IR 05000269/2017003
| ML17305A157 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/01/2017 |
| From: | Frank Ehrhardt NRC/RGN-II/DRP/RPB1 |
| To: | Teresa Ray Duke Energy Corp |
| References | |
| IR 2017003 | |
| Download: ML17305A157 (23) | |
Text
UNITED STATES November 1, 2017
SUBJECT:
OCONEE NUCLEAR STATION - NRC INTEGRATED INSPECTION REPORT 05000269/2017003, 05000270/2017003, AND 05000287/2017003
Dear Mr. Ray:
On September 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Oconee Nuclear Station Units 1, 2, and 3. On October 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.: 50-269, 50-270, 50-287 License Nos.: DPR-38, DPR-47, DPR-55
Enclosure:
IR 05000269/2017003, 05000270/2017003, and 05000287/2017003 w/Attachment: Supplemental Information
REGION II==
Docket Nos.: 50-269, 50-270, 50-287 License Nos.: DPR-38, DPR-47, DPR-55 Report No.: 05000269/2017003, 05000270/2017003, and 05000287/2017003 Licensee: Duke Energy Carolinas, LLC Facility: Oconee Nuclear Station, Units 1, 2, and 3 Location: Seneca, SC 29672 Dates: July 1, 2017 through September 30, 2017 Inspectors: E. Crowe, Senior Resident Inspector N. Childs, Resident Inspector J. Parent, Resident Inspector S. Sanchez, Senior Emergency Preparedness Inspector (Sections 1EP2, 1EP3, 1EP4)
C. Fontana, Emergency Preparedness Inspector (Sections 1EP5, 4OA1)
Approved by: Frank Ehrhardt, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure
SUMMARY
IR 05000269/2017003, 05000270/2017003, and 05000287/2017003, July 1, 2017, through
September 30, 2017; Oconee Nuclear Station, Units 1, 2, and 3; Integrated Inspection Report The report covered a 3-month period of inspection by resident inspectors and regional inspectors. No findings were identified during this inspection period. The NRCs program for overseeing the safe operations of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6.
REPORT DETAILS
Summary of Plant Status
Unit 1: Operated at or near 100 percent rated thermal power (RTP) for the entire inspection period.
Unit 2: Operated at or near 100 percent RTP for the entire inspection period.
Unit 3: The unit began the inspection period at approximately 100 percent RTP. On July 24, 2017, the unit experienced an automatic reactor trip from 100 percent RTP due to a main generator lockout caused by improper operation of a 525KV switchyard relay.
The unit returned to 100 percent RTP on July 26, 2017, and operated at or near 100 percent RTP for the remainder of the inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection
a. Inspection Scope
Impending Adverse Weather Conditions The inspectors reviewed the licensees preparations to protect risk-significant systems from high winds expected during September 11 - 12, 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 the high winds from Hurricane Irma. 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.
b. Findings
No findings were identified.
1R04 Equipment Alignment
a. Inspection Scope
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. The inspectors observed whether there was indication of degradation, and if so, verified the degradation was being appropriately managed in accordance with an aging management program and it had been entered into the licensees corrective action program. Documents reviewed are listed in the attachment.
The inspectors selected the following four systems or trains to inspect:
- Units 1, 2, and 3, backup instrument air (IA) and diesel service air compressors with primary IA compressor tripped
- Units 1, 2, and 3, emergency feedwater (EFW) pumps, switches, and breakers; high pressure injection (HPI) pumps, switches, and breakers; control batteries; and elevated water storage tank with protected service water (PSW) inoperable for greater than 14 days
- Units 1, 2, and 3, emergency AC power system, standby shutdown facility (SSF),and EFW systems during planned replacement of the Keowee main step-up transform and 230 KV switchyard circuit breakers PCB-8 and PCB-9
- Unit 1, 1B essential siphon vacuum (ESV) train due to 1A and 1C ESV train testing
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 four fire areas to assess material condition and operational status of fire protection equipment. Documents reviewed are listed in the attachment.
- Units 1, 2, and 3, PSW building, fire zones PSW-002 and PSW-003
- Unit 3, lube oil purifier, electro hydraulic control (EHC), and heater bay areas, fire zones 1, 2, and 3
- Unit 3, turbine driven EFW, condensate booster, main feedwater (MFW), and motor driven EFW pump areas, fire zones 4, 5, 6, and 7
- Unit 3, hotwell pump, turbine building sump oil skimmer, and powdex/low pressure service water pump areas, fire zones 8 and 9
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 September 13, 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 1A HPI pump tripping and 1B HPI pump failure to auto-start.
Afterwards, a reactor coolant pump (RCP) seal failed on 1A2 RCP and 1RC-1 (pressurizer spray valve) failed in the throttled position. The only main feedwater pump running tripped and the reactor failed to trip as designed causing an anticipated transient without scram (ATWS). Following the ATWS, a large break loss of coolant accident occurred as 1B1 RCP failed to trip. During the scenario events progressed to a point where the crew entered an alert declaration.
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 On July 20, 2017, the inspectors observed licensed operator performance in the main control room during the shift of the Unit 3 main turbine oil tank from a single cooler to a dual cooler operation. On July 24, 2017, the inspectors observed licensed operator performance in the main control room following the automatic trip and subsequent reactor startup.
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.
- Units 1, 2, 3, coolant storage, 1CS-56 inspection and delayed return to MR (a)(2) for coolant storage
- Units 1, 2, 3, Keowee Hydro Unit MR evaluation to transition to (a)(1) status following human performance events
b. Findings
No findings were identified.
1R13 Maintenance Risk Assessments and Emergent Work Control
a. Inspection Scope
The inspectors reviewed the three 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.
- Units 1, 2, and 3, July 7, 2017, during planned maintenance to HPSW-960 which increases risk of auxiliary building flooding
- Units 1, 2, and 3, August 16, 2017, evaluated green risk during planned Keowee main step-up transformer & pneumatic circuit breaker 8 & 9 replacements
- Unit 1, August 17, 2017, evaluated green risk during planned 1A and 1C ESV system test
b. Findings
No findings were identified.
1R15 Operability Determinations and Functionality Assessments
a. Inspection Scope
Operability and Functionality Review The inspectors selected the eight 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.
- Units 1, 2, and 3, Keowee main stepup transformer deluge system u-bolts are not QA-4 certified as described on station drawings, Nuclear Condition Report (NCR) 02144740
- Units 1, 2, and 3, SSF B diesel engine driven water pump water leak, NCR 02146304
- Units 1, 2, and 3, Lee combustion turbine 7C tripped while supplying the Oconee standby electrical buses as required by technical specifications, NCR 02144786
- Units 1, 2, and 3, Keowee Hydro Unit-2 2AG-6 governor pressure relief valve lifted at lower pressure than expected, NCR 02149830
- Unit 1, 1LPSW-4 failed to close in the required stroke time, NCR 02147020
- Unit 2, oil leak discovered on 2A HPI pump, NCR 02151321
- Unit 3, letdown line penetration #6 relief valve 3HP-934 leaking, NCR 02139215
- Unit 3, radiography identified spacer looseness in 3B HPI pump minimum recirculation orifice, NCR 02142750
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 eight 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 20075352, 1A Reactor Building Spray Motor Replacement, July 19, 2017
- WO 20139283, 1PSW-22 Replace Positioner, July 20, 2017
- WO 20139284, 1PSW-24 Replace Positioner, July 20, 2017
- WO 20162675, Replace ACB-1 Jack Shaft, July 20, 2017
- WO 20085998, Engineering Change (EC) 401423 Perform 3CA Battery Discharge Test, July 24, 2017
- WO 20139285, 2PSW-22 Replace Positioner Control Board, July 25, 2017
- WO 20102614, TT/0/A/EC95361/001 - Keowee Main Transformer Commissioning Test, August 21, 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 six 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/0400/015, SSF Submersible Pump Test (procedure accomplished testing of the PSW submersible pump)
- PT/0/A/0500/020, PSW Power Path Test
- PT/1/A/0261/010, Essential Siphon Vacuum System Test
- PT/3/A/0202/011, HPI Pump Test
- PT/3/A/0251/001, Low Pressure Service Water (LPSW) Pump Test - 3A LPSW Pump
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, Section IV.D 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, interviewed personnel responsible for system performance, and observed aspects of periodic siren maintenance and testing. 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, two changes were made to the Radiological Emergency Plan, one change was made to the emergency action levels, along with changes to several 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, Attachment 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 (EP) 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 EP 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 the licensees adequacy in maintaining them. The inspectors evaluated the capabilities of selected radiation monitoring instrumentation to adequately support Emergency Action Level (EAL)declarations. The inspection was conducted in accordance with NRC Inspection Procedure 71114, Attachment 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.
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, Unit 2, and Unit 3 PIs listed below. The inspectors reviewed plant records compiled between September 2016, and September 2017, 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: Mitigating Systems
- safety system functional failures
- heat removal system
Cornerstone: Barrier Integrity
- reactor coolant system specific activity The inspectors sampled licensee submittals relative to the PIs for the emergency preparedness cornerstone listed below for the period October 1, 2016, through June 30, 2017. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 7, was used to confirm the reporting basis for each data element.
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.
Emergency Preparedness Cornerstone
- Drill/Exercise Performance (DEP)
- Emergency Response Organization Drill Participation (ERO)
- Alert and Notification System Reliability (ANS)
b. Findings
No findings were identified.
4OA2 Problem Identification and Resolution
Routine Review The inspectors screened items entered into the licensees corrective action program to identify repetitive equipment failures or specific human performance issues for followup.
The inspectors reviewed NCRs, attended screening meetings, or accessed the licensees computerized corrective action database.
4OA5 Other Activities
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) and monitored the activities associated with the dry fuel storage campaign completed on July 13, 2017. The inspectors reviewed changes made to the ISFSI programs and procedures, including associated 10 CFR 72.48, Changes, Tests, and Experiments, screens and evaluations to verify that changes made were consistent with the license or certificate of compliance. The inspectors reviewed records and observed the loading activities 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 October 20, 2017, the resident inspectors presented the inspection results to Mr.
Tom Ray 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
- K. Brocklesby, Senior Licensing Specialist
- E. Burchfield, Plant Manager
- C. Dunton, Director of Nuclear Site Support
- M. Dunton, Operations Manager
- R. Elliott, Organizational Performance Manager
- T. Grant, Manager Engineering
- D. Hubbard, Organizational Effectiveness Director
- C. King, Assistant Operations Manager
- P. Kuhlman, Senior Emergency Preparedness Specialist
- W. McIntyre, Emergency Preparedness Manager
- R. Meixell, Regulatory Compliance
- J. Ratliff, Reactor Electrical Systems Director
- T. Ray, Site Vice-President
- T. Roland, Operations Specialist
- D. Thompson, Corporate Functional Area Manager
- C. Wasik, Regulatory Affairs Manager
NRC Personnel
- N. Childs, Resident Inspector
- E. Crowe, Senior Resident Inspector
- F. Ehrhardt, Branch Chief
- C. Fontana, Emergency Preparedness Inspector
- J. Parent, Resident Inspector
- S. Sanchez, Senior Emergency Preparedness Inspector
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
None