ML18225A086
| ML18225A086 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/13/2018 |
| From: | Jon Greives Reactor Projects Region 1 Branch 4 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Greives J | |
| References | |
| IR 2018002, ISFSI 2018002 | |
| Download: ML18225A086 (19) | |
See also: IR 05000277/2018002
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BOULEVARD, SUITE 100
KING OF PRUSSIA, PA 19406-2713
August 13, 2018
Mr. Bryan C. Hanson
Senior Vice President, Exelon Generation Company, LLC
President and Chief Nuclear Officer, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: 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:
On June 30, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at
your Peach Bottom Atomic Power Station (Peach Bottom), Units 2 and 3. On July 13, 2018, the
NRC inspectors discussed the results of this inspection with Mr. Matthew Herr, Plant Manager,
and other members of your staff. The results of this inspection are documented in the enclosed
report.
NRC inspectors documented one finding of very low safety significance (Green) in this report.
The finding involved a violation of NRC requirements. The NRC is treating this violation as a
non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest the violation or significance of the NCV, you should provide a response within
30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear
Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with
copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the
NRCs Resident Inspector at Peach Bottom. In addition, if you disagree with a cross-cutting
aspect assignment or a finding not associated with a regulatory requirement in this report, you
should provide a response within 30 days of the date of this inspection report, with the basis for
your disagreement, to the U. S. Nuclear Regulatory Commission, ATTN: Document Control
Desk, Washington, DC, 20555-0001; with copies to the Regional Administrator, Region I, and
the NRCs Resident Inspector at Peach Bottom.
B. Hanson 2
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
cc w/encl: Distribution via ListServ
Non-Sensitive Publicly Available
SUNSI Review
Sensitive Non-Publicly Available
OFFICE RI/DRP RI/DRP RI/DRP
NAME JHeinly via email SBarber JGreives
DATE 8/9/18 8/9/18 8/13/18
1
U.S. NUCLEAR REGULATORY COMMISSION
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. Grieves, Chief
Reactor Projects Branch 4
Division of Reactor Projects
Enclosure
2
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
3
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 (1 Sample)
The inspectors evaluated summer readiness of offsite and alternate AC power systems on
May 3 and 4, 2018.
71111.04 - Equipment Alignment
Partial Walkdowns (3 Samples)
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
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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 (5 Samples)
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 (1 Sample)
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 (1 Sample)
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 (1 Sample)
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
5
71111.13 - Maintenance Risk Assessments and Emergent Work Control (4 Samples)
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 (5 Samples)
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 (1 Sample)
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 (6 Samples)
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 (5 Samples)
(1) Unit 3 reactor protection system B channel control valve fast closure on
April 9, 2018
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(2) Main control room emergency ventilation logic system functional testing (LSFT) on
April 17, 2018
(3) E-2 EDG ventilation LSFT on April 18, 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 (1 Sample)
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,
2018.
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (1 Sample)
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.
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71124.02 - Occupational As Low As Reasonably Achievable (ALARA) Planning
and Controls
Radiological Work Planning (1 Sample)
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.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification (4 Samples)
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 (1 Sample)
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 (1 Sample)
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
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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 (1 Sample)
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)
9
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
10
(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
11
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
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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.
13
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
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
SO 48.7.A, Emergency Cooling Water System Makeup to Tower Using a High
Pressure Service Water Pump, Revision 10
Drawings
6280-M-359, Sheet 1, RCIC System, Revision 50
6280-M-360, Sheet 1, RCIC Pump Turbine Details, Revision 56
71111.05Q
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
6280-M-1-S-42, Sheet 21, RCIC System, Revision 77
6280-M-359, Sheet 2, RCIC System, Revision 48
6280-M-360, Sheet 2, RCIC Pump Turbine Details, Revision 54
14
4260039
Miscellaneous
EC Number: 623997
Procedures
ER-AA-321, IST Valve Evaluation Form, Revision 12
OP-AA-108-115, Operability Determinations, Revision 21
Condition Reports
4120966 4130754
Drawings
6280-M-1-S-42, Sheet 17, RCIC System, Revision 74
6280-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
15
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
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 04135486
Radiation Work Permits
PB-C-18-205
Documents
RP-AA-401, Attachment 2, Combined ALARA / Micro ALARA Plan, U-2 RWCU Sample Sink
Chiller Work 5/21/2018
Procedures
NISP-RP-003, Nuclear Industry Standard Process - Radiological Air Sampling
RP-AA-300, Radiological Survey Program, Revision 16.
16
Condition Reports
04068960 04070035
Documents
PB 2017, P3R21 Refuel Outage Report (10/232017-11/072017)
PB 2018-2022, Dose Excellence Plan, Revision 0
71151
Procedures
ST-O-020-560-2, Reactor Coolant Leakage Test, Revision 13
71152
4000970
Condition Reports
3990487 4012283
Miscellaneous
PB-17-0027, Obtain Spare CS Motor
71153
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