IR 05000275/2025002
| ML25199A207 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/28/2025 |
| From: | Patricia Vossmar NRC/RGN-IV/DORS/PBA |
| To: | Gerfen P Pacific Gas & Electric Co |
| References | |
| IR 2025002 | |
| Download: ML25199A207 (1) | |
Text
July 28, 2025
SUBJECT:
DIABLO CANYON POWER PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000275/2025002 AND 05000323/2025002
Dear Paula A. Gerfen:
On June 30, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Diablo Canyon Power Plant, Units 1 and 2. On July 10, 2025, 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 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Patricia J. Vossmar, Chief Reactor Projects Branch A Division of Operating Reactor Safety 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:
05000275/2025002 and 05000323/2025002
Enterprise Identifier:
I-2025-002-0011
Licensee:
Pacific Gas and Electric Company
Facility:
Diablo Canyon Power Plant, Units 1 and 2
Location:
Avila Beach, CA
Inspection Dates:
April 1, 2025, to June 30, 2025
Inspectors:
B. Baca, Health Physicist
K. Clayton, Senior Operations Engineer
J. Drake, Senior Reactor Inspector
E. Garcia, Resident Inspector
M. Hayes, Senior Resident Inspector
N. Hernandez, Senior Operations Engineer
K. Murphy, Operations Engineer
J. Nadel, Reactor Inspector
J. O'Donnell, Senior Health Physicist
Approved By:
Patricia J. Vossmar, Chief
Reactor Projects Branch A
Division of Operating Reactor Safety
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 began the inspection period at rated thermal power. On April 13, 2025, the unit was shut down to enter refueling outage 1R25. On May 17, 2025, the unit began a controlled power ascension to rated power after completing refueling outage 1R25. The unit reached full power on May 22, 2025. The unit remained at or near rated thermal power for the remainder of the inspection period.
Unit 2 operated at or near rated thermal power for the entire 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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 reactor vessel refueling level indicating system on April 15, 2025
- (2) Unit 2 containment spray pump 2-1 and 2-2 on June 20, 2025
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 containment 140-foot elevation on April 29, 2025
- (2) Unit 1 containment 117-foot elevation on April 30, 2025
- (3) Unit 1 containment 91-foot elevation on May 2, 2025
- (4) Unit 1 and Unit 2 control room on June 16, 2025
- (5) Unit 2 radiological control area 100-foot elevation on June 20, 2025
===71111.08P - Inservice Inspection Activities (PWR) 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 following activities in Unit 1 during refueling outage 1R25 from April 21 to May 1, 2025.
PWR Inservice Inspection Activities Sample - Nondestructive Examination and Welding Activities (IP Section 03.01)===
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
- (1) Ultrasonic examination
1. reactor coolant system, control rod drive mechanism, weld 70
2. reactor coolant system, reactor vessel core exit thermocouple nuclear
3. reactor coolant system, control rod drive mechanism, weld 72
4. pressurizer, pressurizer girth weld 1
5. pressurizer, pressurizer longitudinal weld 6
6. reactor coolant system, reactor head closure studs, studs 1 to 54
7. safety injection system, accumulators, accumulator 1-1, nozzle A, B, CA,
C-1A, CB, D, D skirt, E, G, G skirt
8. safety injection system, accumulators, accumulator 1-2, nozzle A, B, CA,
C-1A, CB, D, D skirt, E, G, G skirt
9. safety injection system, accumulators, accumulator 1-3, nozzle A, B, CA,
C-1A, CB, D, D skirt, E, G, G skirt 10. safety injection system, accumulators, accumulator 1-4, nozzle A, B, CA, C-1A, CB, D, D skirt, E, G, G skirt Magnetic particle examination
1. pressurizer, pressurizer girth weld 10
Visual 3 examination
1. reactor coolant system, reactor vessel bottom penetration bare metal visual
exam of 100 percent of the bottom vessel penetrations Welding activities
1. gas tungsten arc welding:
a.
condensate, condensate storage tank recirculation valve MU-1-673, socket weld 1 b.
condensate, condensate storage tank recirculation valve MU-1-673, socket weld 2 c.
condensate, condensate storage tank recirculation valve MU-1-673, socket weld 3 d.
condensate, condensate storage tank recirculation valve MU-1-673, socket weld 4 e.
condensate, condensate storage tank recirculation valve MU-1-673, socket weld 5 f.
condensate, condensate storage tank recirculation valve MU-1-673, socket weld 6 PWR Inservice Inspection Activities Sample - Vessel Upper Head Penetration Inspection
Activities (IP Section 03.02) (1 Sample)
The inspectors verified that the licensee conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:
(1)
- Diablo Canyon 1R25 bare metal visual 100 percent coverage VT-3 exam of the reactor vessel upper head penetrations PWR Inservice Inspection Activities Sample - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)
The inspectors verified the licensee was managing the boric acid corrosion control program through a review of the following evaluations:
(1)
===50571516, DC-1-09-P-V-SI-1-8808A
- 50680244, DC-1-09-P-V-SI-1-8823
- 51147509, DC-1-08-P-V-CVCS-1-8147
- 51279605, DC-1-07-M-VS-RV1
- 51279636, DC-1-07-P-V-RCS-1-620
- 51279637, DC-1-07-P-V-RCS-1-628
- 51279650, DC-1-09-P-V-SI-1-80
- 51279655, DC-1-09-P-V-SI-1-302D
- 51279656, DC-1-09-P-V-SI-1-8819D
- 51279658, DC-1-09-P-V-SI-1-8902C
- 51281913, DC-1-07-M-TK-PRT1
- 50808856, DC-1-07-P-V-RCS-1-628
- 50914866, DC-1-07-P-V-RCS-1-628
- 51258447, DC-0-19-P-V-LWS-0-805
- 51278814, DC-1-11-P-V-NSS-1-10X
- 51280714, DC-1-08-P-V-CVCS-1-8484A PWR Inservice Inspection Activities Sample - Steam Generator Tube Inspection Activities (Section 03.04)
The inspectors verified that no ASME code inspection of the steam generator tube integrity was required this outage.
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03)===
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating and biennial written examinations administered between May 20, 2025, and June 27, 2025.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on May 23, 2025.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator The inspectors evaluated the adequacy of the licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
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 Unit 1 startup activities from refueling outage 1R25 on May 14, 2025.
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 May 27, 2025.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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 Yellow risk window due to battery charger 1-1 planned maintenance on April 1, 2025
- (2) Unit 1 Yellow risk during reduced inventory with one source of offsite power on April 15, 2025
- (3) Unit 1 condenser saltwater inleakage preventing power ascension on May 21, 2025
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 1 reactor coolant pump 1-3 seal leakoff flow low alarm during dilution on April 2, 2025
- (2) Unit 1 auxiliary feedwater valve LCV-108 failed to close on April 23, 2025
- (3) Unit 1 pressurizer power operated relief valve stem leakage into pressurizer relief tank on May 23, 2025
- (4) Unit 1 atmospheric steam dump valve PCV-19 taken to manual on May 27, 2025
- (5) Unit 1 letdown pressure control valve PCV-135 placed in manual after not controlling in automatic on May 28, 2025
- (6) Unit 2 diesel generator 2-1 return to service without replacing fuel oil booster pump drivebelt on June 12, 2025
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 reactor coolant pump seal venting temporary modification on May 7, 2025
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated refueling outage 1R25 activities from April 13 to May 13, 2025.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (4 Samples)
- (1) Unit 1 auxiliary salt-water pump 1-2 and component cooling water heat exchanger 1-2 return to service following maintenance on April 2, 2025
- (2) Unit 1 emergency diesel generator 1-1 undervoltage relay calibration on May 1, 2025
- (3) Unit 1 emergency core cooling system check valves following maintenance on May 15, 2025
- (4) Unit 2 surveillance test procedure STP M-75G, 4 kV Vital Bus G Undervoltage Relay Calibration, on June 10, 2025
Surveillance Testing (IP Section 03.01) (3 Samples)
- (1) Unit 1 containment closure drill on April 15, 2025
- (2) Unit 1 surveillance test procedure STP M-13H, 4 kV Bus H Non-SI Auto-Transfer Test, on April 15, 2025
- (3) Unit 1 emergency diesel generator 1-3 24-hr load test and hot restart on June 26, 2025
Inservice Testing (IST) (IP Section 03.01) (2 Samples)
- (1) Unit 1 residual heat removal pumps 1-1 and 1-2 on April 16, 2025
- (2) Unit 1 auxiliary feedwater pump 1-1 on May 19, 2025
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (2 Samples)
The inspectors evaluated:
(1)tabletop emergency preparedness drill conducted with emergency crew B on June 25, 2025 (2)tabletop emergency preparedness drill conducted with emergency crew C on June 25,
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, identifies the concentrations and quantities of radioactive materials, and assesses radiological hazards.
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:
(1)surveys of potentially contaminated material leaving the radiologically controlled area at the 85-foot egress (2)workers exiting the Unit 1 containment building 140-foot egress during a refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:
- (1) Unit 1 retrieval of the reactor vessel specimen coupon 'B' on April 21, 2025, using radiation work permit 25-1024, Revision 0
- (2) Unit 1 core barrel setup and removal on April 22, 2025, using radiation work permit 25-1085, Revision 0
- (3) Unit 1 reactor coolant pump seal removal on April 18, 2025, using radiation work permit 25-1050, Revision 0
- (4) Unit 1 pressurizer support welding work on April 21, 2025, using radiation work permit 25-1066, Revision 0 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 (HRAs) and very high radiation areas (VHRAs):
(1)
(VHRA) - Unit 1, 85-foot fuel handling building, fuel transfer tube area (2)
(VHRA) - Unit 1, 91-foot containment building, under reactor vessel plug (3)
(VHRA) - Unit 1, 115-foot auxiliary building, spent resin storage tank area (4)
(HRA) - Unit 1, 91-foot containment building, regenerative heat exchanger room (5)
(HRA) - Unit 1, 100-foot auxiliary building, chemical and volume control system filter covers
- (8) 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.
71124.04 - 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 how the licensee processes, stores, and uses external dosimetry.
Internal Dosimetry (IP Section 03.03) (2 Samples)
The inspectors evaluated the following internal dose assessments:
- (1) assessment 4839 dated November 20, 2023 (2)assessment 5055 dated May 6, 2024
Special Dosimetric Situations (IP Section 03.04) (2 Samples)
The inspectors evaluated the following special dosimetric situations:
(1)five declared pregnant worker files (2)twenty-five effective dose equivalent multipack monitoring packages
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) (IP Section 02.04)===
- (1) Unit 1 (April 1, 2024, through March 30, 2025)
- (2) Unit 2 (April 1, 2024, through March 30, 2025)
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 1 (April 1, 2024, through March 30, 2025)
- (2) Unit 2 (April 1, 2024, through March 30, 2025)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 (April 1, 2024, through March 30, 2025)
- (2) Unit 2 (April 1, 2024, through March 30, 2025)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) April 1, 2024, through March 31, 2025 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) April 1, 2024, through March 31, 2025
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program to identify potential trends in Unit 1 and Unit 2 closure criteria for control board notification tags that might be indicative of a more significant safety issue.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 28, 2025, the inspectors presented the occupational radiation safety inspection results to Paula A. Gerfen, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.
- On May 1, 2025, the inspectors presented the inservice inspection results to Paula A.
Gerfen, Senior Vice President and Chief Nuclear Officer, and other members of the licensee staff.
- On June 5, 2025, the inspectors presented the operator requalification program technical debrief inspection results to Matthew Birkel, Director, Nuclear Training and Accreditation, and other members of the licensee staff.
- On July 3, 2025, the inspectors presented the operator requalification program inspection results to Ted Stanton, Manager, Nuclear Operations Training, and other members of the licensee staff.
- On July 10, 2025, the inspectors presented the integrated inspection results to Paula A.
Gerfen, 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
Drawings
107712-2
Procedures
OP A-2:X
Unit 1, RVRLIS Initial Shutdown Alignment
111805-16
Radiological Control Area (RCA) & H Bloc Elev 140'
111805-20
Radiological Control Area (RCA) Elev. 100'
111805-35
Containment Building Elev. 91'
111805-37
Containment Building Elev. 117'
111805-38
Containment Building Elev. 140'
111906-27
Containment Building Elev. 117'
111906-28
Containment Building Elev. 140'
Drawings
111906-29
Containment Building Elev. 91'
Corrective
Action
Documents
Resulting from
Inspection
Notifications
283379, 51283385
Drawings
6657E64
Diablo Canyon 1 (PGE) SUPREEM General
Assembly
60168812-0020
Weld Rod Slip Checkout Form
04/22/2025
DCPP Form 69-20097
Material Tracking Form
01/27/2025
DCPP Form 69-21998
Straight Beam Calibration Data Sheet
04/29/2025
DCPP Form 69-22135
Magnetic Particle Examination Data Sheet
04/25/2025
Miscellaneous
IG-10-1
Westinghouse InfoGram: REACTOR INTERNALS
LOWER RADIAL SUPPORT CLEVIS INSERT CAP
SCREW DEGRADATION
03/31/2010
AD4.ID2
Plant Leakage Evaluation
AD5.ID2
Inservice Inspection Program
AD7.ID11
Fluid Leak Management Program
ER1.ID2
Boric Acid Corrosion Control Program
ISI X-CRDM
Reactor Vessel Top and Bottom Head Visual
Inspections
MA3
Special Processes
3A
Procedures
NDE MT-1
Magnetic Particle Examination Procedure
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Ultrasonic Examination of Accumulator Tank
Nozzles and Similar Fittings
Visual Examination of Component and Piping
Supports
OM7
Corrective Action Program
PDI-UT-1
PDI Generic Procedure for the Ultrasonic
Examination of Ferritic Pipe Welds - Personnel
Qualification (Various)
D
PDI-UT-10
PDI Generic Procedure for the Ultrasonic
Examination of Dissimilar Metal Piping Welds -
Personnel Qualification (Various)
A
PDI-UT-11
PDI Generic Procedure for the Ultrasonic Detection
and Sizing of Reactor Pressure Vessel Nozzle to
Shell Welds and Nozzle Inner Radius - Personnel
Qualification (Various)
A
PDI-UT-2
PDI Generic Procedure for the Ultrasonic
Examination of Austenitic Pipe Welds - Personnel
Qualification (Various)
A
PDI-UT-3
PDI Generic Procedure for the Ultrasonic Through
Wall Sizing in Pipe Welds - Personnel Qualification
(Various)
C
PDI-UT-5
PDI Generic Procedure for Straight Beam Ultrasonic
Examination of Bolts and Studs - Personnel
Qualification (Various)
B
PDI-UT-6
PDI Generic Procedure for the Manual Ultrasonic
Examination of Reactor Pressure Vessel Welds -
Personnel Qualification (Various)
F
PDI-UT-7
PDI Generic Procedure for the Manual Ultrasonic
Through Wall and Length Sizing of Ultrasonic
Indications in Reactor Pressure Vessel Welds -
Personnel Qualification (Various)
F
PDI-UT-8
PDI Generic Procedure for the Ultrasonic
Examination of Weld Overlaid and Similar and
Dissimilar Metal Welds - Personnel Qualification
E
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
(Various)
STP R-8C
Containment Walkdown for Evidence of Boric Acid
Leakage
TQ1.ID12
Qualification and Certification of NDE Personnel
WDI-STD-1196
Ultrasonic Test Procedure for the Inspection of
1.00-8 Socket Head Clevis Insert Bolts
WPS-5
Welding Procedure Specification for P1 Materials
50474734
U1, RPV Closure Head Bare Metal Visual I
04/22/2025
50997763
U1, RPV Lower Head Inspection
04/18/2025
60150915-0030
Unit 1 PRT: Internal LR Coatings Inspection
04/24/2025
60166073-0050
1R25, ISI NDE & Support, Containment - NDE
Press. Shell to Bottom Hd Circ Weld
04/23/2025
60166073-0140
1R25, ISI NDE & Support, Containment - NDE
Reactor Vessel 1: CRDM 70 Weld
04/23/2025
60166073-0150
1R25, ISI NDE & Support, Containment - NDE
Reactor Vessel 1: CETNA 72 Weld
04/22/2025
60166073-0160
1R25, ISI NDE & Support, Containment - NDE
Reactor Vessel 1: CETNA 74 Weld
04/22/2025
Work Orders
60166073-0610
1R25, ISI NDE & Support, Containment - UT RPV
Studs/VT-1 Nuts & Washers
04/25/2025
Notifications
51195264, 51201199, 51230421
Notification 51235543
OM7.ID12 Implementation Gap
04/24/2024
Notification 51240232
CBP Set 2-3 Excessive Flow Concern
05/20/2024
Notification 51240233
Main Feed Pump 2-2 Suction Press Transient
05/20/2024
Notification 51251512
Error in STP Secondary Review
08/21/2024
Corrective
Action
Documents
TQ2.ID1 Attachment 1
Needs Analysis Guidance for Notification 51237921
Needs Analysis Guidance for Notification 51245454
Needs Analysis Guidance for Notification 51267632
Notification 51288602
25 BRQ Obs: Medical F/U Appts Calendar
06/03/2025
Notification 51288603
25 BRQ Obs: Biennial Physicals Scheduling
06/03/2025
Notification 51288604
25 BRQ Obs: JPM Cue Consistency
06/03/2025
Corrective
Action
Documents
Resulting from
Notification 51288748
25 BRQ Obs: Quantitative Sim Evals
06/04/2025
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Notification 51288898
25 BRQ Obs: Critical Task Review Timing
06/05/2025
Simulator Testing - Steady State Testing (2),
Transient Test 10
Licensed Operator Medical Records
Simulator Setup Checklist
Simulator Security Checklist completed 6/4/2025
Week 1 Crew Remediation - Simulator Crew Failure
05/27/2025
SRT Minutes Sept 2024 thru May 2025
05/12/2025
Simulator Security Checklist
A.33_SCR_2_YR_Report
Simulator Inspection Report
05/12/2025
Closed Mods
Simulator Closed Mods Report
05/12/2025
CYC 25 Sim Physics Test
Simulator Core Physics Test
11/27/2023
OP1.DC10 Attachment 13
RO Reactivation #1
4/3/2025
OP1.DC10 Attachment 14
SRO Reactivation #1 4/14/2025
SRO Reactivation #2 4/1/2025
SRO Reactivation #3 4/23/2025
Open Mods Sim
Simulator Open Mods Report
05/12/2025
R24-7 Package C - RO
First Run RO Written Examination
05/23/2025
R24-7 Package C -SRO
First Run SRO Written
05/23/2025
Sim_Plt_Differences
Simulator to Plant Differences
05/12/2025
STP R-6
Low Power Reload Physics Validation
U1_FWH_1R24_Trip_PEST
Post Event Simulator Test for U1 trip for FWH 1-5A
High Level
2/28/2023
Week 1 Operating Test
Simulator Scenarios (2)
JPMs (6)
Miscellaneous
Week 2 Operating Test
Simulator Scenarios (2)
JPMs (6)
CF2.DC1
Simulator Configuration Management
OM14.ID2
Medical Examinations
13A
OP1.DC10
Conduct of Operations
TQ1.DC28
Simulator Testing
Procedures
TQ2.DC15
Licensed Operator Annual/Biennial Exam
Development and Administration
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
TQ2.DC3
Licensed Operator Continuing Training Program
Simulator Training Guide
05/28/2025
Miscellaneous
Simulator Training Guide
05/27/2025
Procedures
TQ2.DC3
Licensed Operator Continuing Training Program
Corrective
Action
Documents
Notifications
286682
Procedures
AD8.ID4
Outage Fire Risk Mitigation
Work Orders
Corrective
Action
Documents
Notifications
279369, 51280255, 51283598, 51286730,
287149, 51287228, 51289681, 51289759
MP M-21.7A
Diesel Engine Fuel Oil Booster Pump
STP M-21-ENG.2
Diesel Engine Generator Inspection (Every Second
Refueling Outage)
Procedures
Work Orders
Miscellaneous
4*2618
Engineering Drawing Transmittal Form TMOD
60173456
Work Orders
Miscellaneous
1R25 Outage Safety Plan
Corrective
Action
Documents
Notifications
279848
MP E-50.30B
Agastat Type ETR Timing Relay Maintenance
MP E-50.33A
Westinghouse Type SSV-T One Unit Voltage Relay
Maintenance
14A
MP E-50.61
Basler Type BE1-27 Medium Inverse Undervoltage
Relay Maintenance
8A
MP E-50.62
Basler BE1-GPS100 Relay Maintenance
MP M-45.1
Containment Equipment Hatch Door Opening and
Closing
STP M-13H
4KV Bus H Vital Non-SI Auto-Transfer Test
Procedures
STP M-75G
4kV Vital Bus G Undervoltage Relay Calibration
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
STP M-75H
4kV Vital Bus H Undervoltage Relay Calibration
STP M-9G
Diesel Generator 24 Hour Load Test and Hot
Restart Test
STP P-AFW-PS11
Preservice Testing of Turbine-Driven Auxiliary
Feedwater Pump 1-1
8A
STP P-RHR-A11
Comprehensive Testing of Residual Heat Removal
Pump 1-1
STP P-RHR-A12
Comprehensive Testing of Residual Heat Removal
Pump 1-2
STP V-5A2
ECCS Check Valve Leak Test, Post Refueling/Post
Maintenance Valves 8948 A-D, 8818 A-D and 8819
A-D
Work Orders
ALARA Review Committee Meeting - Outage
Management: Dose to Date
04/21/2025
RWP 24-0032
24 ISFSI Campaign
10//23/2024
RWP 24-2001
Post Job ALARA Review: 2R24 General Access to
Containment
05/17/2024
RWP 24-2007
Post Job ALARA Review: 2R24 ISI Activities
05/21/2024
RWP 25-1024
1R25 Reactor Vessel Specimen Retrieval
RWP 25-1050
1R25 Reactor Coolant Pump Work
ALARA Plans
RWP 25-1085
1R25 Core Barrel Movement
Corrective
Action
Documents
Notifications
234625, 51235219, 51235327, 51235328,
235514, 51235978, 51238451, 51245839,
247906, 51248233, 51250709, 51252164,
259255, 51261923, 51261986, 51262619,
268346, 51269443, 51271094, 51275633,
276153, 51234126, 51235607, 51253795,
259423, 51261121, 51233926
Corrective
Action
Documents
Resulting from
Inspection
Notifications
281316
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Unit 2 Radiation Protection Post Outage Report
2R24
07/23/2024
RCP D-230
Radiological Control for Containment Entry
RCP NISP-RP.03
Radiological Air Sampling
RCP NISP-RP.04
Radiological Posting and Labeling
3A
RCP NISP-RP.05
Access Controls for High Radiation Areas
RCP NISP-RP.07
Control of Radioactive Material
1B
RCP NISP-RP.10
Radiological Job Coverage
RP1
Radiation Protection
10A
RP1.DC6
Radiation Protection Code of Conduct
RP1.ID1
ALARA Program
RP1.ID14
Radioactive Material Control
Procedures
RP1.ID16
Radiation Worker Expectations
213019
Salem Radiological Survey: S2 Containment 130'
Reactor Cavity (Upper) - Specimen Sample
Removal
04/07/2023
87113
Unit 1 Containment Entry Into Bioshield for RPC 1-2
Oil Level Check
05/13/2023
2943
2R24 115 CTMT PZR Area RCS-2-8076 valve work
in tent
04/19/2024
93069
2R24 91 CTMT Accumulator 2-3 Entry
04/22/2024
93172
2R24 RHR-2-8702 Release of New Bonnet from
RCA for Machining SAPN51235514EMRP#5012
04/24/2024
93189
2R24 91 CTMT Line 1140 Cutout and Replacement
Loop 2-1 Cold Leg
04/24/2024
93734
140 Greenpad Shiftly Days Morning - 300 ncpm
particle in SOP area just outside the CA. SAPN
238451
05/09/2024
93812
2R24 140 CTMT Post Lower Cavity Decon and
QOTTC Closure
05/11/2024
95333
Follow up to Dose Rate alarm at U2 140 Sundeck
keycard reader. Electronic interference expected
09/10/2024
95734
U1 D230
10/8/2024
Radiation
Surveys
95752
U-1 RCP-D230 Ctmt Air Sample
10/09/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
95767
U-1 RCP-D230 Ctmt Air Sample
10/10/2024
97912
1R25 115 CTMT RCP 1-2 Seal Removal
04/18/2025
98036
1R25 140 Containment Core Specimen Retrieval,
Cutting, and Final Core Offload
04/21/2025
98085
R25 CTMT 165 Pressurizer Grind/Weld
04/22/2025
98095
1R25 140 CTMT Lower Internals Move to Stand
04/22/2025
24-2014
2R24 Upper Cavity Decon, Cavity Entry, Head Set
25-1000
1R25 Non-Containment Work
25-1001
1R25 General Access to Containment
25-1024
1R25 Reactor Vessel Specimen Retrieval
25-1050
1R25 Reactor Coolant Pump Work
25-1066
1R25 Emergent Work
Radiation Work
Permits (RWPs)
25-1085
1R25 Core Barrel Movement
24-IA-01
24 Radiation Protection Audit
11/07/2024
24-QP-01
24 Quality Performance Assessment Report
01/14/2025
Self-
Assessments
259255 - 71124.01 Quick
Hit Self-Assessment
Pre-Inspection on Radiological Hazard Assessment
and Exposure Controls
2/10/2025
Corrective
Action
Documents
Notifications
208072, 51208074, 51208352, 51208353,
208357, 51212324, 51222295, 51226956,
227210, 51231613, 51242847, 51256223,
261121, 51265086, 51267511, 51268346
23 Unit 1 and 2 Radwaste Correlation Factors
04/04/2024
24 Unit 1 and 2 Radwaste Correlation Factors
2/11/2025
24 Unit 1 and 2 Non-Gamma Nuclide
Concentration Determination
04/17/2025
23 Evaluation of the Prospective Evaluation for
CEDE and SDE Reporting and Recording
04/16/2024
Prospective Evaluation for Shallow Dose Equivalent
and Consolidated Guidance for SOE and CEDE
Reporting and Recording - 2022 Evaluation
04/14/2023
NVLAP Lab Code: 100555-
Certificate of Accreditation to ISO/IEC 17025:2017 -
Mirion Technologies (GDS), Inc
07/01/2024
Miscellaneous
RSCS Technical Support
Document No.16-090
Neutron Dosimetry Evaluation at Diablo Canyon
Nuclear Power Plant
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RCP D-330
Personnel Dosimetry Evaluations
RCP-D-370
Evaluation of Internal Deposition of Radioactive
Material
RCP-NISP-RP.03
Radiological Air Sampling
RCP-NISP-RP.06
Personnel Contamination Monitoring
RP1.ID10
Embryo/Fetus Protection Program
Procedures
RP1.ID6
Personnel Dose Limits and Monitoring
Requirements
81151
Reactor Coolant Pump 1-2 Oil Add
2/03/2022
91478
Unit 1 Containment Quarterly Gamma and Neutron
Survey with Seal Table Entry
2/02/2024
2943
2R24 115 Containment Pressurizer Area
04/19/2024
93069
2R24 91 Containment Accumulator 2-3 Entry
04/22/2024
93812
2R24 140 Containment Post Lower Cavity Decon
and QOTTC Closure
05/11/2024
94598
Unit 2 Containment Quarterly Gamma and Neutron
Survey with Seal Table Entry
07/19/2024
95734
Unit 1 RCP-D230 Outside Bioshield 91'
Containment
10/08/2024
95752
Unit 1 RCP-D230 Containment Air Sample
10/09/2024
Radiation
Surveys
95767
Unit 1 RCP-D230 Containment Air Sample
10/10/2024
Self-
Assessments
SAPN 51259257
Perform Quick Hit Self-Assessment Report: NRC IP 71124.04
03/12/2025
First Quarter 2025 gaseous and liquid effluent dose
assessment to members of the public
MSPI Derivation Reports
71151
Miscellaneous
24 Annual Radioactive Effluent Release Report
04/16/2025
Corrective
Action
Documents
Notifications
269590
Procedures
OP1.DC40
Operations Equipment Deficiency and Adverse
Condition Monitoring
17