IR 05000413/2017001
| ML17117A236 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/27/2017 |
| From: | Frank Ehrhardt NRC/RGN-II/DRP/RPB1 |
| To: | Simril T Duke Energy Corp |
| References | |
| IR 2017001 | |
| Download: ML17117A236 (25) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ril 27, 2017
SUBJECT:
CATAWBA NUCLEAR STATION - NRC INTEGRATED INSPECTION REPORT 05000413/2017001 AND 05000414/2017001
Dear Mr. Simril:
On March 31, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Catawba Nuclear Station Units 1 and 2. On April 20, 2017, the NRC inspectors discussed the results of this inspection with you and other members of your staff.
The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any findings or violations of more than minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Frank Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos.: 50-413, 50-414 License Nos.: NPF-35, NPF-52
Enclosure:
IR 05000413/2017001 and 05000414/2017001 w/Attachment: Supplemental Information
REGION II==
Docket Nos.: 50-413, 50-414 License Nos.: NPF-35, NPF-52 Report No.: 05000413/2017001 and 05000414/2017001 Licensee: Duke Energy Carolinas, LLC Facility: Catawba Nuclear Station, Units 1 and 2 Location: York, SC 29745 Dates: January 1, 2017 through March 31, 2017 Inspectors: J. Austin, Senior Resident Inspector C. Scott, Resident Inspector W. Loo, Senior Health Physicist (Sections 1EP2, 1EP3, 1EP4, 1EP5, 4OA1)
S. Sanchez, Senior Emergency Preparedness Inspector (Sections 1EP2, 1EP3, 1EP4, 1EP5, 4OA1)
M. Toth, Project Engineer (Section 4OA5)
Approved by: Frank Ehrhardt, Chief Reactor Projects Branch 1 Enclosure
SUMMARY
IR 05000413/2017001 and 05000414/2017001, January 1, 2017 through March 31, 2017;
Catawba Nuclear Station, Units 1 and 2; Integrated Inspection Report The report covered a three-month period of inspection by the resident inspectors and regional inspectors. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6. No findings were identified during this inspection period.
REPORT DETAILS
Summary of Plant Status
Unit 1: Operated at or near 100 percent rated thermal power for the entire inspection period.
Unit 2: Operated at or near 100 percent rated thermal power for the entire inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection
a. Inspection Scope
.1 Impending Adverse Weather Conditions
The inspectors reviewed the licensees preparations to protect risk-significant systems from cold weather expected during January 6 - 9, 2017. The inspectors evaluated the licensees implementation of adverse weather preparation procedures and compensatory measures, including operator staffing, before the onset of and during the adverse weather conditions. The inspectors reviewed the licensees plans to address the consequences that may result from cold weather. The inspectors verified that operator actions specified in the licensees adverse weather procedure maintain readiness of essential systems. The inspectors verified that required surveillances were current, or were scheduled and completed, if practical, before the onset of anticipated adverse weather conditions. The inspectors also verified that the licensee implemented periodic equipment walkdowns or other measures to ensure that the condition of plant equipment met operability requirements. Documents reviewed are listed in the attachment.
.2 Summer Readiness of Offsite and Alternate AC Power System
The inspectors reviewed the licensees procedures for operation and continued availability of offsite and onsite alternate AC power systems. The inspectors also reviewed the communications protocols between the transmission system operator and the licensee to verify that the appropriate information is exchanged when issues arise that could affect the offsite power system.
The inspectors reviewed the material condition of offsite and onsite alternate AC power systems (including switchyard and transformers) by performing a walkdown of the switchyard. Documents reviewed are listed in the attachment.
b. Findings
No findings were identified.
1R04 Equipment Alignment
a. Inspection Scope
.1 Partial Walkdown
The inspectors verified that critical portions of the selected systems were correctly aligned by performing partial walkdowns. The inspectors selected systems for assessment because they were a redundant or backup system or train, were important for mitigating risk for the current plant conditions, had been recently realigned, or were a single-train system. The inspectors determined the correct system lineup by reviewing plant procedures and drawings. Documents reviewed are listed in the attachment.
The inspectors selected the following four systems or trains to inspect:
- Unit 2, 2B1 and 2B2 component cooling (KC) pump while the 2A KC was out of service (OOS) for maintenance
- Unit 1 and Unit 2, auxiliary feedwater system (CA) makeup sources with the CA condensate storage tank isolated
- Unit 1 and Unit 2, 1B and 2B service water (RN) pumps while the 1A RN pump was OOS for maintenance
- Unit 0 D instrument air (VI) compressor following identification of multiple air leaks
b. Findings
No findings were identified.
1R05 Fire Protection
a. Inspection Scope
Quarterly Inspection The inspectors evaluated the adequacy of selected fire plans by comparing the fire plans to the defined hazards and defense-in-depth features specified in the fire protection program. In evaluating the fire plans, the inspectors assessed the following items:
- control of transient combustibles and ignition sources
- fire detection systems
- fire suppression systems
- manual firefighting equipment and capability
- passive fire protection features
- compensatory measures and fire watches
- issues related to fire protection contained in the licensees corrective action program The inspectors toured the following six fire areas to assess material condition and operational status of fire protection equipment. Documents reviewed are listed in the attachment.
- Unit 1 and Unit 2, cable room, fire area 16
- Unit 1, electrical penetration room, 577 elevation, fire area 13
- Unit 2, electrical penetration room, 577 elevation, fire area 12
- Unit 2, A DG corridor, fire area 43
- Unit 2, A DG room, fire area 27
- Unit 1, exterior doghouse, fire area 51
b. Findings
No findings were identified.
1R06 Flood Protection Measures
a. Inspection Scope
Internal Flooding The inspectors reviewed related flood analysis documents and walked down the area listed below containing risk-significant structures, systems, and components susceptible to flooding. The inspectors verified that plant design features and plant procedures for flood mitigation were consistent with design requirements and internal flooding analysis assumptions. The inspectors also assessed the condition of flood protection barriers and drain systems. In addition, the inspectors verified the licensee was identifying and properly addressing issues using the corrective action program. Documents reviewed are listed in the attachment.
- Unit 2, auxiliary feedwater pump room, 544 elevation
b. Findings
No findings were identified.
1R11 Licensed Operator Requalification Program and Licensed Operator Performance
a. Inspection Scope
.1 Resident Inspector Quarterly Review of Licensed Operator Requalification
On March 23, 2017, the inspectors observed an evaluated simulator scenario administered to an operating crew conducted in accordance with the licensees accredited requalification training program. The scenario involved a main turbine runback, a reactor trip, a control rod misalignment and a small break loss of coolant accident with safety injection.
The inspectors assessed the following:
- licensed operator performance
- the ability of the licensee to administer the scenario and evaluate the operators
- the quality of the post-scenario critique
- simulator performance Documents reviewed are listed in the attachment.
.2 Resident Inspector Quarterly Review of Licensed Operator Performance in the Actual
Plant/Main Control Room The inspectors observed licensed operator performance in the main control room during Unit 2, 2B diesel generator testing on February 28, 2017, and Unit 2, feedwater heater 2B2 level oscillations on March 2, 2017.
The inspectors assessed the following:
- use of plant procedures
- control board manipulations
- communications between crew members
- use and interpretation of instruments, indications, and alarms
- use of human error prevention techniques
- documentation of activities
- management and supervision Documents reviewed are listed in the attachment.
b. Findings
No findings were identified.
1R12 Maintenance Effectiveness
a. Inspection Scope
The inspectors assessed the licensees treatment of the three issues listed below to verify the licensee appropriately addressed equipment problems within the scope of the maintenance rule (10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants). The inspectors reviewed procedures and records to evaluate the licensees identification, assessment, and characterization of the problems as well as their corrective actions for returning the equipment to a satisfactory condition. Documents reviewed are listed in the attachment.
- Condition Report (CR) 2100554, A Control Area Chilled Water (YC) Chiller Tripped on High Inboard Bearing Temperature
- CR 2072520, Unit 1 Rod Control Cabinet Urgent Alarm
- CR 2100643, Unit 1 Evaluation Required per AD-EG-ALL-1210, Repetitive Maintenance Rule Functional Failures Occurred on the Radiation Monitoring System
b. Findings
No findings were identified.
1R13 Maintenance Risk Assessments and Emergent Work Control
a. Inspection Scope
The inspectors reviewed the five maintenance activities listed below to verify that the licensee assessed and managed plant risk as required by 10 CFR 50.65(a)(4) and licensee procedures. The inspectors assessed the adequacy of the licensees risk assessments and implementation of risk management actions. The inspectors also verified that the licensee was identifying and resolving problems with assessing and managing maintenance-related risk using the corrective action program. Additionally, for maintenance resulting from unforeseen situations, the inspectors assessed the effectiveness of the licensees planning and control of emergent work activities.
Documents reviewed are listed in the attachment.
- Unit 1, February 8, 2017, emergent risk assessment for missed surveillance for Unit 1 divide barrier (hatch) integrity inspection
- Unit 1, February 14, 2017, yellow risk condition with 1A DG unavailable for bearing inspection
- Unit 0, February 24, 2017, protection plan with the standby shutdown facility (SSF)
OOS for maintenance
- Unit 2, March 28, 2017, protection plan with the 2B CA pump OOS for testing
b. Findings
No findings were identified.
1R15 Operability Determinations and Functionality Assessments
a. Inspection Scope
Operability and Functionality Review The inspectors selected the six operability determinations or functionality evaluations listed below for review based on the risk-significance of the associated components and systems. The inspectors reviewed the technical adequacy of the determinations to ensure that technical specification operability was properly justified and the components or systems remained capable of performing their design functions. To verify whether components or systems were operable, the inspectors compared the operability and design criteria in the appropriate sections of the technical specification and updated final safety analysis report to the licensees evaluations. Where compensatory measures were required to maintain operability, the inspectors determined whether the measures in place would function as intended and were properly controlled. Additionally, the inspectors reviewed a sample of corrective action documents to verify the licensee was identifying and correcting any deficiencies associated with operability evaluations.
Documents reviewed are listed in the attachment.
- Unit 1, 1NW-61B, Nuclear Service Water (RN) Supply Valve Failed to Open During Performance Test (PT), CR 2074228
- Unit 2, 2A DG Jacket Water Leak, CR 2091344
- Unit 2, Turbine Driven Auxiliary Feedwater Pump Trip and Throttle Valve Control Circuit Found Loose, CR 2057215
- Unit 1, 1B Centrifugal Charging Pump (NV) Thrust Bearing Oil Level Low, CR 2107060
- Unit 1, Rubber Gasket Found in 1B DG Starting Air Inlet Check Valve, 1VG-73, CR 02105977
- Unit 2, 2A1 Component Cooling Pump (KC) Outboard Bearing Oil Level, CR 2089480
b. Findings
No findings were identified.
1R18 Plant Modifications
a. Inspection Scope
The inspectors verified that the three plant modifications listed below did not affect the safety functions of important safety systems. The inspectors confirmed the modifications did not degrade the design bases, licensing bases, and performance capability of risk significant structures, systems and components. The inspectors also verified modifications performed during plant configurations involving increased risk did not place the plant in an unsafe condition. Additionally, the inspectors evaluated whether system operability and availability, configuration control, post-installation test activities, and changes to documents, such as drawings, procedures, and operator training materials, complied with licensee standards and NRC requirements. In addition, the inspectors reviewed a sample of related corrective action documents to verify the licensee was identifying and correcting any deficiencies associated with modifications. Documents reviewed are listed in the attachment.
- Engineering Change (EC) 108655, Radiation Monitors (EMF) Addition to Auxiliary Building Chilled Water System (YN)
- EC 406380, Update Drawing for U-2 Reactor Coolant System Loop #3 Flow Transmitter
- EC 403650, Temporary GAG Installed on 1AS-4 (main steam to auxiliary steam header bypass)
b. Findings
No findings were identified.
1R19 Post-Maintenance Testing
a. Inspection Scope
The inspectors either observed post-maintenance testing or reviewed the test results for the maintenance activities listed below to verify the work performed was completed correctly and the test activities were adequate to verify system operability and functional capability.
- WO 20061746, repair of 'A' YC chiller after on high bearing temperature, February 15, 2017
- WO 20085484, clean/replace 1RN A pump strainer, February 15, 2017
- WO 20129428, preventive maintenance on 2NV865A, standby makeup pump suction from transfer tube, February 21, 2017
- Work Request 2012975, preventive maintenance on turbine driven CA pump 2, March 2, 2017
- WO 20153702, replace safety injection (NI) pump 2A mini-flow isolation, March 16, 2017
- WO 20147707, pre-outage preventive maintenance on 1A DG, March 22, 2017 The inspectors evaluated these activities for the following:
- acceptance criteria were clear and demonstrated operational readiness
- effects of testing on the plant were adequately addressed
- test instrumentation was appropriate
- tests were performed in accordance with approved procedures
- equipment was returned to its operational status following testing
- test documentation was properly evaluated Additionally, the inspectors reviewed a sample of corrective action documents to verify the licensee was identifying and correcting any deficiencies associated with post-maintenance testing. Documents reviewed are listed in the attachment.
b. Findings
No findings were identified.
1R22 Surveillance Testing
a. Inspection Scope
The inspectors reviewed the five surveillance tests listed below and either observed the test or reviewed test results to verify testing adequately demonstrated equipment operability and met technical specification and current licensing basis. The inspectors evaluated the test activities to assess for preconditioning of equipment, procedure adherence, and equipment alignment following completion of the surveillance.
Additionally, the inspectors reviewed a sample of related corrective action documents to verify the licensee was identifying and correcting any deficiencies associated with surveillance testing. Documents reviewed are listed in the attachment.
Routine Surveillance Tests
- PT/0/A/4200/042, Access Door and Hatch Seal Periodic Inspection and Replacement
- PT/2/A/4350/002A, Diesel Generator 2A Operability Test
- PT/2/B/4350/002B, Diesel Generator 2B Operability Test
- PT/1/A/4600/002A, Mode 1 Periodic Surveillance In-Service Tests (IST)
- PT/2/A/4200/005A, Safety Injection Pump 2A Performance Test
b. Findings
No findings were identified.
Cornerstone: Emergency Preparedness
1EP2 Alert and Notification System Evaluation
a. Inspection Scope
The inspectors evaluated the adequacy of the licensees methods for testing and maintaining the alert and notification system in accordance with NRC Inspection Procedure 71114, Attachment 02, Alert and Notification System Evaluation. The applicable planning standard, 10 CFR Part 50.47(b)(5), and its related 10 CFR Part 50, Appendix E requirements were used as reference criteria. The criteria contained in NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, Revision 1, were also used as a reference.
The inspectors reviewed various documents which are listed in the attachment and interviewed personnel responsible for system performance. This inspection activity satisfied one inspection sample for the alert and notification system on a biennial basis.
b. Findings
No findings were identified.
1EP3 Emergency Response Organization Staffing and Augmentation System
a. Inspection Scope
The inspectors reviewed the licensees emergency response organization (ERO)augmentation staffing requirements and process for notifying the ERO to ensure the readiness of key staff for responding to an event and timely facility activation. The qualification records of key position ERO personnel were reviewed to ensure all ERO qualifications were current. A sample of problems identified from augmentation drills or system tests performed since the last inspection was reviewed to assess the effectiveness of corrective actions. The inspection was conducted in accordance with NRC Inspection Procedure 71114, Attachment 03, Emergency Response Organization Staffing and Augmentation System. The applicable planning standard, 10 CFR 50.47(b)(2), and its related 10 CFR 50, Appendix E requirements were used as reference criteria.
The inspectors reviewed various documents which are listed in the attachment. This inspection activity satisfied one inspection sample for the ERO staffing and augmentation system on a biennial basis.
b. Findings
No findings were identified.
1EP4 Emergency Action Level and Emergency Plan Changes
a. Inspection Scope
Since the last NRC inspection of this program area, one change was made to the radiological emergency plan, one change was made to the emergency action levels (EALs), and several changes were made to the implementing procedures. The licensee determined that, in accordance with 10 CFR 50.54(q), the plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50. The inspectors reviewed these changes to evaluate for potential reductions in the effectiveness of the plan. However, this review was not documented in a safety evaluation report and does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, Emergency Action Level and Emergency Plan Changes. The applicable planning standards of 10 CFR 50.47(b), and its related requirements in 10 CFR 50, Appendix E were used as reference criteria. The inspectors reviewed various documents that are listed in the attachment to this report. This inspection activity satisfied one inspection sample for the emergency action level and emergency plan changes on an annual basis.
b. Findings
No findings were identified.
1EP5 Maintenance of Emergency Preparedness
a. Inspection Scope
The inspectors reviewed the corrective actions identified through the emergency preparedness program to determine the significance of the issues, the completeness and effectiveness of corrective actions, and to determine if issues were recurring. The licensees post-event after action reports, self-assessments, and audits were reviewed to assess the licensees ability to be self-critical, thus avoiding complacency and degradation of their emergency preparedness program. Inspectors reviewed the licensees 10 CFR 50.54(q) change process, personnel training, and selected screenings and evaluations to assess adequacy. The inspectors toured facilities and reviewed equipment and facility maintenance records to assess licensees adequacy in maintaining them. The inspectors evaluated the capabilities of selected radiation monitoring instrumentation to adequately support EAL declarations.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 05, Maintenance of Emergency Preparedness. The applicable planning standards, related 10 CFR 50, Appendix E requirements, and 10 CFR 50.54(q) and (t)were used as reference criteria. The inspectors reviewed various documents which are listed in the Attachment. This inspection activity satisfied one inspection sample for the maintenance of emergency preparedness on a biennial basis.
b. Findings
No findings were identified.
1EP6 Drill Evaluation
a. Inspection Scope
The inspectors observed the emergency preparedness drill conducted on January 19, 2017. The inspectors observed licensee activities in the technical support center to evaluate implementation of the emergency plan, including event classification, notification, and protective action recommendations. The inspectors evaluated the licensees performance against criteria established in the licensees procedures.
Additionally, the inspectors attended the post-exercise critique to assess the licensees effectiveness in identifying emergency preparedness weaknesses and verified the identified weaknesses were entered in the corrective action program. Documents reviewed are listed in the attachment.
b. Findings
No findings were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
a. Inspection Scope
The inspectors reviewed a sample of the performance indicator (PI) data, submitted by the licensee, for the Unit 1 and Unit 2 PIs listed below. The inspectors reviewed plant records compiled between January 2016 and December 2016 to verify the accuracy and completeness of the data reported for the station. The inspectors verified that the PI data complied with guidance contained in Nuclear Energy Institute 99-02, Regulatory Assessment Performance Indicator Guideline, and licensee procedures. The inspectors verified the accuracy of reported data that were used to calculate the value of each PI.
In addition, the inspectors reviewed a sample of related corrective action documents to verify the licensee was identifying and correcting any deficiencies associated with PI data. Documents reviewed are listed in the attachment.
Cornerstone: Initiating Events
- unplanned scrams per 7000 critical hours
Cornerstone: Mitigating Systems
- cooling water system
Cornerstone: Barrier Integrity
- reactor coolant system specific activity
Cornerstone: Emergency Preparedness
- drill/exercise performance (DEP)
- emergency response organization (ERO) readiness
- alert and notification system (ANS) reliability For the specified review period, the inspectors examined data reported to the NRC, procedural guidance for reporting PI information, and records used by the licensee to identify potential PI occurrences. 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 alert and notification system reliability through review of a sample of the licensees records of periodic system tests. The inspectors also interviewed the licensee personnel who were responsible for collecting and evaluating the PI data. Licensee procedures, records, and other documents reviewed within this inspection area are listed in the attachment. This inspection satisfied three inspection samples for PI verification on an annual basis.
b. Findings
No findings were identified.
4OA2 Problem Identification and Resolution
.1 Routine Review
The inspectors screened items entered into the licensees corrective action program to identify repetitive equipment failures or specific human performance issues for follow-up.
The inspectors reviewed problem identification program reports, attended screening meetings, or accessed the licensees computerized corrective action database.
.2 Annual Followup of Selected Issues
a. Inspection Scope
The inspectors conducted a detailed review of the following two nuclear condition reports:
- CR 2094372, Configuration Management Challenges
- CR 2040888, Decision Making Process for DG Bearing Inspection The inspectors evaluated the following attributes of the licensees actions:
- complete and accurate identification of the problem in a timely manner
- evaluation and disposition of operability and reportability issues
- consideration of extent of condition, generic implications, common cause, and previous occurrences
- classification and prioritization of the problem
- identification of root and contributing causes of the problem
- identification of any additional condition reports
- completion of corrective actions in a timely manner Documents reviewed are listed in the attachment.
b. Findings and Observations
No findings were identified.
4OA5 Other Activities
.1 Temporary Instruction (TI) 2515/192, Inspection of the Licensees Interim Compensatory
Measures Associated with the Open Phase Condition Design Vulnerabilities in Electric Power Systems.
a. Inspection Scope
The objective of this performance based TI was to verify implementation of interim compensatory measures associated with an open phase condition design vulnerability in electric power systems for operating reactors. The inspectors conducted an inspection to determine if the licensee had implemented the interim compensatory measures listed below. These compensatory measures are to remain in place until permanent automatic detection and protection schemes are installed and declared operable for open phase condition design vulnerability. The inspectors verified the following:
- The licensee identified and discussed with plant staff the lessons-learned from the open phase condition events at U.S. operating plants including the Byron Station open phase condition and its consequences. This included conducting operator training for promptly diagnosing, recognizing consequences, and responding to an open phase condition.
- The licensee updated plant operating procedures to help operators promptly diagnose and respond to open phase conditions on off-site power sources credited for safe shutdown of the plant.
- The licensee established and implemented periodic walkdown activities to inspect switchyard equipment such as insulators, disconnect switches, and transmission line and transformer connections associated with the offsite power circuits to detect a visible open phase condition.
- The licensee ensured that routine maintenance and testing activities on switchyard components have been implemented and maintained. As part of the maintenance and testing activities, the licensee assessed and managed plant risk in accordance with 10 CFR 50.65(a)(4) requirements.
b. Findings
No findings were identified.
.2 Operation of an Independent Spent Fuel Storage Installation (60855.1)
a. Inspection Scope
The inspectors performed a walkdown of the onsite independent spent fuel storage installation (ISFSI). The inspectors reviewed records to verify that the licensee recorded and maintained the location of each fuel assembly placed in the ISFSI. The inspectors also reviewed surveillance records to verify that daily surveillance requirements were performed as required by technical specifications. Documents reviewed are listed in the attachment.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
On April 20, 2017, the resident inspectors presented the inspection results to Mr. Tom Simril and other members of the licensees staff. The inspectors verified that no proprietary information was retained by the inspectors or documented in this report.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- C. Abernathy, Manager, Nuclear Site Services
- S. Andrews, Sr. Engineer Regulatory Affairs,
- T. Arlow, Emergency Planning Manager
- C. Bigham, Director Nuclear Organizational Effectiveness
- M. Carwile, Chemistry Manager
- B. Cauthen, Lead Engineer
- D. Cribb, Senior Emergency Preparedness Specialist
- C. Curry, Plant Manager
- S. Fischer, Senior Emergency Preparedness Specialist
- C. Fletcher, Regulatory Affairs Manager
- N. Flippin, Work Management Manager
- B. Foster, Operations Manager
- T. Jenkins, Maintenance Manager
- L. Keller, General Manager Nuclear Engineering
- B. Leonard, Training Manager
- J. Overly, Fleet Emergency Preparedness Programs Manager
- T. Simril, Site Vice-President
- J. Smith, Radiation Protection Manager
- D. Thompson, Emergency Preparedness Corporate Functional Area Manager
- S. West, Director, Nuclear Plant Security
- C. Wilson, Sr. Engineer Regulatory Affairs
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Closed
TI 2515/192 TI Inspection of the Licensees Interim Compensatory Measures Associated with the Open Phase Condition Design Vulnerabilities in Electric Power Systems (Section 4OA5)