IR 05000275/2020004
| ML21025A435 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/26/2021 |
| From: | Jeffrey Josey NRC/RGN-IV/DRP/RPB-A |
| To: | Welsch J Pacific Gas & Electric Co |
| References | |
| IR 2020004 | |
| Download: ML21025A435 (21) | |
Text
January 26, 2021
SUBJECT:
DIABLO CANYON POWER PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000275/2020004 AND 05000323/2020004
Dear Mr. Welsch:
On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Diablo Canyon Power Plant, Units 1 and 2. On January 7, 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.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance or severity of the violation documented in this 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: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Diablo Canyon Power Plant.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC Resident Inspector at Diablo Canyon Power Plant. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Jeffrey E. Josey, Chief Reactor Projects Branch A Division of Reactor Projects
Docket Nos. 05000275 and 05000323 License Nos. DPR-80 and DPR-82
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000275 and 05000323
License Numbers:
Report Numbers:
05000275/2020004 and 05000323/2020004
Enterprise Identifier: I-2020-004-0009
Licensee:
Pacific Gas and Electric Company
Facility:
Diablo Canyon Power Plant, Units 1 and 2
Location:
Avila Beach, CA
Inspection Dates:
October 1, 2020 to December 31, 2020
Inspectors:
I. Anchondo-Lopez, Materials Engineer
D. Antonangeli, Health Physicist
A. Athar, Resident Inspector
M. Doyle, Operations Engineer
D. Krause, Senior Resident Inspector
J. O'Donnell, Senior Health Physicist
E. Simpson, Health Physicist
Approved By:
Jeffrey E. Josey, Chief
Reactor Projects Branch A
Division of Reactor Projects
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
Failure to Use Procedures While Performing an Activity Affecting Quality Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000275/2020004-01 Open/Closed
[H.12] - Avoid Complacency 71111.13 A self-revealed finding of very low safety significance (Green) and associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was identified on October 8, 2020, as a result of the licensees failure to accomplish an activity affecting quality in accordance with documented procedures.
Specifically, the operators failed to follow the procedure and adequately check to ensure CS-1-37 was closed. This is contrary with OP2.ID1, Clearances, in that documented procedures, affecting quality, were not adhered to while establishing a valve lineup on the Unit 1, containment spray system in preparation for filling the refueling cavity.
PLANT STATUS
Unit 1 began the inspection period in coast-down at 90 percent rated thermal power. On October 3, 2020, the unit was shut down for a refueling outage and was returned to full rated thermal power on November 6, 2020. The unit was at or near full rated thermal power for the remainder of the inspection period.
Unit 2 began the inspection period at full rated thermal power. On October 15, 2020, Unit 2 was shut down due to a hydrogen leak in the main turbine generator. Unit 2 returned to full power on November 28, 2020, and operated at full power until December 2, 2020, when the unit was, again, shut down due to a hydrogen leak in the main turbine generator. The unit was 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 on-site 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 on-site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of high wind and high swell advisories for the intake structure and circulating water system on December 7, 2020.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (1 Sample)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1, shutdown cooling on residual heat removal train A on October 21, 2020
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1, component cooling water system on November 10-18, 2020.
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) Unit 1, containment 117-foot elevation on October 5, 2020
71111.06 - Flood Protection Measures
Cable Degradation (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the cable submergence protection program in the auxiliary saltwater pump vaults on December 28, 2020.
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness and performance of the Unit 1, component cooling water heat exchangers 1-1 and 1-2 on December 21, 2020.
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (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 October 5 to November 5, 2020:
03.01.a - Nondestructive Examination and Welding Activities
- Ultrasonic Examination, Safety Injection Accumulator 1, 2, 3, 4 nozzles
- Ultrasonic Examination, Pressurizer Spray Line, WIB-378
- Ultrasonic Examination, Residual Heat Removal, WIB-228
- Ultrasonic Examination, Residual Heat Removal, WIC-95 03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities
- The inspector observed the following reactor head penetration visual examinations: Penetration 10, 14, 22, 38, 39, 45, 46, and 63
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities
- The inspector reviewed the following boric acid leak evaluations:
Notification Nos. 51090916, 51016159, 51082802.
03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities
- Each steam generator received a full-length 100 percent tube eddy current inspection using a bobbin coil.
- Special Interest locations were inspected as necessary using an eddy current plus point rotating probe.
- Visual inspections were completed to verify previous tubes that had been plugged.
- No issues were identified, and the condition monitoring assessment was satisfied.
03.01.e - Problem Identification and Resolution
- The inspector reviewed 15 condition reports/notifications associated with inservice and operating experience issues and concluded that non-destructive examination/inservice inspection (NDE/ISI) related issues and operating experience are put into the corrective action program at low levels to ensure conditions and problems are identified.
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered on June 23, through July 31, 2020.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during the Unit 1, 1R22 outage shutdown activities on October 3, 2020.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated just-in-time training for the Unit 1 startup using dilute to criticality procedures and licensed operator requalification (LOR)
R204S1 on October 29, 2020, and on December 8, 2020.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (1 Sample)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Containment up-ender maintenance following failure to lower during fuel movement on October 13, 2020
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 1, valve CS-1-37 mispositioned, leak in containment during yellow risk due to lowered inventory on October 3, 2020 (2)boric acid found around RCP 1-1 flanges on October 4, 2020
- (3) Unit 2, emergent risk from unplanned inoperability of emergency diesel generator 2-1 on October 6-7, 2020
- (4) Unit 2, main generator hydrogen leak on October 15, 2020
- (5) Unit 1, yellow outage risk due to being at lowered inventory with single source of offsite power on October 25, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 2, diesel generator 2-1 inoperable due to oil leak on October 4, 2020
- (2) Unit 1, reactor coolant pump (RCP) 1-3 inoperable due to high vibrations on October 29, 2020
- (3) Unit 1, startup bus voltage fluctuations and blowing fuses on October 30, 2020
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Unit 1, incipient fire detection system (IFDS) battery swap on December 4, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Unit 1, component cooling water (CCW) pump 1-2 comprehensive test on October 26, 2020
- (2) Unit 1, containment spray pump 1-1 comprehensive test on October 26, 2020
- (3) Unit 1, dynamic rod worth determination after loading new core on October 29, 2020
- (4) Unit 2, emergency diesel generator 2-3 after major maintenance activities on December 11, 2020
- (5) Unit 1, turbine-driven auxiliary feedwater pump 1-1 maintenance activities on December 14, 2020
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
Unit 1 Refueling Outage 1R22
- (1) The inspectors evaluated refueling outage 1R22 activities from October 3, 2020 through November 2, 2020.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Unit 1, residual heat removal system flush on October 4, 2020
- (2) Unit 1, 4 kV bus F, G, and H, vital bus auto-transfer test on October 5, 2020 (3)diesel generator 2-1 routine surveillance test on October 6, 2020
- (4) Unit 1, main turbine overspeed trip test on November 2, 2020 (5)reload power ascension testing on November 2-3, 2020
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1, chemical and volume control system (CVCS) 1-8152 test and repair on October 26, 2020
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated a reduced scope emergency response organization drill with field monitoring team activation on December 2,
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)
- (1) The inspectors evaluated radiological protection-related instructions to plant workers.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material through the following observations:
(1)observed licensee conduct surveys of potentially contaminated material leaving the radiologically controlled area (RCA)
(2)observed workers exciting the RCA at the 140-foot egress location during the Unit 1 refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) Temporary Reactor Head Removal under radiation work permit (RWP) No. 20-1023.
This work involved Alpha Level II Controls.
- (2) Fuel Transfer Cart Maintenance under RWP No. 20-1026. This work involved significant dose rate gradients, technical specifications high radiation areas, and alpha II level controls.
- (3) Steam Generator Manway Cover/Insert Removal under RWP No. 20-1040. This work involved dose rate gradients, technical specifications high radiation areas, and alpha level II controls.
- (4) Movement of Upper Internals under RWP No. 20-1020. This work involved technical specifications high radiation areas.
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) Unit 1, containment letdown orifice room (2)auxiliary building spent resin tank area
- (3) Unit 1, containment reactor coolant drain tank room
- (4) Unit 1, containment under vessel plug
- (5) Unit 1, containment regenerative heat exchanger room 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.
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Permanent Ventilation Systems (IP Section 03.01) (1 Sample)
The inspectors evaluated the configuration of the following permanently installed ventilation systems:
(1)control room and technical support center ventilation systems
Temporary Ventilation Systems (IP Section 03.02) (2 Samples)
The inspectors evaluated the configuration of the following temporary ventilation systems:
- (1) HEPA ventilation system for the decontamination tent on the 91-foot elevation of the Unit 1, containment building
- (2) HEPA ventilation for under the reactor pressure vessel head on the 140-foot elevation in the Unit 1, containment building
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices.
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Shipment Preparation (IP Section 03.04)
- (1) The inspectors observed a shipment containing radioactive material to determine if it was prepared according to requirements.
Shipment No. RMS-20-084 SCO II - 3 Metal Boxes of SQUID Equipment Return to Vendor UN2913
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
Performance Indicator data were verified for Reactor Coolant System (RCS) Specific Activity
- (1) Unit 1 (October 1, 2019 through September 30, 2020)
- (2) Unit 2 (October 1, 2019 through September 30, 2020)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
Performance Indicator data were verified for Reactor Coolant System (RCS) Leak Rate
- (1) Unit 1 (October 1, 2019 through September 30, 2020)
- (2) Unit 2 (October 1, 2019 through September 30, 2020)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) January 1, 2019 through September 30, 2020 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) January 1, 2019 through September 30, 2020
71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)
- (1) The inspectors evaluated Unit 2 shutdowns and forced outages due to a main generator hydrogen leak and the licensees responses on October 15, 2020, and on December 2,
INSPECTION RESULTS
Failure to Use Procedures While Performing an Activity Affecting Quality Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity
Green NCV 05000275/2020004-01 Open/Closed
[H.12] - Avoid Complacency 71111.13 A self-revealed finding of very low safety significance (Green) and associated non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, was identified on October 8, 2020, as a result of the licensees failure to accomplish an activity affecting quality in accordance with documented procedures. Specifically, the operators failed to follow the procedure and adequately check to ensure CS-1-37 was closed. This is contrary with OP2.ID1, Clearances, in that documented procedures, affecting quality, were not adhered to while establishing a valve lineup on the Unit 1, containment spray system in preparation for filling the refueling cavity.
Description:
During the 1R22 reactor vessel head lift and cavity flood-up, with the plant in a yellow risk window for lowered reactor water inventory, a significant amount of water (approximately 300 gallons) was reported spraying into the 91-foot elevation of containment from an elevation above. This was observed shortly after the head lift had begun, coincident with filling of the refuel cavity. Borated refueling water storage tank (RWST) water sprayed into containment for approximately 30 minutes until valve CS-1-37 was identified as the source of the water and the containment spray system cavity fill process was stopped. Both the reactor head lift and cavity fill activities were paused for approximately 90 minutes.
It was determined that CS-1-37, Containment Spray Header 'A' Drain Valve, a 3/4-inch drain valve, was mispositioned open. This valve had been caution tagged closed per clearance order 1C22-R-12-006 but remained in the open position as both the operator and independent verifier incorrectly believed the valve was closed when no handwheel movement in the closed direction was obtained. The valve is a normally sealed-open valve with a tie-wrap restrictor, sealing the valve handwheel from moving. This tie-wrap was in-place; however, the operators did not see the restricting seal when hanging the clearance order.
The seal procedure is only in-effect during operations and is not tracked once the unit is shut down.
Corrective Actions: The licensee immediately stopped the head lift (raised approximately 2 inches), and within 30 minutes found the open valve and stopped the flow. The licensee additionally took the following actions: verification walkdown of the clearance R-12-006; shift stand-down; containment clean-up; and evaluation of the event for performance improvement which includes remediating the operators involved, improving communications and briefings for clearance activities, and detailing how to deal with difficult--to--manipulate valves.
Corrective Action References: 51091509
Performance Assessment:
Performance Deficiency: Improperly performing a procedure by failing to correctly position a valve while performing a valve lineup activity affecting quality was a performance deficiency warranting further evaluation and within the licensees ability to foresee and correct Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Human Performance attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the inspectors based this determination on the fact that with valve CS-1-37 open, a possible drain path from the refuel cavity was established during an already elevated risk window for lowered reactor coolant inventory (POS 2).
Significance: The inspectors assessed the significance of the finding using Appendix G, Shutdown Safety SDP. Using Exhibit 4, Barrier Integrity Screening Questions, of IMC 0609, Appendix G, Attachment 1, Shutdown Operations Significance Determination Process, Phase 1 Initial screening and Characterization of Findings, the finding was determined to have very low safety significance (Green) because all the screening questions were answered No.
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.
Enforcement:
Violation: This is a violation of 10 CFR Part 50, Appendix B, Criterion V.
Title 10 CFR Part 50, Appendix B, Criterion V, states, in part, Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
Contrary to the above, on October 8, 2020, activities affecting quality were identified as not performed per documented instructions, procedures, or drawings, of a type appropriate to the circumstances. Specifically, the licensee did not ensure the valve line-up prescribed in clearance 1C22-R-12-006 was completed as specified.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Assessment 71153 The inspectors evaluated the licensee's performance during two, Unit 2 controlled shutdowns, required due to a main generator hydrogen leak on October 15, 2020 and on December 2, 2020. The inspectors determined that it was not reasonably within the licensees ability to foresee or correct the cause of the hydrogen leaks and therefore, no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 22, 2020, the inspectors presented the occupational and public safety radiation safety inspection results to Mr. C. Harbor, Site Director, and other members of the licensee staff.
- On November 5, 2020, the inspectors presented the Unit 1 inservice inspection results to Ms. P. Gerfen, Site Vice President, and other members of the licensee staff.
- On January 7, 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
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
20 Storm Season Readiness Memo
2/07/2020
Procedures
OP O-28
Operations Intake Response to Storms or Biofouling
Procedures
OP1.ID10
Intake Management for Storms and Biofouling
Corrective Action
Documents
Notifications
51093529, 51093591, 510977788, 51097933
Procedures
OP B-2:V
RHR - Place In Service
Procedures
OP F-2:VI
CCW System Alignment Verification for Plant Startup
Corrective Action
Documents
Notification
51091354
Drawings
RA-27/28
Fire Drawing: Containment Building Elev. 91 & 117 Unit 1
Corrective Action
Documents
Notification
50653777
Procedures
AWP E-016
Inspection Guide - Maintenance Rule Structural Monitoring
Programs - Civil
Work Orders
64137797
Corrective Action
Documents
Notifications
51088969, 51087648
Procedures
PEP M-234
CCW Heat Exchanger Performance Test
Work Orders
64159953, 64159944
Corrective Action
Documents
Notifications
51018309, 51019678, 51055075, 51055110, 51055176,
51055177, 51063903, 51065848, 51069770, 51071296,
51073505, 51076810, 51016159, 51082802, 51090916
Miscellaneous
Diablo Canyon Unit 1 Refueling Outage 1R22 - Steam
Generator Degradation Assessment
Miscellaneous
SG-CDMP-20-22
Diablo Canyon Unit 1 1R22 Condition Monitoring and
Operational Assessment
Procedures
AD4.ID2
Plant Leakage Evaluation
Procedures
EPRI-PIPE-TWS-
MPA-1
Procedure for Manual Phased Array Ultrasonic Through-Wall
Sizing in Pipe Welds
Procedures
ER1.ID2
Boric Acid Corrosion Control Program
Procedures
ISI X-CRDM
Reactor Vessel Top and Bottom Head Visual Inspections
Procedures
NDE PDI-UT-2
Ultrasonic Examination of Austenitic Piping
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
NDE PDI-UT-3
Ultrasonic Through-Wall Sizing in Pipe Welds
Procedures
NOZ
Ultrasonic Examination of Accumulator Tank Nozzles and
Similar Fittings
Procedures
NDE UT-2
Ultrasonic Thickness Measurement Examination Procedure
Procedures
NDE UT-WOL-
PA1
Manual Phased Array Ultrasonic Exam of Similar &
Dissimilar Metal Overlays Welds
Miscellaneous
20 annual
operating exam
results
71111.11Q Miscellaneous
R204-S1
Scenario
2/08/2020
Corrective Action
Documents
Notifications
51091797, 51092061, 51092251, 51092256
Procedures
STP M-27B
Fuel Transfer System Interlock Verification and Functional
testing
Work Orders
60131805
Corrective Action
Documents
Notifications
51081683, 51081723, 51090768, 51091312, 51091509,
51092605
Drawings
106712
Unit 1 Containment Spray
Miscellaneous
1R22 (AD8.DC55
Att-7)
1R22 Outage Safety Plan
Procedures
AD7.DC6
On-Line Maintenance Risk Management
Procedures
AR PK14-18
Generator Hydrogen System
Procedures
OP AP-30
Main Generator Malfunction
Procedures
OP O-36
Protected Equipment Postings
Procedures
OP1.DC20
Sealed Components
Procedures
OP2.ID1
Clearances
Procedures
OP2.ID2
Tagging Requirements
Corrective Action
Documents
Notifications
50985660, 51054295, 51091312, 51094841, 51094995
Procedures
STP M-91
Diesel Generator Start and Load Tracking
29A
Work Orders
60132181
Engineering
Changes
1000025565
U1 Incipient Fire Detection System (IFDS) Battery Swap
09/29/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Notifications
51100241, 51101795
Procedures
STP M-21-A.1
Diesel Engine Analysis
Procedures
STP M-9A3
Diesel Engine Generator 2-3 Routine Surveillance Test
Procedures
STP M-9B
Overspeed Trip Test of Diesel Generators
Procedures
STP M-9D1
Diesel Generator Full Load Rejection Test
Procedures
STP M-9L
Diesel Generator Shutdown Lockout Relay Test
Procedures
STP P-CCW-A12
Comprehensive Pump Test of Component Cooling Water
Pump 1-2
Procedures
STP P-CSP-A11
Comprehensive Testing of Containment Spray Pump 1-1
Procedures
STP R-6
Low Power Reload Physics Tests
Procedures
STP-P-AFW-11
Routine Surveillance Test of Turbine-Driven Auxiliary
Feedwater Pump 1-1
Work Orders
230081
Corrective Action
Documents
Notifications
51090768, 51091509
Miscellaneous
Data Sample of Personnel Workhours
10/30/2020
Miscellaneous
1R22 (AD8.DC55
Att-7)
Outage Safety Plan 1R22
Miscellaneous
OP A-6:II
RCS Inventory Monitoring
10/10/2020
Miscellaneous
PEP R-8DS1
Diablo Canyon Power Plant Fuel Movement Tracking Sheet
10/19/2020
Procedures
OP A-2:II
Reactor Vessel - Draining the RCS to the Vessel Flange -
With Fuel in Vessel
Procedures
OP L-4
Normal Operation at Power
101
Procedures
OP L-5
Plant Cooldown from Minimum Load to Cold Shutdown
107
Corrective Action
Documents
Notifications
51091058, 51091207, 51091317
Procedures
OP B-2:V
RHR - Place in Service
Procedures
STP M-13F
kV Bus F Non-SI Auto Transfer Test
Procedures
STP M-13G
kV Bus G Non-SI Auto Transfer Test
Procedures
STP M-13H
kV Bus H Non-SI Auto Transfer Test
Procedures
STP M-21B
Main Turbine Overspeed Trip Tests
Procedures
STP M-9A1
Diesel Engine Generator 2-1 Routine Surveillance Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
STP R-40
Reload Power Ascension Testing
Procedures
STP R-40
Reload Power Ascension Testing
Work Orders
60132869
Miscellaneous
Field Monitoring
Team Activation
(FMT) Drill
Scenario
Field Monitoring Team Activation (FMT) Drill Scenario
2/04/2020
Corrective Action
Documents
Notifications
50961599, 51014075, 51014681, 51014777, 51016203,
51017185, 51017810, 51019824, 51019845, 51022267,
51023591, 51028394, 51031037, 51040313, 51047242,
51048484, 51049174, 51049610, 51051377, 51052328,
51052345, 51090908
Miscellaneous
U1 SFP Non-SNM Inventory Dose Rates
10/07/2020
Miscellaneous
U2 SFP Non-SNM Inventory Dose Rates
10/07/2020
Miscellaneous
10/07/2020
Procedures
RCP D-310
RCA Access Control
Procedures
RCP NISP-RP.02
Radiation and Contamination Surveys
Procedures
RCP NISP-RP.04
Radiological Posting and Labeling
Procedures
RCP NISP-RP.05
Access Controls for High Radiation Areas
Procedures
RP1.DC6
Radiation Protection Code of Conduct
Procedures
RP1.ID16
Radiation Worker Expectations
Procedures
RP1.ID17
Control and Storage of Non Special Nuclear Material
03/02/2019
Radiation
Surveys
74403, 74610,
74801,
74810, 74826,
74832,
75101, 75106,
75114
Radiation Work
Permits (RWPs)
RWP 20-1020
1R22 Disassembly and Reassembly
Radiation Work
Permits (RWPs)
RWP 20-1023
1R22 Fuel movement and Under Water Work
Radiation Work
Permits (RWPs)
RWP 20-1026
1R22 Lower Cavity & Transfer Canal Work, Lower Cavity
Decon
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation Work
Permits (RWPs)
RWP 20-1040
1R22 Steam Generator (Primary Side)
Self-Assessments # 2020-IA-1
20 Radiation Protection Programs Audit
01/29/2020
Self-Assessments Quick Hit Self-
Assessment
Report
Pre-Inspection on Radiological Hazard Assessment and
Exposure Controls
09/01/2020
ALARA Plans
20-1040
Respirator Use Evaluation
10/12/2020
ALARA Plans
20-1040
ALARA Plan - Unit 1
09/25/2020
Corrective Action
Documents
Notifications
51020066, 51034518, 51034619, 51038096, 51039243,
51039296, 51054218, 51060942, 51086588, 51088058
Miscellaneous
Monthly E-Plan Minimum Quantity SCBA Inventory
08/28/2020
Miscellaneous
20-21429
Trace Gas Analysis
07/16/2020
Miscellaneous
20-24746
Trace Gas Analysis
08/13/2020
Procedures
OM6.ID10
Respiratory Protection Program
Procedures
PEP M-96
TSC Ventilation Systems - DOP and Halide Penetration
Tests
9A
Procedures
RCP D-707A
MSA FireHawk (NIOSH) Self-Contained Breathing
Apparatus Inspection
Procedures
RCP D-710
Use of Supplied Air Respirators Using Airlines
Procedures
RCP D-712
MAXAIR Powered Air Purifying Respirator
Procedures
RCP D-722
Use of the MSA OptimAir TL Powered Air-Purifying
Respirator Hood
Procedures
RCP D-732
Respirator Fit Testing
Procedures
STP M-53
Control Room Ventilation System - DOP and Halide
Penetration Tests
Radiation
Surveys
75106
1R22 91 CTMT Decon SG HEPA Pre-filter Housings
10/20/2020
Radiation Work
Permits (RWPs)
RWP 20-1040
1R22 Disassembly and Reassembly
Self-Assessments # 2020-IA-1
20 Radiation Protection Programs Audit
01/29/2020
Self-Assessments 51086757
In-plant Airborne Radioactivity Control and Mitigation (NRC
IP 71124.03 - Effective 1/1/2020)
09/17/2020
Work Orders
64160544
Unit 1 Control Room Ventilation System Testing
04/08/2019
Work Orders
64161425
Unit 2 Control Room Ventilation System Testing
04/11/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Shipping Records RMS-20-084
Shipping Package for (3) Metal boxes shipped SCO-II and
(1) Non-Rad 20 ' C-Van
10/20/2020
71151
Miscellaneous
Unit 1, 2019-2020 RCS specific activity data
71151
Miscellaneous
Unit 2, 2019-2020 RCS specific activity data
71151
Miscellaneous
Unit 1, 2019-2020 RCS leak rate data
71151
Miscellaneous
Unit 2, 2019-2020 RCS leak rate data