IR 05000424/2009002
| ML091200371 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/30/2009 |
| From: | Scott Shaeffer NRC/RGN-II/DRP/RPB2 |
| To: | Tynan T Southern Nuclear Operating Co |
| References | |
| IR-09-002 | |
| Download: ML091200371 (23) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
SAM NUNN ATLANTA FEDERAL CENTER 61 FORSYTH STREET, SW, SUITE 23T85 ATLANTA, GEORGIA 30303-8931 April 30, 2009 Mr. Tom E. Tynan Vice President Southern Nuclear Operating Company, Inc.
Vogtle Electric Generating Plant 7821 River Road Waynesboro, GA 30830 SUBJECT: VOGTLE ELECTRIC GENERATING PLANT - NRC INTEGRATED INSPECTION REPORT 05000424/2009002 AND 05000425/2009002 AND MEETING
SUMMARY
Dear Mr. Tynan:
On, March 31 2009, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Vogtle Electric Generating Plant, Units 1 and 2. The enclosed integrated inspection report documents the inspection findings, which were discussed on April 29, 2009, with Mr. C. R.
Dedrickson 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 the Code of Federal Regulations 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/
Scott M. Shaeffer, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos.: 50-424, 50-425 License Nos.: NPF-68 and NPF-81 Enclosures: Inspection Report 05000424/2009002 and 05000429/2009002 w/Attachment: 1. SUPPLEMENTAL INFORMATION 2. PUBLIC OUTREACH MEETING MATERIAL cc w/encl: (See page 2)
_________________________ X SUNSI REVIEW COMPLETE SMS OFFICE RII/DRP RII/DRP RII/DRP RII/DRP RII/DRP SIGNATURE SMS /RA/ via email SMS /RA for/ SMS /RA for/ EDM /RA/
NAME S. Shaeffer L. Cain T. Chandler T. Lighty E. Morris DATE 04/30/2009 04/30/2009 04/30/2009 04/30/2009 04/30/2009 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
SNC 2 cc w/encl: Dr. Carol Couch Angela Thornhill Director Managing Attorney and Compliance Officer Environmental Protection Southern Nuclear Operating Company, Inc. Department of Natural Resources Electronic Mail Distribution Electronic Mail Distribution N. J. Stringfellow Cynthia Sanders Manager Program Manager Licensing Radioactive Materials Program Southern Nuclear Operating Company, Inc. Department of Natural Resources Electronic Mail Distribution Electronic Mail Distribution Jeffrey T. Gasser Jim Sommerville Executive Vice President (Acting) Chief Southern Nuclear Operating Company, Inc. Environmental Protection Division Electronic Mail Distribution Department of Natural Resources Electronic Mail Distribution L. Mike Stinson Vice President Mr. Steven M. Jackson Fleet Operations Support Senior Engineer - Power Supply Southern Nuclear Operating Company, Inc. Municipal Electric Authority of Georgia Electronic Mail Distribution Electronic Mail Distribution Michael A. MacFarlane Mr. Reece McAlister Southern Nuclear Operating Company, Inc. Executive Secretary 40 Inverness Center Parkway Georgia Public Service Commission P.O. Box 1295 Electronic Mail Distribution Birmingham, AL 35201-1295 Office of the Attorney General David H. Jones Electronic Mail Distribution Vice President Engineering Office of the County Commissioner Southern Nuclear Operating Company, Inc. Burke County Commission Electronic Mail Distribution Electronic Mail Distribution Bob Masse Mr. N. Holcomb Resident Manager Commissioner Vogtle Electric Generating Plant Department of Natural Resources Oglethorpe Power Corporation Electronic Mail Distribution Electronic Mail Distribution Director Moanica Caston Consumers' Utility Counsel Division Vice President and General Counsel Govenor's Office of Consumer Affairs Southern Nuclear Operating Company, Inc. 2 M. L. King, Jr. Drive Electronic Mail Distribution Plaza Level East; Suite 356 Atlanta, GA 30334-4600 Lee Foley Manager of Contracts Generation Susan E. Jenkins Oglethorpe Power Corporation Director, Division of Waste Management Electronic Mail Distribution Bureau of Land and Waste Management S.C. Department of Health and Arthur H. Domby, Esq. Environmental Control Troutman Sanders Electronic Mail Distribution Electronic Mail Distribution
SNC 3 Letter to Tom E. Tynan from Scott M. Shaeffer dated April 30, 2009 SUBJECT: VOGTLE ELECTRIC GENERATING PLANT - NRC INTEGRATED INSPECTION REPORT 05000424/2009002 AND 05000425/2009002 AND MEETING SUMMARY Distribution w/encl:
C. Evans, RII L. Slack, RII OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMVogtle Resource
U. S. NUCLEAR REGULATORY COMMISSION REGION II Docket Nos.: 50-424, 50-425 License Nos.: NPF-68, NPF-81 Report Nos.: 05000424/2009002 and 05000425/2009002 Licensee: Southern Nuclear Operating Company, Inc. (SNC)
Facility: Vogtle Electric Generating Plant, Units 1 and 2 Location: Waynesboro, GA 30830 Dates: January 1, 2009 through March 31, 2009 Inspectors: L. Cain, Senior Resident Inspector E. Morris, Acting Senior Resident Inspector T. Chandler, Resident Inspector Approved by: Scott M. Shaeffer, Chief Reactor Projects Branch 2 Division of Reactor Projects
SUMMARY OF FINDINGS IR 05000424/2009-002, 05000425/2009-002; 1/01/2009 - 3/31/2009; Vogtle Electric Generating Plant, Units 1 and 2; Routine Integrated Inspection Report The report covered a three-month period of inspection by three resident inspectors. No findings of significance were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Rev 4 dated December 2006.
REPORT DETAILS
Summary of Plant Status
Unit 1 operated at full rated thermal power for the entire inspection period.
Unit 2 operated at essentially full rated thermal power for the entire inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity
1R01 Adverse Weather Protection
a. Inspection Scope
Impending Adverse Weather Condition Review. During the week of January 12-16, the inspectors reviewed licensee procedure 11877-1 and 11877-2, Cold Weather Checklist, to verify the licensee had implemented actions to prepare the plant site for predicted severe weather conditions of sub-freezing temperatures. The inspectors walked down various safety-significant areas of the plant to verify the licensees ability to respond to the predicted adverse weather conditions.
b. Findings
No findings of significance were identified.
1R04 Equipment Alignment
a. Inspection Scope
Partial System 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 documents listed in the Attachment. Additionally, the inspectors reviewed the condition report database to verify that equipment alignment problems were being identified and appropriately resolved.
C 1A emergency diesel generator (EDG) during the 1B EDG outage C 1A control building engineered safeguards features (ESF) ventilation system during the 1B system outage C 2A residual heat removal (RHR) system during 2B RHR system outage Complete System Walkdown. The inspectors performed a complete walkdown of the Unit 1 train A 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 reviewed control room logs, condition reports, and system health reports 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
Fire Drill Observation. On February 18, inspectors observed a fire drill from the control room, the primary fire brigade locker, and the fire scene. The fire was simulated to be in the 2A EDG building. The inspectors assessed the adequacy of the fire drill and fire brigade response using licensee procedures 92000-C, Fire Protection Program; 92005-C, Fire Response Procedure; NMP-TR-425, Fire Drill Program; 92861-2, Zone 160 -
Diesel Generator Building Fire Fighting Preplan; and 17103A-C, Annunciator Response Procedures for the Fire Alarm Computer. The inspectors evaluated the fire brigade performance to verify that they responded to the fire in a timely manner, donned proper protective clothing, used self-contained breathing apparatus, and had the equipment necessary to control and extinguish the fire. The inspectors assessed the adequacy of the fire brigade?s fire fighting strategy including entry into the fire area, communications, search and rescue, and equipment usage.
Fire Area Tours. The inspectors walked down the following five 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 condition report (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 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 south main steam valve house C Unit 2 auxiliary component cooling water (ACCW) heat exchanger rooms C Unit 1 control building level A east penetration areas C Unit 1 control building level A west penetration areas C Unit 2 containment spray pump rooms
b. Findings
No findings of significance were identified.
1R11 Licensed Operator Requalification
a. Inspection Scope
Resident Quarterly Observation. The inspectors observed operator performance on January 28, during licensed operator simulator training described in Simulator Exercise Guide Segment 20091 As-Found #3. The simulator scenarios covered operator actions resulting from a loss of nuclear service cooling water pump, a failure of a steam generator pressure instrument, and a steam generator tube rupture. 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 the post-evaluation critique
b. Findings
No findings of significance were identified.
1R12 Maintenance Effectiveness
a. Inspection Scope
The inspectors reviewed the following two CRs and applicable safety-significant systems to evaluate the effectiveness of the licensees handling of equipment performance problems and to verify 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 control room logs, system health reports, the maintenance rule database, and maintenance work orders (WO). Also, the inspectors interviewed system engineers and the maintenance rule coordinator to assess the accuracy of identified performance deficiencies and extent of condition.
C CR 2009100412, 2B NSCW Tower Fan No. 3 failed to auto start C CR 2009100558, 1A EDG Exhaust Silencer has four sheared anchor bolts
b. Findings
No findings of significance were identified.
1R13 Maintenance Risk Assessments and Emergent Work Evaluation
a. Inspection Scope
The inspectors reviewed the following five work activities to verify plant risk was properly assessed by the licensee prior to conducting the activities. 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 at the appropriate level, entered into the corrective action program, and appropriately resolved.
C WO 10900033, Unit 1 Train B EDG lube oil keep warm pump repair C Unit 1 Train A EDG system outage C Unit 2 Train A ACCW pump number 1 system outage C WO 2081945002 Unit 2 Train B RHR pump maintenance concurrent with a slave relay test on valves associated with the turbine driven auxiliary feed water pump C Unit 2 Train A AFW system outage
b. Findings
No findings of significance were identified.
1R15 Operability Evaluations
a. Inspection Scope
The inspectors reviewed the following five evaluations to verify they met the requirements of procedure NMP-GM-002, Corrective Action Program, and NMP-GM-002-001, Corrective Action Program Instructions. The scope of this inspection included a review of the technical adequacy of the evaluations, the adequacy of compensatory measures, and the impact on continued plant operation.
C CR 2009100570, bent anchor bolt on south concrete pier of 1B EDG silencer C CR 2009101163, availability of Plant Wilson while credited to provide electrical power during Unit 1 EDG B extended allowed outage C CR 2009101616, low oil level in 1A ESF chilled water pump C CR 2009102149, part of dipstick, washer, and nut fell into 2A EDG return oil sump C CR 2009102408, oil leak from 2B RHR pump upper bearing into motor cavity
b. Findings
No findings of significance were identified.
1R18 Plant Modifications
a. Inspection Scope
Temporary Modifications. The inspectors reviewed temporary modification TM 2090168501 (U2) and associated 10CFR50.59 screening criteria against the system design bases documentation and procedure 00307-C, Temporary Modifications. This temporary modification replaced circuit breaker 2ABA11, feeder supply breaker to the Class 1E battery charger 2CD1CB, with an equivalent breaker that did not have 52b auxiliary contacts. The 52b auxiliary contacts are used to provide input to the MCC 2ABA trouble alarm. Use of the temporary modification allowed continued operation of the safety-related battery charger until a breaker with 52b auxiliary contacts could be procured, tested, and installed. The inspectors reviewed implementation, configuration control, post-installation test activities, drawing and procedure updates, and operator awareness for this temporary modification.
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 were sufficient to meet the Technical Specifications operability requirements.
C WO 2071319001 and WO 2080461101, 2B ESF chilled water system outage C WO 1071698301, Replace 1B NSCW fan #4 motor C WO 2080254201, ACCW pump #1 outage C 1A EDG Allowed Outage Time C NSCW 1B cooling tower fan #3 motor replacement outage C 2A AFW pump outage
b. Findings
No findings of significance were identified.
1R22 Surveillance Testing
a. Inspection Scope
The inspectors reviewed the following six 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 14980B-1, Diesel Generator 1B Operability Test C 14982-1, Diesel Generator Fuel Oil Transfer system 18 month test C 28931C, Thirty-One Day Battery Maintenance (1D train battery)
In-Service Tests (IST)
C 14805B-1, Train B RHR pump IST and response time test C 14825-2, Train B Containment Spray (2HV-9003B, Containment Sump Suction only)
RCS Leakage Detection C 14905-1, Unit 1 RCS Leakage Calculation (Inventory Balance)
b. Findings
No findings of significance were identified.
Cornerstone: Emergency Preparedness
1EP6 Drill Evaluation
a. Inspection Scope
The inspectors reviewed the facility activation exercise guide 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 Classifications, and 91305-C, Protective Action Guidelines.
C On February 11, the licensee conducted an emergency preparedness drill involving a reactor coolant pump trip, followed by an anticipated transient without trip (ATWT).
Following the ATWT, the operators responded to a loss of all feedwater, a loss of coolant accident, and a containment leak. The technical support center and operations support center were activated and the site participated in the exercise.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification
a. Inspection Scope
The inspectors sampled licensee submittals for the listed PIs during the period from January 1, 2008 through December 31, 2008, for Unit 1 and Unit 2. The inspectors verified the licensees basis in reporting each data element using the PI definitions and guidance contained in procedure 00163-C, NRC Performance Indicator and Monthly Operating Report Preparation and Submittal, and Nuclear Energy Institute document NEI 99-02, Regulatory Assessment Indicator Guideline.
Mitigating Systems Cornerstone C Unplanned Scrams per 7,000 Critical Hours C Unplanned Scrams with Complications C Unplanned Transients per 7,000 Critical Hours The inspectors reviewed Unit 1 and Unit 2 operator log entries, the Vogtle Electric Generating Plant Unit 1 and Unit 2 NRC Mitigating System Performance Index Basis Document, the monthly operating reports and monthly PI summary reports to verify that the licensee had accurately submitted the PI data.
b. Findings
No findings of significance were identified.
4OA2 Identification and Resolution of Problems
.1 Daily Condition Report Review. 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 Focused Review
a. Inspection Scope
The inspectors performed a detailed review of the following CRs 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 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.
C CR 2007101312 C CR 2007111120
b. Findings and Observations
No findings of significance were identified.
4OA5 Other Activities
.1 Quarterly Resident Inspector Observations of Security Personnel and Activities
a. Inspection Scope
During the inspection period, the inspectors conducted observations of security force personnel and activities to ensure that the activities were consistent with licensee security procedures and regulatory requirements relating to nuclear plant security. These observations took place during both normal and off-normal plant working hours.
b. Findings and Observations
No findings of significance were identified.
.2 (Closed) Temporary Instruction (TI) 2515/176, EDG TS Surveillance Requirements
Regarding Endurance and Margin Testing
a. Inspection Scope
Inspection activities for TI 2515/176 were previously completed and documented in inspection report 05000424, 425/2008004, and this TI is considered closed at Vogtle Generating Plant; however, TI 2515/176 will not expire until August 31, 2009. The information gathered while completing this temporary instruction was forwarded to the Office of Nuclear Reactor Regulation for review and evaluation.
b. Inspection Findings No findings of significance were identified.
4OA6 Meetings, Including Exit
.1 Exit Meeting
On April 29, the resident inspectors presented the inspection results to Mr. C. R.
Dedrickson and other members of his staff, who acknowledged the findings. The inspectors confirmed that proprietary information was not provided or examined during the inspection.
.2 Annual Assessment Meeting Summary
On March 27, the NRCs Chief of Reactor Projects Branch 2 and Senior Resident Inspector met with Tom Tynan and other members of the licensee staff to discuss the NRCs annual assessment of the Vogtle Electric Generating Plant safety performance for the period of January 1 through December 31, 2008. The annual assessment results were previously provided to Southern Nuclear via letter dated March 4, 2009.
On March 26, 2009, the NRCs Chief of Reactor Projects Branch 2, and the Resident Inspectors, held a meeting for members of the public and local officials. This Category 3 public meeting provided an open house public forum to engage the public in a discussion of regulatory issues related to the NRCs ROP and annual assessment of the Vogtle Electric Generating Plant safety performance for the period January 1 through December 31, 2008. The poster board presentation material used for discussions is attached.
ATTACHMENT: 1.
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- R. Brown, Training and Emergency Preparedness Manager
- C. Buck, Chemistry Manager
- W. Copeland, Performance Analysis Supervisor
- R. Dedrickson, Plant Manager
- K. Dyar, Security Manager
- I. Kochery, Health Physics Manager
- T. Tynan, Site Vice-President
- D. Vineyard, Operations Manager
- J. Williams, Site Support Manager
- T. Youngblood, Site Engineering Manager
NRC personnel
- S. Shaeffer, Chief, Region II Reactor Projects Branch 2
LIST OF REPORT ITEMS
Closed
2515/176 TI EDG TS Surveillance Requirements Regarding Endurance and Margin Testing (Section 4OA5)