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| {{#Wiki_filter:May 12, 2021 | | {{#Wiki_filter: |
| Mr. Rod L. Penfield
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| Site Vice President
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| Energy Harbor Nuclear Corp.
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| Perry Nuclear Power Plant
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| 10 Center Road
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| Perry, OH 44081
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| SUBJECT: PERRY NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT
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| 05000440/2021001
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| Dear Mr. Penfield:
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| On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
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| at Perry Nuclear Power Plant. On April 28, 2021, the NRC inspectors discussed the results of
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| this inspection with you and other members of your staff. The results of this inspection are
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| documented in the enclosed report.
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| One finding of very low safety significance (Green) is documented in this report. This finding
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| involved a violation of NRC requirements. We are treating this violation as a non-cited violation
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| (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
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| If you contest the violation or the significance or severity of the violation documented in this
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| inspection report, 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:
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| Document Control Desk, Washington, DC 20555-0001; with copies to the Regional
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| Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector
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| at Perry Nuclear Power Plant.
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| If you disagree with a cross-cutting aspect assignment in this report, you should provide a
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| response within 30 days of the date of this inspection report, with the basis for your
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| disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk,
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| Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the
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| NRC Resident Inspector at Perry Nuclear Power Plant.
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| | |
| R. Penfield 2
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| This letter, its enclosure, and your response (if any) will be made available for public inspection
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| and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
| |
| Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public
| |
| Inspections, Exemptions, Requests for Withholding.
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| Sincerely,
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| /RA/
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| Billy C. Dickson, Jr., Chief
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| Branch 2
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| Division of Reactor Projects
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| Docket No. 05000440
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| License No. NPF-58
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| Enclosure:
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| As stated
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| cc w/ encl: Distribution via LISTSERV
| |
| | |
| | |
| ML21132A095
| |
| SUNSI Review
| |
| Non-Sensitive Publicly Available
| |
| Sensitive Non-Publicly Available
| |
| OFFICE RIII RIII
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| NAME RRiuz:ve via email BDickson via email
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| DATE 5/11/2021 5/12/2021
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|
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| U.S. NUCLEAR REGULATORY COMMISSION
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| Inspection Report
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| Docket Number: 05000440
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| License Number: NPF-58
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| Report Number: 05000440/2021001
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| Enterprise Identifier: I-2021-001-0045
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| Licensee: Energy Harbor Nuclear Corp.
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| Facility: Perry Nuclear Power Plant
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| Location: Perry, Ohio
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| Inspection Dates: January 01, 2021 to March 31, 2021
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| Inspectors: S. Bell, Health Physicist
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| V. Myers, Senior Health Physicist
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| J. Neurauter, Senior Reactor Inspector
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| T. Ospino, Resident Inspector
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| J. Steffes, Senior Resident Inspector
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| T. Taylor, Fermi Resident Inspector
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| Approved By: Billy C. Dickson, Jr., Chief
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| Branch 2
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| Division of Reactor Projects
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| Enclosure
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| | |
| SUMMARY
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| The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
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| performance by conducting an integrated inspection at Perry Nuclear Power Plant, in
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| accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs
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| program for overseeing the safe operation of commercial nuclear power reactors. Refer to
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| https://www.nrc.gov/reactors/operating/oversight.html for more information.
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| List of Findings and Violations
| |
| Human Performance Error Resulted in Unplanned RCIC Unavailability
| |
| Cornerstone Significance Cross-Cutting Report
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| Aspect Section
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| Mitigating Green [H.12] - Avoid 71111.22
| |
| Systems NCV 05000440/2021001-01 Complacency
| |
| Open/Closed
| |
| A finding of very low safety significance (Green) and associated non-cited violation of
| |
| TS 5.4.1, "Procedures," was self-revealed on January 19, 2021, when an unexpected isolation
| |
| of the RCIC steam supply occurred. Specifically, during performance of SVI-E31-T5395A,
| |
| "RCIC Steam Line Flow High Channel Functional for E31-N684A," Revision 8, the licensee
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| failed to lift the lead from terminal B4 for relay 1E51-K24, resulting in the closure of the RCIC
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| steam supply outboard valve and an unplanned limiting condition for operation (LCO) entry
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| and unavailability of the RCIC system.
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| Additional Tracking Items
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| None.
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| 2
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| | |
| PLANT STATUS
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| Perry Nuclear Power Plant began the inspection period at 97 percent of rated thermal power in
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| coastdown operations before a refueling outage. On January 10, 2021, the 1B feedwater heater
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| isolated. The isolation resulted in a power perturbation. In response to the power perturbation
| |
| and feedwater heater isolation, the operators lowered reactor power to 79 percent to maintain
| |
| margin to thermal limits per abnormal operating procedures. High water level conditions caused
| |
| the heater isolation. The high-water level condition resulted from a failed circuit card in the level
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| transmitter for the alternate level controller. Operators restored level using the normal level
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| controller. The operators returned the unit to maximum attainable power and continued
| |
| coastdown operations on January 11, 2021. On March 6, 2021, operators shutdown the
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| reactor to commence refueling outage 1R18. The reactor remained shut down in the refueling
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| outage for the remainder of the inspection period.
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| INSPECTION SCOPES
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| Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
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| effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
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| 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
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| complete when the IP requirements most appropriate to the inspection activity were met
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| consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
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| Program - Operations Phase. The inspectors reviewed selected procedures and records,
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| observed activities, and interviewed personnel to assess licensee performance and compliance
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| with Commission rules and regulations, license conditions, site procedures, and standards.
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| Starting on March 20, 2020, in response to the National Emergency declared by the President
| |
| of the United States on the public health risks of the Coronavirus Disease 2019
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| (COVID-19), resident inspectors were directed to begin telework and to remotely access
| |
| licensee information using available technology. During this time, the resident inspectors
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| performed periodic site visits each week; conducted plant status activities as described in
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| IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site
| |
| portions of IPs. In addition, resident and regional baseline inspections were evaluated to
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| determine if all or portions of the objectives and requirements stated in the IP could be
| |
| performed remotely. If the inspections could be performed remotely, they were conducted per
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| the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The
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| inspections documented below met the objectives and requirements for completion of the IP.
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| 3
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| | |
| REACTOR SAFETY
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| 71111.04 - Equipment Alignment
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| Partial Walkdown Sample (IP Section 03.01) (4 Samples)
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| The inspectors evaluated system configurations during partial walkdowns of the following
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| systems/trains:
| |
| (1) High pressure core spray (HPCS) system on February 9, 2021
| |
| (2) Division 2 diesel generator while division 1 vital bus was removed from service for
| |
| modification on March 13, 2021
| |
| (3) Residual heat removal (RHR) B partial alignment due to outage configuration on
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| March 14, 2021
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| (4) Electrical bus and load alignment due to outage configuration on March 15, 2021
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| 71111.05 - Fire Protection
| |
| Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)
| |
| The inspectors evaluated the implementation of the fire protection program by conducting a
| |
| walkdown and performing a review to verify program compliance, equipment functionality,
| |
| material condition, and operational readiness of the following fire areas:
| |
| (1) Quarterly fire protection alarm test on January 14, 2021
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| Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
| |
| (1) Fire protection drill on January 27, 2021
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| 71111.08G - Inservice Inspection Activities (BWR)
| |
| BWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding
| |
| Activities (IP Section 03.01) (1 Sample)
| |
| (1) The inspectors verified that the reactor coolant system boundary, reactor vessel
| |
| internals, risk-significant piping system boundaries, and containment boundary were
| |
| appropriately monitored for degradation and that repairs and replacements were
| |
| appropriately fabricated, examined and accepted by reviewing the documentation of
| |
| the following activities from March 8, 2021 to March 18, 2021:
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| 03.01.a - Nondestructive Examination and Welding Activities.
| |
| 1. Ultrasonic Examination (UT) of Main Steam System 26 Inch Elbow to Pipe
| |
| Weld, American Society of Mechanical Engineers (ASME) Category R-A,
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| Component 1B21-0006
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| 2. UT of Reactor Vessel Top Head Meridional Weld, ASME Category B-A,
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| Component 1B13-DM
| |
| 3. UT of Reactor Vessel Feedwater Nozzle Weld, ASME Category R-A,
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| Component 1B13-N4E-KB
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| 4
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| | |
| 4. Liquid Penetrant Examination (PT) of Control Rod Drive System Piping
| |
| Support Welded Attachment, ASME Category C-C, Component
| |
| 1C11-H0040-WA
| |
| 5. Magnetic Particle Examination (MT) of Reactor Vessel Top Head to Top Head
| |
| Flange Meridional Weld, ASME Category B-A, Component 1B13-AG
| |
| 6. MT of Main Steam System Flued Head Fitting to Process Pipe Attachment
| |
| Weld, ASME Category B-K, Component 1B21-P124-WA
| |
| 7. Visual Examination (VT-3) of High-Pressure Core Spray System Pipe
| |
| Restraint, ASME Category F-A, Component 1E22-H0034
| |
| 8. Visual Examinations of Chilled Water System: VT-3 of Pipe Anchor, ASME
| |
| Category F-A, Component 1P47-H0219 and VT-1 of Pipe Anchor Integral
| |
| Attachment Weld, ASME Category D-A, Component 1P47-H0219-WA
| |
| 9. AVR-R17-01, ASME Section XI Flaw Evaluation, Weld ID 1B13-AE
| |
| 10. Pipe Replacement of Essential Service Water System B Piping between
| |
| Valve 1P45F0541B and Heat Exchanger 1P42B0001B and between
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| Valve 1P45F0541B and Second Downstream Elbow; Weld Numbers
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| 200726587-01, -02, -03, -04, -05, -06 and -07 (WO 200726587)
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| 11. Pipe Replacement of Reactor Water Clean Up System; Spool Piece between
| |
| Heat Exchangers 1G33B0001C and 1G33B0002A; Weld Numbers
| |
| 200724734-01, -02, -03, -04, -05, -06, and -07 (WO 200724734)
| |
| The above volumetric (UT) and surface (PT and MT) examination records were
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| selected from the previous outage in 2019 (1R17), since there were no ISI exams or
| |
| aging management related exams performed during this outage (1R18).
| |
| 71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
| |
| Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
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| (1 Sample)
| |
| (1) The inspectors observed and evaluated licensed operator performance in the
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| Control Room during plant shutdown and cooldown activities for the 1R18 refueling
| |
| outage on March 6 to 7, 2021.
| |
| 71111.12 - Maintenance Effectiveness
| |
| Maintenance Effectiveness (IP Section 03.01) (4 Samples)
| |
| The inspectors evaluated the effectiveness of maintenance to ensure the following
| |
| structures, systems, and components (SSCs) remain capable of performing their intended
| |
| function:
| |
| (1) Combustible gas mixing system A failure on December 22, 2020
| |
| (2) Containment radiation monitor outboard isolation loss of indication on
| |
| January 15, 2021
| |
| (3) Inclined fuel transfer system failure on March 16, 2021
| |
| (4) Division 1 emergency core cooling systems (ECCS) integrated test failures and
| |
| resolution on March 22 to 24, 2021
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| 5
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| | |
| 71111.13 - Maintenance Risk Assessments and Emergent Work Control
| |
| Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)
| |
| The inspectors evaluated the accuracy and completeness of risk assessments for the
| |
| following planned and emergent work activities to ensure configuration changes and
| |
| appropriate work controls were addressed:
| |
| (1) Plant risk assessment related to D1A electrical bus emergent work started on
| |
| November 30, 2020
| |
| (2) Emergent work for annunciator system ground alarms on January 7, 2021
| |
| (3) Emergent work related to electro-hydraulic pump A leak and spill on
| |
| January 25, 2021
| |
| (4) Reactor feed pump turbine "B" emergent work on February 22 to 24, 2021
| |
| (5) Plant risk assessment during the Division 1 ECCS integrated test between
| |
| March 22 to 24, 2021
| |
| 71111.15 - Operability Determinations and Functionality Assessments
| |
| Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
| |
| The inspectors evaluated the licensee's justifications and actions associated with the
| |
| following operability determinations and functionality assessments:
| |
| (1) Combustible gas mixing system A (CR 2020-09635) failure and common cause
| |
| review on December 22, 2020
| |
| (2) Operability review based on CR 2020-09501 related to the Technical Support Center
| |
| radiation monitor on January 4, 2021
| |
| (3) Reactor core isolation cooling (RCIC) system operability verification based on
| |
| CR 2021-00338 on January 19, 2021
| |
| (4) Operability review for SCRAM insertion times after shutdown on March 6, 2021
| |
| (5) Operability review for safety relief valves (SRV) after set pressure testing on
| |
| March 29, 2021
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| 71111.18 - Plant Modifications
| |
| Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
| |
| (3 Samples)
| |
| The inspectors evaluated the following temporary or permanent modifications:
| |
| (1) Dedicated open phase control room annunciator modification on December 17, 2020
| |
| (2) Installation of temporary jumpers to bypass the rod block as part of outage emergent
| |
| activities on March 17, 2021
| |
| (3) Breaker EH1114 relay modification associated with Engineering Change 11-0559-002
| |
| on March 16, 2021
| |
| 6
| |
| | |
| 71111.19 - Post-Maintenance Testing
| |
| Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)
| |
| The inspectors evaluated the following post-maintenance test activities to verify system
| |
| operability and functionality:
| |
| (1) Technical support center testing following radiation monitor repair work on
| |
| December 16, 2020, to January 4, 2021
| |
| (2) Division 3 emergency service water testing following packing adjustment on
| |
| January 5, 2021
| |
| (3) Testing of the containment radiation monitor outboard isolation valve following blown
| |
| fuse replacement on January 15, 2021
| |
| (4) Testing following average power range monitor A and B power supply replacement
| |
| on January 19, 2021
| |
| (5) "B" reactor protection system trip channel Potter-Brumfield relay replacement for
| |
| 1C71A-K012B, work order 200391663
| |
| (6) Testing following replacement of control rod drive mechanisms on March 17, 2021
| |
| (7) Testing following replacement of "A" RHR relays on March 22 to 24, 2021
| |
| (8) SRV test following replacement on March 29, 2021
| |
| 71111.20 - Refueling and Other Outage Activities
| |
| Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
| |
| (1) (Partial)
| |
| The inspectors evaluated refueling outage 1R18 activities from March 6 to
| |
| March 31, 2021. 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, refueling operations,
| |
| reactor coolant system instrumentation, outage plan and shutdown risk.
| |
| 71111.22 - Surveillance Testing
| |
| The inspectors evaluated the following surveillance tests:
| |
| Surveillance Tests (other) (IP Section 03.01) (6 Samples)
| |
| (1) SRV pressure actuation channel A test on January 20, 2021
| |
| (2) HPCS pump test on February 1, 2021
| |
| (3) Fuel pool cooling and cleanup system surveillance on February 3, 2021
| |
| (4) Control rod maximum scram-based insertion time on March 6, 2021
| |
| (5) Division 1 standby diesel generator load rejection test on March 8, 2021
| |
| (6) Division 1 ECCS integrated test between March 22 to 24, 2021
| |
| Inservice Testing (IP Section 03.01) (1 Sample)
| |
| (1) "C" RHR system pump and valve operability test, work order 200792521.
| |
| 7
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| | |
| Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
| |
| (1) Leak rate test for the shutdown cooling A to the feedwater shutdown isolation valve
| |
| 1E12-F050A on March 22, 2021
| |
| FLEX Testing (IP Section 03.02) (1 Sample)
| |
| (1) Calibration check of FLEX fuel pool level transmitter on January 27, 2021
| |
| RADIATION SAFETY
| |
| 71124.01 - Radiological Hazard Assessment and Exposure Controls
| |
| Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
| |
| (1) The inspectors evaluated how the licensee identifies the magnitude and extent of
| |
| radiation levels and the concentrations and quantities of radioactive materials and
| |
| how the licensee assesses radiological hazards.
| |
| Instructions to Workers (IP Section 03.02) (1 Sample)
| |
| The inspectors evaluated instructions to workers including radiation work permits used to
| |
| access high radiation areas.
| |
| (1) The inspectors evaluated radiological protection related instructions to plant workers
| |
| for emergent diving activities on the inclined fuel transfer system.
| |
| Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
| |
| The inspectors evaluated licensee processes for monitoring and controlling contamination
| |
| and radioactive material.
| |
| (1) The inspectors observed workers exiting the radiologically controlled area (RCA).
| |
| (2) The inspectors observed licensee surveys of potentially contaminated material
| |
| leaving the radiologically controlled area.
| |
| Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
| |
| The inspectors evaluated in-plant radiological conditions during facility walkdowns and
| |
| observation of the following radiological work activities.
| |
| (1) Inclined fuel transfer system diving activities under RWP 210910
| |
| (2) Flow accelerated corrosion exams in the reactor water cleanup heat exchanger and
| |
| pump room under RWP 210602
| |
| (3) Control rod drive mechanism exchange under RWP 210518
| |
| 8
| |
| | |
| High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)
| |
| The inspectors evaluated licensee controls of the following High Radiation Areas and Very
| |
| High Radiation Areas:
| |
| (1) Locked high radiation area for reactor water clean-up pump repair in the auxiliary
| |
| building 599'
| |
| (2) Locked high radiation area for the fuel pool cooling pump room in the intermediate
| |
| building 574'
| |
| (3) Locked high radiation area established for fuel moves in containment 620'
| |
| Radiation Worker Performance and Radiation Protection Technician Proficiency
| |
| (IP Section 03.06) (1 Sample)
| |
| (1) The inspectors evaluated radiation worker and radiation protection technician
| |
| performance as it pertains to radiation protection requirements.
| |
| 71124.02 - Occupational ALARA Planning and Controls
| |
| Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (3 Samples)
| |
| The inspectors reviewed as low as reasonably achievable practices and radiological work
| |
| controls for the following work activities.
| |
| (1) Inclined fuel transfer system diving activities under RWP 210910
| |
| (2) Flow accelerated corrosion exams in the reactor water cleanup heat exchanger and
| |
| pump room under RWP 210602
| |
| (3) Control rod drive mechanism exchange under RWP 210518
| |
| Radiation Worker Performance (IP Section 03.04) (1 Sample)
| |
| The inspectors evaluated radiation worker and radiation protection technician performance
| |
| during:
| |
| (1) Inclined fuel transfer system diving activities under RWP 210910
| |
| 71124.05 - Radiation Monitoring Instrumentation
| |
| Walkdowns and Observations (IP Section 03.01) (5 Samples)
| |
| The inspectors evaluated the following radiation detection instrumentation during plant
| |
| walkdowns:
| |
| (1) Radiation monitors (portal monitor, personnel contamination monitor and small article
| |
| monitor) located at the RCA exit.
| |
| (2) Portable radiation survey instrumentation located at the RCA exit and the
| |
| Instrumentation Calibration Facility (Geiger Mueller contamination monitoring
| |
| instruments and dose rate survey instruments including ion chambers, pressurized
| |
| ion chambers and Telepoles).
| |
| (3) Gamma spectroscopy systems and liquid scintillation instrumentation located within
| |
| the Chemistry Counting Room.
| |
| 9
| |
| | |
| (4) JL Shepherd Model 89 instrumentation calibrator.
| |
| (5) Area Radiation Monitors and Continuous Air Monitors in the Fuel Handling Building
| |
| Calibration and Testing Program (IP Section 03.02) (1 Sample)
| |
| The inspectors evaluated the calibration and testing of the following radiation detection
| |
| instruments:
| |
| (1) Canberra Argos Personal Contamination Monitor, SN L70L004V
| |
| 71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage,
| |
| & Transportation
| |
| Radioactive Material Storage (IP Section 03.01) (2 Samples)
| |
| The inspectors evaluated the licensee's performance in controlling, labelling and securing
| |
| radioactive materials in the following locations.
| |
| (1) Outside radioactive material storage locations
| |
| (2) Radiation protection radioactive source storage locations (calibration facility and RCA
| |
| exit)
| |
| Radioactive Waste System Walkdown (IP Section 03.02 (1 Sample)
| |
| (1) Inspectors walked down accessible portions of the solid radioactive waste systems
| |
| located in the radioactive waste handling building and evaluated system configuration
| |
| and functionality.
| |
| Waste Characterization and Classification (IP Section 03.03) (2 Samples)
| |
| (1) The inspectors evaluated the licensees characterization and classification of
| |
| shipment 19-1030 consisting of reactor water cleanup resin radioactive waste
| |
| (2) The inspectors evaluated the licensees characterization and classification of
| |
| shipment 20-1026 consisting of spent resin radioactive waste
| |
| Shipment Preparation (IP Section 03.04) (1 Sample)
| |
| (1) The inspectors observed shipment number 21-008, containing radioactive
| |
| contaminated laundry.
| |
| Shipping Records (IP Section 03.05) (5 Samples)
| |
| The inspectors evaluated the following non-excepted radioactive material shipments through
| |
| a record review:
| |
| (1) Radioactive waste shipment 19-1030 consisting of reactor water cleanup resin
| |
| transported in a Type B package
| |
| (2) Radioactive waste shipment 20-1026 consisting of dewatered resin transported in
| |
| a general design package
| |
| (3) Radioactive waste shipment 19-1025 consisting of reactor water cleanup resin
| |
| transported in a Type B package
| |
| 10
| |
| | |
| (4) Radioactive material shipment 19-3033 consisting of control rod drive mechanisms
| |
| transported in a Type A package
| |
| OTHER ACTIVITIES - BASELINE
| |
| 71153 - Follow-up of Events and Notices of Enforcement Discretion
| |
| Event Report (IP Section 03.02) (1 Sample)
| |
| The inspectors evaluated the following licensee event reports (LERs):
| |
| (1) LER 2020-002-00, Standby Liquid Control System Rendered Inoperable due to Valve
| |
| Misposition (ADAMS Accession No. ML20293A204). The inspection conclusions
| |
| associated with this LER are documented in this report under Inspection Results
| |
| Section 71153.
| |
| INSPECTION RESULTS
| |
| Human Performance Error Resulted in Unplanned RCIC Unavailability
| |
| Cornerstone Significance Cross-Cutting Report
| |
| Aspect Section
| |
| Mitigating Green [H.12] - Avoid 71111.22
| |
| Systems NCV 05000440/2021001-01 Complacency
| |
| Open/Closed
| |
| A finding of very low safety significance (Green) and associated non-cited violation of
| |
| TS 5.4.1, "Procedures," was self-revealed on January 19, 2021, when an unexpected
| |
| isolation of the RCIC steam supply occurred. Specifically, during performance of
| |
| SVI-E31-T5395A, "RCIC Steam Line Flow High Channel Functional for E31-N684A,"
| |
| Revision 8, the licensee failed to lift the lead from terminal B4 for relay 1E51-K24, resulting in
| |
| the closure of the RCIC steam supply outboard valve and an unplanned limiting condition for
| |
| operation (LCO) entry and unavailability of the RCIC system.
| |
| Description:
| |
| On January 19, 2021, during the performance of SVI-E31-T5395A, RCIC Steam Line Flow
| |
| High Channel Functional for E31-N684A, Revision 8, the licensee received several control
| |
| room alarms and identified that the RCIC steam supply outboard valve was closed. The
| |
| licensee determined that an inadvertent isolation of the RCIC system and an unplanned
| |
| inoperability had occurred. The inspectors determined that procedural steps were not
| |
| implemented during the surveillance test, as written. Specifically, the licensee failed to
| |
| perform Section 5.1 appropriately, steps 72a and 72b, and complete the independent
| |
| verification to ensure the correct lead was lifted from terminal B4 associated with relay
| |
| 1E51-K24. This failure resulted in the closure of the RCIC steam supply outboard valve and
| |
| the RCIC system unavailability.
| |
| Corrective Actions: Immediate corrective actions included securing from the surveillance,
| |
| restoration of the RCIC steam supply flow path and RCIC system operability.
| |
| Corrective Action References: CR 2021-00338, Wrong Lead lifted during Surveillance
| |
| Performance 1/19/2021.
| |
| 11
| |
| | |
| Performance Assessment:
| |
| Performance Deficiency: The resident inspectors determined that the licensees failure to
| |
| implement Section 5.1, Steps 72a and 72b of SVI-E31-T5395A, RCIC steam line flow high
| |
| channel functional for E31-N684A, Revision 8, was a performance deficiency. Specifically,
| |
| the failure to ensure the correct lead was lifted from terminal B4 of the relay 1E51-K24 in
| |
| accordance with the procedure directly led to the inoperability and unavailability of the RCIC
| |
| system.
| |
| Screening: The inspectors determined the performance deficiency was more than minor
| |
| because it was associated with the Human Performance attribute of the Mitigating Systems
| |
| cornerstone and adversely affected the cornerstone objective to ensure the availability,
| |
| reliability, and capability of systems that respond to initiating events to prevent undesirable
| |
| consequences. The resident inspectors determined the performance deficiency was more
| |
| than minor because it was associated with the Human Performance attribute of the Mitigating
| |
| Systems cornerstone and adversely affected the cornerstone objective to ensure the
| |
| availability, reliability, and capability of systems that respond to initiating events to prevent
| |
| undesirable consequences. Specifically, the licensee failed to lift the correct lead from
| |
| terminal B4 of relay 1E51-K24, which directly led to the closure of the RCIC steam supply
| |
| outboard valve and steam flow path isolation, thus negatively impacting the availability of the
| |
| RCIC system.
| |
| Significance: The inspectors assessed the significance of the finding using Appendix A, The
| |
| Significance Determination Process (SDP) for Findings At-Power. The inspectors screened
| |
| the finding against the Mitigating Systems screening questions in Exhibit 2 and answered
| |
| "NO" to all screening questions. Therefore, the finding screened to very low safety
| |
| significance (Green).
| |
| Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the
| |
| possibility of mistakes, latent issues, and inherent risk, even while expecting successful
| |
| outcomes. Individuals implement appropriate error reduction tools. Specifically, the licensee
| |
| failed to implement error reduction tools from Section 4.2.5.3 of NOBP-LP-2601, "Human
| |
| Performance Program," Revision 13, independent verification which resulted in the failure to
| |
| implement the procedure as written.
| |
| Enforcement:
| |
| Violation: Technical Specification 5.4.1, "Procedures," requires, in part, that written
| |
| procedures/instructions be established, implemented, and maintained covering the following
| |
| activities: the applicable procedures recommended in Regulatory Guide (RG) 1.33,
| |
| Revision 2, Appendix A, dated February 1978. RG 1.33, Revision 2, Appendix A,
| |
| Section 8b(2)(r), states, in part, that for the reactor core isolation system "Specific procedures
| |
| for surveillance tests, inspections, and calibrations should be written (implementing
| |
| procedures are required for each surveillance test, inspection, or calibration listed in the
| |
| technical specifications."
| |
| Contrary to the above, on January 19, 2020, while performing an activity affecting quality, the
| |
| licensee did not accomplish a surveillance test in accordance with the procedure and
| |
| incorrectly performed a step in surveillance procedure SVI-E31-T5395A, and failed to lift the
| |
| proper lead. Specifically, the licensee failed to lift the lead from terminal B4 from relay
| |
| 1E51A-K24 resulting in an unplanned entry into Technical Specification 3.5.3, Condition A,
| |
| and adversely affected the availability of the RCIC system.
| |
| 12
| |
| | |
| Enforcement Action: This violation is being treated as a non-cited violation, consistent with
| |
| Section 2.3.2 of the Enforcement Policy.
| |
| Minor Violation 71153
| |
| Minor Violation: Licensee Event Report (LER) 05000440/2020-002 documented a condition
| |
| where the standby liquid control (SLC) system was rendered inoperable due to a valve
| |
| alignment issue. The event occurred on August 21, 2020, from 0953 to 1307 hours
| |
| (approximately 3 hours). The licensee submitted the LER to the NRC according to
| |
| 10 CFR 50.73 (a)(2)(v)(A) and 50.73 (a)(2)(v)(D) for a condition that could have prevented
| |
| the fulfillment of the safety function of a system needed to shut down the reactor and mitigate
| |
| the consequences of an accident.
| |
| The LER stated that on August 20, 2020, Periodic Test Instruction, PTI-C41-P0001, Standby
| |
| Liquid Control Transfer System Pump, and Valve Operability Test, was being performed on
| |
| the SLC system. During the test on August 20, 2020, at 1248 hours, a valve misposition
| |
| resulted in the inadvertent addition of 226 gallons of water to the SLC storage tank, causing
| |
| an unintended dilution of the boron solution. On August 21, 2020, at 0953 hours, the SLC
| |
| system was declared inoperable when the sample results for the SLC storage tank confirmed
| |
| the boron solution concentration did not meet Technical Specification (TS) 3.1.7 criteria. The
| |
| licensee restored operability on August 21, 2020, at 1307 hours.
| |
| While reviewing LER 05000440/2020-002, the inspectors identified that the diluted boron
| |
| solution concentration existed for a time longer than permitted by TS 3.1.7. Following the
| |
| guidance in NUREG-1022 Revision 3 "Event Report Guidelines 10 CFR 50.72 and 50.73, the
| |
| inspectors determined that the licensee should have reported the diluted boron solution
| |
| concentration to the NRC as a condition which was prohibited by the plant's Technical
| |
| Specifications, pursuant to 10 CFR 50.73 (a)(2)(i)(B). Specifically, the diluted boron solution
| |
| concentration existed for longer (approximately 24 hours) than the total 20 hours allowed for
| |
| restoration and shutdown outage time per Technical Specifications. The licensee plans on
| |
| submitting a revised LER in response to the minor violation.
| |
| Screening: The inspectors determined the performance deficiency was minor. Specifically,
| |
| the failure to identify 10 CFR 50.73 (a)(2)(i)(B) on a Licensee Event Report did not impact the
| |
| completeness or accuracy of performance indicator data or other information provided to the
| |
| agency, as is provided in Enforcement Policy Example 6.9(d)(10).
| |
| Enforcement: This failure to comply with 10 CFR 50.73 (a)(2)(i)(B) constitutes a minor
| |
| violation that is not subject to enforcement action in accordance with the NRCs Enforcement
| |
| Policy.
| |
| 13
| |
| | |
| EXIT MEETINGS AND DEBRIEFS
| |
| The inspectors verified no proprietary information was retained or documented in this report.
| |
| * On April 28, 2021, the inspectors presented the integrated inspection results to
| |
| Mr. R. Penfield, Site Vice President, and other members of the licensee staff.
| |
| * On February 5, 2021, the inspectors presented the radiation protection baseline
| |
| inspection results to Mr. R. Penfield, Site Vice President, and other members of the
| |
| licensee staff.
| |
| * On March 18, 2021, the inspectors presented the Inservice Inspection results to
| |
| Mr. C. Elliott, Plant General Manager, and other members of the licensee staff.
| |
| * On March 25, 2021, the inspectors presented the radiation protection baseline
| |
| inspection results to Mr. R. Penfield, Site Vice President, and other members of the
| |
| licensee staff.
| |
| * On April 28, 2021, the inspectors presented the integrated inspection results inspection
| |
| results to Mr. R. Penfield, Site Vice President, and other members of the licensee staff.
| |
| 14
| |
| | |
| DOCUMENTS REVIEWED
| |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| 71111.04 Drawings 302-0351-00000 Standby Diesel Generator Starting Air GG
| |
| 302-0352-00000 Standby Diesel Generator Fuel Oil System LL
| |
| 302-0353-00000 Standby Diesel Generator Lube Oil T
| |
| Procedures ELI-R22 15KV and 5KV Metal Clad Switchgear 3/15/2021
| |
| VLI-E12 Residual Heat Removal System 3/14/2021
| |
| VLI-E22A High Pressure Core Spray 10
| |
| VLI-R44 Division 1 and 2 Diesel Generator Starting Air System 6
| |
| VLI-R45 Division 1 and 2 Diesel Generator Fuel Oil System (Unit 1) 5
| |
| VLI-R47 Division 1 and 2 Diesel Generator Lube Oil 7
| |
| 71111.05 Procedures FPI-A-B02 Fire Brigade Drills 01/27/2021
| |
| Work Orders 200750956 Quarterly Fire Alarm 01/14/2021
| |
| 71111.08G Corrective Action CR-2019-02185 Foreign Material Head Tensioner Lock Washer Dropped in 03/19/2019
| |
| Documents Cavity
| |
| CR-2019-02328 Relevant Indication Identified During Containment Surface 03/14/2019
| |
| Exams
| |
| CR-2019-02523 1C22D0012B Found with Internal Parts Missing - Potential 03/19/2019
| |
| Foreign Material
| |
| CR-2019-02677 During IVVI Piece of Foreign Material Identified Between Jet 03/22/2019
| |
| Pumps 16 and 17
| |
| CR-2019-02704 During IVVI Piece of Foreign Material Identified at Jet Pump 03/23/2019
| |
| 17
| |
| CR-2019-02893 Foreign Material Found Inside Reactor Vessel During Core 03/28/2019
| |
| Verification
| |
| CR-2019-02956 Legacy Foreign Material Discovered in Inner Bellows 03/29/2019
| |
| CR-2019-02990 Foreign Material - Piece of Rope Found in Inner Bellows 03/30/2019
| |
| After Draindown
| |
| CR-2019-03147 Leakage Identified During Reactor Pressure Vessel Test 04/03/2019
| |
| CR-2019-03157 Documentation of Identified Mechanical Joint Leakage 04/04/2019
| |
| Identified During Reactor Pressure Vessel Leak Test (1R17)
| |
| CR-2019-03358 Roll-Up Condition Report Following 1R17 Refuel - Foreign 04/09/2019
| |
| Material Focused Observations
| |
| CR-2019-04170 Additional Pitting Discovered in Piping Downstream of 05/07/2019
| |
| 15
| |
| | |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| Emergency Service Water
| |
| CR-2020-02539 Mechanical Leakage Identified During ISI-P2-T2200-3 03/23/2020
| |
| CR-2020-06809 1R16 Snubber As-Built Discrepancy 08/31/2020
| |
| Corrective Action ATA-2021-4926 Remove "Snubbers" from Definition of VT-3 in NQI-1042, 03/12/2021
| |
| Documents Paragraph 3.15 to Align with Language Contained in ASME
| |
| Resulting from Section XI (2013 Edition), IWA-2213
| |
| Inspection
| |
| Drawings 304-672-105 Piping Isometric, Reactor Water Clean-Up System, Reactor D
| |
| Building
| |
| 305-002-113 ISI Piping Isometric, System P47 Chilled Water System Loop A
| |
| B
| |
| 305-006-103 Reactor Vessel Closure Head, Circumferential and A
| |
| Meridional Weld Arrangement
| |
| 305-006-108 ISI, System 1B13, Reactor Vessel Feedwater Nozzle Weld D
| |
| Arrangement
| |
| 305-605-103 ISI Piping Isometric, System B21, Main Steam Loop C C
| |
| 305-605-107 ISI Piping Isometric, System B21, Main Steam Loop A, D
| |
| Steam Tunnel Elevation 620-6
| |
| 305-701-102 ISI Piping Isometric, High Pressure Core Spray D
| |
| 305-871-104 System C11, Control Rod Drive, Loop B, Reactor Building C
| |
| Elevation 620-6
| |
| 92-701-0034 Pipe Support Mark Number 1E22-H0034 A
| |
| 92-871-0040 Pipe Support Mark 1C11-H0040 2
| |
| B-312-641 Containment Penetration Detail, Type K F
| |
| Miscellaneous RRP 200724734 Repair Replacement Plan: Remove and Replace Reactor 0
| |
| Water Clean Up Heat Exchanger 4 Spool Piece Between
| |
| Heat Exchangers 1G33B0001C and 1G33B0002A
| |
| RRP 200726587 Repair Replacement Plan: Remove 3" Bypass 0
| |
| Piping/Components and Replace 14" Spool Piece Between
| |
| Valve 1 P45F0541 B and Heat Exchanger 1 P4280001 B.
| |
| Also Replace Portion of Spool Piece Between Valve
| |
| 1 P45F0541 B and Second Elbow Downstream of the Valve.
| |
| Reference ECP 18-0162-002
| |
| WPS 1.1.2-001 Welding Procedure Specification: P1 Gr. 1 & 2 to P1 Gr, 13
| |
| 16
| |
| | |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| 1&2
| |
| NDE Reports 0941-19A-003 Liquid Penetrant Examination (PT): Piping Support Welded 03/13/2019
| |
| Attachment: Component 1C11-H0040-WA
| |
| 0942-19A-008 Magnetic Particle Examination (MT): Top Head to Top Head 03/21/2019
| |
| Flange: Component 1B13-AG
| |
| 0942-19A-010 Magnetic Particle Examination (MT): P124 Flued Head 03/25/2019
| |
| Fitting to Process Pipe Attachment Weld: Component
| |
| 1B21-P124-WA
| |
| 0942-19B-009 Magnetic Particle Examination (MT): 14 Pipe to 14 Elbow 03/13/2019
| |
| 0942-19B-014 Magnetic Particle Examination (MT): Flange to Pipe 03/13/2019
| |
| 0942-19B-015 Magnetic Particle Examination (MT): Pipe to Elbow Butt 03/13/2019
| |
| Welds
| |
| 0942-19B-016 Magnetic Particle Examination (MT): (2) Half Coupling to 03/13/2019
| |
| Pipe and Flange to Pipe Welds
| |
| 0942-19B-017 Magnetic Particle Examination (MT): 14 Flange to 14 Elbow 03/13/2019
| |
| Butt Weld (Repair)
| |
| 0942-19B-025 Magnetic Particle Examination (MT): 14 Pipe to 14 Elbow 03/25/2019
| |
| FW-07
| |
| 0942-19B-031 Magnetic Particle Examination (MT): 4 Spool Piping 03/07/2019
| |
| 1042-19B-018 Visual Examination System Leakage (VT-2): Order 03/27/2019
| |
| 200726587 Piping Replacement
| |
| 1042-21-023 Visual Examination of Pipe Hanger, Support, or Restraint 03/04/2021
| |
| (VT-3): Chilled Water System, Pipe Anchor, Component
| |
| 1P47-H0219 Located on ISI Drawing 305-002-113
| |
| 1042-21-024 Visual Examination of Welds (VT-1): Chilled Water System 03/08/2021
| |
| Pipe Anchor Integral Attachment, Component
| |
| 1P47-H0219-WA Located on ISI Drawing 305-002-113
| |
| 1042-21-029 Visual Examination of Pipe Hanger, Support, or Restraint 03/04/2021
| |
| (VT-3): Mechanical Snubber, Drawing 305-701-102,
| |
| Component 1E22-H0034
| |
| APR-R17-02 Ultrasonic Examination Summary Sheet, System 1B13, Weld 03/282019
| |
| Number 1B13-N4E-KB, Safe-End to Nozzle
| |
| MVR-004 UT Report with Calibration Records C-007 and C-008: 03/23/2019
| |
| Component 1B13-DM
| |
| 17
| |
| | |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| UT-19-E006 UT Calibration/Examination Report: Component 1B21-006 03/15/2019
| |
| Procedures GEH-UT-247 Procedure for Phased Array Ultrasonic Examination of 4
| |
| Dissimilar Metal Welds
| |
| GEH-UT-300 Procedure for Manual Examination of Reactor Vessel 12
| |
| Assembly Welds in Accordance with PDI
| |
| NOP-CC-5762 Appendix VIII Procedure for Ultrasonic Examination of 3
| |
| Ferritic Welds
| |
| NQI-0941 Liquid Penetrant Examination 22
| |
| NQI-0942 Magnetic Particle Examination 22
| |
| NQI-1042 Visual Examination 20
| |
| Work Orders 200718215 Reactor Vessel Top Head Meridional Weld Examination 03/21/2019
| |
| 200718218 Piping Weld Exams on Main Steam Lines 04/17/2019
| |
| 200724734 Replace 4 Piping - RWCU Piping Between Heat 04/11/2019
| |
| Exchangers 1G33B0001C and 1G33B0002A
| |
| 200726587 Replace 14 Piping - ESW B Piping Between 1P45F0541B 04/09/2019
| |
| and Heat Exchanger 1P42B0001B and Between Valve
| |
| 1P45F0541B and Second Elbow Downstream of Valve
| |
| 200728323 1B13 Reactor and Internals Non-Destructive Examination 04/18/2019
| |
| 200794288 System P47 Exams: Pre-1R18 03/12/2021
| |
| 200794289 ISI of Piping, Supports, and Components of P42, P47, and 03/12/2021
| |
| E22 Systems
| |
| 71111.11Q Miscellaneous Evolution Specific Perry Nuclear Power Plant End of Cycle 18 Shutdown 0
| |
| Reactivity Plan
| |
| Procedures IOI-3 Power Changes 81
| |
| IOI-4 Shutdown 26
| |
| 71111.12 Corrective Action 2021-00266 Loss of Indication for Containment Radiation Monitor 01/15/2021
| |
| Documents Outboard Isolation
| |
| 2021-01834 IFT Cable Damaged During Transfer 03/14/2021
| |
| Miscellaneous NOP-ER-3004-03 Maintenance Rule Failure Review Form 04
| |
| NOP-SS-3001-02 Procedure Approval Form 12
| |
| 71111.13 Corrective Action 2021-00128 Multiple Alarms Received Coincident with Annunciator 01/7/2021
| |
| Documents System Ground
| |
| 2021-00455 EHC Pump A Leak 01/25/2021
| |
| 18
| |
| | |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| 2021-01200 Planned Work Not Able to be Released as Scheduled Due to 02/23/2021
| |
| Leakby Aux Condenser B Air Removal Suction Valve
| |
| 2021-02121 Unplanned Division 1 DG Start During Integrated 03/23/2021
| |
| LOOP/LOCA Test
| |
| Work Orders 200840213 Determine and Correct the Cause Ground on Electrical Bus 11/30/2020
| |
| D1A CR 2020-09061
| |
| 71111.15 Corrective Action 2020-09501 Ventilation Radiation Monitor Gas Channel Reading Erratic 12/16/2020
| |
| Documents 2021-00338 Wrong Lead Lifted During Surveillance Performance 01/20/2021
| |
| 2021-01707 Rod SCRAM Time Recorder Did Not Perform as Expected 03/10/2021
| |
| 2021-09635 Combustible Gas Mixing Compressor Suction Valve Would 12/22/2020
| |
| Not Re-Open Following Compressor Start
| |
| Work Orders 200798943 Safety Relief Valve Removes, Replaces and Offsite Testing 03/23/2021
| |
| 71111.18 Engineering 11-0559-002 Spring Charging Motor Margin Improvement - EH 1114 0
| |
| Changes ECP 15-0057 Installation of U1/U2 Startup Transformer 02/26/2018
| |
| Engineering ECP 19-0203-002 Dedicated Open Phase Control Room Annunciators - Unit 2 07/10/2020
| |
| Evaluations
| |
| Work Orders 200846449 Jumper Request to Remove Rod Block 03/17/2021
| |
| 71111.19 Corrective Action 2021-00266 Loss of Indication for Containment Radiation Monitor 01/15/2021
| |
| Documents Outboard Isolation
| |
| Procedures SVI-B21-T2100 Safety Relief Valve (SRV) Set Pressure Testing 7
| |
| SVI-D17-T2001 Plant Radiation Monitoring Isolation Valves Operability Test 8
| |
| Work Orders 100841399 Technical Support Center Ventilation Radiation Monitor Gas 01/4/2021
| |
| Channel Reading Erratic Replacement
| |
| 200391663 Replace Relay 1C17A-K0112B Reactor Protection System 0
| |
| Trip Channel B
| |
| 200536387 Replace Relays 1E12-K18A/19A 03/22/2021
| |
| 200594427 Replace Power Supply PS22 01/12/2021
| |
| 200727023 Install ECP-11-0559-002 74 Power Monitoring Relay in 03/14/2021
| |
| Breaker EH1114
| |
| 200762809 Inspect/Tighten Packing-ESW PMP Div III 01/5/2021
| |
| 200795982 Control Unit Hydraulic 03/17/2021
| |
| 71111.20 Corrective Action 2021-01545 Condensate Booster Pump C Tripped Following Reactor 03/6/2021
| |
| Documents Recirculation Pump Downshift
| |
| 19
| |
| | |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| 2021-01557 Feedwater Heater 3A Isolated on High Level Following 03/6/2021
| |
| Recirculating Pump Downshift to Slow Speed
| |
| 2021-01564 Control Rod 02-27 Did Not Settle at 00 03/7/2021
| |
| 2021-01604 Scaffold Level Inadvertently Dropped in the Suppression 03/8/2021
| |
| Pool During Scaffold Erection
| |
| 2021-01829 Leak in High Pressure Core Spray Room 03/14/2021
| |
| 2021-01857 As Found Blockage of 3-Inch Fire Protection System to 03/15/2021
| |
| Emergency Service Water Pipe Connection
| |
| 2021-01939 Fuel Assembly 18P568 Identified as Cycle 18 Fuel Defect 03/17/2021
| |
| 2021-02011 Design Discrepancies Contained Within the Engineering 03/19/2021
| |
| Change Package for the 1B33-F060B Side Drain Appendage
| |
| 2021-02117 Ground Detected on DC Bus 03/22/2021
| |
| 2021-02159 Loose Bushing Terminal Lead Connectors Found in Unit 1 03/24/2021
| |
| Start-Up Transformer
| |
| 2021-02237 Issues Noted on Post Maintenance Tests for Scram 03/25/2021
| |
| Discharge Volume Vent and Drain Valves
| |
| 2021-02312 Control Rod Drive Mechanism Temperature for Rod 34-43 03/27/2021
| |
| Indicates Failed
| |
| 2021-02428 Hard Ground Indicated on DC Bus D-1-B 03/31/2021
| |
| Miscellaneous 1R18 Shutdown Defense-In-Depth Report 1
| |
| Procedures SVI-B21-T1176 Reactor Coolant System Heat Up and Cooldown 03/7/2021
| |
| Surveillance
| |
| 71111.22 Procedures GMI-0067 Under-Vessel Maintenance Activities 19
| |
| IMI-E2-47 Installation of Reactor Refuel Level Instrumentation for 03/9/2021
| |
| IOI-9
| |
| SVI-B21-T2100 Safety Relief Valve (SRV) Set Pressure Testing 7
| |
| SVI-E12-T2210 Leak Rate Test for RHR to FWD Injection Valves 03/24/2021
| |
| 1E12-F050A and 1E12-F053A
| |
| SVI-G41-T2002 Fuel Pool Cooling and Cleanup System Operability Test 02/3/2021
| |
| SVI-R43-T7000-A Division 1 ECCS Integrated Test 12
| |
| TXI-0460 Division 1 Standby Diesel Generator Load Rejection Test 03/8/2021
| |
| Work Orders 200751888 SRV Pressure Actuation Channel a Functional for 01/20/2021
| |
| 1B21-N668A
| |
| 200778903 Spent Fuel Pool Level Instrument 1X13N0003 Calibration 01/27/2021
| |
| 20
| |
| | |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| Check
| |
| 200778904 Level Sensor Calibration 02/3/2021
| |
| 200778926 Standby Oil Pump Testing 1N27C0006A 12/30/2020
| |
| 200783921 Control Rod Maximum SCRAM Insertion Time 03/6/2021
| |
| 200792417 High Pressure Core Spray Pump and Valve Operability Test 02/1/2021
| |
| 71124.01 Corrective Action CR-2021-01739 Two Unbriefed Dose Rate Alarms Received in Containment 03/11/2021
| |
| Documents Annulus 690' Elevation
| |
| Corrective Action CR-2021-01952 NRC Comment During Radiological Hazards/ALARA 03/16/2021
| |
| Documents Inspection for Loss of Telemetry
| |
| Resulting from
| |
| Inspection
| |
| Radiation N/A Radiological Surveys for Lower Inclined Fuel Transfer 03/15/2021
| |
| Surveys System
| |
| PY-M-20210310- Reactor Water Cleanup Heat Exchanger Room Post Pump 03/09/2021
| |
| 7 Failure Verification Survey for Flow Accelerated Corrosion
| |
| Exam Work
| |
| PY-M-20210312- Scaffold Extension for Flow Accelerated Corrosion Exam 03/12/2021
| |
| 37
| |
| Radiation Work 210518 Undervessel Activities 0
| |
| Permits (RWPs) 210602 Flow Accelerated Corrosion Exams in the Reactor Water 0
| |
| Clean-Up Heat Exchanger and Pump Room
| |
| 210910 Inclined Fuel Transfer System Diving Activities and Support 0
| |
| Work
| |
| 71124.02 ALARA Plans ALARA Plan Undervessel Activities 0
| |
| 210518
| |
| ALARA Plan Flow Accelerated Corrosion Exams in the Reactor Water 0
| |
| 210602 Clean-Up Heat Exchanger Room
| |
| ALARA Plan ALARA Plan for Inclined Fuel Transfer System Diving and 0
| |
| 210910 Support Activities
| |
| 71124.05 Calibration Canberra Argos Personal Contamination Monitor; 02/17/2021
| |
| Records SN L70L004V
| |
| 71124.08 Corrective Action 2019-03353 Radwaste Processing Inventory Issues 04/09/2019
| |
| Documents 2019-06245 Radwaste Tanks Require Multiple Iterations of Processing in 07/24/2019
| |
| Order to Become Transfer Quality
| |
| 21
| |
| | |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| 2020-07918 Pre NRC-Assessment ATA 2020-10589 Identified 10/13/2020
| |
| Deficiencies in Closure Packages for SVI-E31-T5190
| |
| Miscellaneous 20118 Radioactive Material Transportation Training Record 07/09/2020
| |
| 451802001 10 CFR 61 Laboratory Analysis of Reactor Water Clean-Up 05/25/2018
| |
| Resin
| |
| 510237001 10 CFR 61 Laboratory Analysis of Spent Resin 02/25/2020
| |
| Procedures NOP-OP-4502 Control of Radioactive Material 7
| |
| NOP-OP-5201 Shipment of Radioactive Material-Waste 10
| |
| PCP-0000 Process Control Program 15
| |
| RPI-1301 Movement of Radioactive Material/Waste Outside of 13
| |
| Radiologically Controlled Areas and Onsite Interim Storage
| |
| Self-Assessments ATA-2020-10589 Pre NRC-Inspection - Radioactive Solid Waste Processing 11/13/2020
| |
| and Radioactive Material Handling, Storage, and
| |
| Transportation
| |
| Shipping Records 19-1025 Radioactive Waste Shipment of Reactor Water Cleanup 06/05/2019
| |
| Resin
| |
| 19-1030 Radioactive Waste Shipment of Reactor Water Cleanup 07/23/2019
| |
| Resin
| |
| 19-3033 Radioactive Material Shipment of Control Rod Drive 07/18/2019
| |
| Mechanisms
| |
| 20-1026 Radioactive Waste Shipment of Dewatered Resin 11/30/2020
| |
| 21-2008 Radioactive Material Shipment Containing Radiologically 03/18/2021
| |
| Contaminated Laundry
| |
| Work Orders 200752735 Radioactive Source Inventory/Leak Test Record 09/03/2020
| |
| 22
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| }} | | }} |
