenser Water Box Differential Pressure; June 19, 2009 - Operational Decision Making Instrument, Main Condenser Water Box Fouling ; May 27, 2009 - Circulating Water System Enhanced Biocide Pan-Main Condenser Water Box Differential Pressure; June 2009

Attachment 4OA5 Other Activities

Other: -

DB-PA-09-01; Fleet Oversight Quarterly Report, First Quarter - 2009

Attachment