IR 05000424/2005005
| ML060300332 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/30/2005 |
| From: | Widmann M NRC/RGN-II/DRP/RPB2 |
| To: | Grissette D Southern Nuclear Operating Co |
| References | |
| IR-05-005 | |
| Download: ML060300332 (22) | |
Text
ary 30, 2005
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT - NRC INTEGRATED INSPECTION REPORT 05000424/2005005 AND 05000425/2005005
Dear Mr. Grissette:
On December 31, 2005, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection 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 and compliance with the Commissions 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 NRCs Rules of Practice, a copy of this letter, its enclosures, 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 the NRCs 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, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos.: 50-424, 50-425 License Nos.: NPF-68, NPF-81
Enclosure:
Inspection Report 05000424/2005005 and 05000425/2005005 w/Attachment: Supplemental Information
REGION II==
Docket 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 2 Location: 7821 River Road Waynesboro, GA 30830 Dates: October 1, 2005 through December 31, 2005 Inspectors: G. McCoy, Senior (Sr.) Resident Inspector B. 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, Chief Reactor 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 Electric
Generating Plant, Units 1 and 2; routine integrated report.
The report covered a three-month period of inspection by resident inspectors, operations engineers, and an emergency preparedness inspector. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
NRC-Identified and Self-Revealing Findings
No findings of significance were identified.
Licensee-Identified Violations
None.
REPORT DETAILS
Summary of Plant Status
Unit 1 operated at rated thermal power (RTP) until October 17 when the unit tripped due to a feedwater regulating valve failing shut. The unit was restarted on October 19 and operated at full RTP for the remainder of this report period.
Unit 2 started the inspection period in a refueling outage. The unit was restarted on October 14 and 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.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity
1R01 Adverse Weather Protection
a. Inspection Scope
Seasonal Readiness Review. The inspectors performed a walkdown of the following two 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 and completed 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) system
b. Findings
No findings of significance were identified.
1R04 Equipment Alignment
a. Inspection Scope
Partial Walkdown. The inspectors performed partial walkdowns of the following three systems 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.
C Unit 1 train A emergency diesel generator (EDG) during EDG train B maintenance C Unit 2 train B motor driven auxiliary feedwater (MDAFW) and turbine driven auxiliary feedwater (TDAFW) during EDG train A maintenance C Unit 1 train A auxiliary component cooling water (ACCW) system during train B ACCW maintenance Complete System Walkdown. The inspectors performed a complete walkdown of the Unit 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 comparing the required position in the system operating procedure to the actual position. The inspectors 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. Findings
No findings of significance were identified.
1R05 Fire Protection
a. Inspection Scope
The inspectors walked down the following nine plant areas to verify the licensee was controlling 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 licensees fire protection 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 licensees 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.
C Unit 1, train B component cooling water (CCW) pump room C Unit 1, train A and B remote shutdown panel rooms C Unit 1, train A and B class 1E 4.16 KV switchgear rooms C Unit 2, train A and B SI pump rooms C Unit 2, train B EDG and associated day tank rooms C Unit 1, train B cable spreading room C Unit 1, train A ESF chiller and filter rooms C Unit 2, train B NSCW cooling tower C Unit 2, train A NSCW cooling tower
b. Findings
No findings of significance were identified.
1R11 Licensed Operator Requalification
a. Inspection Scope
Resident Quarterly Review. The inspectors evaluated operator performance on October 24, 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:
C Correct use of the abnormal and emergency operating procedures C Ability to identify and implement appropriate actions in accordance with the requirements of the Technical Specifications C Clarity and formality of communications in accordance with procedure 10000-C, Conduct of Operations C Proper control board manipulations including critical operator actions C Quality of supervisory command and control C Effectiveness of post-evaluation critique Biennial Requalification Program Inspection. The inspectors reviewed the facility operating history, documentation, interviewed licensee personnel, and observed the administration of simulator operating tests associated with the licensees 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 Power Reactors, and Inspection Procedure (IP) 71111.11, Licensed Operator Requalification Program. The inspectors also reviewed and evaluated the licensees simulation facility for 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. Findings
No findings of significance were identified.
1R12 Maintenance Effectiveness
a. Inspection Scope
The inspectors reviewed the following two risk significant systems to assess the effectiveness of the licensees handling of equipment performance problems and to verify that the licensees 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 licensees failure characterization, establishment of performance criteria or 50.65 (a)(1) performance goals, and adequacy of corrective actions. Other documents reviewed during this inspection included system health reports, the maintenance rule database, and maintenance work orders (MWOs). Also, the inspectors interviewed system engineers and the maintenance rule coordinator to assess the accuracy of identified performance deficiencies and extent of condition. Documents reviewed are listed in the Attachment.
C 125 Volts Direct Current (VDC) battery chargers C Residual Heat Removal (RHR) system
b. Findings
No findings of significance were identified.
1R13 Maintenance Risk Assessments and Emergent Work Control
a. Inspection Scope
The inspectors reviewed the following five risk significant and emergent work activities to 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.
C Unit 1 train A sequencer failure C Unit 2 train A CCW outage C Unit 2 train B NSCW fan replacement C Unit 2 slave relay tests C Risk evaluation to allow entering Mode 2 for startup following the Unit 2 forced outage
b. Findings
No findings of significance were identified.
1R14 Operator Performance During Non-Routine Plant Evolutions
a. Inspection Scope
For the following two non-routine plant evolutions, the inspectors reviewed the operating crews 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.
C Unit 1 reactor trip after the failure of 1FV0510, Loop 2 Main Feed Regulating Valve C Unit 2 reactor shutdown and cooldown to repair leak near 2HV8701B, A train RHR upstream suction isolation valve from Loop 1 hot leg
b. Findings
No findings of significance were identified.
1R15 Operability Evaluations
a. Inspection Scope
The inspectors reviewed the following four evaluations to verify they met the requirements 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.
C CR 2005100831, Overtorque condition on 2FV5155, AFW miniflow control valve C CR 2005110040, Failure of 2A sequencer C CR 2005108771, Erratic bearing temperature indication on the 2B MDAFW pump C CR 2005109313, Leak on seal table flux thimble J-10
b. Findings
No findings of significance were identified.
1R17 Permanent Plant Modifications
a. Inspection Scope
The inspectors reviewed the following Design Change Package (DCP) to verify the requirements of procedure 58007-C, Design Change Packages, were being met. The inspectors reviewed the modification to verify it did not degrade the system design bases, licensing bases, or performance capability, and that plant risk was not increased unnecessarily during implementation of the modification.
C DCP 2009006401, Diesel Generator K1 and FF Relay Replacement
b. Findings
No findings of significance were identified.
1R19 Post-Maintenance Testing
a. Inspection Scope
The inspectors either observed post-maintenance testing or reviewed the test results for the following six maintenance activities to verify that the testing met the requirements of procedure 29401-C, Work Order Functional Tests, for ensuring equipment operability and functional capability was restored. The inspectors also reviewed the test procedures to verify the acceptance criteria was sufficient to meet the Technical Specifications (TS) operability requirements.
C MWO 20533399, Failure of plant protection card 2TY-421A C MWO 20495051, Unit 2 train B AFW pump motor replacement C DCP 20190034, TDAFW turbine speed control replacement C MWO 20201282, Diesel generator K1 and FF relay replacement C MWO 20538861, Repair of Unit 2 train A NSCW fan 1 C MWO 20534901, Repair of 2PV3000
b. Findings
No findings of significance were identified.
1R20 Refueling and Outage Activities
a. Inspection Scope
Refueling Outage. The inspectors performed the inspection activities described below for the Unit 2 refueling outage that began on September 17, 2005.
The inspectors confirmed that, when the licensee removed equipment from service, the licensee 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 instruments to verify that the instruments provided accurate indication and that allowances were made for instrumentation errors.
C Reviewed the status and configuration of electrical systems to verify that those systems met TS requirements and the licensees outage risk control plan.
C Observed decay heat removal parameters to verify that the system was properly functioning and providing cooling to the core.
C Reviewed system alignments to verify that the flow paths, configurations, and alternative means for inventory addition were consistent with the outage risk plan C Reviewed selected control room operations to verify that the licensee was controlling reactivity in accordance with the technical specifications.
C 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.
C Observed licensee control of containment penetrations to verify that the requirements of the technical specifications were met.
C Reviewed the licensees plans for changing plant configurations to verify that technical specifications, license conditions, and other requirements, commitments, and administrative procedure prerequisites were met prior to changing plant configurations.
C Reviewed RCS boundary leakage and the setting of containment integrity.
C Examined the containment prior to reactor startup to verify that debris had not been left which could affect performance of the containment sumps.
Forced Outages. For the two forced outages during the inspection period, the inspectors performed the following inspection activities.
- Reviewed RCS pressure, level, and temperature instruments to 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 those systems met TS requirements and the licensees outage risk control plan.
- Observed decay heat removal parameters to verify that the system was properly functioning and providing cooling to the core.
- Reviewed selected control room operations to verify that the licensee was controlling reactivity 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 requirements of the technical specifications were met. (Unit 2 only)
- Reviewed the licensees plans for changing plant configurations to verify that technical specifications, 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 left which could affect performance of the containment sumps. (Unit 2 only)
The two forced outages are described below. Documents reviewed are listed in the
.
C Unit 1 Main Feedwater Regulating Valve (MFRV) for Loop 2, 1FV0510, failed shut C Unit 2 shutdown to investigate increased RCS unidentified leakage and repair a failed RHR suction bypass line weld
b. Findings
No findings of significance were identified.
1R22 Surveillance Testing
a. Inspection Scope
The inspectors reviewed the following five surveillance test procedures and either observed the testing or reviewed test results to verify that testing was conducted in accordance with the procedures and that the acceptance criteria adequately demonstrated that the equipment was operable. Additionally, the inspectors reviewed the CR database to verify that the licensee had adequately identified and implemented appropriate corrective actions for surveillance test problems.
Surveillance Tests C 14666-2, train A EDG and engineered safety feature ventilation system (ESFAS) test C 14667-2, train B EDG and ESFAS test C 14980B-2, Unit 2 train B EDG operability test In-Service Test C 14807-2, MDAFW Pump and Check Valve Inservice and Response Time Test Containment Isolation Valve Test C 14210-2, Containment building penetration verification test
b. Findings
No findings of significance were identified.
1R23 Temporary Plant Modifications
a. Inspection Scope
The inspectors evaluated the following two Temporary Modifications (TMs) and associated 10 CFR 50.59 screening against the system design basis documentation and UFSAR to verify that the modifications did not adversely affect the safety functions of important safety systems. Additionally, the inspectors reviewed licensee procedure 00307-C, Temporary Modifications, to verify if the modification was properly developed and implemented.
C TM 20524619, ultrasonic level detection C TM 20542256, temporary freeze seal to allow repair of 2HV8701B
b. Findings
No findings of significance were identified.
Cornerstone: Emergency Preparedness
1EP6 Drill Evaluation
a. Inspection Scope
The inspectors reviewed Dynamic Scenario #29 and observed the following emergency response 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 licensees critique to verify one was conducted to identify performance weaknesses and improvements.
- On October 25, the licensee conducted a simulator exercise involving a major steam line break and a simultaneous failure of the reactor to automatically trip.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification
a. Inspection Scope
The 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) Reliability The inspectors reviewed the licensees procedure for developing the data for the EP PIs. The inspectors examined data reported to the NRC for the period January - June 2005. 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 a sample of drill and event records. The inspectors reviewed selected training records to verify the accuracy of the PI for ERO drill participation for personnel assigned to key positions in the ERO. The inspectors verified the accuracy of the PI for ANS reliability through review of a sample of the licensees records of periodic system tests.
Documents reviewed are listed in the Attachment.
b. Findings
No findings of significance were identified.
4OA2 Identification and Resolution of Problems
.1 Daily Screening of Corrective Action Items
As required by Inspection Procedure 71152, Identification and Resolution of Problems, and in 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 licensees corrective action program. This review was accomplished by either attending daily screening meetings that briefly discussed major CRs, or accessing the licensees computerized corrective action database and reviewing each CR that was initiated.
.2 Annual Sample Review
a. Inspection Scope
The inspectors performed a detailed review of the following CR to verify the full extent of the issue was identified, an appropriate evaluation was performed, and appropriate corrective actions were specified and prioritized. The inspectors evaluated the CR against the licensees 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.
C CR 2005106877, Failure of the K1 relay on the Unit 2 train B diesel generator
b. Findings and Observations
No findings of significance were identified.
.3 Semi-Annual Trend Review
a. Inspection Scope
As required by Inspection Procedure 71152, Identification and Resolution of Problems, the inspectors performed a review of the licensees Corrective Action Program (CAP)and associated documents to identify trends, which could indicate the existence of a more significant safety issue. The inspectors 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 inspectors review nominally considered the six month period of June 2005 through December 2005, although some examples extended beyond those dates when the scope of the trend warranted. Inspectors also reviewed several CRs associated with operability determinations, which occurred during the period. The inspectors 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 licensees trend reports were reviewed for adequacy. The inspectors also evaluated the trend reports against the requirements of the licensees corrective action program as specified in licensee procedure NMP-GM-002, Corrective Action Program, and 10 CFR 50, Appendix B.
b. Findings and Observations
No findings of significance were identified.
4OA3 Event Follow-up
a. Inspection Scope
Unit 1 Reactor Trip. The inspectors reviewed the licensees actions associated with the reactor trip that occurred on October 17. The inspectors observed plant parameters for mitigating systems and fission product barriers, evaluated performance of systems and operators, and confirmed the proper classification and reporting of the event.
Documents reviewed are listed in the Attachment.
b. Findings
No findings of significance were identified.
4OA6 Meetings, Including Exit
On 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