IR 05000261/2017003
| ML17298B445 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/25/2017 |
| From: | Steven Rose NRC/RGN-II/DRP/RPB4 |
| To: | Kapopoulos E Duke Energy Progress |
| References | |
| IR 2017003 | |
| Download: ML17298B445 (18) | |
Text
UNITED STATES October 25, 2017
SUBJECT:
H. B. ROBINSON STEAM ELECTRIC PLANT - NUCLEAR REGULATORY COMMISSION INTEGRATED INSPECTION REPORT 05000261/2017003
Dear Mr. Kapopoulos:
On September 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your H. B. Robinson Steam Electric Plant, Unit 2. On October 25, 2017, the NRC inspectors discussed the results of this inspection with you and members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation 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/
Steven D. Rose, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket No.: 50-261 License No.: DPR-23
Enclosure:
Inspection Report 05000261/2017003 w/Attachment: Supplemental Information
REGION II==
Docket Nos.: 50-261 License Nos.: DPR-23 Report No.: 05000261/2017003 Licensee: Duke Energy Progress, LLC Facility: H. B. Robinson Steam Electric Plant, Unit 2 Location: 3581 West Entrance Road Hartsville, SC 29550 Dates: July 1, 2017 through September 30, 2017 Inspectors: J. Rotton, Senior Resident Inspector G. Eatmon, Acting Senior Resident Inspector A. Beasten, Resident Inspector D. Jackson, Project Engineer (Section 1R04)
A. Alen, Vogtle Resident Inspector (Section 1R22)
Approved by: Steven D. Rose, Chief Reactor Projects Branch 4 Division of Reactor Projects Enclosure
SUMMARY
Integrated Inspection Report 05000261/2017003, July 1, 2017, through September 30, 2017;
Duke Energy Progress, LLC, H. B. Robinson Steam Electric Plant, Unit 2, Integrated Inspection Report.
The report covered a 3-month period of inspection by resident inspectors and two visiting 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
The unit began the inspection period at essentially 100 percent power and remained there for the duration of the quarter.
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 potential hurricane conditions expected during September 8-11, 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 ramifications of potentially lasting effects that may result from potential hurricane conditions. 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
.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 systems or trains to inspect:
- B containment spray pump while A containment spray pump was out of service for pump alignment
- B emergency diesel generator (EDG) starting air following the B EDG monthly slow speed start
- A service water booster pump (SWBP) while B SWBP was out of service for planned maintenance
.2 Complete Walkdown
The inspectors verified the alignment of the component cooling water system. The inspectors selected this system for assessment because it is a risk-significant mitigating system. The inspectors determined the correct system lineup by reviewing plant procedures, drawings, the updated final safety analysis report, and other documents.
The inspectors reviewed records related to the systems outstanding design issues, maintenance work requests, and deficiencies. The inspectors verified that the selected system was correctly aligned by performing a complete walkdown of accessible components.
To verify the licensee was identifying and resolving equipment alignment discrepancies, the inspectors reviewed corrective action documents, including condition reports and outstanding work orders (WOs). The inspectors also reviewed periodic reports containing information on the status of risk-significant systems, including maintenance rule reports and system health reports. Documents reviewed are listed in the attachment.
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
- water-based fire suppression systems
- gaseous 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 five fire areas to assess material condition and operational status of fire protection equipment. Documents reviewed are listed in the attachment.
- Auxiliary Building Hallway - Central, fire zone 7
- A EDG room, fire zone 2
- Unit 2 cable spread room, fire zone 19
- Rod control room, fire zone 21
- Safety injection pump room, fire zone 3
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 14, 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 stuck open pressurizer spray valve followed by two faulted steam generators outside of containment.
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 21, 2017, the inspectors observed licensed operator performance in the main control room during licensee procedure AOP-003, Malfunction of Reactor Makeup Control.
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 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.
- Nuclear condition report (NCR) 02134763, A CV Spray Pump binding during alignment
- NCR 02144775, 4kV Bus 2 underfrequency trip relay failure
b. Findings
No findings were identified.
1R13 Maintenance Risk Assessments and Emergent Work Control
a. Inspection Scope
The inspectors reviewed the 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.
- July 3-5, 2017, Green risk for emergent work due to issues on containment spray pump A maintenance
- August 7-10, 2017, Green risk for emergent transmission work due to a lightning strike that caused a loss of both auto transformers and multiple sources of 115kV offsite power
- September 14-15, 2017, Emergent green risk for blown steam dump fuses during MST-020
- August 18, 2017, Emergent green risk for 4kV Bus 2 underfrequency trip relay failure and RPS half-trip actuation
- September 13, 2017, Green risk for steam driven auxiliary feedwater (AFW) pump routine maintenance
b. Findings
No findings were identified.
1R15 Operability Determinations and Functionality Assessments
a. Inspection Scope
The inspectors selected the 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.
- NCR 02134816, B SWBP oil level lowering and NCR 02151341, Oil level is dropping in the bubbler for the B SWBP
- NCR 02153161, HVE-17 Damper for B EDG Room not fully closed
- NCR 02134817, C Main transformer oil pumps and fans failure
- NCR 02142653, A and B motor driven AFW pumps flow control valve handwheel locking chain interference with seismic restraints
- NCR02142731, Scaffold in contact with A containment spray pump piping
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 20183706, Charging pump A middle plunger oil leak
- WO 20106048, Contingency task for low margin on containment spray pump A during OST-352-1
- WO 20196752, Bank 1 steam dump loss of indication
- WO 20058597, Dedicated shutdown diesel generator maintenance outage
- WO 20193761, 4kV Bus 2 underfrequency relay failure replacement 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 surveillance tests listed below and either observed the test or reviewed test results to verify testing activities adequately demonstrated that the affected SSCs remained capable of performing the intended safety functions (under conditions as close as practical to design bases conditions or as required by technical specifications) and maintained their operational readiness.
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
- OST-401-2, EDG B Slow Speed Start
- OST-409-1, EDG A Fast Speed Start
- OST-948, Dedicated Shutdown Diesel Generator Auto-start
- OWP-011, Nuclear Instrumentation, and PIC-112, Axial Power Distribution Calibration In-Service Tests (IST)
- OST-908-2, Component Cooling Water Pump A Test Reactor Coolant System Leak Detection
- OST-051, Reactor Coolant System Leakage Evaluation
b. Findings
No findings were identified.
Cornerstone: Emergency Preparedness
1EP6 Drill Evaluation
a. Inspection Scope
The inspectors observed the emergency preparedness drill conducted on July 11, 2017.
The inspectors observed licensee activities in the simulator and/or 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.
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 2 PIs listed below. The inspectors reviewed plant records compiled between April 1, 2016 and March 31, 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: Initiating Events
- unplanned scrams per 7000 critical hours
- unplanned power changes per 7000 critical hours
Cornerstone: Mitigating Systems
- emergency ac power system
- heat removal system
Cornerstone: Barrier Integrity
- reactor coolant system specific activity
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 followup.
The inspectors reviewed condition 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 condition reports:
- NCR 02138493, No Boric Acid Flow while Borating
- NCR 02134817, Pumps and Fans Failed on C Main Transformer 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
No findings were identified.
4OA6 Meetings, Including Exit
On October 25, 2017, the resident inspectors presented the inspection results to Mr. Kapopoulos and other members of the licensees staff. The inspectors confirmed that no proprietary information was retained by the inspectors or documented in this report.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
- F. Giannone, Training Manager
- T. Giese, Manager, Operations Training
- D. Hall, Nuclear Oversite Manager
- S. Hall, Acting Radiation Protection Superintendent
- G. Hartzer, Chemistry Manager
- D. Hoffman, Manager, Operations
- J. Kammer, General Manager, Engineering
- E. Kapopoulos, Site Vice President
- T. Kirwin, Manager, Maintenance
- J. Krakuszeski, Plant General Manager
- C. Orr, Manager, Nuclear Work Management
- T. Pilo, Regulatory Affairs Manager
- D. Pitsley, Manager, Emergency Preparedness
- C. Sherman, Organizational Effectiveness Director
- J. Wild, Regulatory Affairs
NRC personnel
- J. Rotton, Senior Resident Inspector
- A. Beasten, Resident Inspector
- S. Rose, Branch Chief, Region II
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
None