IR 05000424/2005005

IR 05000424-05-005, IR 05000425-05-005, on 10/01/2005 - 12/31/2005; Vogtle, Units 1 and 2, Routine Integrated Report

ML060300332
Person / Time
Site:	Vogtle
Issue date:	01/30/2005
From:	Widmann M T NRC/RGN-II/DRP/RPB2
To:	Grissette D E Southern Nuclear Operating Co
References
IR-05-005
Download: ML060300332 (22)

Text

January 30, 2005

Southern Nuclear Operating Company, Inc.ATTN:D. E. Grissette, Jr.Vice President - Vogtle ProjectP. O. Box 1295 Birmingham, AL 35201-1295

SUBJECT: VOGTLE ELECTRIC GENERATING PLANT - NRC INTEGRATED INSPECTIONREPORT 05000424/2005005 AND 05000425/2005005

Dear Mr. Grissette:

On December 31, 2005, the U. S. Nuclear Regulatory Commission (NRC) completed aninspection at your Vogtle Electric Generating Plant (VEGP), Units 1 and 2. The enclosed integrated inspection report documents the inspection results, which were discussed on January 11, 2006, with Mr. T. Tynan and other members of your staff.The inspection examined activities conducted under your license as they relate to safety andcompliance 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, itsenclosures, and your response (if any) will be available electronically for public inspection in theNRC Public Document Room or from the Publicly Available Records (PARS) component of theNRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,/RA/Malcolm T. Widmann, ChiefReactor Projects Branch 2 Division of Reactor ProjectsDocket Nos.: 50-424, 50-425License Nos.: NPF-68, NPF-81

Enclosure:

Inspection Report 05000424/2005005 and 05000425/2005005

w/Attachment:

Supplemental Informationcc w/encl: (See page 2)

SNC2cc w/encl:J. T. Gasser Executive Vice President Southern Nuclear Operating Company, Inc.

Electronic Mail DistributionT. E. TynanGeneral Manager, Plant Vogtle Southern Nuclear Operating Company, Inc.

Electronic Mail DistributionN. J. StringfellowManager-Licensing Southern Nuclear Operating Company, Inc.

Electronic Mail DistributionBentina C. TerrySouthern Nuclear Operating Company, Inc.

Bin B-022 P. O. Box 1295 Birmingham, AL 35201-1295Director, Consumers' Utility CounselDivision Governor's Office of Consumer Affairs 2 M. L. King, Jr. Drive Plaza Level East; Suite 356 Atlanta, GA 30334-4600Office of the County CommissionerBurke County Commission Waynesboro, GA 30830Director, Department of Natural Resources205 Butler Street, SE, Suite 1252 Atlanta, GA 30334Manager, Radioactive Materials ProgramDepartment of Natural Resources Electronic Mail DistributionAttorney GeneralLaw Department 132 Judicial Building Atlanta, GA 30334Laurence BergenOglethorpe Power Corporation Electronic Mail DistributionResident ManagerOglethorpe Power Corporation Alvin W. Vogtle Nuclear Plant Electronic Mail DistributionArthur H. Domby, Esq.Troutman Sanders Electronic Mail DistributioinSenior Engineer - Power SupplyMunicipal Electric Authority of Georgia Electronic Mail DistributionReece McAlisterExecutive Secretary Georgia Public Service Commission 244 Washington Street, SW Atlanta, GA 30334Distribution w/encl: (See page 3)

_________________________OFFICERII:DRPRII:DRPRII:DRPRII:DRPRII:DRSRII:DRSRII:DRSSIGNATUREGJM1 by emailBCA1 by emailDSS by emailJAH5 by emailSDR2SDR forJLK1 by emailNAMEGMccoyBAndersonDSimpkinsJHickeyDRoseRBaldwinJKrehDATE01/24/0601/23/0601/23/0601/23/0601/23/0601/23/0601/24/06 E-MAIL COPY? YESNO YESNO YESNO YESNO YESNO YESNO YESNO EnclosureU. S. NUCLEAR REGULATORY COMMISSIONREGION IIDocket Nos.: 50-424, 50-425 License Nos.: NPF-68, NPF-81 Report Nos.:05000424/2005005 and 05000425/2005005 Licensee:Southern Nuclear Operating Company, Inc.Facility:Vogtle Electric Generating Plant, Units 1 and 2Location:7821 River RoadWaynesboro, GA 30830Dates:October 1, 2005 through December 31, 2005 Inspectors:G. McCoy, Senior (Sr.) Resident InspectorB. Anderson, Resident Inspector D. Simpkins, Sr. Resident Inspector, Edwin I. Hatch Nuclear Plant J. Hickey, Resident Inspector, Edwin I. Hatch Nuclear Plant S. Rose, Sr. Operations Engineer (Section 1R11)

R. Baldwin, Sr. Operations Engineer (Section 1R11)

J. Kreh, Emergency Preparedness Inspector (Section 4OA1)Approved by:Malcolm T. Widmann, ChiefReactor Projects Branch 2 Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS

IR 05000424/2005-005, 05000425/2005-005; 10/01/2005 - 12/31/2005; Vogtle ElectricGenerating Plant, Units 1 and 2; routine integrated report.The report covered a three-month period of inspection by resident inspectors, operationsengineers, and an emergency preparedness inspector. The NRC's program for overseeing thesafe operation of commercial nuclear power reactors is described NUREG-1649, "ReactorOversight Process," Revision 3, dated July 2000.A.

NRC-Identified and Self-Revealing Findings

No findings of significance were identified.

B.Licensee-Identified Violations

None.

Enclosure

REPORT DETAILS

Summary of Plant StatusUnit 1 operated at rated thermal power (RTP) until October 17 when the unit tripped due to afeedwater regulating valve failing shut. The unit was restarted on October 19 and operated atfull RTP for the remainder of this report period.Unit 2 started the inspection period in a refueling outage. The unit was restarted on October 14and attained RTP on October 18. On December 9, the unit was shutdown to repair a failed primary boundary weld. The unit was restarted on December 18 and operated at full RTP for the remainder of this report period.1.REACTOR SAFETYCornerstones: Initiating Events, Mitigating Systems, Barrier Integrity1R01Adverse Weather Protectiona.Inspection ScopeSeasonal Readiness Review. The inspectors performed a walkdown of the followingtwo systems to verify they would remain functional during low temperature conditions. The inspectors reviewed preventive maintenance activities associated with heat tracing and freeze protection systems to verify they were appropriately scheduled andcompleted prior to the onset of cold weather. The inspectors reviewed compensatory actions to verify they were implemented for degraded or inoperable heat trace and freeze protection equipment. Additionally, the inspectors reviewed the condition report (CR) database to verify that adverse weather related items were being identified and appropriately resolved. Documents reviewed are listed in the Attachment.*Unit 1 auxiliary feedwater (AFW) system*Unit 2 safety injection (SI) systemb.FindingsNo findings of significance were identified.

1R04 Equipment Alignmenta.Inspection Scope

Partial Walkdown. The inspectors performed partial walkdowns of the following threesystems to verify correct system alignment. The inspectors checked for correct valve and electrical power alignments by comparing positions of valves, switches, and breakers to the procedures and drawings listed in the Attachment. Additionally, the inspectors reviewed the CR database to verify that equipment alignment problems were being identified and appropriately resolved.

2EnclosureUnit 1 train A emergency diesel generator (EDG) during EDG train B maintenanceUnit 2 train B motor driven auxiliary feedwater (MDAFW) and turbine driven auxiliaryfeedwater (TDAFW) during EDG train A maintenanceUnit 1 train A auxiliary component cooling water (ACCW) system during train B ACCWmaintenanceComplete System Walkdown. The inspectors performed a complete walkdown of theUnit 1 nuclear service cooling water (NSCW) system. The inspectors performed a detailed check of valve positions, electrical breaker positions, and operating switch positions to evaluate the operability of the redundant trains or components by comparingthe required position in the system operating procedure to the actual position. Theinspectors also interviewed personnel, reviewed control room logs and CRs to verify that alignment and equipment discrepancies were being identified and appropriately resolved. The documents reviewed are listed in the Attachment.b.FindingsNo findings of significance were identified.

1R05 Fire Protectiona.Inspection ScopeThe inspectors walked down the following nine plant areas to verify the licensee wascontrolling combustible materials and ignition sources as required by procedures

92015-C, Use, Control, and Storage of Flammable/Combustible Materials, and 92020-C, Control of Ignition Sources. The inspectors assessed the observable condition of fire detection, suppression, and protection systems and reviewed the licensee's fireprotection Limiting Condition for Operation log and CR database to verify that the corrective actions for degraded equipment were identified and appropriately prioritized.

The inspectors also reviewed the licensee's fire protection program to verify the requirements of Updated Final Safety Analysis Report (UFSAR) Section 9.5.1, Fire Protection Program, and Appendix 9A, Fire Hazards Analysis, were met. Documents reviewed are listed in the Attachment.Unit 1, train B component cooling water (CCW) pump roomUnit 1, train A and B remote shutdown panel roomsUnit 1, train A and B class 1E 4.16 KV switchgear roomsUnit 2, train A and B SI pump roomsUnit 2, train B EDG and associated day tank roomsUnit 1, train B cable spreading roomUnit 1, train A ESF chiller and filter roomsUnit 2, train B NSCW cooling towerUnit 2, train A NSCW cooling tower 3Enclosureb.FindingsNo findings of significance were identified.

1R11 Licensed Operator Requalificationa.Inspection ScopeResident Quarterly Review.

The inspectors evaluated operator performance on October24, 2005 during licensed operator simulator training as described on Dynamic Simulator Scenario DS-10. The simulator scenario covered operator actions resulting from a total loss of ACCW flow resulting in a manual plant trip and a safety injection due to a subsequent loss of coolant accident. Documents reviewed are listed in the Attachment.

The inspectors specifically assessed the following areas:Correct use of the abnormal and emergency operating proceduresAbility to identify and implement appropriate actions in accordance with therequirements of the Technical SpecificationsClarity and formality of communications in accordance with procedure 10000-C,Conduct of OperationsProper control board manipulations including critical operator actionsQuality of supervisory command and controlEffectiveness of post-evaluation critiqueBiennial Requalification Program Inspection. The inspectors reviewed the facilityoperating history, documentation, interviewed licensee personnel, and observed the administration of simulator operating tests associated with the licensee's operator requalification program to assess the effectiveness of the licensee in implementing requalification requirements of 10 CFR 55. The evaluations were also performed to determine if the licensee effectively implemented operator requalification guidelines established in NUREG-1021, Operator Licensing Examination Standards for PowerReactors, and Inspection Procedure (IP) 71111.11, Licensed Operator Requalification Program. The inspectors also reviewed and evaluated the licensee's simulation facilityfor adequacy for use in operator licensing examinations and observed two operator crews during the performance of the operating tests. Documentation reviewed included written examinations, Job Performance Measures (JPMs), simulator scenarios, licensee procedures, on-shift records, simulator modification request records and performance test records, the feedback process, licensed operator qualification records, remediation plans, watchstanding, and medical records. The records were inspected against the criteria listed in IP 71111.11. Documents reviewed during the inspection are listed in the

.b.FindingsNo findings of significance were identified.

4Enclosure1R12Maintenance Effectivenessa.Inspection ScopeThe inspectors reviewed the following two risk significant systems to assess theeffectiveness of the licensee's handling of equipment performance problems and to verify that the licensee's maintenance efforts met the requirements of 10 CFR 50.65(the Maintenance Rule) and licensee procedure 50028-C, Engineering Maintenance Rule Implementation. The reviews included adequacy of the licensee's failure characterization, establishment of performance criteria or 50.65 (a)(1) performance goals, and adequacy of corrective actions. Other documents reviewed during this inspection incl uded system health reports, the maintenance rule database, andmaintenance work orders (MWOs). Also, the inspectors interviewed system engineersand the maintenance rule coordinator to assess the accuracy of identified performance deficiencies and extent of condition. Documents reviewed are listed in the Attachment.125 Volts Direct Current (VDC) battery chargersResidual Heat Removal (RHR) systemb.FindingsNo findings of significance were identified.

1R13 Maintenance Risk Assessments and Emergent Work Controla.Inspection ScopeThe inspectors reviewed the following five risk significant and emergent work activitiesto verify plant risk was properly assessed by the licensee prior to conducting the work.

The inspectors reviewed risk assessments and risk management controls implemented for these activities to verify they were completed in accordance with procedure 00354-C, Maintenance Scheduling, and 10 CFR 50.65(a)(4). The inspectors also reviewed the CR database to verify that maintenance risk assessment problems were being identified and appropriately resolved.Unit 1 train A sequencer failure Unit 2 train A CCW outageUnit 2 train B NSCW fan replacementUnit 2 slave relay tests Risk evaluation to allow entering Mode 2 for startup following the Unit 2 forced outageb.FindingsNo findings of significance were identified.

5Enclosure1R14Operator Performance During Non-Routine Plant Evolutionsa.Inspection ScopeFor the following two non-routine plant evolutions, the inspectors reviewed the operatingcrew's performance, operator logs, control board indications, and plant computer data to verify that operator response was in accordance with the associated plant procedures. Documents reviewed are listed in the Attachment. Unit 1 reactor trip after the failure of 1FV0510, Loop 2 Main Feed Regulating ValveUnit 2 reactor shutdown and cooldown to repair leak near 2HV8701B, A train RHRupstream suction isolation valve from Loop 1 hot legb.FindingsNo findings of significance were identified.

1R15 Operability Evaluationsa.Inspection ScopeThe inspectors reviewed the following four evaluations to verify they met therequirements of Nuclear Management Procedure (NMP)-GM-002, Corrective Action

Program, and NMP-002-GL02, Corrective Action Program Details and Expectations Guideline. This scope included a review of the technical adequacy of the evaluations, the adequacy of compensatory measures, and the impact on continued plant operation.CR 2005100831, Overtorque condition on 2FV5155, AFW miniflow control valveCR 2005110040, Failure of 2A sequencerCR 2005108771, Erratic bearing temperature indication on the 2B MDAFW pumpCR 2005109313, Leak on seal table flux thimble J-10

b. Findings

No findings of significance were identified.

1R17 Permanent Plant Modificationsa.Inspection ScopeThe inspectors reviewed the following Design Change Package (DCP) to verify therequirements of procedure 58007-C, Design Change Packages, were being met.

The inspectors reviewed the modification to verify it did not degrade the system designbases, licensing bases, or performance capability, and that plant risk was not increasedunnecessarily during implementation of the modification.DCP 2009006401, Diesel Generator K1 and FF Relay Replacement 6Enclosureb.FindingsNo findings of significance were identified.

1R19 Post-Maintenance Testinga.Inspection ScopeThe inspectors either observed post-maintenance testing or reviewed the test results forthe following six maintenance activities to verify that the testing met the requirements ofprocedure 29401-C, Work Order Functional Tests, for ensuring equipment operabilityand functional capability was restored.

The inspectors also reviewed the testprocedures to verify the acceptance criteria was sufficient to meet the Technical Specifications (TS) operability requirements.MWO 20533399, Failure of plant protection card 2TY-421AMWO 20495051, Unit 2 train B AFW pump motor replacementDCP 20190034, TDAFW turbine speed control replacementMWO 20201282, Diesel generator K1 and FF relay replacementMWO 20538861, Repair of Unit 2 train A NSCW fan 1MWO 20534901, Repair of 2PV3000b.FindingsNo findings of significance were identified.

1R20 Refueling and Outage Activitiesa.Inspection ScopeRefueling Outage.

The inspectors performed the inspection activities described belowfor the Unit 2 refueling outage that began on September 17, 2005. The inspectors confirmed that, when the licensee removed equipment from service, thelicensee maintained defense-in-depth commensurate with the outage risk control plan for key safety functions and applicable technical specifications and that configuration changes due to emergent work and unexpected conditions were controlled in accordance with the outage risk control plan. During the outage, the inspectors:*Reviewed reactor coolant system (RCS) pressure, level, and temperature instrumentsto verify that the instruments provided accurate indication and that allowances were made for instrumentation errors.Reviewed the status and configuration of electrical systems to verify that thosesystems met TS requirements and the licensee's outage risk control plan.Observed decay heat removal parameters to verify that t he system was properlyfunctioning and providing cooling to the core.

7EnclosureReviewed system alignments to verify that the flow paths, configurations, andalternative means for inventory addition were consistent with the outage risk planReviewed selected control room operations to verify that the licensee was controllingreactivity in accordance with the technical specifications.Reviewed the outage risk plan to verify that activities, systems, and/or componentswhich could cause unexpected reactivity changes were identified in the outage risk plan and were controlled.Observed licensee control of containment penetrations to verify that the requirementsof the technical specifications were met.Reviewed the licensee's plans for changing plant configurations to verify that technicalspecifications, license conditions, and other requirements, commitments, and administrative procedure prerequisites were met prior to changing plant configurations. Reviewed RCS boundary leakage and the setting of containment integrity. Examined the containment prior to reactor startup to verify that debris had not beenleft which could affect performance of the containment sumps.Forced Outages. For the two forced outages during the inspection period, theinspectors performed the following inspection activities. *Reviewed RCS pressure, level, and temperature instruments to verify that theinstruments provided accurate indication and that allowances were made for instrumentation errors.*Reviewed the status and configuration of electrical systems to verify that thosesystems met TS requirements and the licensee's outage risk control plan.*Observed decay heat removal parameters to verify that the system was properlyfunctioning and providing cooling to the core.*Reviewed selected control room operations to verify that the licensee was controllingreactivity in accordance with the technical specifications.*Reviewed the outage risk plan to verify that activities, systems, and/or components,which could cause unexpected reactivity changes, were identified in the outage risk plan and were controlled.*Observed licensee control of containment penetrations to verify that the requirementsof the technical specifications were met. (Unit 2 only)*Reviewed the licensee's plans for changing plant configurations to verify that technicalspecifications, license conditions, and other requirements, commitments, and administrative procedure prerequisites were met prior to changing plant configurations. *Examined containment prior to reactor startup to verify that debris had not been leftwhich could affect performance of the containment sumps. (Unit 2 only)The two forced outages are described below. Documents reviewed are listed in theAttachment.Unit 1 Main Feedwater Regulating Valve (MFRV) for Loop 2, 1FV0510, failed shutUnit 2 shutdown to investigate increased RCS unidentified leakage and repair a failedRHR suction bypass line weld 8Enclosureb.FindingsNo findings of significance were identified.

1R22 Surveillance Testinga.Inspection ScopeThe inspectors reviewed the following five surveillance test procedures and eitherobserved the testing or reviewed test results to verify that testing was conducted in

accordance with the procedures and that the acceptance criteria adequatelydemonstrated that the equipment was operable. Additionally, the inspectors reviewedthe CR database to verify that the licensee had adequately identified and implementedappropriate corrective actions for surveillance test problems. Surveillance Tests14666-2, train A EDG and engineered safety feature ventilation system (ESFAS) test14667-2, train B EDG and ESFAS test14980B-2, Unit 2 train B EDG operability testIn-Service Test14807-2, MDAFW Pump and Check Valve Inservice and Response Time TestContainment Isolation Valve Test14210-2, Containment building penetration verification testb.FindingsNo findings of significance were identified.

1R23 Temporary Plant Modificationsa.Inspection ScopeThe inspectors evaluated the following two Temporary Modifications (TMs) andassociated 10 CFR 50.59 screening against t

he system design basis documentationand UFSAR to verify that the modifications did not adversely affect the safety functions of important safety systems. Additionally, the inspectors reviewed licensee procedure00307-C, Temporary Modifications, to verify if the modification was properly developed and implemented.TM 20524619, ultrasonic level detectionTM 20542256, temporary freeze seal to allow repair of 2HV8701Bb.FindingsNo findings of significance were identified.

9EnclosureCornerstone: Emergency Preparedness1EP6Drill Evaluationa.Inspection ScopeThe inspectors reviewed Dynamic Scenario #29 and observed the following emergencyresponse activity to verify the licensee was properly classifying emergency events, making the required notifications, and making appropriate protective action recommendations in accordance with procedures 91001-C, Emergency Classification and Implementing Instructions, 91002-C, Emergency Notifications, and 91305-C, Protective Action Guidelines. Additionally, the inspectors reviewed the licensee's critique to verify one was conducted to identify performance weaknesses and improvements.*On October 25, the licensee conducted a simulator exercise involving a major steamline break and a simultaneous failure of the reactor to automatically trip.b.FindingsNo findings of significance were identified.4.OTHER ACTIVITIES4OA1Performance Indicator (PI) Verificationa.Inspection ScopeThe inspection was conducted in accordance with NRC Inspection Procedure 71151,Performance Indicator Verification. The applicable planning standard 10 CFR 50.9 and NEI 99-02, Regulatory Assessment Performance Indicator Guidelines, Revision 3, were used as reference criteria. Cornerstone: Emergency Preparedness*Drill and Exercise Performance (DEP)*Emergency Response Organization (ERO) Drill Participation*Alert Notification System (ANS) ReliabilityThe inspectors reviewed the licensee's procedure for developing the data for the EPPIs. The inspectors examined data reported to the NRC for the period January - June2005. Procedural guidance for reporting PI information and records used by the licensee to identify potential PI occurrences were also reviewed. The inspectors verified the accuracy of the PI for ERO drill and exercise performance through review of asample of drill and event records. The inspectors reviewed selected training records toverify the accuracy of the PI for ERO drill participation for personnel assigned to keypositions in the ERO. The inspectors verified the accuracy of the PI for ANS reliability 10Enclosurethrough review of a sample of the licensee's records of periodic system tests. Documents reviewed are listed in the Attachment.b.FindingsNo findings of significance were identified.4OA2Identification and Resolution of Problems.1Daily Screening of Corrective Action ItemsAs required by Inspection Procedure 71152, Identification and Resolution of Problems, andin order to help identify repetitive equipment failures or specific human performance issues for follow-up, the inspectors performed a daily screening of items entered into the licensee's corrective action program. This review was accomplished by either attending daily screening meetings that briefly discussed major CRs, or accessing the licensee's computerized corrective action database and reviewing each CR that was initiated..2Annual Sample Reviewa.Inspection ScopeThe inspectors performed a detailed review of the following CR to verify the full extent ofthe issue was identified, an appropriate evaluation was performed, and appropriate corrective actions were specified and prioritized. The inspectors evaluated the CR against the licensee's corrective action program as delineated in licensee procedure NMP-GM-002, Corrective Action Program, and 10 CFR 50, Appendix B. Documents reviewed are listed in the Attachment.CR 2005106877, Failure of the K1 relay on the Unit 2 train B diesel generatorb.Findings and ObservationsNo findings of significance were identified..3Semi-Annual Trend Reviewa.Inspection ScopeAs required by Inspection Procedure 71152, Identification and Resolution of Problems,the inspectors performed a review of the licensee's Corrective Action Program (CAP)and associated documents to identify trends, which could indicate the existence of a more significant safety issue. The inspector's review was focused on repetitive equipment issues, but also considered the results of daily inspector CR item screening discussed in section 4OA2.1, licensee trending efforts, and licensee human performance results. The inspector's review nominally considered the six month period of June 2005 through December 2005, although some examples extended beyond 11Enclosurethose dates when the scope of the trend warranted. Inspectors also reviewed severalCRs associated with operability determinations, which occurred during the period. Theinspectors compared and contrasted their results with the results contained in the licensees two latest quarterly trend reports. Corrective actions associated with a sample of the issues identified in the licensee's trend reports were reviewed for adequacy. The inspectors also evaluated the trend reports against the requirements of the licensee's corrective action program as specified in licensee procedure NMP-GM-002, Corrective Action Program, and 10 CFR 50, Appendix B.b.Findings and ObservationsNo findings of significance were identified.4OA3Event Follow-upa.Inspection ScopeUnit 1 Reactor Trip. The inspectors reviewed the licensee's actions associated with thereactor trip that occurred on October 17. The inspectors observed plant parameters for mitigating systems and fission product barriers, evaluated performance of systems andoperators, and confirmed the proper classification and reporting of the event.

Documents reviewed are listed in the Attachment.b.FindingsNo findings of significance were identified.4OA6Meetings, Including ExitOn January 11, 2006, the resident inspectors presented the inspection results to Mr. T.Tynan and other members of his staff, who acknowledged the findings. The inspectors confirmed that proprietary information was not provided or examined during the inspection.ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

R. Brown, Training and Emergency Preparedness Manager

C. Buck, Chemistry Manager

J. Robinson, Operations Manager

K. Dyar, Security Manager

T. Tynan, Nuclear Plant General Manager

I. Kochery, Health Physics Manager

J. Williams, Assistant General Manager - Plant Support

S. Swanson, Engineering Support Manager

R. Dedrickson, Assistant General Manager - Operations

NRC personnel

M. Widmann, Chief, Region II Reactor Project Branch 2

Section 1R01:

Adverse Weather ProtectionProcedures11877-1/2, Cold Weather Checklist11901-1/2, Heat Tracing System Alignment

13901-1/2, Heat Tracing System

50050-C, Heat Tracing Program

CR 2005107217

Section 1R04:

Equipment AlignmentProcedures14980A-1, Diesel Generator 1A Operability Test11145-1, Diesel Generator Alignment

11146-1, Diesel Generator Fuel Oil Transfer System Alignment

13610-2, Auxiliary Feedwater System11610-2, Auxiliary Feedwater System Alignment11716-1, Auxiliary Component Cooling Water System Alignment13716-1, Auxiliary Component Cooling Water System11150-1, Nuclear Service Cooling Water System AlignmentDrawings1X4DB170-1, P&I Diagram Generator System Train A2X4DB161-1, P&I Diagram Aux Feedwater System Condensate Storage and Degasifier System

2X4DB161-2, P&I Diagram Aux Feedwater System

2X4DB161-3, P&I Diagram Aux Feedwater System Aux Feedwater Pump Turbine Driver

1X4DB138, Aux Component Cooling Water System

1X4DB133-1, 2, P&I Diagram, NCSW System

1X4DB134, P&I Diagram, NCSW System

1X4DB135-1, 2, P&I Diagram, NCSW System

AX4DD300, Plot Plan

A-2Attachment1X4DE315, Equipment Location Layout, Unit 1 Aux Bldg level 21X4DE316, Equipment Location Layout, Unit 1 AFW Pumphouse and CST

1X4DE317, Equipment Location Layout, Unit 1 Containment, Control and Fuel Handling Bldg,level 11X4DE318, Equipment Location Layout, Unit 1 Aux Bldg level 1

1X4DE320, Equipment Location Layout, Unit 1 Containment, Control and Fuel Handling Bldg,level A1X4DE321, Equipment Location Layout, Unit 1 Aux Bldg level A

1X4DE322, Equipment Location Layout, Unit 1 Containment, Control and Fuel Handling Bldg,level B1X4DE323, Equipment Location Layout, Unit 1 Aux Bldg level B

1X4DE324, Equipment Location Layout, Unit 1 Aux Bldg level C

1X4DE325, Equipment Location Layout, Unit 1 Aux Bldg level D

1X4DE327, Equipment Location Layout, Unit 1 Diesel Generator Bldg.

1X4DE330, Equipment Location Layout, Unit 1 Diesel Generator Bldg.Other DocumentsCondition Report 2005107781Work Order 10302403

Caution Tag 1-CA-05-00614

Section 1R05:

Fire ProtectionProcedures92732-1, Zone 32, Auxiliary Building - Level B Fire Fighting Preplan92862-2, Zone 162 Diesel Generator Building Fire Fighting Preplan

2864-2, Zone 164 Diesel Generator Building, Train B DFO Day Tank Fire Fighting Preplan

2792-1, Zone 92 Control Building Level A Fire Fighting Preplan

2791-1, Zone 91 Control Building Level A Fire Fighting Preplan

2798-1, Zone 98 Control Building Level A Fire Fighting Preplan

2803-1, Zone 103 Control Building Level A Fire Fighting Preplan

2737-1, Zone 37 Auxiliary Building Level A Fire Fighting Preplan92820-1, Zone 120 Control Building Level 2 Fire Fighting Preplan

2826A-1, Zone 126A Control Building Level 3 Fire Fighting Preplan

2860B-2, Zone 160B - NSCW Pumphouse - Train B Fire Fighting Preplan

2860-2, Zone 160A - NSCW Pumphouse - Train A Fire Fighting Preplan

Section 1R11: Licensed Operator RequalificationResident Quarterly ReviewProcedures18001-C, Primary Systems Instrumentation Malfunction19000-C,

E-0 Reactor Trip or Safety Injection

19010-C, E-1 Loss of Reactor or Secondary Coolant

19012-C,

ES-1.2 Post-LOCA Cooldown and Depressurization

91001-C, Emergency Classification and Implementing Instructions

A-3AttachmentBiennial Requalification Program InspectionProcedures00709-C, Training Review Boards and Working Committees, Revision 1500750-C, Systems Approach to Training, Revision 7.0

00715-C, Licensed Operator Requalification Program, Revision 19.2

10010-C, Operator Qualification Program, Revision 29

60001-C, Exam Administration Policy, Revision 13.2

60007-C, Licensed Operator Requlification Examination Guidelines, Revision 12

60008-C, Examination Security Program, Revision 5.0

200-C, Simulator Maintenance Procedure, Revision 11

201-C, Simulator Training & Documentation, Revision 14

203-C, Simulator Certification, Revision 6.1Scenarios:

DS #34, Revision 4, Scenario DS #13, Revision 15Badge Access Transaction Reports for Reactivation of Licenses (3)

Licensed Operator Medical Records (10)

Feedback Summaries Human Performance Errors Written Exams Reviewed: five written exams that were administered for the 2003-2004 biennial requalification exams, weeks 1, 2, 3, 4 and 5.Simulator Performance Testing

Steady State Test 100%, Tested 4/29/04

Transient Test 07-01, Reactor Trip from 100% power BOL, Tested 4/22/04

Transient Test 07-05, Single Reactor Coolant Pump Trip at 20% power, Tested 4/24/04

Transient Test 07-06, Main Turbine Trip W/O a Reactor Trip 35% power, Tested 4/22/04

Malfunction Testing 05-02, LOCA Inside Containment from 100% power hot leg #2

Malfunction Testing 05-10, Loss of Emergency Generators 100% power, EOL, EDG 1A Fails to Start Malfunction Testing 05-34(a), CVCS Makeup & RCS Dilution from CVCS Malfunction

==Section 1R12: Maintenance EffectivenessCRs

2005109045,

2005108628,

2005108459,

2004150610,

2004151434,

2005100901,

2005100909,

2005101276,

2005102076,

2005102859,

2005102894, 2005103849,==

2005107704,

2005108706, 2005109196WOs

20529550,

20529642,

20529835,

20529642,

20530658,

20529835,

10400508,

10404472,

10515679,

10517379,

10517454,

10517701,

10517702,

20101327,

20202075,

20202843,

20404473,

20519191, 20526797Action Items

2005203262,

2005203263,

2005203264,

2005203265,

2005203266,

2005203267,

2005203268,

2005203626,

2005203628,

2005204021, System Health Report, Residual Heat Removal System, 3

rd Quarter 2005System Health Report, 125 VDC System, 1

st Quarter 2005System Health Report, 125 VDC System, 2

nd Quarter 2005System Health Report, 125 VDC System, 3

rd Quarter 2005

A-4AttachmentSection 1R14: Operator Performance During Non-Routine Plant Evolutions12004-C, Power Operation12005-C, Reactor Shutdown to Hot Standby

2006-C, Unit Cooldown to Cold Shutdown

19000-C, E-0 Reactor Trip or Safety Injection

19001-C,

ES-0.1 Reactor Trip Response

Section 1R20:

Refueling and Outage ActivitiesProcedures93663-C, Verification of Core Loading Pattern93300-C, Conduct of Refueling Operations

2005-C, Reactor Shutdown to Hot Standby (Mode 2 to Mode 3)

2006-C, Unit Cooldown to Cold Shutdown

2007-C, Refueling Operations (Entry into Mode 6)

2008-C, Midloop Operations

14900-C, Containment Exit Inspection

Section 4OA1: Performance Indicator (PI) VerificationProcedures, Records, and DataDocumentation package (scenario/time line/event notification forms/critique report) for

ERO drill on 04/28/2005

Documentation package (Control Room log/event time line/critique report) for Notification of Unusual Event (missed) declaration on 03/16/2005

Documentation of DEP opportunities:

Licensed Operator Requalification Simulator Log for

06/13/2005, 06/17/2005, 06/20/2005, 06/27/2005Documentation of offsite siren weekly silent tests, 01/01/2005 - 06/30/2005Records of drill and exercise participation by ERO personnel, 2003-2005

Section 4OA2: Identification and Resolution of ProblemsQuarterly

CAP Trend Report, May through July 2005CR

2005111142,

2005111449,

2005111573,

2005110659,

2005109678, 2005109388,

2005110657,

2005110866,

CR 2005104123

rd Quarter 2005 system health report for the diesel generatorsVendor relay specification sheet, Telemechanique NEMA rated industrial controls

MWOs

20519648,

20525436,

10525503, 10525505

Section 4OA3: Event Follow-upProcedures19000-C,

E-0 Reactor Trip or Safety Injection19001-C,

ES-0.1 Reactor Trip Response

91001-C, Emergency Classification and Implementing Instructions