IR 05000440/2018001
| ML18129A406 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/09/2018 |
| From: | Billy Dickson NRC/RGN-III/DRP/B5 |
| To: | Hamilton D FirstEnergy Nuclear Operating Co |
| References | |
| IR 2018001 | |
| Download: ML18129A406 (20) | |
Text
UNITED STATES May 9, 2018
SUBJECT:
PERRY NUCLEAR POWER PLANTNRC INTEGRATED INSPECTION REPORT 05000440/2018001
Dear Mr. Hamilton:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a baseline inspection at your Perry Nuclear Power Plant. On April 4, 2018, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
Based on the results of this inspection, the NRC has identified one issue that was evaluated under the traditional enforcement process. The NRC determined that the issue was a NRC-identified Severity Level IV violation. 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, 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 III; the Director, Office of Enforcement; and the NRC Resident Inspector at the Perry Nuclear Power Plant 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/
Billy Dickson, Chief Branch 5 Division of Reactor Projects Docket No. 50-440 License No. NPF-58 Enclosure:
Inspection Report 05000440/2018001 cc: Distribution via ListServ
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting an integrated quarterly inspection at Perry Nuclear Power Plant Unit 1 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. An NRC violation and additional items are summarized in the tables below.
List of Findings and Violations Failure to Notify the NRC within 60 Days of a Condition Prohibited by Technical Specifications Cornerstone Significance Cross-Cutting Report Aspect Section Not Applicable Severity Level IV Not Applicable 71153 NCV 05000440/2018001-01 Closed The inspectors identified a Severity Level IV Non-Cited Violation of 10 CFR 50.73, Licensee Event Report System, for the licensees failure to report a condition that was prohibited by the plants Technical Specifications to the U.S. Nuclear Regulatory Commission (NRC) within 60 days. Specifically, the licensee did not report a condition that, as determined by the NRC, rendered the Division 2 Diesel Generator (DG) inoperable for a period longer than the Technical Specification allowed completion times of its associated required actions.
Additional Tracking Items Type Issue Number Title Report Status Section LER 05000440/2018-001-00 Loss of Safety Function 71153 Closed and Violation of Technical Specifications due to Diode Failure LER 05000440/2017-007-00 High Pressure Core Spray 71153 Closed Inoperability due to System Leak LER 05000440/2017-006-00 Loss of Safety Function 71153 Closed due to the Inoperability of Both Trains of Motor Control Center Ventilation LER 05000440/2017-002-00 Loss of Safety Function 71153 Closed due to Main Turbine Bypass Valve Opening
TABLE OF CONTENTS
PLANT STATUS
....................................................................................................................... 4
INSPECTION SCOPES
............................................................................................................ 4
REACTOR SAFETY
................................................................................................................. 4
RADIATION SAFETY
............................................................................................................... 7
OTHER ACTIVITIES - BASELINE
........................................................................................... 7
INSPECTION RESULTS
.............................................................................................................. 8
EXIT MEETINGS AND DEBRIEFS
............................................................................................ 11
DOCUMENTS REVIEWED
......................................................................................................... 11
PLANT STATUS
The plant operated at, or near, full power from January 1, 2018, until February 24, 2018, when
power was lowered to approximately 60 percent power to perform a rod sequence exchange
and to perform corrective maintenance on the steam system. The plant returned to full power
on February 25, 2018, and remained at, or near, full power for the remainder of the inspection
period with minor reductions in power to support routine surveillances.
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 licensee performance and
compliance with Commission rules and regulations, license conditions, site procedures, and
standards.
REACTOR SAFETY
71111.01Adverse Weather Protection
Seasonal Extreme Weather (1 Sample)
The inspectors evaluated readiness for seasonal extreme weather conditions prior to the
onset of extremely cold weather.
71111.04Equipment Alignment
Partial Walkdown (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1) High Pressure Core Spray and Division 3 DG on February 28, 2018;
(2) Emergency Service Water (ESW) 'A' on February 26 and 27, 2018; and
(3) Division 2 DG on February 16, 2018.
Complete Walkdown (1 Sample)
The inspectors evaluated system configurations during a complete walkdown of the Standby
Liquid Control system the week of January 29, 2018.
71111.05AQFire Protection Annual/Quarterly
Quarterly Inspection (4 Samples)
The inspectors evaluated fire protection program implementation in the following selected
areas:
(1) Control Complex 574 foot elevation; Fire Zones 0CC-1A, B, and C on
February 16, 2018;
(2) Control Complex 599 and 654 foot elevations; Fire Zones 2 and 5A on March 2, 2018;
(3) Intermediate Building 574, 585, and 599 foot elevations; Fire Zones 0IB-1 and 0IB-2 on
February 27, 2018; and
(4) Division 3 DG room; Fire Zone 1DG-1b on February 9, 2018.
71111.11Licensed Operator Requalification Program and Licensed Operator Performance
Operator Requalification (1 Sample)
The inspectors observed and evaluated a crew of licensed operators responses to an
Anticipated-Transient-Without-Scram accident in the licensees simulator during licensed
operator requalification training on February 12, 2018.
Operator Performance (1 Sample)
The inspectors observed and evaluated licensed operators response to alarms and control and
coordination of activities involving heightened risk in the control room on January 9, 18, 29,
and 30, 2018. Observed activities included an ESW surveillance, crew response to a
service water header low pressure alarm, and an invalid area high radiation alarm in the
turbine building.
71111.12Maintenance Effectiveness
Routine Maintenance Effectiveness (2 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated
with the following equipment and/or safety significant functions:
(1) Vital Direct Current electrical systems; and
(2) High Pressure Core Spray System.
71111.13Maintenance Risk Assessments and Emergent Work Control (5 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent
work activities:
(1) Division 2 DG abnormal noise during run on January 31, 2018;
(2) Division 1 Residual Heat Removal (RHR) out-of-service for Division 1 Remote Shutdown
Panel testing on February 20, 2018;
(3) Control Rod Drive (CRD) Pump 'A' replacement from February 26 through
March 1, 2018;
(4) Average Power Range Monitoring (APRM) System C upscale alarm repair on
March 7, 2018 through March 8, 2018; and
(5) The ESW Sluice Gate A maintenance; Hydrant 24 (fast fire water) repairs; Service
Water Pump C maintenance on March 19 through March 20, 2018.
71111.15Operability Determinations and Functionality Assessments (7 Samples)
The inspectors evaluated the following operability determinations and functionality
assessments:
(1) Flex Bay 2 equipment availability determination from January 2 through 5, 2018;
(2) Area radiation monitors, functionality assessment on January 9, 19, and
February 9, 2018;
(3) Fast fire water alternate injection availability determination from January 31 through
February 1, 2018;
(4) Division 2 DG abnormal noise during run on January 31 and February 1, 2018;
(5) Class 1E 480 VAC bus voltage indicating high out-of-band operability determination on
February 5, 2018;
(6) Reactor Core Isolation Cooling (RCIC) waterleg pump high vibrations on
February 12, 2018; and
(7) Scaffolding and housekeeping issue from February 9 through March 1, 2018.
71111.18Plant Modifications (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
(1) High Pressure Core Spray system minimum flow piping through wall leak weld overlay.
71111.19Post Maintenance Testing (5 Samples)
The inspectors evaluated the following post maintenance tests:
(1) The RCIC maintenance outage on January 30, 2018;
(2) Division 2 DG abnormal noise troubleshooting/repairs on February 1, 2018;
(3) Unit 1 Division 3 battery replacement from February 5 through February 20, 2018;
(4) CRD Pump A replacement from February 26 through March 1, 2018;
(5) ESW Sluice Gate A maintenance from March 19, 2018 through March 23, 2018.
71111.22Surveillance Testing
The inspectors evaluated the following surveillance tests:
Routine (4 Samples)
(1) Standby Liquid Control B pump and valve operability test on February 2, 2018;
(2) Division 1 Remote Shutdown Panel testing on February 20 and 21, 2018;
(3) Reactor Pressure Vessel (RPV) Steam Dome and RHR cut-in permissive high pressure
channel 'B' calibration on February 28 and March 1, 2018; and
(4) Emergency Core Cooling System (ECCS) Drywell pressure high channel 'B' calibration
on March 1, 2018.
In-service (1 Sample)
(1) ESW Pump 'B' and valve operability test on January 29, 2018.
71114.06Drill Evaluation
Drill/Training Evolution (1 Sample)
The inspectors observed a simulator evolution for licensed operators on
February 12, 2018, which required emergency plan implementation and included in the
licensees performance indicator for drill and exercise performance.
RADIATION SAFETY
71124.01Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (1 Sample)
The inspectors evaluated radiological hazards assessments and controls.
Instructions to Workers (1 Sample)
The inspectors evaluated worker instructions.
Contamination and Radioactive Material Control (1 Sample)
The inspectors evaluated contamination and radioactive material controls.
Radiological Hazards Control and Work Coverage (1 Sample)
The inspectors evaluated radiological hazards control and work coverage.
High Radiation Area and Very High Radiation Area Controls (1 Sample)
The inspectors evaluated risk-significant high radiation area and very high radiation area
controls.
Radiation Worker Performance and Radiation Protection Technician Proficiency (1 Sample)
The inspectors evaluated radiation worker performance and radiation protection technician
proficiency.
OTHER ACTIVITIES - BASELINE
71151Performance Indicator Verification (3 Samples)
The inspectors verified licensee performance indicators submittals listed below:
(1) IE01: Unplanned Scrams per 7000 Critical Hours - 1 Sample (January 1, 2017, through
December 31, 2017);
(2) IE03: Unplanned Power Changes per 7000 Critical Hours - 1 Sample (January 1, 2017,
through December 31, 2017); and
(3) IE04: Unplanned Scrams with Complications - 1 Sample (January 1, 2017, through
December 31, 2017).
71152Problem Identification and Resolution
Semiannual Trend Review (1 Sample)
The inspectors reviewed the licensees corrective action program from July 1, 2017, through
December 31, 2017, for trends that might be indicative of a more significant safety issue.
Annual Follow-Up of Selected Issues (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program
related to the following issues:
(1) CR 2017-12527; Flex Storage Bay #2 ambient temperature before 40 degrees
Fahrenheit, and multiple temporary heaters not being pre-staged for extreme cold
weather preparations; and
(2) CR 2018-00132; Effects of internal flooding in the Control Complex 620 elevation
hallway and switchgear rooms.
71153Follow-Up of Events and Notices of Enforcement Discretion
Licensee Event Reports (4 Samples)
The inspectors evaluated the following licensee event reports which can be accessed at
https://lersearch.inl.gov/LERSearchCriteria.aspx:
(1) Licensee Event Report (LER) 05000440/2017007-00; High Pressure Core Spray
Inoperability due to System Leak on March 14, 2018;
(2) LER 05000440/2017006-00; Loss of Safety Function due to the Inoperability of Both
Trains of Motor Control Center Ventilation on March 15, 2018;
(3) LER 05000440/2017002-00; Loss of Safety Function due to Main Turbine Bypass Valve
Opening on March 16, 2018; and
(4) LER 0500440/2018001-00; Loss of Safety Function and Violation of Technical
Specifications due to Diode Failure on March 31, 2018.
INSPECTION RESULTS
71152Problem Identification and Resolution
Observation 71152Semi-Annual Trend Review
The licensee and other external organizations noted several trends during reviews of
activities, events, and issues that occurred in the last six months of 2017. Two trends stood
out. The first was that the causes of important recurring issues were not broadly investigated.
The trend also questioned if remaining planned actions were sufficient to arrest the issues.
The result has been longstanding performance issues in the areas of controlling foreign
material, industrial safety, chemical control, and lifting and rigging. The second trend was
more broadly focused on procedure use and adherence, which the inspectors determined
from two more narrowly focused trends identified by the licensee. These two trends were
shortfalls in the application of maintenance fundamentals contributing to some recent
operational challenges and workers did not always recognize the importance of conscious
implementation of error prevention techniques during planned daily activities. The results
were unplanned entries into Technical Specification limiting condition of operations action
statements, increased potential for damage to equipment, missed Technical Specification
surveillance requirements, unavailability of safety systems, material falling into open fuel
pools, improper dose control, and preventable injuries. Each issue was minor in terms of
significance, but, when reviewed in aggregate, revealed a trend in behaviors that might lead to
more significant issues in the future. The inspectors determined that the licensee had and
continued to take actions to address the identified issues and the behaviors that contributed to
the trends.
Observation 71152Annual Follow-Up of Selected
Issues
For each sample documented in this inspection report (IR), the inspectors confirmed that both
the actions taken and the actions planned by the licensee were appropriate based on the
individual circumstances identified in the condition reports. Specifically, for the Flex
equipment maintained in Storage Bay No. 2, the licensee removed the diesel fuel from the
N+1 air compressor to prevent the diesel fuel from gumming up the injectors at reduced
temperatures. In addition, the licensee developed an action plan to install heaters in the
storage bay to maintain temperatures above 40 degrees Fahrenheit before the onset of
extremely cold weather in the fall of 2018. For the flooding concerns, the licensee has
updated the calculations regarding the effects of internal flooding in the Control Complex 620
elevation switchgear rooms for the fire water piping that was not previously accounted for.
The new calculations showed that additional water would not adversely affect the equipment
in the switchgear rooms.
71153Follow-Up of Events and Notices of Enforcement Discretion
Failure to Notify the NRC within 60 Days of a Condition Prohibited by Technical Specifications
Cornerstone Severity Cross-Cutting Aspect Report
Section
Not Applicable Severity Level IV Not Applicable 71153
Closed
The inspectors identified a Severity Level IV Non-Cited Violation of 10 CFR 50.73, Licensee
Event Report System, for the licensees failure to report a condition that was prohibited by
the plants Technical Specifications to the NRC within 60 days. Specifically, the licensee did
not report a condition that, as determined by the NRC, rendered the Division 2 DG inoperable
for a period longer than the Technical Specification allowed completion times of its associated
required actions.
Description:
In a letter dated August 24, 2017 (IR 05000440/2017010; ML17236A187), the NRC provided
the final significance determination of the preliminary White finding discussed in NRC
IR 05000440/2017009, dated June 5, 2017 (ML17156A750). The August 24 letter and its
enclosures document the NRCs position that a performance deficiency associated with a
diode installation on the Division 2 DG emergency start circuit rendered the DG inoperable
from April 2, 2015 until November 8, 2016. Technical Specification 3.8.1 allow a 14-day
completion time to restore an inoperable D
- G. If the DG is not restored in 14 days, there are
required actions to be in Mode 3 and Mode 4 with completion times of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
respectively. Since the DG was not restored within the required completion times and the
plant was not in Mode 3 with the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the NRC determined that a violation of the
Technical Specifications occurred. As such, the inspectors determined a License Event
Report (LER) for a condition which was prohibited by the plants Technical Specifications was
required. An LER is required if a condition existed for a time longer than permitted by the TS
(i.e., greater than the total allowed restoration and shutdown outage time (or completion time
in the STS)), even if the condition was not discovered until after the allowable time had
elapsed and the condition was rectified immediately upon discovery.
Although the NRC documented the violation of a condition prohibited by the plants Technical
Specifications in an IR, a LER is still required. NUREG 1022 provides additional guidance for
such a situation. Despite the fact the NRC identified a reportable event or condition to the
licensee via inspection activities, Section 2.6 of the NUREG states, in part, that such
conditions do not satisfy 10 CFR 50.73. The regulations in 10 CFR 50.73 specifically require
a submittal of a written LER for an event or condition that meets the criteria stated in those
rules. Therefore, a LER was required within 60 days of August 24, 2017, the date of the final
significance determination letter. No LER was submitted until March, 2018.
Corrective Action: The licensee submitted LER 05000440/2018-001-00 on
March 28, 2018.
Corrective Action Reference: CR 2018-01763
Performance Assessment:
The inspectors determined this violation was associated with a minor performance deficiency.
Enforcement:
The Reactor ROPs significance determination process does not specifically consider the
regulatory process impact in its assessment of licensee performance. Therefore, it is
necessary to address this violation which impedes the NRCs ability to regulate using
traditional enforcement to adequately deter non-compliance.
Violation: Title 10 CFR 50.73(a)(2)(i)(B), Licensee Event Report System, requires, in part
that the licensee shall report any operation or condition which was prohibited by the plants
Technical Specifications within 60 days of discovery of the condition.
Contrary to the above, the licensee failed to notify the NRC within 60 days of receiving the
final determination that the licensee was in a condition prohibited by technical specifications.
Specifically, as determined by the NRC on August 24, 2017, the Division 2 DG was
inoperable from April 2, 2015, until November 8, 2016, which exceeded the allowed
completion times. The licensee did not submit the LER until March 28, 2018.
Severity: IV
Disposition: This violation is being treated as a NCV, consistent with Section 2.3.2 of the
EXIT MEETINGS AND DEBRIEFS
The inspectors confirmed that proprietary information was controlled to protect from public
disclosure. No proprietary information was documented in this report.
- On March 30, 2018, an interim exit meeting was conducted for the inspection results of the
Radiation Safety Program review with Mr.
- F. Payne, Plant General Manager, and other
members of the licensee staff.
- On April 4, 2018, the inspector presented the resident inspector quarterly report inspection
results to Mr. D. Hamilton and other members of the licensee staff.
DOCUMENTS REVIEWED
71111.01Adverse Weather Protection
- CR 2017-12527; Flex Storage Bay No. 2 Ambient Temp Below 40F; December 31, 2017
- CR 2017-12528; Temp Heaters not Staged per Needs of ONI-R36-2; December 31, 2017
- ECP 14-0283-000; Flex Storage Modifications; Revision 4
- eSOMS Plant Narrative Logs; January 1,2, 6, and 7, 2018
- IOI-0015; Seasonal Variations; Revision 29
- ONI-R36-2; Extreme Cold Weather; Revision 8
71111.04Equipment Alignment
- CR 2018-01018; Standby Liquid Control Storage Tank Level Rising; February 5, 2018
- PDB-H0001; 125 VDC Bus ED-1-A; Revision 2
- PDB-H0007; EF-1-A Load List; Revision 2
- PDB-H0008; EF-1-B Load List; Revision 2
- PDB-H0009; EF-1-C Load List; Revision 1
- PDB-H0010; EF-1-D Load List; Revision 2
- VLI-C41; Standby Liquid Control System; Revision 8
- VLI-E22A; High Pressure Core Spray; Revision 10
- VLI-P45; Emergency Service Water System; Revision 19
- VLI-R44/E22B; Division 3 Diesel Generator; Revision 10
- VLI-R44; Division 1 and 2 Diesel Generator Starting Air System; Revision 6
- VLI-R45/E22B; Division 3 Diesel Generator; Revision 3
- VLI-R45; Division 1 and 2 Diesel Generator Fuel Oil System (Unit 1); Revision 5
- VLI-R46/E22B; Division 3 Diesel Generator; Revision 6
- VLI-R46; Division 1 and 2 Diesel Generator Jacket Water Systems (Unit 1); Revision 4
- VLI-R47/E22B; Division 3 Diesel Generator; Revision 4
- VLI-R47; Division 1 and 2 Diesel Generator Lube Oil; Revision 7
- VLI-R48/E22B; Division 3 Diesel Generator; Revision1
- VLI-R48; Division 1 and 2 Diesel Generator Exhaust, Intake and Crankcase Systems;
Revision 6
71111.05AQFire Protection Annual/Quarterly
- CR 2018-02027; U.S. Nuclear Regulatory Commission (NRC) ID: Electrical Wiring in the
Unit 2 NLO Break, Brief, and Locker Area is not Permanent; March 6, 2018
- FPI-0CC; Control Complex; Revision 10
- FPI-0IB; Intermediate Building; Revision 9
- FPI-1DG; Diesel Generator Building; Revision 8
- FPI-1RB; Reactor Building; Revision 4
- FPI-A-A01; Preparation, Review and Approval of Pre-Fire Plan and Fire Protection
Instructions; Revision 5
- FPI-A-B01; Fire Brigade Station, Equipment Inspection and Maintenance; Revision 8
- PAP-1910; Fire Protection Program; Revision 39
71111.11Licensed Operator Requalification Program and Licensed Operator Performance
- eSOMS Plant Narrative Logs; February 1 and 2, 2018
- eSOMS Plant Narrative Logs; January 9, 18, 29, 30, 2018
- NOBP-TR-1151; Nuclear Operating Business Practice; Revision 4
- NOP-OP-1002; Conduct of Operations; Revision 12
- NOP-OP-1009; Operability Determinations and Functionality Assessments; Revision 7
- OTLC-30582806-PY-SGC2 Cycle 6 2018 Evaluate Scenario C2; Revision 0
71111.12Maintenance Effectiveness
- CR 2014-16991; Sludge Found In High Pressure Core Spray (HPCS) Fast Fire Water
Injection Line; November 13, 2014
- CR 2017-09920; Unit 1 Division 3 Reserve Battery Charger Identified Minor Oil Leakage on
the C2, C3, and C4 Capacitors; August 17, 2016
- CR 2018-02185; NRC ID: Documentation Concerns Identified with the Replacement of the
Unit 1 Division 3 Battery; March 9, 2018
- Drawing Number 302-0701-00000; High Pressure Core Spray System; Revision KK
- ECP 17-03760; Temporary Repair of a Pinhole Leak in High Pressure Core Spray Elbow with
a Weld Overlay; December 24, 2017
- Perry Nuclear Power Plant, Plant Health Report 2017-01-E22A-High Pressure Core Spray
System; July 31, 2017
- Perry Nuclear Power Plant, Plant Health Report 2017-02-E22A-High Pressure Core Spray
System; January 31, 2018
- Perry Nuclear Power Plant, Plant Health Report 2017-02-R42-DC Systems (Batteries,
Chargers, and Switchgear); January 31, 2018
- SVI-E22-T5213; Service Test of Battery Capacity-Division 3 (Unit 1); Revision 11
- SVI-E22-T5217; Performance Test of Battery Capacity-Division 3 (Unit 1); Revision 13
- WO 200189778; Replace HPCS Pump Discharge Pressure Transmitter; May 14, 2016
- WO 200451459; Replace All Cells in the Unit 1 Division 3 Battery; February 20, 2018
- WO 200623170; Sludge Downstream of 1E22F0031 CR 2014-16991 Documents the Sludge
Condition. Remove Subject Sludge; May 12, 2016
- WO 200630320; Repair Unit 1 Division 1 Normal Charger; January 28, 2015
- WO 200644355; Partial PMI-0030 HPCS Test Return to Suppression Pool Valve; May 9, 2017
- WO 200644356; Partial PMI-0030 HPCS Suppression Pool Suction Valve; May 11, 2017
- WO 200644361; Partial PMI-0030 HPCS Injection Valve; May 9, 2017
- WO 200647793; Inservice Inspection (ISI) Examinations of HPCS Snubber; March 3, 2017
- WO 200657000; Partial PMI-0030 HPCS Condensate Storage Tank (CST) Suction Isolation;
August 7, 2017
- WO 200673604; Repair Normal Charger EFD-1-A, Float Voltage would not Adjust in Band;
February 16, 2016
- WO 200690712; Replace Capacitors C3, C4, and C5 (Minor Leaking) on Division 3 Battery
Charger; June 9, 2017
- WO 200690740; Local Leak-Rate Test (LLRT) Support-E22T9409 (1E22D0005);
March 14, 2017
- WO 200702207; Repair Instrument Root for HPCS Test Pressure Instrument;
January 14, 2017
71111.13Maintenance Risk Assessments and Emergent Work Control
- CR 2018-02059; APRM C Upscale Alarm Locked in; March 7, 2018
- NOP-OP-1007; Risk Management; Revision 24
- NOP-WM-1001; Order Planning Process; Revision 28
- PAP-1924 Risk-Informed Safety Assessment and Risk Management; Revision 9
- SOI-C51; APRM; Revision 19
- SOI-P45/49; Emergency Service Water and Screen Wash Systems; Revision 31
- SOI-P45/49; Sluice Gate Maintenance; Revision 7
- WO 200170891; Clean and Inspect Bus L21; March 19, 2018
- WO 200612097; Replace Control Rod Drive (CRD) Pump A; February 26, 2018
- WO 200674968; Inspect/Lubricate/Test Sluice Gate; March 19, 2018
- WO 200741192; Investigate Abnormal Noises Division 2 EDG; February 1, 2018
- WO 200744564; T/S Repair APRM C Upscale Locked in; March 8, 2018
71111.15Operability Determinations and Functionality Assessments
- Calculation PSTG-0001; PNPP Class 1E Power Distribution System Voltage Study;
Revision 8
- CR 2018-00208; 1D21-K162 (Area Rad Monitor Turbine Room West) Alert and High Alarms;
January 9, 2018
- CR 2018-00755; Underground Fire Service Water Leak Identified; January 28, 2018
- CR 2018-00825; Post Event 4.0 Crew Critique for the ONI-ZZZ-06 Entry for the Fire Water
Leak at Hydrant 24, January 30, 2018
- CR 2018-00905; Class 1E 480 Bus Voltage Indicating High out of Band per Plant Equipment
Rounds; February 1, 2018
- CR 2018-01060; Div. 3 Diesel Supply Fan, 1M43C0002C, Relay Chattering During Operation;
February 6, 2018
- CR 2018-01193; NRC ID: CR 2018-00208 May not have Fully Identified the Issue;
February 9, 2018
- CR 2018-01227; RCIC Water Leg Pump Vibrations High; February 12, 2018
- CR 2018-01407; NRC ID: Control Complex 574 Elevation Scaffold Laydown Area Storage in
Close Proximity to Control Complex Chill Wwater; February 16, 2018
- CR 2018-01741; NRC ID: IB 599 Scaffold Storage Area Improperly Stored;
February 27, 2018
- CR 2018-01741; NRC ID: IB 599 Scaffold Storage; February 27, 2018
- CR 2018-01785; NRC Identified Shielding Equipment not Stabilized; February 28, 2018
- CR 2018-0887, Abnormal Noise during Division 2 EDG Run; January 1, 2018
- CR G202-2008-40964; Component Design Basis Inspection (CDBI) Concern Grid Voltage
Above Maximum Analyzed Limit; May 28, 2008
- ECP 14-0283-000; Flex Storage Modifications; Revision 4
- EOP-SPI4.6; Fast Fire Water Alternate Injection; Revision 1
- eSOMS Plant Narrative Log; January 9, 2018
- eSOMS Plant Narrative Logs; January 1 and 2, 2018
- eSOMS Plant Narrative Logs; January 28 and 29, 2018
- FCR 24484; Scaffold Storage; November 12, 1997
- ICI-B22-2; AC Switchboard and Panel Voltmeters (B22-2); Revision 4
- IOI-0015; Seasonal Variations; Revision 29
- NOP-LP-7300; FLEX Program for the Perry Nuclear Power Plant (PNPP); Revision 1
- NOP-MM-5008; Control of Scaffolding; Revision 1
- NORM-OP-1012; Material Readiness and Housekeeping Inspection Program Areas and
Owners; Revision 4
- ONI-R36-2; Extreme Cold Weather; Revision 8
- ONI-S11; Hi/Low Voltage; Revision 10
- PAP-0204; Housekeeping / Cleanliness Control Program; Revision 29
- PAP-0204; Housekeeping/Cleanliness Control Program; Revision 29
- PDB-H0007; EF-1-A Load List; Revision 2
- PDB-H0008; EF-1-B Load List; Revision 2
- PDB-H0009; EF-1-C Load List; Revision 1
- PDB-H0010; EF-1-D Load List; Revision 2
- PDB-R0003; Flex Specifications; Revision 2
- SOI-D21; Area Radiation Monitoring System; Revision 4
- SVI-R10-T5228; On-Site Power Distribution System Verification; Revision 7
- Updated Safety Analysis Report (USAR) 9.4; Revision 12
71111.18Plant Modifications
- 1E22G003A Addendum No. A-01; Pipe Stress Analysis 1E22G003A; Revision 3
- CR 2017-12407; Through-Wall Leak in HPCS Min Flow Piping Elbow; December 23, 2017
- ECP No. 17-0423-001; Weld Overlay on Through-Wall Leak in HPCS Minimum Flow Piping
Elbow; Revision 0
- NOP-CC-5762; Appendix VIII Procedure for Ultrasonic Examination of Ferritic Pipe Welds;
Revision 2
- NOP-M-5008; Control of Scaffolding; Revision 1
- NQI-0946; Digital Ultrasonic Thickness Measurement; Revision 12
- Report No. 0942-17B-051; Magnetic Particle Examination; December 24, 2017
- WO 200737512; Perform Weld Overlay of Pin Hole in 4 Elbow; ECP No. 17-0423-001;
January 5, 2018
71111.19Post Maintenance Testing
- CR 2018-01462; Unit 1 Div 3 Battery Without 200451459 Surveillance Test Cover Sheets
Raised Questions to Operations in Reference to Vendor Testing; February 19, 2018
- FTI-F0036; Post-Maintenance Test Manual; Revision 11
- GEI-0049; AC and DC Motor Testing; Revision 8
- NOP-ER-3030; Surveillance Frequency Control Program, Revision 0
- NOP-WM-1005; Work Management Order Testing Process; Revision 6
- PDB-R0002; Perry Surveillance Test Interval List; Revision 2
- SOI-C11; Control Rod Drive Hydraulic System; Revision 29
- SOI-P45/49; Emergency Service Water and Screen Wash Systems; Revision 31
- SOI-P45/49; Sluice Gate Maintenance; Revision 7
- TAI-2000-2; Vibration Monitoring; Revision 5
- TAI-2000-5; Electric Motor Predictive Monitoring Program; Revision 6
- WO 200451459; Replace All Cells in the Unit 1 Division 3 Batter; February 5, 2018
- WO 200518410; Lube Oil Cooler Inspection and Cleaning; January 27, 2018
- WO 200612097; Replace CRD Pump A; February 26, 2018
- WO 200674968; Inspect/Lubricate / Test Sluice Gate; March 19, 2018
- WO 200675074; Replace RCIC Waterleg Pump; January 25, 2018
- WO 200690671; Change Oil Filter, Sample Oil, Inspect RCIC Turbine; January 27, 2018
- WO 200701700; Perform Static MOV Test RCIC Steam Shutoff SMB-0 on Four Inch Borg
Warner Globe; January 27, 2018
- WO 200741192; Investigate Abnormal Noises Division 2 EDG; February 1, 2018
71111.22Surveillance Testing
- CR 2018-01018; Standby Liquid Control Storage Tank Level Rising; February 5, 2018
- CR 2018-01550; Division 1 Shutdown Surveillance Step Unable to be Performed as Written;
February 21, 2018
- CR 2018-01817; SVI-B21-T0138B (200675187) Data Exceeded PMMD Program Drift Limit
Criteria; March 1, 2018
- Partial, SVI-C41-T2001-B; Standby Liquid Control B Pump and Valve Operability Test;
February 5, 2018
- SVI-B21-T0033-B; RPV Steam Dome and RHR Cut-In Permissive High Pressure Channel B
Calibration for 1B21-N678B; February 28, 2018
- SVI-B21-T0138-B; ECCS Drywell Pressure High Channel 'B' Calibration for 1B21-N094B;
March 1, 2018
- SVI-C41-T1026; Standby Liquid Control Boron Concentration; February 5, 2018
- SVI-C41-T2001-B; Standby Liquid Control B Pump and Valve Operability Test;
February 3, 2018
- SVI-C61-T1201; Remote Shutdown Panel 1C61-P001 Control Operability Test RHR A,
ESW A, ECC A, and Division 1 Diesel Generator; Revision 15
- SVI-P45-T2002; ESW Pump B and Valve Operability Test; Revision 39
- WO 200674925; (24M) RPV Steam Dome and RHR Cut-In Permissive High Pressure Channel
B Calibration for 1B21-N678B; February 28, 2018
- WO 200675187; (24M) ECCS Drywell Pressure High Channel B Calibration for
1B21- N094B; March 1, 2018
- WO 200680426; Standby Liquid Control B Pump and Valve Operability Test;
February 3, 2018
- WO 200680470; ESW Pump B and Valve Operability Test; January 29, 2018
- WO 200681295; SVI-C61T1201; February 19, 2018
- WO200741544; Partial, Standby Liquid Control B Pump and Valve Operability Test;
February 5, 2018
71114.06Drill Evaluation
- OTLC-30582806-PY-SGC2 Cycle 6 2018 Evaluate Scenario C2; Revision 0
71124.01Radiological Hazard Assessment and Exposure Controls
- CR 2017-02582; Elevated Counts on Radiological Air Sample Containment 690 Refueling
Floor; March 9, 2017
- CR 2017-02770; Emerging Trend in Radiological Performance; March 12, 2017
- CR 2017-03241; Radiological Stop Work Criteria was Met for Work on 1B33F0023B Plug
Drain Appendage; March 22, 2017
- CR 2017-03617; Airborne Radioactivity on the Refuel Floor Stopped Work; March 30, 2017
- CR 2017-03754; Worker Received Dose Rate Alarm During Close Out Inspection;
April 2, 2018
- CR 2017-05573; Radiation Protection Periodic Barrier/Barricade Surveillance Performed by
Unqualified Personnel; May 16, 2017
- CR 2017-08708; MS-C-17-08-03; Improper ALARA WIP Documentation; August 23, 2017
- CR 2017-10762; Radiological Survey PY-M-20170718-1 Contains Incomplete Information;
October 25, 2017
- Electronic Dosimetry Dose and Dose Rate Alarms; April 1, 2017 to present
- National Source Tracking System 2018 Reconciliation; January 8, 2018
- NOP-OP-4101; Access controls for Radiologically Controlled Areas; Revision 14
- Periodic Barrier/Barricade Surveillance; March 22, 2018
- Radioactive Source Leak Test Data; August 20, 2017
- Radioactive Source Leak Test Data; February 22, 2018
- Radioactive Storage Yard Inventory Logs; March 2018
- Radiological Air Sample Records; Various Records
- Radiological Survey Records; Various Records
- RWP 17-0113; 1N23D0001 F Septa Filter Replacement; Revision 0
- RWP 18-0203; RW Liner Processing/Storing/Shipments <50R; Revision 0
- RWP 18-0309; RW Area-Waste Collector/Floor Drain Collector Filter; Revision 0
- RWP 18-0312; OG Preheater/Recombiner Steam Leak; Revision 0
- SVI-E31-T5190; Sealed Source Leak Test and Inventory; Revision 8
71151Performance Indicator Verification
- NOBP-LP-4012; NRC Performance Indicators; Revision 5
- NOBP-LP-4012; NRC Performance Indicators; Revision 6
- NOBP-LP-4012-01; Unplanned Scrams per 7,000 Critical Hours; Revision 2; January, 2017
through December, 2017
- NOBP-LP-4012-02; Unplanned Scrams with Complications (USwC); Revision 3;
January, 2017 through December, 2017
- NOBP-LP-4012-03; Unplanned Power Changes per 7,000 Critical Hours; Revision 2;
January, 2017 through December, 2017
71152Problem Identification and Resolution
- CR 2018-00916; Cognitive Trending has Identified a Rise in Operations Worker Practices
- CR 2018-01018; SLC Storage Tank Level Rising; February 5, 2018
- CRs for January, 2018; February 1, 2018
71153Follow-Up of Events and Notices of Enforcement Discretion
- CR 2018-01763; NRC ID: LER Required for DG Diode Failure; February 28, 2018
- NRC IR 05000440/2017009 (ML17156A750); NRC Inspection Report and Preliminary White
Finding; June 5, 2017
- NRC IR 05000440/2017010 (ML17236A187): Final Significance Determination of a White
Finding and Notice of Violation; August 24, 2017
- NUREG 1022; Event Report Guidelines 10 CFR 50.72 and 50.73; Revision 3
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE RD. SUITE 210
LISLE, ILLINOIS 60532-4352
May 9, 2018
Mr. David B. Hamilton
Site Vice President
FirstEnergy Nuclear Operating Company
Perry Nuclear Power Plant
Reg Affairs-A210
Center Road, P.O. Box 97
Perry, OH 44081-0097
SUBJECT: PERRY NUCLEAR POWER PLANTNRC INTEGRATED INSPECTION REPORT
Dear Mr. Hamilton:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a baseline
inspection at your Perry Nuclear Power Plant. On April 4, 2018, the NRC inspectors discussed
the results of this inspection with you and other members of your staff. The results of this
inspection are documented in the enclosed report.
Based on the results of this inspection, the NRC has identified one issue that was evaluated
under the traditional enforcement process. The NRC determined that the issue was a
NRC-identified Severity Level IV violation. 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, you should provide a response within 30 days of the date of this
inspection report, with the basis for your denial, to the
ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional
Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector
at the Perry Nuclear Power Plant
D. Hamilton -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 at the NRC Public Document
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
Sincerely,
/RA/
Billy Dickson, Chief
Branch 5
Division of Reactor Projects
Docket No. 50-440
License No. NPF-58
Enclosure:
Inspection Report 05000440/2018001
cc: Distribution via ListServ
D. Hamilton -3-
Letter to David Hamilton from Billy Dickson dated May 9, 2018
SUBJECT: PERRY NUCLEAR POWER PLANTNRC INTEGRATED INSPECTION REPORT