IR 05000440/2019001
| ML19127A241 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/07/2019 |
| From: | Dariusz Szwarc NRC/RGN-III/DRP/B2 |
| To: | Hamilton D FirstEnergy Nuclear Operating Co |
| References | |
| IR 2019001 | |
| Download: ML19127A241 (18) | |
Text
SUBJECT:
PERRY NUCLEAR GENERATING PLANT, UNIT 1NRC INTEGRATED INSPECTION REPORT 05000440/2019001
Dear Mr. Hamilton:
On March 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Perry Nuclear Generating Plant, Unit 1. On April 10, 2019, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspectors did not identify any finding or violation of more than minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Dariusz Szwarc, Acting Chief Branch 2 Division of Reactor Projects Docket No.: 05000440 License No.: NPF-58
Enclosure:
Inspection Report 05000440/2019001
Inspection Report
Docket Number: 05000440 License Number: NPF-58 Report Number: 05000440/2019001 Enterprise Identifier: I-2019-001-0059 Licensee: FirstEnergy Nuclear Operating Company Facility: Perry Nuclear Generating Plant, Unit 1 Location: Perry, OH 44081 Inspection Dates: January 01, 2019 to March 31, 2019 Inspectors: S. Bell, Health Physicist V. Meghani, Reactor Inspector V. Myers, Senior Health Physicist J. Nance, Resident Inspector J. Park, Reactor Inspector N. Peterka, Fuel Facility Inspector J. Rutkowski, Project Engineer J. Steffes, Senior Resident Inspector Approved By: Dariusz Szwarc, Acting Chief Branch 2 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a quarterly inspection at Perry Nuclear Generating 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. Findings and violations being considered in the NRCs assessment are summarized in the table below.
List of Findings and Violations No findings or violations were identified.
Additional Tracking Items Type Issue Number Title Report Section Status URI 05000440/2018003-01 Application of ASME Code Case 71152 Closed N-513-3 for the Emergency Service Water (ESW) Piping Degradations
PLANT STATUS
Perry Nuclear Power Plant began the inspection period at 89 percent of rated thermal power in coastdown operations prior to a refueling outage. On February 25, 2019, the unit scrammed in response to a turbine trip caused by a loss of excitation to the generator. The loss of excitation was caused by a loss of electrical continuity between the exciter brushes and collector rings. The licensee repaired the exciter brushes and collector rings, commenced a reactor start upon February 27, 2019, and synchronized to the grid on February 28, 2019.
The unit achieved maximum attainable power and continued coastdown operations on March 5, 2019. On March 9, 2019, the unit was shutdown for refuel outage 1R17. The reactor remained shutdown in the refueling outage for the remainder of the inspection period.
On April 25, 2018, FirstEnergy Solutions (FES) / FirstEnergy Nuclear Operating Company (FENOC) notified the U.S. Nuclear Regulatory Commission (NRC) that they intend to shut down all four of their operating nuclear power plants (ADAMS Accession Number ML18115A007). Perry Nuclear Power Plant, Unit 1, is scheduled to be shut down May 31, 2021. On March 31, 2018, FES, FirstEnergy Nuclear Generation (FENGEN), and FENOC filed for bankruptcy. The NRC continues to maintain focus on public health and safety and the protection of the environment. This will include a continuous evaluation by inspectors to determine whether the licensees financial condition is impacting safe operation of the plant.
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
71111.01 - Adverse Weather Protection Impending Severe Weather Sample (IP Section 03.03)
The inspectors evaluated readiness for impending adverse weather conditions for Winter Storm Jayden and severe cold on January 28 and 29, 2019.
71111.04 - Equipment Alignment Partial Walkdown (IP Section 02.01)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) High pressure core spray and emergency diesel generator/division 3 on January 18, 2019;
- (2) Emergency diesel generator/division 2 on February 12, 2019; and
- (3) Train "B" emergency closed cooling system while the division 1 emergency diesel generator was unavailable on February 22, 2019.
71111.05A - Fire Protection (Annual) Annual Inspection (IP Section 03.02)
The inspectors evaluated fire brigade performance on February 4, 2019.
71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Diesel generator building division 3 diesel generator room fire zone 1DG-1B on January 18, 2019;
- (2) Control complex 599 and 654 foot elevation fire zones 2 and 5a on February 11 and 14, 2019;
- (3) Control complex 574 foot elevation fire zones 1a,b, and c on February 14, 2019; and
- (4) Intermediate building 574, 585, and 599 foot elevations, fire zones FZ 0IB-1, and FZ 0IB-2 on February 23, 2019.
71111.08G - In Service Inspection Activities BWR In Service Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)
The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from March 11 to March 15, 2019 03.01.a - Nondestructive Examination and Welding Activities.
- Ultrasonic examination (UT) of High Pressure Core Spray, 12 inch elbow-to-pipe weld, 1E22-0003
- Ultrasonic examination (UT) of High Pressure Core Spray, 12 inch elbow-to-pipe weld, 1E22-0003
- Visual examination (VT3) of Snubber pipe support, 1E22-H0005
- Visual examination (VT3) of Variable spring pipe support, 1E22-H0006
- Visual examination (VT3) of Containment Steam Tunnel, Elevation 616-649, AZ 340-20, 1T23-022-I
- AVR-16-07, ASME Section XI Flaw Evaluation, Weld ID 1B13-N1A-KA
- Replace 4 elbow on High Pressure Core Spray Minimum Flow Line (WO 200737508)
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
The inspectors observed and evaluated licensed operator performance in the Control Room during reactor shutdown for refueling outage on March 9, 2019, plant cooldown operations following reactor scram on February 25, 2019, and for operator actions with core flow greater than design flow limit on February 11, 2019.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
The inspectors observed and evaluated an operations crew-evaluation scenario in the plant training simulator on January 14, 2019.
71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Single point vulnerability of 125 VDC distribution system due to unexpected 125 VDC Unit 1 Division 1 Normal Battery Charger inoperability for not being able to maintain proper voltage on January 28, 2019;
- (2) Division 1 diesel generator left bank cylinder number 5 jacket water flange leakage repair on February 12 to 13, 2019;
- (3) Main steam re-heater 2B 1st stage drain tank level control troubleshooting and replacement activities on January 16, 2019; and
- (4) Plant risk evaluation while interbus transformer LH-1-A removed from service for maintenance during the refueling outage on March 26 to 28, 2019.
71111.15 - Operability Determinations and Functionality Assessments Operability Determinations and Functionality Assessments (IP Section 02.01)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Redundant Reactivity Control System Division 2 operability determination;
- (2) Suppression Pool Atmospheric Penetration Isolation Valve, 1P87-F071, operability determination;
- (3) 125 VDC Unit 1 Division 1 Normal Battery Charger operability determination;
- (4) Combustion gas hydrogen analyzer 'A' and 'B' sample containment isolation valves operability determination; and
- (5) B5B pump failed to start during quarterly testing on February 6, 2019.
71111.19 - Post Maintenance Testing Post Maintenance Test Sample (IP Section 03.01)
The inspectors evaluated the following post maintenance tests:
- (1) 125 VDC unit 1 division 1 normal battery charger repair post maintenance test on February 11 to 12, 2019;
- (2) Post maintenance test following control rod drive pump 'B' seal pressure switch and auxiliary oil pump start permissive switch calibrations and adjustments on January 24, 2019;
- (3) Division 1 emergency diesel generator jacket water leak repair post maintenance test work order 200780644;
- (4) Diesel driven fire pump coolant leak post maintenance test work order 200780675; and
- (5) SVI-R22-T5073, Division 2, 4-Kilovolt Bus EH-12 Undervoltage/Degraded Voltage Channel Calibration and Logic System Functional Test following system modification on March 19, 2019.
==71111.20 - Refueling and Other Outage Activities Refueling/Other Outage Sample (IP Section 03.01) (1 Sample 1 Partial)
- (1) The inspectors evaluated forced outage activities following turbine trip and subsequent reactor trip due to a loss of turbine generator excitation from February 25 to 28, 2019; and (2) (Partial) The inspectors evaluated refueling outage 1R17 activities from March 9 to March 31, 2019. Activities evaluated by the inspectors included, but were not limited to, shutdown and cooldown operations, reduced inventory control, containment walkdown, reactor vessel disassembly for heavy load controls and shutdown risk.
==71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests:
==
Containment Isolation Valve (ISO) (IP Section 03.01)==
SVI-E21-T2200, Low-Pressure Core Spray Isolation Valve Leak Rate Test on March 28, 2019.
In Service Testing (IST) (IP Section 03.01) (1 Sample)
SVI-P45-T2003, High Pressure Core Spray Emergency Service Water Pump and Valve Operability Test on January 7, 2019.
Surveillance Testing (IP Section 03.01) (7 Samples)
- (1) Temporary external flood barrier inspections on January 17, 2019;
- (2) SVI-C71-T0257-D, Turbine Stop Valve Channel 'D' closure and EOC-RPT Response Time Test on January 17 and 18, 2019;
- (3) SVI-M51-T2001, Combustible Gas Control System Valves Full Exercise and Stroke Time Test on February 19 and 20, 2019;
- (4) SVI-E21-T2001, Low Pressure Core Spray Pump and Valve Operability Test on February 20 and 21, 2019;
- (5) SVI-R43-T1330, Simultaneous Start of All Diesel Generators on March 28, 2019;
- (6) TXI-0457, Division 2 Standby Diesel Generator Load Rejection Test on March 12 to 13, 2019; and
- (7) PTI-N32-P0003, Turbine Overspeed Test on March 10, 2019.
71114.06 - Drill Evaluation Drill and/or Simulator-Based Licensed Operator Requalification Training (IP Section 02.01)
The inspectors evaluated:
- a simulator-based licensed operator requalification training on January 14,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls Contamination and Radioactive Material Control (IP Section 02.03)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material. The inspectors verified the following sealed sources are accounted for and are intact:
- Source Number 41.00 Cs-137
- Source Number 42.00 Cs-137 High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)
The inspectors evaluated risk-significant high radiation area and very high radiation area controls.
Instructions to Workers (IP Section 02.02) (1 Sample)
The inspectors evaluated instructions to workers including radiation work permits (RWPs)used to access high radiation areas:
Radiation work packages
- RWP 190907; 1R17 Refueling Activities; Revision 0
- RWP 190518; 1R17 Undervessel Activities; Revision 0 Electronic alarming dosimeter alarms
- Dose Alarm, 05/12/18 09:48
- Dose Rate Alarm, 03/17/19 01:00
- Dose Rate Alarm, 03/21/19 04:06
- Dose Rate Alarm, 03/14/19 13:17 Labeling of containers
- 40' Sealand Container
- 690' Refuel Floor Equipment Boxes
- (5) Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)
The inspectors evaluated radiation worker performance and radiation protection technician proficiency.
Radiological Hazard Assessment (IP Section 02.01) (1 Sample)
The inspectors evaluated radiological hazards assessments and controls. The inspectors reviewed the following:
Radiological surveys
- 1R17 Undervessel
- 1R17 690' Refuel Floor
- 1R17 Drywell Bioshield Risk significant radiological work activities
- 1R17 Refuel Floor Activities
- 1R17 Drywell Bioshield ISI
- 1R17 Undervessel Air sample survey records
- 690 Refuel Floor NE; 03/15/19 01:15
- 690 Refuel Floor NE; 03/15/19 10:55
- 690 Refuel Floor NE; 03/15/19 14:36
- 690 Refuel Floor NW; 03/13/19 14:17 Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
Radiological work package for areas with airborne radioactivity
- RWP 190907; 1R17 Refueling Activities; Revision 0
- RWP 190518; 1R17 Undervessel Activities, Revision 0
71124.02 - Occupational ALARA Planning and Controls Implementation of ALARA and Radiological Work Controls (IPSection 02.03)
The inspectors reviewed ALARA practices and radiological work controls by reviewing the following activities:
- RWP 190518, 1R17 Undervessel Activities, Revision 0
- RWP 190907, 1R17 Refueling Activities, Revision 0
Radiation Worker Performance (IP Section 02.04) (1 Sample)
The inspectors evaluated radiation worker and radiation protection technician performance during the 1R17 refueling outage. Observations of activities are listed in section 02.03.
71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation Radioactive Material Storage (IP Section 02.01)
The inspectors evaluated radioactive material storage in the follow areas:
- The Outside Container Storage Yard
- The WHARF (indoor radioactive material storage building)
Container check (e.g., swelling, leakage and deformation)
- Concrete Shielded Storage Containers
- 20' Sealand Containers
- 40' Sealand Containers
- Miscellaneous Radioactive Material Storage Containers in the Outside Container Storage Yard Radioactive Waste System Walkdown (IP Section 02.02) (1 Sample)
The inspectors evaluated the following radioactive waste processing systems during plant walkdowns:
Liquid or solid radioactive waste processing systems
- Liquid Radwaste Processing System Radioactive waste resin and/or sludge discharges processes:
- Avantech Ultra Rapid Dewatering Processing System
Shipment Preparation (IP Section 02.04) (1 Sample)
The inspectors evaluated [and observed] the radioactive material shipment preparation processes.
- 19-2002; Radioactive Material Shipment (Laundry) 03/06/19
Shipping Records (IP Section 02.05) (1 Sample)
The inspectors evaluated the following non-excepted package shipment records:
- 17-1037; Radioactive Waste Shipment; Decontamination Resin; 7/17/17
- 18-1016; Radioactive Waste Shipment; Resin; 06/07/18
- 18-3004; Radioactive Material Shipment; 03/01/18
- 19-2002; Radioactive Material Shipment; 03/06/19 Waste Characterization and Classification (IP Section 02.03) (1 Sample)
The inspectors evaluated the radioactive waste characterization and classification for the following waste streams:
- Primary System Resin
- Decontamination System Resin
- Dry Active Waste (DAW)
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===
Unit 1 (January 1, 2018 - December 31, 2018)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)
(1 Sample)
Unit 1 (January 1, 2018 - December 31, 2018)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
Unit 1 (January 1, 2018 - December 31, 2018)
==71152 - Problem Identification and Resolution Annual Follow-Up of Selected Issues (IP Section 02.03) (1 Partial)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- URI 05000440/2018003-01, Application of ASME Code Case N-513-3 for the Emergency Service Water (ESW) Piping Degradations.
The inspectors' review and closure of the URI did not constitute an inspection sample.
71153 - Follow-Up of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)==
The inspectors evaluated plant response to a turbine trip and reactor scram and the associated licensee performance on February 26 to 27,
INSPECTION RESULTS
Unresolved Item Application of ASME Code Case N-513-3 for the 71152 (Closed) Emergency Service Water (ESW) Piping Degradations05000440/2018003-01
Description:
On June 13th, 2018, a through-wall leak on the 20 Emergency Service Water (ESW) piping was identified in condition report (CR) 2018-05504. The licensee elected to apply American Society of Mechanical Engineer (ASME) Code Case N-513-3, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping, Section XI, Division 1 to evaluate this flaw to justify leaving the degraded ESW piping system in service for a limited period without repair/replacement. In accordance with the code case, the licensee performed a sample expansion to five additional locations and identified localized wall degradation on the 8 ESW elbow on July 10, 2018. The inspectors identified that the licensee used an alternate methodology, not described in the code case, to evaluate this degradation on the pipe elbow.
The licensee also did not perform another examination scope expansion to five additional locations for the degradation on the pipe elbow, as that flaw was not deemed as rejectable in that evaluation. However, wording in the code case seemed to imply that the sample expansion requirement applied to all flaws, not just those rejectable. As a result, the inspectors generated an Unresolved Item (URI)05000440/2018003-01 associated with the licensees application of the ASME Code Case N-513-3. Specifically,
- (1) whether the licensee was required to use the methodology described in the Code Case Section 3.2 in evaluating a flaw identified during a sample expansion performed in accordance with the code case, and
- (2) whether the licensees decision to stop the scope expansion for additional examinations that is discussed in Code Case Section 5(b) was appropriate. In response to the inspectors concern, the licensee initiated CR 2018-08483, NRC ID: Code Case N-513-3 Interpretation on September 26, 2018.
The licensee completed examination of five additional locations in November of 2018.
The inspectors discussed this issue with staff from the Office of Nuclear Reactor Regulation (NRR), who in turn interfaced with ASME code committee members regarding the intent of the code case, and concluded that the wording in this particular code case is ambiguous with respect to
- (1) and
- (2) above. Discussions on how to best add clarity to the code case wording continued. Based on this review, no performance deficiencies and associated violations of NRC regulations were identified, and URI 05000440/2018003-01 is closed.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 10, 2019, the inspector presented the quarterly integrated inspection results to David B. Hamilton and other members of the licensee staff.
DOCUMENTS REVIEWED
71111.01Adverse Weather Protection
- IOI-0015; Seasonal Variations; Revision 30
- ONI-R36-2; Extreme Cold Weather; Revision 9
71111.04Equipment Alignment
- VLI-E22A; High Pressure Core Spray; 01/18/2019
- VLI-P42; Emergency Closed Cooling System; Revision 20
- VLI-R44; Division 1 and 2 Diesel Generator Starting Air System; Revision 6
- VLI-R45; Division 1 and 2 Diesel Generator Fuel Oil System (Unit 1); Revision 5
- VLI-R46; Division 1 and 2 Diesel Generator Jacket Water Systems; Revision 4
- VLI-R47; Division 1 and 2 Diesel Generator Lube Oil; Revision 7
- VLI-R48; Division 1 and 2 Diesel Generator Exhaust, Intake and Crankcase Systems;
Revision 6
71111.05AQFire Protection Annual/Quarterly
- CR 2019-00783; Fire Control Monitoring Station Operator Missed a Fire Alarm; 01/25/2019
- FDU-1125-020419; Annulus Exhaust B Sample Pump Unannounced Fire Drill; 02/04/2019
- FPI-0IB; Intermediate Building Pre-Fire Plan Instruction; 02/23/2019
- FPI-1DG; Diesel Generator Building Pre-Fire Plan Instruction; 01/18/2019
- FPI-A-B02; Fire Brigade Drills; Revision 9
- ONI-P54; Fire; Revision 25
- PNPP No. 7015; Fire Drill Planning Guide; 02/04/2016
71111.08Inservice Inspection Activities
- CR 2017-01617; Snubber Orientation does not Match Drawing; 02/13/2017
- CR 2017-02708; FME: Dosimeter Fell into Core from workers Pocket on Auxiliary Work
Platform; 03/11/2017
- CR 2017-03125; FME: Reactor Instrument Dry Tube Tip Broke During Removal from RPV;
03/19/2017
- CR 2017-03444; Feature of the FME Shield was not FME; 03/26/2017
- CR 2017-03453; Unacceptable Initial Acceptance Criteria for ISI-E12-T1111-2; 03/26/2017
- CR 2017-03564; 1R16 IVVI Condition Monitoring Exam of Steam Dryer Upper Ring Indication;
03/29/2017
- CR 2017-03582; FME: Foreign Material Discovered on Cavity Floor Prior to RVCH Move;
03/29/2017
- CR 2018-10721; Part 21 Industry Report-Emergency Diesel Generator Electro-Motive Diesel
Fuel Oil Pump Loose Bolts, Perry not Impacted; 12/06/2018
- ECP 17-0423-002; Rework 4 Elbow on HPCS Minimum Flow Line; Revision 1
- PDQS 878; PDI-UT-1, PDI Generic Procedure for the Ultrasonic Examination of Ferritic Pipe
Welds; Revision G
- Procedure NOP-CC-5762; Appendix VIII Procedure for Ultrasonic Examination of Ferritic Pipe
Welds; Revision 3
- Procedure NQI-1042; Visual Examinations; Revision 18
- WPS 1.1.2-001; Welding Procedure, P1 to P1; Revision 13
71111.11Licensed Operator Requalification Program and Licensed Operator Performance
- Evolution Specific Reactivity Plan; End of Cycle 17 Shutdown; Revision 0
- IOI-8; Shutdown by Manual Reactor Scram; Revision 8
- OTLC-3058201901; Evaluated Simulator Scenario; 01/14/2019
71111.13Maintenance Risk Assessments and Emergent Work Control
- CR 2019-00208; MSR 2B 1st Stage Drain Tank Level Control Oscillation; 01/09/2019
- CR 2018-08669;Signs of Jacket Water Leak Identified; 10/02/2018
- CR 2019-00868; Voltage Swings on EFD1A Battery Charger; 01/28/2019
- CR 2019-01106; Division 1 Diesel Left Bank #5 Jacket Water Leak; 02/05/2019
- Drawing 302-0115-00000; High Pressure Heater; Revision V
- eSOMS Plant Narrative Log; 01/28/2019
- eSOMS Plant Narrative Log; 01/29/2019
- NOP-OP-1007; Risk Management; Revision 29
- NOP-OP-1007-01 Rev. 04; Risk Management Plan Division 1 DG Inoperability; 01/29/2019
- PAP-1924; Risk-Informed Safety Assessment and Risk Management; Revision 9
- SVI-R42-T5228; Unit 1 Division 1 Charger (EFD-1-A) Load Test; Revision 4
- WO 200742236; Troubleshoot 2B Moisture Separator Reheater (MSR) 1st Stage Drain Tank
Alternate Drain Valve; 01/17/2019
71111.15Operability Determinations and Functionality Assessments
- CR 2016-02128; Safety Relief Valve 1B21F0047H Seat Leakage; 02/13/2016
- CR 2018-07911; Unexpected RRCS Div 1 P001 Alarm; 09/06/2018
- CR 2018-11111; Safety Relief Valve SN#160870(1B21F0047H) Found with Cracked Nozzle
After Disassembly by Vendor; 12/19/2018
- CR 2018-11165; NRC ID: Degraded Flood Barriers in Unit 2 Interbus Alley; 12/21/2018
- CR 2019-00826; Godwin HL5M Fire Pump Not Starting; 02/06/2019
- CR 2019-00830; Pipe Leak Between 1P87-F071 and 1P-87-F155 Piping; 01/28/2019
- CR 2019-01507; Combustible Gas, H2 Analyzer A Sample Valves Stroke time Open Times
Out of Spec; 02/19/2019
- CR 2019-01545; Combustible Gas, H2 Analyzer B Sample Valves, Stroke time Close Times
Out of Spec; 02/19/2019
- eSOMS Plant Narrative Log; 02/19/2019
- PDB-R0002; Perry Surveillance Test Interval List; Revision 4
- SVI-B21-T0209 A; ATWS-RPV Level 2; Revision 1
- SVI-M51-T2007B; Hydrogen Analyzer B and Post Accident Sampling System (Gaseous)
Solenoid Valve Position Indication Test; Revision 6
71111.19Post Maintenance Testing
- WO 200297091; Calibration of CRD Pump B Oil Pressure Switch; 01/18/2019
- SVI-R22-T5073; Division 2 4 KV Bus EH12 Undervoltage/Degraded Voltage Channel
Calibration and Logic System Functional Test; Revision 11
- SVI-R43-T1317; Diesel Generator Start and Load Division 1, Revision 23
- WO 200218569; Calibrate Pressure Switch 1C11N0702B; 01/18/2019
- WO 200754230; SVI-R43T1317 Division 1 D/G Start and Load; 04/14/2019
- WO 200779985; Repair Voltage Swings EFD1A Battery Charger Post Maintenance Testing;
01/29/2019
- WO 200780644; Division 1 Emergency Diesel Generator; 02/06/2019
- WO 200780675; Diesel Fire Service Pump Repair; 02/18/2019
71111.20-Refueling and Other Outage Activities
- 1R17 Shutdown Defense-in-Depth Report; Revision 0
- CR 2019-01671; Main Generator/Main Turbine Trip Resulting in a Reactor Scram; 02/25/2019
- CR 2019-02114; Recirc HPU Auto Swap from A1 to A2; 03/10/2019
- CR 2019-02115; Accumulated Dose Alarm Received While Pinning Spring Cans in Aux
Steam Tunnel; 03/10/2019
- CR 2019-02117; Unplanned Entry into TS 3.10.9 Condition A During Upper Pool Draining for
1R17; 03/10/2019
- CR 2019-02128; Reactor Head to Main Steam Line A Vent Valve is Damaged and Position
Indication in the Control Room is Erroneous; 03/11/2019
- CR 2019-02144; Potential Human Performance Trend-Site Protection; 03/11/2019
- CR 2019-02145; Limitorque Actuator Upper Housing Cover Found Cracked; 03/11/2019
- CR 2019-02298; Hydraulic Oil Spilled into Refueling Cavity; 03/12/2019
- CR 2019-02374; Poor Radworker Practice Results in PCE to Other Workers; 03/15/2019
- CR 2019-02619; GE Level III Exceeded Accumulated Dose Alarm While on the Refuel Floor;
03/21/2019
- CR 2019-02728; Accumulated Dose Alarm Received by GE Individual; 03/24/2019
- CR 2019-02732; Individual Alarmed PAF Portal Monitor Upon Exiting; 03/24/2019
- CR 2019-02979; Accumulated Dose Alarm Received by DZ Pipefitter-1R17; 03/30/2019
- CR 2019-02985; 2 DZ Atlantic RP Techs Received Accumulated Dose Alarms-1R17;
03/30/2019
- CR 2019-02987; Radiological Stop Work Implemented-1R17; 03/30/2019
- CR 2019-03019; RF17 Personnel Contamination Event; 03/31/2019
- CR 2019-01708; RX Recirculation B Outer Seal; 02/25/2019
- Evolution Specific Reactivity Plan; Startup 128 Part 1; Revision 0
- IMI-E2-47; Installation of Reactor Refuel Level Instrumentation for IOI-9; Revision 8
- NOBP-LP-2012; Fleet Oversight Standards, Expectations, Reporting, Analysis and
Elevation/Escalation; Revision 12
- NOBP-OP-0007; Conduct of Infrequently Performed Tests or Evolutions; Revision 6
- SVI-B21-T1176; RCS Heatup and Cooldown Surveillance; 03/10/2019
- SVI-E51-T1298; RCIC Actuation Logic System Functional Test; Revision 13
71111.22Surveillance Testing
- CR 2019-00515; Additional Half Scram Brought In Due to M&TE Unable to Sense Dry
Contacts; 01/17/2019
- NOP-OP-1007-01 Rev. 05; Risk Management Plan for RPS Channel D 1/2 Scrams;
01/17/2019
- PTI-N32-P0003; Turbine Overspeed Test; Revision 8
- SVI-C71-T0257-D; TSV Channel D Closure; Revision 1
- SVI-E21-T2200; Low Pressure Core Spray Isolation Valve Leak Rate Test; Revision 12
- SVI-M51-T2001; Combustible Gas Control System Valves Full Exercise and Strike Time
Test; Revision 12
- SVI-P45-T2003; HPCS EWS Pump and Valve Operability Test; Revision 25
- SVI-R43-T1330; Simultaneous Start of All Diesel Generators; Revision 10
- TXI-0457; Division 2 Standby Diesel Generator Load Rejection Test; 01/22/2019
- WO 200515324; LPCS Pump Min Flow Valve MCC Bucket Checks; 02/12/2019
- WO 200515325; LPCS Test Valve to Suppression Pool Buck Electrical Check; 02/14/2019
71114.06Drill Evaluation
- OTLC-3058201901; Evaluated Simulator Scenario; 01/14/2019
71124.01Radiological Hazard Assessment and Exposure Controls
- 2019 Annual Nationally Tracked Radioactive Source Reconciliation; 01/07/2019
- Airborne Radioactivity Calculation Worksheet; 690 Refuel Floor NE; 03/15/2019 01:15
- Airborne Radioactivity Calculation Worksheet; 690 Refuel Floor NE; 03/15/2019 10:55
- Airborne Radioactivity Calculation Worksheet; 690 Refuel Floor NE; 03/15/2019 14:36
- Airborne Radioactivity Calculation Worksheet; 690 Refuel Floor NW; 03/13/2019 14:17
- CR 2018-02853; NRC Observation-Air Sampler on North End of Refuel Floor did not have the
Particulate Paper Properly Centered; 03/27/2019
- CR 2019-02318; 1R17 Dose Rate Alarm in the Reactor Cavity; 03/14/2019
- CR 2019-02831; ISI Activities in Steam Tunnel Due to Inadequate RWP Setpoints and
Inconsistent RCA Surveys; 03/25/2019
- CR 2019-02918; NRC Identified Errors on Air Sample Results Paperwork; 03/28/2019
- Critical Point Survey Data Sheet; Undated
- Cycle 17 Source Term Report; 09/25/2019
- Electronic Dosimeter Dose and Dose Rate Alarm Logs; 03/01/18 through 03/25/2019
- NOP-OP-4101; Access Controls for Radiologically Controlled Areas; Revision 16
- NOP-OP-4107; Radiation Work Permit (RWP); Revision 18
- NOP-OP-4206; Bioassays; Revision 4
- Radiation Protection Electronic Logs; 03/11/2019
- Radiation Protection Electronic Logs; 03/18/2019
- Radioactive Source Inventory and Leak Tests; 02/07/2019
- Radiological Surveys; 690 Refuel Floor; 03/2019
- Radiological Surveys; Bioshield Activities 03/2019
- Radiological Surveys; Undervessel; 03/2019
- Self-Assessment; Pre NRC Hazard Assessment and Exposure Controls, Occupational
ALARA Planning and Controls; 01/16/2019
- SVI-E31-T5190; Sealed Source Leak Test and Inventory; Revision 8
71124.02Occupational ALARA Planning and Controls
- RWP 190518; 1R17 Undervessel Activities; Revision 0 and Associated ALARA Plans
- RWP 190622; 1R17 Bioshield ISI Activities; Revision 0 and Associated ALARA Plans
- RWP 190907; 1R17 Refueling Activities; Revision 0 and Associated ALARA Plans
- Site ALARA Committee Meeting; 1R17 Outage Package; 03/25/2019
71124.08Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,
and Transportation
- 10 CFR 61 Analysis; Decontamination Resin; 04/06/2017
- 10 CFR 61 Analysis; Dry Active Waste; 05/05/2017
- 10 CFR 61 Analysis; Spent Resin Tank; 10/26/2017
- 10 CFR 61 Scaling Factor Trending Data; 2018
- 17-1037; Radioactive Waste Shipment; Decontamination Resin; 07/17/2017
- 18-1016; Radioactive Waste Shipment; Resin; 06/07/2018
- 18-3004; Radioactive Material Shipment; 03/01/20218
- 19-2002; Radioactive Material Shipment; 03/06/2019
- Avantech Factory Acceptance Testing for Perry Ultra Rapid Dewatering System and Fill Head;
Revision 2
- Avantech Site Acceptance Testing for Perry Ultra Rapid Dewatering System and Fill Head;
Revision 0
- CR 2017-01575; Decreasing Radwaste Available Capacity Due to Processing Challenges;
2/12/2017
- CR 2017-04733; Follow-up for Arevas Failure to Follow Conditions in TN-RAM Packaging
Certificate of Compliance; 04/27/2017
- CR 2017-08418; Solid Radwaste Resin Dewatering Pump Degraded Performance;
08/13/2017
- CR 2017-10925; Radwaste Liner not Shipped as Scheduled due to Change in Resin
Processing; 10/31/2017
- CR 2019-01059; Degrading Pump Flows in Radwaste; 02/04/2019
- CR 2019-01956; A Waste Collector Filter Shell Closure Air Bellow has Ruptured; 03/05/2019
- HPI-H005; 10CFR61 Compliance Sampling Program; Revision 3
- NOP-OP-5201; Shipment of Radioactive Material-Waste; Revision 9
- PAP-525; Solid Radwaste Administration; Revision 9
- Process Control Program; Revision 1
- Quarterly/Annual Inspection of Outside Radioactive Material and Radwaste Containers;
2/26/2019
- Radwaste Collective Issues Status Report; 03/05/2019
- RWI-G51; Solid Radwaste Solidification System; Revision 23
71151Performance Indicator Verification
- NOBP-LP-4012-01Rev. 02; Unplanned Scrams per 7,000 Critical Hours; January through
December, 2018
- NOBP-LP-4012-02 Rev. 03; Unplanned Scrams with Complications (USwC),
January through December, 2018
- NOBP-LP-4012-03 Rev. 02; Unplanned Power Changes per 7,000 Critical Hours;
January through December, 2018
71153Follow-Up of Events and Notices of Enforcement Discretion
- CR 2019-01671; Main Generator/Main Turbine Trip Resulting in a Reactor Scram; 02/25/2019
- Evolution Specific Reactivity Plan Startup 128 Part 2; Revision 0
- IOI-0001; Cold Startup; Revision 50
- WO 200644720; Inspect/Replace Main Generator Brushes; 02/26/2019 and 02/27/2019
16