IR 05000275/2020002
ML20203M732 | |
Person / Time | |
---|---|
Site: | Diablo Canyon |
Issue date: | 07/22/2020 |
From: | Jeffrey Josey NRC/RGN-IV/DRP/RPB-A |
To: | Welsch J Pacific Gas & Electric Co |
References | |
IR 05000275/2020002, IR 05000323/2020002, IR 2020002 | |
Download: ML20203M732 (19) | |
Text
July 22, 2020
SUBJECT:
DIABLO CANYON POWER PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000275/2020002 AND 05000323/2020002
Dear Mr. Welsch:
On June 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Diablo Canyon Power Plant, Units 1 and 2. On July 9, 2020, the NRC inspectors discussed the results of this inspection with Ms. P. Gerfen, Site Vice President, 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, Digitally signed by Jeffrey Jeffrey Josey Josey Date: 2020.07.21 18:26:47-05'00'
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: DPR-80 and DPR-82 Report Numbers: 05000275/2020002 and 05000323/2020002 Enterprise Identifier: I-2020-002-0009 Licensee: Pacific Gas and Electric Company Facility: Diablo Canyon Power Plant, Units 1 and 2 Location: Avila Beach, CA Inspection Dates: April 1, 2020 to June 30, 2020 Inspectors: A. Athar, Resident Inspector C. Newport, Senior Resident Inspector J. Reynoso, Resident Inspector S. Hedger, Emergency Preparedness Inspector 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
Type Issue Number Title Report Section Status URI 05000275,05000323/ Failure to Replace Early 71114.02 Closed 2019004-02 Warning System Batteries at Periodicity Required by the Alert and Notification System Design Report
PLANT STATUS
Units 1 and 2 began the inspection period at full power.
On May 11, 2020, Unit 1 reduced power to 55 percent to clean water boxes and condensers. Unit 1 returned to full power on May 17, 2020.
On June 13, 2020, Unit 2 reduced power to 99 percent due to a group rod misalignment. Unit 2 returned to full power on June 30, 2020.
Units 1 and 2 operated at full power 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 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 (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 and during that time conducted plant status activities as described in Inspection Manual Chapter 2515, Appendix D; 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 on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
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, component cooling water trains A/B on May 4, 2020
- (2) Unit 1, containment spray train B on May 18, 2020
- (3) Unit 1, emergency diesel generator 1-1 on June 22, 2020
- (4) Unit 1, emergency diesel generator 1-3 on June 28, 2020
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Units 1 and 2 auxiliary feedwater system on April 20, 2020.
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) Units 1 and 2, turbine building 104 foot elevation on April 6, 2020
- (2) Units 1 and 2, radiological control area 115 foot elevation on April 27, 2020
- (3) Unit 2, turbine building 85 foot elevation emergency diesel generator rooms on April 30, 2020
- (4) Units 1 and 2, intake structure on May 11, 2020
- (5) Unit 1, turbine building 85 foot elevation, emergency diesel generator rooms on June 26, 2020
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the following areas:
- (1) Control building H block on June 18, 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 following activities:
- Unit 2, fire alarm response on June 18, 2020
- Unit 2, control rod bank misalignment troubleshooting activities on June 25, 2020
- Unit 1, vital battery short-term technical specification entry on June 26, 2020
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator annual exams on June 23, 2020.
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 (SSCs) remain capable of performing their intended function:
- (1) Units 1 and 2, radiation monitors on April 21, 2020
- (2) Units 1 and 2, diesel generator fuel oil system on May 7, 2020
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
- (1) Units 1 and 2, residual heat removal train A and B thermocouple commercial dedication on May 21, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 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, emergency diesel generator 2-3 air start and turbo booster piping air leak on April 8, 2020
- (2) Unit 1, emergency diesel generator rooms scaffolding and seismic induced system interactions evaluations on April 13, 2020
- (3) Units 1 and 2, seismic induced system interactions and housekeeping in fuel handling building on April 27, 2020
- (4) Unit 1, emergency diesel generator 1-3 major maintenance on June 24, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 2, emergency diesel generator 2-3, day tank level switch failure on April 9, 2020
- (2) Unit 1, auxiliary feedwater system level control valve LCV-107 failure to open due to degraded wiring on April 10, 2020
- (3) Units 1 and 2, structural weld acceptance criteria and technical basis compliance issues on April 21, 2020
- (4) Unit 2, auxiliary saltwater pump 2-1 low-pressure auto start inoperable on May 7, 2020
- (5) Unit 1, residual heat removal pump thermocouple leakage on May 20, 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) Units 1 and 2, equipment control guideline surveillance frequency modification on April 2, 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, turbine driven auxiliary feedwater system planned maintenance on April 8, 2020
- (2) Units 1 and 2, control room ventilation backdraft damper BD-67 repairs on April 20, 2020
- (3) Unit 2, auxiliary building ventilation system fan S-33 damper overhaul on May 5, 2020
- (4) Unit 2, rod control maintenance after control rod misalignment on June 15, 2020
- (5) Unit 1, emergency diesel generator 1-3 major maintenance activities on June 28, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Units 1 and 2, control room charcoal filter preheater testing, per STP M-6A, on
April 17, 2020 Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Unit 2, turbine-driven auxiliary feedwater system valve LCV-113 in-service test, per STP V-3P6B, on June 1, 2020
RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)
- (1) Units 1 and 2, reactor coolant system water inventory balance surveillance, per STP R-10C, on June 2, 2020
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated input provided by the Federal Emergency Management Agency (FEMA) regarding an observed deviation from the licensee's Early Warning System (EWS) maintenance program as described in the approved Alert and Notification System design report. The deviation was identified during an inspection conducted October 21-24, 2019.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The licensee submitted two summaries of emergency plan changes. The changes, summarized on March 2, 2020, involved implementation of a recent license amendment addressing emergency response organization staffing in addition to Emergency Plan Section 5, Revision 5.01. Changes communicated to the NRC on May 7, 2020, involved Emergency Plan Section 7 (Revision 5.01), Section 8 (Revision 4.17), and Appendix F (Revision 5.01). The inspectors conducted an in-office review of the changes from April 7 to June 30, 2020. This evaluation does not constitute NRC approval.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) ===
- (1) Unit 1 (04/01/2019 - 03/31/2020)
- (2) Unit 2 (04/01/2019 - 03/31/2020)
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 1 (04/01/2019 - 03/31/2020)
- (2) Unit 2 (04/01/2019 - 03/31/2020)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 (04/01/2019 - 03/31/2020)
- (2) Unit 2 (04/01/2019 - 03/31/2020)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) The inspectors evaluated a change made to the surveillance frequency of STP M-21C, Main Turbine Valve Testing, in accordance with ECG
OTHER ACTIVITIES
- TEMPORARY INSTRUCTION, INFREQUENT, AND ABNORMAL Evaluation of Diablo Canyon Power Plant Safety Condition in Light of Financial Conditions Because Pacific Gas and Electric Corporation, and its subsidiary, Pacific Gas and Electric Company (the licensee), was under bankruptcy protection/reorganization during the inspection period, NRC Region IV conducted special reviews of processes at Diablo Canyon Power Plant.
Using the flexibilities in the baseline inspection program, the inspectors evaluated several aspects of the licensees operations to determine whether the financial condition of the licensee impacted plant safety. The factors reviewed during this period included:
- (1) impact on staffing,
- (2) corrective maintenance backlog,
- (3) changes to the planned maintenance schedule,
- (4) corrective action program implementation, and
- (5) any reduction in outage scope, including risk-significant modifications. Considering the licensees financial difficulties, the inspectors verified that licensee personnel continued to identify problems at an appropriate threshold and enter these problems into the corrective action program for resolution. The inspectors also verified that the licensee continued to develop and implement corrective actions commensurate with the significance of the problems identified.
The special review of processes at Diablo Canyon Power Plant included continuous reviews by the resident inspectors, as well as the specialist-led baseline inspections completed during the inspection period which are documented in this report. During this period, the inspectors did not identify any indications that the licensees financial circumstances were adversely affecting plant performance and safety.
INSPECTION RESULTS
Unresolved Item Failure to Replace Early Warning System Batteries at 71114.02 (Closed) Periodicity Required by the Alert and Notification System Design Report URI 05000275,05000323/2019004-02
Description:
During an inspection conducted October 21-24, 2019, the inspectors identified a deviation between the licensees maintenance program for outdoor emergency warning sirens and the licensees commitments as described in their FEMA approved Alert and Notification System (ANS) design report. Therefore, inspectors documented the apparent deviation between emergency warning siren maintenance practices and maintenance commitments in Unresolved Item 05000275,05000323/2019004-02 (ML20023B809). On February 20, 2020, the NRC requested a review by FEMA to establish whether the licensee was in compliance with ANS requirements (ML20042E957).
Response was provided by FEMA on April 2, 2020 (ML20121A265). FEMA indicated that the licensees 5-year battery-replacement interval was inconsistent with the approved ANS design report. The issue was acknowledged as a deviation from the design report. However, information available to them provided by the battery manufacturer supports the change in battery replacement periodicity. Based on this, the deviation does not meet the definition of a significant change as defined in 44 CFR 350.14(b). FEMA recommended that the licensee provide an addendum to the design report addressing the battery replacement interval change.
Based on FEMAs input, the inspectors concluded that the practice of changing the emergency warning system siren batteries at 5-year intervals was not in compliance with the approved ANS design report. However, since the deviation did not meet FEMAs determination criteria of constituting a significant change, it is considered a minor performance deficiency. The issue is being addressed by the licensee in the corrective action program.
Corrective Action Reference: Notification 51052363 Minor Violation 71152 Minor Violation: On March 26, 2020, the licensee made a change to surveillance frequency requirement SR 0.2 of the applicability section of the ECG. This change allowed any surveillance frequency required by the ECG to be extended up to two times its specified interval if a risk analysis is completed and plant senior management approval is obtained.
The inspectors evaluated a change made to the surveillance frequency of STP M-21C, Main Turbine Valve Testing, in accordance with the new ECG SR 0.2 requirements. The inspectors determined that while the change made to the STP M-21C frequency as well as the corresponding risk analysis were appropriate and in accordance with applicable station procedures, the method in which the ECG 0.2 generic surveillance statement itself was changed was inappropriately conducted by the licensee. Specifically, the licensee incorrectly determined that the 10 CFR 50.59 change process did not apply because the change to the generic ECG SR 0.2 applicability was a maintenance activity and therefore covered under the requirements of 10 CFR 50.65(a)(4); therefore, a screen to determine if a more detailed evaluation or NRC prior approval was required was not conducted.
Screening: The inspectors determined the performance deficiency was minor. The failure to appropriately screen the ECG 0.2 change in accordance with 10 CFR 50.59(d)(1) was determined to be a performance deficiency within the licensees ability to foresee and correct. The performance deficiency was determined to be minor in accordance with Inspection Manual Chapter 0612, Appendix B, since it did not adversely impact a cornerstone objective. Specifically, it was determined after appropriate 50.59 screening, that the change to ECG 0.2 did not require NRC prior approval.
Enforcement:
This failure to comply with 10 CFR 50.59 (d)(1) constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On May 27, 2020, the inspectors presented the Early Warning System Battery Maintenance Issue Closure inspection results to Mr. M. Ginn, Manager, Emergency Preparedness, and other members of the licensee staff.
- On June 29, 2020, the inspectors presented the Early Warning System Battery Maintenance Issue Follow-Up inspection results to Mr. M. Ginn, Manager, Emergency Preparedness, and other members of the licensee staff.
- On June 29, 2020, the inspectors presented the Emergency Plan Revision In-Office Review inspection results to Mr. M. Ginn, Manager, Emergency Preparedness, and other members of the licensee staff.
- On July 9, 2020, the inspectors presented the integrated inspection results to Ms. P. Gerfen, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.04 Corrective Action Notifications 51035773, 50969288, 51022906, 51003565, 51066789,
Documents 51063350, 50981727, 51008678, 51079088
Drawings 106703-03 Feedwater System Unit 1 AFW 81
106721 Diesel Fuel Oil System, Sheet 2 38
106721 Starting Air and Dryer System for Diesel Engine 1-1 43
106721 Turbo Charger Air Assist and Dryer System for Diesel Engine 37
1-1
106721 Engine Fuel Oil System 46
106732 Component Cooling Water - Unit 1 AFW 75
107714-2 CCW system one-line drawing 65
Miscellaneous OADM 005670 - Caution Tag AXS-0-84 1
Procedures OP D-1:II Auxiliary Feedwater System - Alignment Verification 35B
OP F-2:VI CCW System Alignment Verification 2
OP I-2:II Containment Spray System - Alignment 20
OP J-6B:III-A Diesel Generator 1-3 - Alignment Checklist 0
71111.05 Corrective Action Notifications 50937063, 50663810, 51069952, 51065945, 51015502,
Documents 51046421, 51067228, 51023037, 51073603, 51067123
Drawings 111805 Unit 2 Turbine Building Elevation 85, Sheet 60 3
111805 Unit 1 Turbine Building Elevation 85', Sheet 50 1
111805 RA-9 Fire Pre-Plan Drawing H- Block area 115-foot elev. Sheet 14 3
111805 RA17 Fire Pre-Plan Drawing Radiological Control Area 115-foot 3
elev. Sheet 22
111805 TB-17 Fire Pre-Plan Drawing Turbine Building 104-foot elev. Sheet 2
111805 TB-6 Fire Pre-Plan Drawing Turbine Building 104-foot elev. Sheet 2
PA1/2 Pre-Fire Plans Intake Structure 2
Miscellaneous SFS-2-8791 Scaffolding Evaluation Unit 2, 115-ft FHB 04/14/2020
TCP #13647 Transient Combustible Permit, 480 V temp power 2
Procedures OM8.ID4 Control of Flammable and Combustible Materials 31
Inspection Type Designation Description or Title Revision or
Procedure Date
STP M-67C Monthly Hose Reel Station Inspection 28
Work Orders 60119390, 60117465, 60113458, 60126743
71111.06 Miscellaneous 89-17 Cable Spreading Room Flood Depth Due to MELB 0
71111.11Q Procedures OP1.DC10 Conduct of Operations 59
71111.12 Corrective Action Notifications 51075596, 51068158, 51075582, 51072190, 51072577,
Documents 51072863, 51025604, 51029399, 51030660, 51031604,
510332561, 51066099, 51068783, 51039658, 51064989,
51068753, 51072671, 51073328, 51073219, 51073284
Miscellaneous Safety Related Radiation Monitoring System Maintenance 4
Rule Scoping Document
DCP M-049160 DFO Underground Tank Replacement 0
PC-21-01 Emergency Diesel Generator Maintenance Rule Performance 18
Worksheets Criteria Functions
PC-39A-01 Safety Related Radiation Monitoring System Maintenance 0
Rule Worksheet
RPE 8*02647 (J- Replacement Part Evaluation RHR Thermocouple Assembly 05/11/2020
7448)
System 21 Maintenance Rule-Risk Significance Evaluation System 21A 2
Appendix B
Procedures CF3.ID13 Replacement Part Evaluation and CITE 31
CF4.ID3 Modification Implementation 31
MA1.ID17 Maintenance Rule Program 33
STP M-10A Diesel Fuel Oil Inventory 25
STP M-9A1 Diesel Emergency Generator Routine Surveillance 12
71111.13 Corrective Action Notifications 51069760, 51069677, 51038997, 51019330, 51065486,
Documents 51068864, 51016637, 51016483, 51048791, 51072540,
299740, A0637464, 50689736, 51073603, 51013197,
51078594, 51064740, 51077616
Miscellaneous NEA-CSNJ / NEA-Lessons Learned from Common-Cause Failures of 09/26/2018
R2018 Emergency Diesel Generators
Procedures AD4.ID3 SISIP Housekeeping Activities 16
AD7.DC6 On-Line Maintenance Risk Management 28
AD7.ID14 Assessment of Integrated Risk 23
AD7.ID15 On Line Maintenance Outage Window Execution 5
Inspection Type Designation Description or Title Revision or
Procedure Date
AD7.ID4 On-Line Maintenance Scheduling 30
AD7.ID5 Scaffold Material Structure 15
AWP WM-001 Integrated Risk Supplement Classification Guidance 12
MA1.ID7 Control of Plant Floor Loading 6
OP J-6B:IX Diesel Generator Extended On-Line Maintenance 17
OP O-36 Protected Equipment Posting 22
Work Orders 60126863, 60126040, 68058485, 68058482, 60119390,
64148066, 64197844
71111.15 Corrective Action Notifications 51071963, 51072091, 51072425, 50198746, 51075582,
Documents 51072190, 51068158, 51072190, 51076074, 51075596,
51076074, 51072107, 51073881, 51068753, 51072671
Drawings 437507 Auxiliary Feedwater Motor Operated Valves, Sheet 1 26
Miscellaneous RPE J-7488 RHR Thermocouple Assembly 1
Procedures MP E-53.10A Preventative Maintenance of Limitorque Motor Operators 45
OM4.ID14 Notification Review Team 33
OM7.ID11 10 CFR 21 Reportability Review Process 4A
OM7.ID12 Operability Determination 40
STP V-3P5 Exercising Valves LCV-106, 107, 108, and 109 Auxiliary 21
Feedwater Pump Discharge
Work Orders 60127363, 60119346
71111.18 Corrective Action Notifications 51028999, 51078353, 51070575, 51070746, 51070565
Documents
Miscellaneous NEI 96-07 Guidelines for 10 CFR 50.59 Implementation 1
PRA 20-03 Acceptable Delay Time for Turbine Stop Valve Surveillance 0
Testing STP M-21C
Procedures OM7.ID13 Technical Evaluations 7
STP M-21C Main Turbine Valve Testing 46
TS3.ID2 License Basis Impact Evaluations 44A
71111.19 Corrective Action Notifications 51071932, 50171963, 51072425, 51073219, 51034157,
Documents 51067980, 51067017, 51070207, 51070208, 51074230,
51067154, 51078136, 51079140, 51079263, 51079609
Drawings 663228-286 Westinghouse Rod Control System Corrective Maintenance 0
Guide
Inspection Type Designation Description or Title Revision or
Procedure Date
Procedures CF5.ID11 Lubricant Control 9B
MP E-53.10A Preventative Maintenance of Limitorque Motor Operators 45
MP I-1.6-5 Rod Control Slave Cycler Current Order Timing Verification 5
MP I-1.6-6 Rod Control Current Order and Coil Regulation Verification 6
MP M-23-FAN.4 Preventative Maintenance of Ventilation Fans With Dampers 10
and Inlet Vanes
MP M-3.7A Terry Turbine Trip Valve FCV-152 Maintenance 11
MP M-4.25 Auxiliary Feedwater Pump Turbine Governor Maintenance 18
OP H-5:I Control Room Ventilation - Prepare for Service 21
STP M-21-ENG.1 Diesel Generator Inspection (Every Refueling Outage) 27
STP M-21-RTS.1 Return Diesel Engine to Service Following Outage 20
Maintenance
STP M-6A Testing of Control Room Ventilation System 58
STP M-9A3 Diesel Generator 1-3 Routine Surveillance Test 13
STP M-9D1 Diesel Generator Full Load Rejection Test 27
STP R-1A Exercising Full Length Control Rods 26
STP V-3P5 Exercising Valves LCV-106, 107, 108, and 109 Auxiliary 21
Feedwater Pump Discharge
Work Orders 64178346, 60127363, 64178353, 64230160, 60117949,
60118687, 60127438, 64227179, 60120224, 60126407,
60126219, 60129080, 64197844, 64197819, 64192196,
64192650
71111.22 Corrective Action Notifications 50601322, 50978652, 51067736, 51050902, 51076749,
Documents 51077861, 51077862, 51070772, 51077236, 51077155
Procedures STP I-IB Routine Daily Checks, Attachment 12.1 Modes 1-3 109
STP M-6A Testing of Control Room Ventilation System 58
STP Rl-10C RCS water inventory balance 14
STP V-3P6B Exercising Valves LCV-115 and 113 Auxiliary Feedwater 28
Pump Discharge
Work Orders 64116122, 64229749
71114.02 Miscellaneous Letter from Bruce Response to Request for Assistance to Address a Concern 04/02/2020
- C. Foreman, Regarding Diablo Canyon Power Plant Alert and Notification
Federal System Battery Maintenance Practices
Emergency
Inspection Type Designation Description or Title Revision or
Procedure Date
Management
Agency; to Robert
- E. Kahler, Nuclear
Regulatory
Commission
Letter from Robert Request for Assistance to Address a Concern Regarding 02/20/2020
- E. Kahler, Nuclear Diablo Canyon Power Plant Alert and Notification System
Regulatory Battery Maintenance Practices
Commission, to
Bruce
- C.
Foreman, Federal
Emergency
Management
Agency
71114.04 Corrective Action Notifications 51057096, 5107932
Documents
Corrective Action Notifications 51073114, 51077872
Documents
Resulting from
Inspection
Miscellaneous DCL-18-064 Diablo Canyon Units 1 and 2; Docket No. 50-275, OL-DPR-80; 09/12/2018
Docket No. 50-323, OL-DPR-82; License Amendment
Request 18-01, Request to Revise Emergency Plan Response
Organization Staffing and Augmentation
DCL-19-039 Diablo Canyon Units 1 and 2; Docket No. 50-275, OL-DPR-80; 05/02/2019
Docket No. 50-323, OL-DPR-82; Response to NRC Request
for Additional Information Regarding "License Amendment
Request 18-01, Request to Revise Emergency Plan Response
Organization Staffing and Augmentation"
DCL-19-056 Diablo Canyon Units 1 and 2; Docket No. 50-275, OL-DPR-80; 07/03/2019
Docket No. 50-323, OL-DPR-82; Response to NRC Request
for Additional Information (Supplemental) Regarding "License
Amendment Request 18-01, Request to Revise Emergency
Plan Response Organization Staffing and Augmentation"
Inspection Type Designation Description or Title Revision or
Procedure Date
DCL-20-009 Docket No. 50-275, OL-DPR-80; Docket No. 50-323, OL-DPR- 03/02/2020
2; Diablo Canyon Units 1 and 2; Docket No. 72-26, Materials
License No. SNM-2511; Diablo Canyon Independent Spent
Fuel Storage Installation; Emergency Plan Update
DCL-20-038 Docket No. 50-275, OL-DPR-80; Docket No. 50-323, OL-DPR- 05/07/2020
2; Diablo Canyon Units 1 and 2; Docket No. 72-26, Materials
License No. SNM-2511; Diablo Canyon Independent Spent
Fuel Storage Installation; Emergency Plan Update
Lesson No. Basic Radiological Emergency Plan Training 21
EPD500
Lesson No. ERO Overview of License Amendments 233/235 (U1/U2) 0
JITTEP1901
Lesson No. 90-Minute LAR for Specific Positions 0
JITTEP1902
QUAL #: EP-19 I&C, Mechanical, Electrical, & Operations Coordinator 01/24/2020
Qual #: EP-22 Electrical Engineer 6
Qual #: EP-35 Mechanical Engineer 7
Tracking Number 50.54(q) Screening Evaluation Form 12/30/2019
2019-37
Tracking Number: 50.54(q) Screening Evaluation Form 01/08/2020
20-01
Tracking Number: 50.54(q) Effectiveness Evaluation Form 03/31/2020
20-18
Tracking Number: 50.54(q) Effectiveness Evaluation Form 03/31/2020
20-20
Tracking Number: 50.54(q) Effectiveness Evaluation Form 03/31/2020
20-21
Procedures AD1.ID2 Procedure Process Control 47
EP EF-1 Activation and Operation of the Technical Support Center 57, 58
EP EF-2 Activation and Operation of the Operational Support Center 42
EP R-2 Release of Airborne Radioactive Materials Initial Assessment 38
EP RB-10 Protective Action Recommendations 21
EP RB-3 Stable Iodine Thyroid Blocking 9, 10
OM10.ID2 Emergency Plan Revision and Review 13A
Inspection Type Designation Description or Title Revision or
Procedure Date
OM10.ID4 Emergency Response Organization Management 17
71151 Corrective Action Notification 51075212
Documents
Miscellaneous CDE 4.0 UAI Unit 1/2, MSPI Derivation Report MS05/MS06/MS07 05/10/2020
MSPI Self- Attachment 1: Calculation File C.10, DCPP PRA Model 12/01/2012
Assessment Technical Adequacy
NEI 99-02 Regulatory Assessment Performance Indicator Guideline 7
71152 Corrective Action Notifications 51070575, 51028999, 51078353
Documents
Miscellaneous Equipment Control Guidelines 9
NEI 96-07 Guidelines for 10 CFR 50.59 Implementation 1
PRA 20-03 Acceptable Delay Time for Turbine Stop Valve Surveillance 0
Testing STP M-21C
Procedures STP M-21C Main Turbine Valve Testing 46
TS3.ID2 Applicability Determination 1
17