IR 05000277/2018002
| ML18347A482 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/13/2018 |
| From: | Jon Greives Reactor Projects Region 1 Branch 4 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Greives J | |
| References | |
| IR 2018002 | |
| Download: ML18347A482 (19) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ber 13, 2018
SUBJECT:
ERRATA FOR PEACH BOTTOM ATOMIC POWER STATION - INTEGRATED INSPECTION REPORT 05000277/2018002 AND 05000278/2018002 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07200029/2018002
Dear Mr. Hanson:
The U.S. Nuclear Regulatory Commission (NRC) identified an omission in the original issuance of NRC Integrated Inspection Report 05000277/2018002 and 05000278/2018002 and Independent Spent Fuel Storage Installation Report 07200029/2018002, dated August 13, 2018 (ADAMS Accession No. ML18225A086). Specifically, the inspection report inadvertently omitted the completion of four samples in the Radiation Safety section pertaining to Inspection Procedure 71124.04, Occupational Dose Assessment. As a result, the NRC is reissuing the report in its entirety to correct this omission. The necessary corrections are reflected in the enclosed revised report.
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 the NRCs Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Jonathan E. Greives, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Numbers: 50-277 and 50-278 License Numbers: DPR-44 and DPR-56
Enclosure:
Inspection Report 05000277/2018002 and 05000278/2018002 and 07200029/2018002
Inspection Report
Docket Numbers: 50-277 and 50-278 License Numbers: DPR-44 and DPR-56 Report Numbers: 05000277/2018002 and 05000278/2018002 and 07200029/2018002 Enterprise Identifier: I-2018-002-0064 Licensee: Exelon Generation Company, LLC Facility: Peach Bottom Atomic Power Station, Units 2 and 3 Location: Delta, Pennsylvania Inspection Dates: April 1, 2018 to June 30, 2018 Inspectors: J. Heinly, Senior Resident Inspector B. Smith, Resident Inspector O. Masnyk Bailey, Health Physicist J. Cassata, Health Physicist J. Nicholson, Senior Health Physicist M. Orr, Reactor Inspector A. Turilin, Project Engineer Approved By: Jonathan E. Greives, Chief Reactor Projects Branch 4 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Exelons performance at
Peach Bottom Atomic Power Station, Units 2 and 3, by conducting the baseline inspections described in this report in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC-identified and self-revealed findings, violations, and additional items are summarized in the table below.
List of Findings and Violations Failure to Identify and Promptly Correct a Condition Adverse to Quality Concerning Battery Charger 2B-003-1 Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green NCV P.1 - Problem 71111.19 Systems 05000277/2018-002-01 Identification and Opened/Closed Resolution Identification The NRC identified a Green non-cited violation (NCV) of 10 Code of Federal Regulations (CFR) Part 50, Appendix B, Criterion XVI, Corrective Action, because Exelon did not identify and promptly correct a condition adverse to quality (CAQ) commensurate with its safety significance concerning the 2BD-003-1 safety-related battery charger. Specifically, Exelon did not appropriately prioritize repairs for a CAQ and, as a result, the 2BD-003-1 battery charger failed to operate when placed in service on June 5, 2018.
Additional Tracking Items Type Issue number Title Report Status Section LER 05000277/2018-001-00 Fire Safe Shutdown 71153 Closed Requirements Not Met for Spurious Operation of Valves at a High-Low Pressure Interface
PLANT STATUS
Unit 2 began the inspection period at rated thermal power (RTP). On June 1, 2018, the unit was down powered to 58 percent thermal power to perform summer readiness waterbox cleaning.
The unit was returned to RTP on June 2, 2018, and remained at or near RTP for the remainder of the inspection period.
Unit 3 began the inspection period at RTP. On April 9, 2018, the unit was down powered to 57 percent thermal power to perform power suppression testing for a suspected fuel leak. The unit was returned to RTP on April 12, 2018. On June 8, 2018, the 3B adjustable speed drive tripped off-line and the unit was down powered to 40 percent RTP. Exelon repaired a failed power supply on the 3B adjustable speed drive system and the unit was returned to RTP on June 11, 2018. The unit remained at or near RTP for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification, and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess Exelons performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection Summer Readiness
The inspectors evaluated summer readiness of offsite and alternate AC power systems on May 3 and 4, 2018.
71111.04 - Equipment Alignment Partial Walkdowns
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 reactor core isolation cooling (RCIC) on May 2, 2018
- (2) Offsite power and station blackout on June 14, 2018
- (3) Emergency cooling tower (ECT) on June 25, 2018
Complete Walkdown (1 Sample)
The inspectors evaluated system configurations during a complete walkdown of the Unit 2 high-pressure coolant injection from May 11 through 18, 2018.
71111.05AQ - Fire Protection Annual/Quarterly Quarterly Inspection
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Unit 3 turbine building, 116 elevation on April 10, 2018
- (2) Unit 2 reactor building, 195 general area on April 26, 2018
- (3) ECT, 136 general area on May 3, 2018
- (4) Unit 2 core spray (CS) instrument room, 116 elevation, on May 18, 2018
- (5) Unit 3 main transformer yard on May 21, 2018
71111.07 - Heat Sink Performance Heat Sink
The inspectors evaluated Exelons monitoring and maintenance of the E-4 emergency diesel generator (EDG) heat exchanger on May 7, 2018.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification
The inspectors observed and evaluated the simulator scenario involving a torus leak and anticipated transient without scram on May 7, 2018.
Operator Performance (1 Sample)
The inspectors observed a downpower to support Unit 3 fuel power suppression testing from April 9 through 11, 2018.
71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) a(1) determination for Unit 3 failed fuel assembly from April 30 through May 4, 2018
71111.13 - Maintenance Risk Assessments and Emergent Work Control
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Unit 3 RCIC unavailable and yellow risk on April 22, 2018
- (2) Unit 2 high-pressure coolant injection unavailable and yellow risk on May 2, 2018
- (3) E-1 EDG high crank case pressure trip unavailability on May 4, 2018
- (4) Unit 2 high-pressure service water A inlet to ECT Reservoir valve repairs on June 4, 2018
71111.15 - Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Unit 2 C residual heat removal (RHR) heat exchanger leak on April 6, 2018
- (2) Unit 2 torus vacuum relief valve pressure switch out of service on April 12, 2018
- (3) Unit 2 RCIC MO-2-13-20 valve degraded stroke time on April 25, 2018
- (4) Unit 3 D battery charger fail alarm on May 22, 2018
- (5) Unit 2 and Unit 3 automatic depressurization system backup nitrogen time delay relays out of calibration on June 18, 2018
71111.18 - Plant Modifications
The inspectors evaluated the following permanent modification:
- (1) Engineering Change Package EC07-00031, Unit 3 CS Full Flow Test Valve MO-3-14-026A Not Able to Meet Minimum Thrust on June 12, 2018
71111.19 - Post-Maintenance Testing
The inspectors evaluated post-maintenance testing for the following maintenance/repair activities:
- (1) Unit 3 RCIC failed pressure switch replacement on April 23, 2018
- (2) Unit 2 AO-2-40B-20467 actuator replacement on April 24, 2018
- (3) E-1 EDG high crank case pressure on May 4, 2018
- (4) E-4 EDG cylinder liner replacement on May 17, 2018
- (5) Unit 2 B battery charger repair on June 6, 2018
- (6) E-3 EDG high temperature and turbo charger replacement on June 14, 2018
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Routine
- (1) Unit 3 reactor protection system B channel control valve fast closure on April 9, 2018
- (2) Main control room emergency ventilation logic system functional testing (LSFT) on April 17, 2018
- (4) Chemical storage accounting inventory on April 30, 2018
- (5) Unit 3 B RHR surveillance test on June 7, 2018
Inservice (1 Sample)
- (1) Unit 2 A CS inservice test on May 29, 2018
71114.06 - Drill Evaluation Drill/Training Evolution
The inspectors observed and evaluated the simulator scenario and emergency classification and notifications involving a torus leak and anticipated transient without scram on May 7,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment
The inspectors conducted independent radiation measurements during walkdowns of the facility and reviewed:
- (1) The radiological survey program
- (2) Any changes to plant operations since the last inspection
- (3) Recent plant radiation surveys for radiological work activities
- (4) Air sampling and analysis
- (5) Continuous air monitor use
Contamination and Radioactive Material Control (1 Sample)
The inspectors observed the monitoring of potentially contaminated material leaving the radiological controlled area and inspected the methods and radiation monitoring instrumentation used for control, survey, and release of that material. The inspectors selected several sealed sources from inventory records and assessed whether the sources were accounted for and were tested for loose surface contamination. The inspectors evaluated whether any recent transactions involving nationally tracked sources were reported in accordance with requirements.
Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)
The inspectors evaluated radiation worker performance with respect to radiation protection work permit requirements. The inspectors evaluated radiation protection technicians in performance of radiation surveys and in providing radiological job coverage.
71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning and Controls Radiological Work Planning
The inspectors evaluated radiological work planning by reviewing significant work activities to verify that ALARA planning was integrated into work procedures and radiation work permit documents.
Radiation Worker Performance (1 Sample)
The inspectors observed radiation worker and radiation protection technician performance during radiological work to evaluate worker ALARA performance according to specified work controls and procedures.
71124.04 Occupational Dose Assessment Source Term Characterization
The inspectors verified the licensee has characterized the radiation types and energies being monitored and has developed appropriate scaling factors for hard-to-detect radionuclide activity and alpha radionuclides in internal dose assessments.
External Dosimetry (1 Sample)
The inspectors evaluated external dosimetry to include the following:
- (1) Verification of National Voluntary Laboratory Accreditation Program accreditation for dosimetry processor
- (2) Onsite storage of passive dosimeters
- (3) Determine if bias and correlations for electronic alarming dosimeter are appropriate
Internal Dosimetry (1 Sample)
The inspectors evaluated the internal dosimetry program to include routine bioassay, special bioassay, and dose assessments.
Special Dosimetric Situations (1 Sample)
The inspectors evaluated special dosimetric situations to include declared pregnant workers, dosimeter placement and assessment of effective dose equivalent for external exposures, shallow dose equivalent, neutron dose assessment, and dose of legal record.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below for the period from April 1, 2017 through March 31, 2018.
- (1) Unit 2 Reactor Coolant System (RCS) Activity (BI01)
- (2) Unit 3 RCS Activity (BI01)
- (3) Unit 2 RCS Leakage (B102)
- (4) Unit 3 RCS Leakage (B102)
71152 - Problem Identification and Resolution Semi-Annual Trend Review
The inspectors reviewed Exelons corrective action program (CAP) for trends that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (2 Samples)
The inspectors reviewed Exelons implementation of its CAP related to the following issues:
- (1) Issue Report (IR) 3963696, Cable reliability program on May 29, 2018
- (2) IR 3999563, CS motor vibration trend and extent of condition on June 21, 2018
71153 - Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports
The inspectors evaluated the following Exelon event report which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:
- (1) Licensee Event Report (LER) 05000277/2018-001-00, Fire Safe Shutdown Requirements Not Met for Spurious Operation of Valves at a High-Low Pressure Interface on March 14, 2018. The review for this event is documented in IR 05000277/2018010 and 05000278/2018010 as a licensee-identified NCV.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT, AND ABNORMAL
60855.1 - Operation of an Independent Spent Fuel Storage Installation
The inspectors evaluated Exelons independent spent fuel storage installation cask loading on June 18-22, 2018. Specifically, the inspectors reviewed or observed the following activities:
- (1) Fuel selection and fuel loading
- (2) Heavy load movement of the loaded TN-68 cask
- (3) Closure bolting
- (4) Final helium leak test
- (5) Radiological field surveys
- (6) Drying and backfill evolutions
- (7) Transfer and transport evolutions
- (8) Radiological field surveys
INSPECTION RESULTS
Failure to Identify and Promptly Correct a Condition Adverse to Quality Concerning Battery Charger 2B-003-1 Cornerstone Significance Cross-cutting Report Aspect Section Mitigating Green NCV P.1 - Problem 71111.19 Systems05000277/2018002-01 Identification and Resolution, Identification
Introduction:
The NRC identified a NCV of 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, because Exelon did not identify and promptly correct a CAQ commensurate with its safety significance concerning the 2BD-003-1 safety-related battery charger. Specifically, Exelon did not appropriately prioritize repairs for a CAQ and, as a result, the 2BD-003-1 battery charger failed to operate when placed in service on June 5, 2018.
Description:
Peach Bottom has two independent safety-related 125/250 VDC systems per unit. Each system is comprised of two 125 V batteries, each with its own charger panel consisting of two 100 percent chargers. The safety-related chargers are full wave, silicon controlled rectifiers, suitable for float charging the lead-calcium battery at 2.25 V per cell, and supplying an equalizing charge at 2.33 V per cell. The chargers operate from 480 V, 3 phase, 60 Hz sources supplied from separate 480 V motor control centers and are capable of carrying the normal DC system load and, at the same time, supplying charging current to keep the batteries in a fully charged condition.
On March 5, 2018, IR 4111441 was initiated for Exelon to investigate and troubleshoot a fan failure alarm of the 2BD-003-1 battery charger under Work Order (WO) 4755435. The IR was placed on Exelons priority work list (PWL) and operators swapped in-service battery chargers to the 2BD-003-2 charger in preparation to conduct troubleshooting on the 2BD-003-01 charger. During the troubleshooting for the fan failure alarm, Exelons fix-it-now (FIN)department observed a separate condition; the battery fail alarm light was lit when the battery was placed in-service but unloaded.
IR 4116697 was initiated and closed to WO 4755435 to investigate the new issue concerning the lit 2BD-003-01 fail light. Exelon installed a recorder to obtain data on the 2BD-003-1 while in service before swapping back to the 2BD-003-2 to remain in-service. The recorder data was reviewed for both unloaded and full load battery service. IR 4116697 documents that under full load service, the 2BD-003-1 showed no abnormalities in the recorder traces and that the battery fail light extinguished when load was placed on the charger. The IR recommended no additional actions and concluded that the condition was being worked under and could be closed to WO 4755435. Subsequently, the 2BD-003-1 issue was removed from the PWL.
However, after March 19, 2018, during review of the in-service unloaded traces identified during troubleshooting, FIN identified that the frequency reading on the silicon-controlled rectifier (SCR) bus was 180 Hz as opposed to the expected 360 Hz. FIN also observed that the gate pulses originating from the negative gate SCR driver board were approximately half the amplitude of the positive driver board, and consequently half the amplitude of what would be expected pulses from the negative board. Additionally, FIN observed that the fail light returned to being lit when the battery was unloaded. Following the troubleshooting, FIN concluded that the negative SCR gate driver board and/or the connectors on the harness of the driver board were degraded. FIN initiated a material request on April 3, 2018, to the station warehouse to obtain an in-stock negative gate SCR driver board for replacement. The inspectors identified that this new information that FIN had noted was not documented in a new IR, nor added to the existing IR 4116697, nor documented in the WO completion notes, but only kept on an unofficial record by the FIN lead technician. Therefore, Exelon missed the opportunity to place the issue back on their PWL, to evaluate the risk of a degraded negative SCR gate driver board, and to have work control assign a due date commensurate with Exelons Procedure WC-AA-106, Attachment 1, Revision 18, Priority Screening Matrix.
Considering the part was in stock and work could be performed while 2BD-003-01 was not in-service, the inspectors determined it was reasonable for Exelon to have repaired the degraded condition before the condition worsened or the charger was placed back into service.
On June 5, 2018, Exelon attempted to place the 2BD-003-01 battery charger in service; however, voltage could not be maintained at 130 VDC. Exelon secured 2BD-003-01, entered Technical Specification (TS) 3.8.4, which required restoration of the Unit 2 DC electrical power subsystem within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and then to be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Exelon subsequently placed the 2BD-003-02 battery charger in-service, and exited TS 3.8.4. IR 4144546 was then initiated and troubleshooting recommenced to determine why there was insufficient DC output on 2BD-003-01. Exelon determined that the negative SCR gate driver board had failed rendering 2BD-003-01 inoperable. The negative SCR gate driver board was replaced with the in-stock driver board, the battery charger was tested satisfactorily, and was returned to an operable status with no abnormalities being identified. Exelon subsequently captured the inspectors concerns regarding CAP documentation and prioritization in IR 4149360 written on June 21, 2018.
Corrective Actions: Exelon replaced the negative SCR gate driver board and restored the charger. Additionall, Exelon initiated IR 4149360 to address advocating an earlier repair window, communicating troubleshooting results in a formal manner to other departments (operations, work control, maintenance), and ensuring troubleshooting results are documented in a quality record.
Corrective Action Reference: IR 4149360
Performance Assessment:
Performance Deficiency: The inspectors determined that Exelons failure to identify and promptly perform corrective actions commensurate with the safety significance of a degraded battery charger is a performance deficiency reasonably within Exelons ability to foresee and correct. Specifically, Exelon missed an opportunity by not adequately prioritizing repairs of a degraded negative SCR gate driver board that eventually failed the 2BD-003-1 battery charger on June 5, 2018.
Screening: The finding is more than minor, because it is associated with the Equipment Performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone's objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences (i.e., core damage)
Specifically, 2BD-003-1 failed to perform its safety-related function as a result of Exelon not prioritizing repairs for a CAQ.
Significance: The inspectors evaluated the significance of the finding using IMC 0609, Appendix A, Significance Determination Process for Findings at Power, Exhibit 2 -
Mitigating Systems Screening Questions. The inspectors determined this finding was of very low safety significance (Green) because the finding was not a design deficiency, not a loss of a safety function, and was not the loss of function of a single train for longer than its TS allowed outage time.
Cross-Cutting Aspect: The inspectors determined this finding had a cross-cutting aspect in the area of Problem Identification and Resolution, Identification, because Exelon did not ensure the issue was entered in the CAP in sufficient detail to ensure it could be appropriately prioritized, trended, and assigned for resolution. [P.1]
Enforcement:
Violation: 10 CFR Part 50, Appendix B, Criterion XVI, Corrective Action, requires that measures shall be established to assure conditions adverse to quality are promptly identified and corrected. Contrary to this requirement, from March 19, 2018, until June 5, 2018, Exelon did not promptly identify and correct a CAQ associated with a degraded battery charger 2BD-003-1. Specifically, Exelon did not appropriately prioritize repairs for a CAQ commensurate with its safety significance. As a result, battery charger 2BD-003-1 failed to operate when placed in service on June 5, 2018.
Disposition: This violation is being treated as an NCV, consistent with Section 2.3.2a of the Enforcement Policy.
Observations 71152 Semi-Annual Trend Review The inspectors evaluated a sample of issues and events that occurred over the course of the first and second quarters of 2018 to determine whether issues were appropriately considered as emerging or adverse trends. The inspectors verified that these issues were addressed within the scope of the CAP or through department review.
The inspectors review did not identify any new adverse trends; however, they did identify multiple condition reports that detail CAQs related to engineering programs that are intended to identify, manage, and retain plant design and safety margins. Specifically, the inspectors reviewed issues with the roles and responsibilities within the Structural Monitoring, GL 89-13, In-Service Testing, and Aging Management programs. The inspectors identified that elevated engineering turnover rate and substantial engineering department reorganization was a primary contributor to the documented issues. The inspectors determined that the issues were adequately documented in the CAP (IRs 4094922, 4097435) and reasonable actions have been created to address the issues. While most actions have not been in effect long enough to adequately assess their impact, the inspectors did note positive improvement in the structural monitoring program. The inspectors will continue to monitor the effectiveness of the corrective actions.
Exelon did identify an adverse trend in equipment reliability due to several safety-related and non-safety-related equipment failures in the past six months. These issues were documented in IRs 4155918 and 4155200. The inspectors reviewed the IRs; however, the actions associated have not been completed and will be reviewed under future inspection samples.
The inspectors did not identify any issues of concern at this time.
Exelon performed a self-assessment of the CAP and identified one deficiency and multiple recommendations which were documented in IR 4072771. The deficiency related to the stations adequacy of actions to address an NRC-identified issue of concern documented in an IR. Specifically, the station identified that a required action was not created to address the concern and documented the issue in the CAP under IR 4142994. Furthermore, Exelon reviewed NRC-identified IRs that were closed to work requests that currently remained open.
Exelons review did not identify any immediate safety concerns or operability issues with the remaining work requests. The inspectors determined that Exelons review was adequate and that the deficiency was minor. However, the inspectors noted that an NCV,05000278/2018001-01, had been documented in Inspection Report 2018001 for the failure to perform timely corrective actions for an NRC-identified concern, similar to the deficiency noted above. In addition, the inspectors documented an NCV,05000277/2018002-01, for failure to perform prompt corrective actions for a known degraded condition on the 2B battery charger in this report. The inspectors continue to review the corrective actions from these events and monitor the performance of the CAP to take timely corrective actions for known degraded conditions. No additional issues of concern were identified.
Observations 71152 Cable Reliability Program The inspectors did not identify any findings during the review. However, the inspectors identified the following observations. Exelon missed two opportunities, in 2016 and in 2018, to replace cables associated with the Unit 3 emergency auxiliary transformer after testing results in 2014 concluded that the cables were in the action range and required replacement at the next available work window. In 2018, the validity of the 2014 testing results was brought into question by Exelon. The inspectors noted that the invalid test results identified by the cable reliability program could have been identified and communicated as early as 2014.
Since the communication did not take place until 2018, the station did not appropriately prioritize the replacement schedule given the true condition of the cables. The inspectors also noted that during the period between 2014 and 2018, Exelons cable reliability program held four different program owners which contributed to less program ownership and program continuity than expected.
The inspectors determined that these observations were minor, in that, there had not been an actual adverse impact regarding actual cable performance. Additionally, Exelons cable reliability program had accomplished separate corrective actions to repair multiple underground vaults containing cables important to safety and these repairs had effectively limited the ingress of water into the vaults. The inspectors determined that these actions have adequately protected the medium voltage cables from degradation due to submergence in water. No issues of concern were identified.
Observations 71152 Core Spray Motor Vibrations The inspectors reviewed Exelons corrective actions for an elevated vibration trend on the 2C core spray motor documented under IR 3999563 and NCV 05000277/2017008001. Exelon appropriately entered the issue into their CAP and developed actions to troubleshoot and correct the CAQ. The cause of the elevated vibrations were identified to be resonance vibration of the motor occurring at the normal running speed of the pump. This resonance has induced an elevated vibration in the motor. Exelon is currently performing interim actions to mitigate the resonance vibration while long term actions for the motor replacement can be accomplished. In addition, an extent of condition review was performed on all safety-related vertically mounted pumps which included RHR, high-pressure service water, and emergency service water. It was identified that additional core spray motors had symptoms of resonance vibration, although less significant than the 2C motor. Exelon has established corrective actions to replace these motors with refurbished motors on a staggered schedule. The inspectors determined that Exelons completed and proposed actions were reasonable. The inspectors noted that Exelon consulted with industry vibration experts to develop extensive and in-depth troubleshooting and mitigating actions. The actions appeared reasonable and commensurate with the safety significance of the issue. No additional issues of concern were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 13, 2018, the inspectors presented the quarterly resident inspector inspection results to Mr. Matthew Herr, Plant Manager, and other members of the Exelon staff.
DOCUMENTS REVIEWED
Procedures
MA-AA-716-230-1003, Thermography Program Guide, Revision 5
SE-16, Attachment A, Generation Dispatch TSO Communications to Peach Bottom, Revision 11
Procedures
SO 48.7.A, Emergency Cooling Water System Makeup to Tower Using a High
Pressure Service Water Pump, Revision 10
ST-O-51H-201-2, SBO Line TS 3.8.1 B.1 Verification, Revision 4
ST-O-054-951-2, Offsite and Onsite Electrical Power Breaker Alignment and Power Availability
Check with a Start-Up source and/or EDG Inoperable, Revision 7
Drawings
280-M-359, Sheet 1, RCIC System, Revision 50
280-M-360, Sheet 1, RCIC Pump Turbine Details, Revision 56
Procedures
PF-5F, Unit 2 Reactor Building, CS Instrument Room, Elevation 116-0, Revision 4
PF-5K, Unit 2 Reactor Building, General Area, Elevation 195, Revision 7
PF-136, ECT, General Area, Elevation 123-0/153-0, Revision 3
PF-152, Unit 3 Main Transformer Yard, Revision 6
Procedures
ER-AA-340-1002, Service Water Heat Exchanger Inspection Guide, Revision 7
WC-AA-101-1004, E-4 EDG TSA - WW 1819/1820, Revision 8
Procedures
CC-AA-301, Engineering Standard Request Form, Revision 3
CC-MA-103-2001, Setpoint Methodology for PB and Limerick Generating Station, Revision 2
MA-MA-796-024-1001, Scaffolding Criteria for the Mid-Atlantic Stations, Revision 9
OP-PB-108-117-1000, PB Protected Equipment Tracking Sheet, Attachment 1
SI3P-13-72-ABCE, Calibration Check of RCIC Pump and Turbine Pressure Switches
PS 3-13-67-1 and PS 3-13-72A/B, Revision 7
WC-AA-101-1006, On-line Risk Management and Assessment, Revision 2
Drawings
280-M-1-S-42, Sheet 21, RCIC System, Revision 77
280-M-359, Sheet 2, RCIC System, Revision 48
280-M-360, Sheet 2, RCIC Pump Turbine Details, Revision 54
260039
Miscellaneous
EC Number: 623997
Procedures
ER-AA-321, IST Valve Evaluation Form, Revision 12
OP-AA-108-115, Operability Determinations, Revision 21
Condition Reports
20966 4130754
Drawings
280-M-1-S-42, Sheet 17, RCIC System, Revision 74
280-M-359, Sheet 1, RCIC System, Revision 50
1311814
Engineering Change
ECR PB 07-00031, MO-3-14-026A Not Able to Meet Minimum Thrust, Revision 0
Procedures
MA-AA-716-004, Conduct of Troubleshooting, Revision 15
MA-AA-716-234, FIN Team Process, Revision 12
RT-O-052-254-2, E-4 Diesel Generator Inspection Post-Maintenance Functional Test,
Revision 37
ST-I-052-254-2, E-4 Diesel Generator Inspection Post-Maintenance Instrumentation and Logic
Test, Revision 7
ST-I-052-264-2, E-4 Diesel Generator Inspection Post-Maintenance Handswitch Logic Test,
Revision 3
ST-M-57B-762-2, Battery Charger 2BD003-1 and 2BD003-2 Capability Test, Revision 6
ST-O-052-311-2, E-1 Diesel Generator Slow Start Full Load and IST Test, Revision 22
ST-O-052-414-2, E-4 Diesel Generator Fast Start and Full Load Test, Revision 26
ST-O-094-400-2, Stroke Time Testing of Valves for Pre-Maintenance or PMT, Revision 5
WC-AA-106, Priority Screening Matrix, Attachment 1, Revision 18
WC-AA-111-F-01, Surveillance WO Disposition Sheet, Revision 0
Condition Reports
2685664 3968502 4019553 4025384 4054307 4056725
4066576 4070794 4072646 4078903 4111441 4116697
4130767 4134248 4138230 4138464 4139205 4144536
4144592 4149360
Drawings
D-11938-10, Wiring Diag. Charger 1, Model 130/200R3-S Battery Charger Power State,
Sheet 1 of 1
04306095-01 04595788 04755435
Miscellaneous
Battery Information, 2BD003-1 dated June 6, 2018
Log Entries Search Report dated June 5, 2018
Procedures
EN-AA-501, Controlled Material Storage Owner Inspection Checklist, Attachment 6, Revision 3
SI3F-10-109-B1C2, Calibration Check of RHR B Loop Flow Instruments FT-3-10-109B,
FR-3-10-143, FI-3-10-139B, FT-3-10-111B, FT-3-10-91076B, FT-3-10-91076D,
FI-3-10-91076B, FI-3-10-91076D, and FI-3-10-136B, Revision 7
ST-I-40D-200-2, Control Room Emergency Ventilation LSFT, Revision 11
Miscellaneous
Pennsylvania Tier II Emergency and Hazardous Chemical Inventory, PB, dated January 1, 2017
to December 31, 2017
Condition Reports
1668149 4125513 4314575
Procedures
RP-AA-401, Operational ALARA Planning and Controls, Revision 23
RP-AA-463-1001, Fuel Surveillance Guidance, Revision 4
RW-PB-570, Storage of Radioactive Material and Radiation Waste at the Low Radiation
Storage Area, Revision 007
SF-421, Radiation Protection Requirements for Spent Fuel Casks TN-68-01 through TN-68-44
and TN-68-48 through TN-68-92 Loading and Transport Operations, Revision 008
Condition Reports
04079512 04084790 04098830 04099291
04120191 04122576 04124748 04135486
Radiation Work Permits
PB-C-18-205
PB-C-18-309
PB-C-18-315
Documents
OP-AA-108-111, Attachment 1, Adverse Condition Monitoring and Contingency Plan, dated
4/18/2018
RP-AA-401, Attachment 2, Combined ALARA / Micro ALARA Plan, U-2 RWCU Sample Sink
Chiller Work, dated 5/21/2018
RP-AA-401, Attachment 2, Combined ALARA / Micro ALARA Plan, Floor Drain and Waste
Collector Pump, dated 4/16/2018
RP-AA-401, Attachment 2, Combined ALARA / Micro ALARA Plan, Tri-Nuke Filter Motor, dated
4/25/2018
RP-AA-441, Attachment 2, TEDE ALARA Evaluation of Screening Worksheet, Floor Drain and
Waste Collector Pump, dated 4/25/2018
RP-AA-463-1001, Attachment 5, Radiation Protection Checklist for Nuclear Fuel Failures, dated
4/10/2018.
Procedures
NISP-RP-003, Nuclear Industry Standard Process - Radiological Air Sampling
RP-AA-300, Radiological Survey Program, Revision 16
Condition Reports
4068960 4070035
Documents
PB 2017, P3R21 Refuel Outage Report (10/232017-11/072017)
PB 2018-2022, Dose Excellence Plan, Revision 0
Condition Reports
4062440 4084790
71151
Procedures
ST-O-020-560-2, Reactor Coolant Leakage Test, Revision 13
4000970
Condition Reports
3990487 4012283
Miscellaneous
PB-17-0027, Obtain Spare CS Motor
Procedures
SF-221, Spent Fuel Casks TN-68 Loading and Transport Operations, Revision 20
SF-421, Radiation Protection Requirements for Spent Fuel Casks TN-68-01 through TN-68-44
and TN-68-48 through TN-68-92 Loading and Transport Operations, Revision 8