IR 05000275/2021001

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DC IR 2021-001-drk, Diablo Canyon Power Plant Units 1 & 2 - Integrated Inspection Report 05000275/2021001, 05000323/2021001, & Independent Spent Fuel Storage Installation Inspection Report 07200026/2021001
ML21118A017
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 05/07/2021
From: Jeffrey Josey
NRC/RGN-IV/DRP
To: Welsch J
Pacific Gas & Electric Co
References
IR 2021001
Download: ML21118A017 (24)
v • d • e


Text

May 7, 2021

SUBJECT:

DIABLO CANYON POWER PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000275/2021001 AND 05000323/2021001 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200026/2021001

Dear Mr. Welsch:

On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Diablo Canyon Power Plant, Units 1 and 2. On April 8, 2021, 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.

No findings or violations of more than minor significance were identified during this inspection.

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 Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Digitally signed by Jeffrey Jeffrey Josey Josey Date: 2021.05.07 07:58:36-05'00'

Jeffrey E. Josey, Chief Reactor Projects Branch A Division of Reactor Projects Docket Nos. 05000275, 05000323, and 07200026 License Nos. DPR-80, DPR-82, SNM-2511

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000275, 05000323, and 07200026 License Numbers: DPR-80, DPR-82, and SNM-2511 Report Numbers: 05000275/2021001, 05000323/2021001, and 07200026/2021001 Enterprise Identifier: I-2021-001-0003 and I-2021-001-0116 Licensee: Pacific Gas and Electric Company (PG&E)

Facility: Diablo Canyon Power Plant, Units 1 and 2, and associated Independent Spent Fuel Storage Installation (ISFSI)

Location: Avila Beach, CA Inspection Dates: January 1, 2021 to March 31, 2021 Inspectors: D. Antonangeli, Health Physicist A. Athar, Resident Inspector L. Brookhart, Senior Spent Fuel Storage Inspector J. Drake, Senior Reactor Inspector N. Greene, Senior Health Physicist D. Krause, Senior Resident Inspector J. ODonnell, Senior Health Physicist Approved By: Jeffrey E. Josey, Chief Reactor Projects Branch A Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Diablo Canyon Power Plant, Units 1 and 2, 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.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 operated at or near rated thermal power for the entire inspection period.

Unit 2 entered the inspection period shut down due to a hydrogen leak in the main turbine generator. Unit 2 returned to full power on January 16, 2021, and operated at full power until January 26, 2021, when the unit reduced power to approximately 80 percent due to high vibrations in the main generator stator. The unit operated at or near 80 percent rated thermal power until February 3, 2021, when the unit was shut down to effect repairs on the main generator stator. The unit entered a refueling outage on February 21, 2021, and remained shut down for the remainder of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors 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.

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 (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed onsite portions of IPs. In addition, resident and regional baseline inspections were evaluated to 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 the applicable IP. In some cases, portions of an IP were completed remotely and onsite. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather due to heavy swells and high winds on January 8, 2021.

External Flooding Sample (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding due to a torrential rain event on January 29, 2021.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 2, service cooling water pump 2-2 on January 28, 2021
(2) Unit 2, safety injection pump 2-2 on February 1, 2021
(3) Unit 2, emergency diesel generator 2-1 on March 8, 2021
(4) Unit 2, residual heat removal shutdown cooling pump 2-1 on March 9, 2021 Complete Walkdown Sample (IP Section 03.02) (1 Partial)

The inspectors evaluated system configurations during complete walkdowns of the following systems/trains:

(1) (Partial)

The inspectors started evaluating system configurations during a complete walkdown of the Unit 2, Component Cooling Water system on March 23, 2021, and continued the sample walkdown into the second quarter.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)

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) Unit 1, turbine building, 119-foot elevation on January 4, 2021
(2) Unit 2, turbine building, 140-foot elevation on January 11, 2021
(3) Unit 2, radiological control area, 100-foot elevation on February 2, 2021
(4) Unit 1, radiological control area, 73-foot elevation on February 5, 2021
(5) Unit 1, radiological control area 8-B-1, 140-foot elevation on February 19, 2021

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on January 24, 2021.

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated internal flooding mitigation protections in the Unit 2, component cooling water, RV-46 freeze-seal maintenance on March 19, 2021.

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness and performance of Unit 2, component cooling water heat exchangers 2-1 and 2-2 thermal performance on March 3, 2021.

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

Main article: IP 71111.08
(1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, 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 15-29, 2021:

03.01.a - Nondestructive Examination and Welding Activities

  • Notification 51083610, Auxiliary Feedwater Piping relevant indications accepted for continued service
  • Welding
  • Gas Tungsten Arc Welding o Safety Injection System Accumulator 2-1, FW 1 Nozzle D o Safety Injection System Accumulator 2-1, FW 2 Nozzle D o Safety Injection System Accumulator 2-1, FW 1 Nozzle B o Safety Injection System Accumulator 2-1, FW 2 Nozzle B o Safety Injection System Accumulator 2-4, FW 1 Nozzle C1B o Safety Injection System Accumulator 2-4, FW 2 Nozzle C1B 03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities 1. Reviewed the following Notifications for boric acid leaks: 51064523,

===51082169, 51065620, 51067236, 51067238, 51078028, 51082231, 51064129, 51066443, 51067132, 51067133, 51067136, 51067137, 51067237, 51067270, 51067337, 51069685, 51082238, 51084352, 51084353, 51085607, 51087075, 51087166, 51087186, 51102822, 51102823, 51102824, 51102833, 51102834, 51102885, 51103084, 51103186, 51103846, 51059714, 51059716, 51065241, 51065242, 51067250, 51067253, 51067259 The inspector evaluated a sample of 71 condition reports associated with inservice inspection activities. No findings or violations of more than minor significance were identified.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

=

Main article: IP 51082
(1) The inspectors observed and evaluated licensed operator performance in the Control Room during Unit 2 startup on January 10, 2021.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated a crew of licensed operators during simulator training on February 11, 2021.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:

(1) Unit 1, component cooling pump 1-3 end bell leak on January 12, 2021
(2) incipient fire detector EFID01, EFID01 Zone 4 airflow out-of-tolerance on March 25, 2021

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) Unit 2, high vibrations in main generator end windings on February 1, 2021
(2) Unit 2, pressurizer relief valve PCV-456, slow stroke time rendering valve inoperable on February 22, 2021
(3) Unit 2, emergent risk associated with beginning refueling outage 2R22 on February 23, 2021
(4) Unit 2, steam generator 2-2 inlet stop valve FW-2-80 on March 1, 2021
(5) Unit 2, yellow outage risk due to being at lowered inventory with single source of offsite power on March 15, 2021

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Unit 2, emergency diesel generator 3 lost surveillance on January 12, 2021
(2) Unit 2, DA-U2 LCV-110 hand controller failure on February 25, 2021
(3) Unit 2, 27XHHT load shed relay failed to trip on March 8, 2021
(4) Unit 2, containment spray flow sensor P-CSP-A21-FI-930 giving unexpected indications on March 16, 2021
(5) Unit 2, safety injection (SI) inlet from refueling water storage tank valve SI-8976 failed to close during STP on March 23, 2021
(6) Unit 2, accumulator 2-1 nozzle leak on March 24, 2021

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

(2 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) Unit 2, 480 VAC bus H outage temporary power modifications on January 21, 2021
(2) Unit 2, main turbine bearing No.10 CARDOX sensor TS-46 temporary modification on January 28, 2021

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)

The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:

(1) Unit 2, residual heat removal pump 2-2 on February 16, 2021
(2) Unit 2, control room ventilation system filter 2/2A on March 3, 2021
(3) Unit 2, load shed relay 27XHHT on March 8, 2021
(4) Unit 2, emergency diesel generator 2-2 after major maintenance activities on March 11, 2021
(5) Unit 2, SI-2-8802A stroke test on March 22, 2021
(6) Unit 2, RHR-2-8702 stroke test on March 22, 2021

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)

The inspectors evaluated refueling outage 2R22 activities in accordance with Section 03.01.

(1) (Partial)

The inspectors started evaluation of the Unit 2, refueling outage 2R22 activities that commenced on February 21, 2021, and continued into the second quarter.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (Other) (IP Section 03.01)

Main article: IP 71111.22
(1) Unit 1, emergency diesel generator 1-3 routine surveillance, per STP M-9A3, on January 5, 2021
(2) Unit 2, safety injection pump 2-2 on January 20, 2021
(3) 4 kV bus H auto transfer test on February 25, 2021
(4) Unit 1, component cooling water pump 1-1 on March 4, 2021

Inservice Testing (IP Section 03.01) (1 Sample)

(1) Unit 1, auxiliary saltwater pump 1-1 on January 7, 2021

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Unit 2, penetration 31 containment isolation valve leak testing on March 17, 2021

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated a tabletop emergency preparedness drill in the Technical Support Center on February 10,

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 (RWPs)used to access high radiation areas.

(1) The inspectors reviewed the following radiation work packages, electronic alarming dosimeters, and labeling of radioactive containers:
  • RWP 2021-2066, "2R22 Emergent Work," Revision 1
  • RWP 2021-0042, "Radioactive Waste Activities," Revision 0
  • DN 51109334 - Two workers' electronic dosimeters alarmed indicative of electromagnetic interference in a satellite radiologically controlled area (RCA)in Building 111 while working on the spare reactor coolant pump (RCP) motor
  • DN 51110284 - Worker's electronic dosimeter alarmed due to a hardware reset, not actual dose rates
  • DN 51110679 - Worker exited containment when electronic dosimeter alarmed; recorded dose rate insufficient to trip alarm; dosimeter removed from service with hardware malfunction
  • Yellow Radioactive trash bags near RCP 2-3
  • Westinghouse equipment storage box 30016120 in the East Yard
  • Tri Nuke filtration system stored in the Hot Machine Shop on the 140-foot elevation of the Fuel Handling Building

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) Observed licensee surveys of potentially contaminated material leaving the RCA
(2) Observed workers exiting the Unit 2 containment building during a refueling outage

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 radiological work activities. No work packages were available for review for airborne radioactivity. The inspector reviewed the following work packages:

(1) RWP 2021-2066, "2R22 Emergent Work," Revision 1, specifically for accumulator work in Alpha Level 2 areas (Task 66)
(2) RWP 2021-2050, "2R22 Reactor Coolant Pump Work," Revision 0, specifically changing reactor coolant pump seals for RCP 2-3
(3) RWP 2021-0042, "Radioactive Waste Activities," Revision 0, specifically the transfer of spent resin to an outside shielded storage container and the changing of Refueling Water Purification Filter 1-1 High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Under Reactor Vessel Plug was controlled as a Very High Radiation Area on the Unit 2 Containment Building, 91-foot elevation
(2) Regenerative Heat Exchanger room was controlled as a Locked High Radiation Area (LHRA) on the Unit 2, Containment Building, 91-foot elevation
(3) Liquid Hold-Up Tank room was controlled as an LHRA on the Unit 2, Auxiliary Building, 100-foot elevation
(4) Bay No. 2 was controlled as an LHRA for the common Radwaste Storage Building, 115-foot elevation
(5) Refueling Water Purification Filter 1-1 was controlled as an LHRA in the Unit 1, Fuel Handling Building, 100-foot elevation 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

Radiological Work Planning (IP Section 03.01) (5 Samples)

The inspectors evaluated the licensees radiological work planning. The inspectors reviewed the following activities:

(1) RWP 19-2020, "2R21 Reactor Disassembly and Reassembly"
(2) RWP 19-2040, "2R21 Steam Generator Work (Primary Side)"
(3) RWP 20-1020, "1R22 Reactor Disassembly and Reassembly"
(4) RWP 20-1040, "1R22 Steam Generator Work (Primary Side)"
(5) RWP 20-1076, "1R22 Transfer Cart and Upender Repair" Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (4 Samples)

The inspectors evaluated dose estimates and exposure tracking. The inspectors reviewed the following as low as reasonably achievable planning documents:

(1) Diablo Canyon Power Plant 1R21 Post Outage ALARA Report, March 18, 2019
(2) Diablo Canyon Power Plant 2R21 Post Outage ALARA Report, December 18, 2019
(3) Diablo Canyon Power Plant 1R22 Post Outage ALARA Report, January 27, 2021
(4) Diablo Canyon Power Plant 2R20 Post Outage ALARA Report, August 15, 2018

Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (2 Samples)

The inspectors reviewed as low as reasonably achievable practices and radiological work controls. The inspectors reviewed the following activities during Unit 2, Refueling Outage 22:

(1) Welding within Accumulators under RWP 21-2066, "2R22 Emergent Work,"

Revision 1

(2) Reactor Coolant Pump 2-3 Seal Work under RWP 21-2050, "2R22 RCP Work,"

Revision 0 Radiation Worker Performance (IP Section 02.04) (1 Sample)

The inspectors evaluated radiation worker and radiation protection technician performance during:

(1) The inspectors evaluated the implementation of as low as is reasonably achievable techniques for work activities during outage 2R22.

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to external dosimetry that is used to assign occupational dose, including issuance, use, and storage of dosimetry.

Internal Dosimetry (IP Section 03.03) (1 Sample)

The inspectors evaluated the internal dosimetry program implementation.

(1) The inspectors reviewed the following:

Whole Body Counts

  • None were available during this inspection.

In-Vitro Internal Monitoring

  • None were available during this inspection.

Dose Assessments Performed Using Air Sampling and Derived Air Concentration-Hour Monitoring

  • None were available during this inspection.

Although there were no specific occurrences of whole body counts, in-vitro internal monitoring, or dose assessments using air sampling, the inspectors did review associated procedures and discussed relative processes with the licensee to determine the adequacy of their program.

Special Dosimetric Situations (IP Section 03.04) (2 Samples)

The inspectors evaluated the following special dosimetric situation:

(1) Licensee's implementation of requirements to manage radiation protection of five declared pregnant workers
(2) EDEX dose assessment and redacted NRC Form 5 for five individuals using multipack dosimetry

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicator submittals listed below:

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 03.01) ===

Main article: IP 71151
(1) Unit 1 (January 1, 2020, through December 31, 2020)
(2) Unit 2 (January 1, 2020, through December 31, 2020)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 03.02)

(2 Samples)

(1) Unit 1 (January 1, 2020, through December 31, 2020)
(2) Unit 2 (January 1, 2020, through December 31, 2020)

IE04: Unplanned Scrams with Complications Sample (IP Section 03.03) (2 Samples)

(1) Unit 1 (January 1, 2020, through December 31, 2020)
(2) Unit 2 (January 1, 2020, through December 31, 2020)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 03.15) (1 Sample)

(1) Unit 1 (October 1, 2020, through December 31, 2020)

Unit 2 (October 1, 2020, through December 31, 2020)

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 03.16) (1 Sample)

(1) Unit 1 (October 1, 2020, through December 31, 2020)

Unit 2 (October 1, 2020, through December 31, 2020)

71152 - Problem Identification and Resolution

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in safety injection accumulator leakage that might be indicative of a more significant safety issue on January 20, 2021.

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

(1) The inspectors reviewed the licensee's implementation of its corrective action program related to unexpected cycling of the main steam safety valve on January 20,

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===60855 - Operation of an Independent Spent Fuel Storage Installation (ISFSI) The inspectors performed a review of the licensees ISFSI activities to verify compliance with requirements of the site-specific License SNM-2511, License Amendment 5, and the Independent Spent Fuel Storage Installation Final Safety Analysis Report (FSAR), Revision

8. The inspectors reviewed selected procedures, corrective action reports, and records to verify

ISFSI operations were compliant with the site-specific licenses technical specifications, requirements in the FSAR, and NRC regulations.

Operation of An ISFSI ===

Main article: IP 60855
(1) The inspectors evaluated the licensees operation of the ISFSI, January 19-21, 2021, during an onsite inspection. The Diablo Canyon Power Plant ISFSI consisted of seven concrete pads for a total area of 49,980 square feet. Each pad was designed to hold 20 Holtec International HI-STORM 100SA storage casks which are securely anchored to steel embedment plates in the concrete. At the time of the inspection, the ISFSI contained 58 storage casks (out of 140 total possible) loaded with Multi-Purpose Canisters, each with 32 spent fuel assemblies (MPC-32).

The inspectors evaluated the following:

  • The inspectors performed a walkdown of the ISFSI pad and completed an independent radiation survey
  • Fuel contents for the canisters loaded since the last NRC ISFSI inspection, the inspectors reviewed the contents of casks 55-58 against the license's technical specifications for approved contents
  • Radiation surveys for dose at the owner-controlled boundary to verify compliance with the requirements of 10 CFR 72.104 for calendar years 2019 and 2020
  • Selected ISFSI-related condition reports (Notifications) issued since the last NRC ISFSI inspection (July 2018)
  • Quality assurance (QA) program implementation, including recent QA audits, surveillances, receipt inspection, and quality control activities related to ISFSI operations
  • Compliance to technical specifications for operational surveillance activities and FSAR required annual maintenance activities
  • Documentation of annual maintenance activities for the sites cask handling crane
  • Selected licensee design changes and program changes to the ISFSI performed under the site's 10 CFR 72.48 program
  • Changes made by the licensee in the ISFSI, FSAR from Revision 7 to Revision

INSPECTION RESULTS

Observation: Main Steam Safety Valve (MSSV) Operational Vulnerabilities 71152 Several instances of MSSV actuations were noted during normal operational plant maneuvers over the last 12 months that had the potential to impact reactor coolant system (RCS) cooldown and main steam system overpressure functions. The primary purpose of MSSVs is to provide overpressure protection for the secondary system. The MSSVs also provide protection against over pressurizing the reactor coolant pressure boundary by providing a heat sink for the removal of energy from the (RCS) if the preferred heat sink is not available as well as impacting RCS cooldown rates should an MSSV remain open. While the MSSVs maintained operability and compliance with technical specifications, the actuations were observed as operational burdens during plant start-ups and shutdowns.

The inspectors reviewed licensee corrective actions associated with Notification 51098721 U2 SG 2-2 Safety Lifted Early, 51093299 DA-RV-7 lifted at below setpoint, 51092867 R211; HC-405 Operation, and 51073275 DA-RV-58 Safety Lift While Rolling Turbine. The inspectors assessed the following performance attributes in their review:

  • complete and accurate identification of the problem in a timely manner commensurate with its safety significance and ease of discovery;
  • consideration of the extent of condition, generic implications, common cause, and previous occurrences;
  • evaluation and disposition of operability/functionality/reportability issues;
  • classification and prioritization of the resolution of the problem commensurate with safety significance;
  • identification of corrective actions, which were appropriately focused to correct the problem; and
  • completion of corrective actions in a timely manner commensurate with the safety significance of the issue.

The inspectors selected these samples due to the operability impact associated MSSVs; a safety significant system. Inspectors focused review of the above attributes on the licensees corrective actions associated with the above notifications and several others. Inspectors did not identify a performance deficiency with this issue.

Observation: Potential adverse trends involving changes in Safety Injection 71152 Accumulator level.

The inspectors performed a semiannual review, of the licensee's corrective action and adverse condition monitoring programs, from July 1-December 31, 2020, for potential adverse trends. The inspectors noted instances of safety injection accumulator leakage.

Accumulators provide a passive supply of boric acid to the reactor coolant system during a large break loss of coolant accident. Changes in level caused by leakage into or out of the accumulator could change boric acid concentration or accumulator volume to a non-conforming condition. Based on these events, the inspectors reviewed the licensees corrective action program (Notifications 51095887, LTCA-DA - Accumulator 1-2 in-leakage, and 51082247, Accumulator 2-1 low level) trend reports, equipment problem lists, and additional documents, to identify trends that might indicate the existence of a more significant safety issue. Programmatic requirements and processes were also reviewed to determine whether adverse conditions related to SI accumulators were being appropriately tracked, managed, and resolved. The inspectors also reviewed the licensees selection of criteria or set points for which further evaluation or action was designated to assess the health of the adverse condition monitoring program.

The inspectors did not identify any significant trends that might indicate the existence of more significant safety concerns that had not been previously addressed by the licensee, nor did the inspectors identify any performance deficiency with this issue.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

  • On January 21, 2021, the inspectors presented the routine ISFSI Inspection results to Ms. P. Gerfen, Site Vice President, and other members of the licensee staff.
  • On March 4, 2021, the inspectors presented the radiation safety inspection results to Ms. P. Gerfen and other members of the licensee staff.
  • On March 25, 2021, the inspectors presented the occupational radiation safety inspection results to Ms. P. Gerfen and other members of the licensee staff.
  • On March 29, 2021, the inspectors presented the Unit 2 inservice inspection results to Ms. P Gerfen and other members of the licensee staff.
  • On April 8, 2021, the inspectors presented the integrated inspection results to Mr. J. Welsch, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

60855 Corrective Action Notifications 50443110, 50981033, 50238622, 5574154

Documents

Engineering LBIE-S-2010-133 Nozzle Bulge Tolerance and Configuration Change 0

Changes MMD M000084 Unit 2 Cycle 22 Core Reload Design 5

Engineering PEP R-70 MPC-32 Loading Plan Design Casks 07-06 through 07-09 5

Evaluations PEP R-MPC-32 Determination of Fuel Assemblies for Qualified Storage in 06/21/2018

the MPC for UFO7

Miscellaneous FineNet#191550001 2019 ISFSI and Fuel Management Audit 08/06/2019

NCR 0517-74 Oversized Baseplate Holes Supplier Disposition Request 01/31/2018

NCR 0517-75 HI-STORM Drawing Dimensional Discrepancy 01/19/2018

NCR 05320-50 MPC Vent and Drain Tubes Supplier Disposition Request 01/15/2018

Shipping Records CoC 0523-047 Certificate of Conformance MPC-32 S/N 503 02/20/2018

CoC 0523-048 Certificate of Conformance MPC-32 S/N 504 02/22/2018

CoC 0523-049 Certificate of Conformance MPC-32 S/N 505 02/22/2018

Work Order 64222689

71111.01 Corrective Action Notifications 51105390, 51105415

Documents

Procedures CP M-16 Severe Weather 17

OP O-28 Intake Management 36

71111.04 Drawings 107715 Unit 2 Service Cooling Water System 50

108010 Unit 2 Residual Heat Removal System 31

108015 Unit 2 Service Water Cooling System 26

Miscellaneous 107710 U-2 Residual Heat Removal System Valve Designation 05/18/2016

Procedures OM8.ID4 Control of Flammable and Combustible Materials 32

OP B-2:V U2 RHR - Place in Service 39

OP B-3A:II Safety Injection System Alignment Verification for Plant 23B

Startup

OP F-1:II U2 Service Cooling Water - Place in Service 21A

OP J-6B:I-A Diesel Generator 2-1 - Alignment Checklist 0

OP K-10A13 Sealed Component Checklist for Safety Injection Pump 2-2 3

71111.05 Corrective Action Notifications 51105964, 51109215, 51109216, 51109827

Documents

Drawings 11805 Sheet 72 2

RA-12 Radiological Control Area (RCA) Elev. 140' Unit 1 3

RA-15 Radiological Control Area (RCA) Elev. 100' Unit 2 3

RA-3 Radiological Control Area (RCA) Elev. 73' Unit 1 3

TB-21 Fire Drawing: Turbine Building Elev. 140'

TB-8 Fire Drawing: Turbine Building Elev. 119'

Procedures CP M-6 Site Fire Response 40

TQ1.DC12 Fire Brigade and Emergency Response Training 16

71111.06 Drawings 107714 Component Cooling Water System 66

71111.07A Corrective Action Notifications 51109263, 51109480

Documents

Procedures OM11.ID9 Visitor Escorts 4

PEP M-234 CCW Heat Exchanger Performance Test 20

SP 106 Security Reporting 34

Work Orders 64172011

71111.08P Corrective Action Notifications 51103887, 51103527, 51102884, 51101542, 51101516,

Documents 51100379, 51099726, 51098161, 51097842, 51097781,

51095864, 51086232, 51086202, 51084933, 51084912,

51083540, 51082880, 51082881, 51082882, 51082883,

51082884, 51082910, 51082911, 51082912, 51082913,

51082914, 51082918, 51082919, 51083110, 51083111,

51083112, 51083113, 51083114, 51083115, 51083116,

51083121, 51083138, 51083139, 51083181, 51083182,

51079406, 51073835, 51069760, 51065847, 51065849,

51064523, 51063831, 51063857, 51059819, 51059054,

51058792, 51056284, 51054430, 51052551, 51049947,

51047201, 51047202, 51046786, 51064523, 51082169,

51103084, 51065242, 51093152, 51082880, 51060220,

51069761, 51065242, 51064523, 51046786, 51057867,

51083610

Miscellaneous Quick HIT Self-Assessment for Reactor Coolant System 11/06/2013

Materials Degradation Management Program (RCS MDMP)

and Steam Generator Management Program (SGMP)

20 ISI SA Final 2020 ISI SELF-ASSESSMENT REPORT 09/22/2020

Report

TS1.ID10 Reactor Coolant System Materials Degradation 5/6/7/8

Management Program

TS5.DC1 Engineering Programs 10

Procedures NDE VT 2-1 Visual Examination During Section XI System Pressure Test 5

71111.11Q Procedures OP L-1 Plant Heatup from Hot Shutdown to Hot Standby 88

OP L-2 Hot Standby to Startup Mode 45

STP R-17 Estimated Critical Conditions 21

STP R-19 Shutdown Margin Determination 33

71111.12 Corrective Action Notifications 51104396, 51088988, 51111442

Documents

Procedures STP I-18-IFD.A Incipient Fire Detection System Operability and Channel 2

Functional Test, Unit 2

Work Orders 64205001, 64219801, 64139131, 60134380, 64130702,

231654, 64235481

71111.13 Corrective Action Notifications 51108219, 51109191, 51109210, 51109086, 51109166,

Documents 51108586, 51106514, 51099522, 51105816, 51109565

Miscellaneous 2R21 Outage Safety Plan 0a

2R22 (AD8.DC55 2R22 Outage Safety Plan 0

Att 7)

FW-2-80 51108586 Fault Tree A

Procedures OP O-36 Protected Equipment Postings 24

STP I-7-PCV456 U2 Pressurizer PORV PCV-456 Calibration 10

STP V-3J2 Exercising Pressurizer Power Operated Relief Valves 19

Work Orders 64145255

71111.15 Corrective Action Notifications 51103677, 51109572, 51108525, 51108448, 50967066,

Documents 51109572, 51110830, 51109847, 51111446

Procedures STP P-CSP-A21 Comprehensive Testing of Containment Spray Pump 2-1 16

Work Orders 60135410, 60135682, 64168637

71111.18 Corrective Action Notification 51104084

Documents

Drawings 441233 MCC Bus Section 22M 32

441239 480VAC Bus H 48

Miscellaneous 4000002059 Temporary Modification - Provide Power to TPRM22 during 0

480VAC Bus H Maintenance in 2R22

Work Order 60133461

71111.19 Corrective Action Notifications 51107345, 51107346

Documents

Procedures MP E-53.10A Preventative Maintenance of Limitorque Motor Operators 45

MP E-60.2HHXFER Circuit Functional Test - 4KV Bus "H" Auto Transfer Scheme 3

MP M-23-DMP.1 Control Room Envelope Boundary Damper Maintenance 7

STP M-9L Diesel Generator Shutdown Lockout Relay Test 30

STP P-RHR-22 Routine Surveillance Test of RHR Pump 2-2 28

STP V-3M5 Exercising Valves RHR-8701 and RHR-8702, Reactor 0A

Coolant Loop 4 to RHR Suction

Work Orders 60118610, 60118681, 64163830, 60122970, 64215001,

64135086

71111.22 Corrective Action Notifications 51102290, 51102805

Documents

Procedures STP M-13F 4KV Bus F Non-SI Auto-Transfer Test 68

STP M-9A3 Diesel Engine Generator 1-3 Routine Surveillance Test 13

STP P-ASW-A-11 Comprehensive Test of Auxiliary Saltwater Pump 1-1 13A

STP P-CCW-A11 U1 Comprehensive Pump Test of Component Cooling Water 7

Pump 1-1

STP P-SIP-22 Routine Surveillance Test of Safety Injection Pump 2-2 37

STP V-631 Penetration 31 Containment Isolation Valve Leak Testing 23

Work Order 64245136

71114.06 Procedures OM10.DC1 Emergency Preparedness Drills and Exercises 11

71124.01 Corrective Action Notifications 51093746, 51093748, 51095076, 51099489, 51099789,

Documents 51100621, 51102727, 51102887, 51107375, 51107521,

51107653, 51109334, 51109481, 51110284, 51110679

Procedures RCP D-310 RCA Access Control 27

RCP NISP-RP.02 Radiation and Contamination Surveys 4

RCP NISP-RP.04 Radiological Posting and Labeling 3

RCP NISP-RP.05 Access Controls for High Radiation Areas 5

RCP NISP-RP.11 Radiological Protection Fundamentals 0

RP1 Radiation Protection 10

RP1.DC6 Radiation Protection Code of Conduct 6

RP1.ID16 Radiation Worker Expectations 15

RP1.ID17 Control and Storage of Non Special Nuclear Material 0A

Radiation 07.02.057 Lapel Air Sample for RCP 2-3 03/22/2021

Surveys 07.02.084 Lapel Air Sample for RCP 2-3 03/22/2021

Survey # 74936, 76821, 76959, 76971, 76974, 77099, 77290, 77317,

77382, 77419, 77430, 77491, 77492

Radiation Work 2021-0042 Radioactive Waste Activities 0

Permits (RWPs) 2021-2050 2R22 Reactor Coolant Pump Work 0

21-2066 2R22 Emergent Work 1

Self-Assessments Radiation Protection Section Annual Review 02/04/2021

51108445 Pre-Inspection on Radiological Hazard Assessment and 02/17/2021

Exposure Controls

71124.02 Corrective Action Notifications 51030302, 51039000, 51045380, 51046675, 51049431,

Documents 51057182, 51065397, 51064499, 51080620, 51090235,

51090908, 51090239, 51090908, 51092294, 51092527,

51101683, 51103147, 51108141

Miscellaneous Unit 1 Average SRMP Dose Rates 01/14/2021

2018 Radiation Protection Section Annual Review 10/24/2019

2019 Radiation Protection Section Annual Review 08/03/2020

DCPP 1R22 Post Outage ALARA Report 01/27/2021

DCPP 2R21 Post Outage ALARA Report 12/18/2019

DCPP 2R20 Post Outage ALARA Report 08/15/2018

1R22 Alpha Sample Analysis 01/27/2021

2R21 Alpha Sample Analysis 05/28/2020

DCPP 1R21 Post Outage ALARA Report 03/18/2019

Unit 2 Average SRMP Dose Rates 01/14/2021

238 Unit 2 Scupper Drain Line 06/03/2019

249 Unit 2 Scupper Drain Line (Spot Shielding) 09/23/2019

51039268 2R21 Lessons Learned - RP

Procedures RCP D-200 Writing RWPs and ALARA Procedures 59

RCP D-202 RWP Work Instructions 17

RCP-200 Writing RWPs and ALARA Processes 59

RP1 Radiation Protection 10

RP1.ID1 ALARA Program 11

RP1.ID16 Radiation Worker Expectations 15

RP1.ID2 Use and Control of Temporary Radiation Shielding 18

RP1.ID9 Radiation Work Permits 13A

Radiation 68893 140' Auxiliary Building - West 09/18/2019

Surveys 74330 140' U1 Containment 10/04/2020

74782 115' Rad Waste Yard 10/13/2020

74848 140' U1 Containment 10/14/2020

Radiation Work 19-2001 2R21 General Access to CTMT 0

Permits (RWPs) 19-2020 2R21 Reactor Disassembly and Reassembly 0

19-2040 2R21 Steam Generator Work (Primary Side) 0

20-1020 1R22 Reactor Disassembly and Reassembly 0

20-1023 1R22 Fuel Movement and Under Water Work 1

20-1040 1R22 Steam Generator Work (Primary Side) 0

20-1076 1R22 Transfer Cart and Upender Repair 0

21-0042 Radioactive Waste Activities 0

21-2050 2R22 Reactor Coolant Pump Work 0

21-2066 2R22 Emergent Work 1

Self-Assessments Radiation Protection Section Annual Review - 2019

20-1A-1 2020 Radiation Protection Programs Audit 01/29/2020

51103147 NRC Attachment 71124.02 Occupational ALARA Planning 01/15/2021

and Controls

71124.04 Corrective Action Notifications 51050144, 51072589, 51084612, 51085004, 51085354,

Documents 51091115, 51093749

Miscellaneous EDEX Multipack Dosimetry - Compartmental Dose Values 2019-2020

for a Monitoring Period ( for five individuals)

DCPP ISFSI Neutron TLD Factor Characterization 12/16/2015

2016 ISFSI Neutron Follow-up Survey 09/22/2016

Fastscan WBC - MDA Sensitivity Test 05/27/2020

20 Dosimetry Fastscan MDA Sensitivity Test 05/26/2020

2R21 Alpha Sample Analysis 05/28/2020

1R22 Alpha Sample Analysis 01/27/2021

DC HPGe Bed MDA Sensitivity Test 05/27/2020

100555-0 NVLAP Certificate of Accreditation to ISO/IEC 17025:2017 -

Mirion Technologies (GDS), Inc - Ionizing Radiation

Dosimetry

NRC Form 5 Occupational Dose Record for a Monitoring Period ( for five 2019-2020

individuals)

TSD 16-090 Neutron Dosimetry Evaluation at Diablo Canyon Nuclear 1

Power Plant

Procedures RCP D-320 DLR Issue and Control 28

RCP D-328 Implementation of Personnel Dosimetry Effective Dose 4

Equivalent

RCP D-330 Personnel Dosimetry Evaluations 15

RCP D-370 Evaluation of Internal Deposition of Radioactive Material 14

RCP D-954 Thermo Electronic Dosimeter Operation 28

RCP D-957 DMC 2000 Dosimeter 6

RCP D-958 MGP 3000 Dosimeter 5

RCP NISP-RP.03 Radiological Air Sampling 5

RP1.ID10 Embryo/Fetus Protection program 9

RP1.ID6 Personnel Dose Limits and Monitoring Requirements 16

Self-Assessments Radiation Protection Section Annual Review - 2020 02/04/2021

Radiation Protection Section Annual Review - 2019 08/03/2020

71151 Miscellaneous Report DCPP Summary Generation Performance Report: 2020

Report DCPP Unit 1 Summary - 2020 Performance Indicators -

Initiating Events

Report DCPP Unit 2 Summary - 2020 Performance Indicators -

Initiating Events

71152 Corrective Action Notifications 51093299, 51095887, 51099523, 51098721, 51092587,

Documents 51095570, 51092428, 51082247, 51092779, 51097211,

51092867, 51073275, 51059901

Work Order 60086182

2

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