IR 05000275/2020001

Integrated Inspection Report 05000275/2020001 and 05000323/2020001

ML20108F545
Person / Time
Site:	Diablo Canyon
Issue date:	04/16/2020
From:	Jeffrey Josey NRC/RGN-IV/DRP/RPB-A
To:	Welsch J Pacific Gas & Electric Co
References
IR 2020001
Preceding documents:	ML19351D046 (17 December 2019)
Download: ML20108F545 (23)

Text

April 16, 2020

SUBJECT:

DIABLO CANYON POWER PLANT, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000275/2020001 AND 05000323/2020001

Dear Mr. Welsch:

On March 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Diablo Canyon Power Plant, Units 1 and 2. On April 9, 2020, the NRC inspectors discussed the results of this inspection with Ms. Paula Gerfen, Site Vice President, 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: DPR-80 and DPR-82 Report Numbers: 05000275/2020001 and 05000323/2020001 Enterprise Identifier: I-2020-001-0009 Licensee: Pacific Gas & Electric Company Facility: Diablo Canyon Power Plant, Units 1 and 2 Location: Avila Beach, California Inspection Dates: January 1, 2020 to March 31, 2020 Inspectors: M. Chambers, Physical Security Inspector M. Doyle, Operations Engineer N. Hernandez, Operations Engineer R. Kopriva, Senior Reactor Inspector L. Merker, Acting Senior Resident Inspector C. Newport, Senior Resident Inspector J. Reynoso, Resident Inspector W. Smith, Health Physicist F. Thomas, Reactor 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

Failure to Follow Procedure Results in Inoperable Containment Spray Systems Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green [H.5] - Work 71153 NCV 05000275,05000323/2020001-01 Management Open/Closed The inspectors reviewed a self-revealed, Green, non-cited violation of 10 CFR Part 50,

Appendix B, Criterion V, "Instructions, Procedures, and Drawings," for failure to follow the requirements of procedure OP L-6, "Cold Shutdown/Refueling." Specifically, while preparing for a reactor plant mode transition, the licensee inadvertently rendered both trains of containment spray inoperable in Mode 4, a mode of operation with both containment spray trains required to be operable.

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000323/2019-001-00 LER 2019-001-00 for Diablo 71153 Closed Canyon Power Plant, Unit 2,

Containment Spray Inoperable in Mode 4.

PLANT STATUS

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

Unit 2 began the inspection period at full power. On February 13, 2020, Unit 2 was taken off line by controlled shutdown due to an equipment failure resulting in an unplanned technical specification entry. Unit 2 returned to full power on February 17, 2020, and remained at or near rated thermal 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 (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. From January 1 - March 19, 2020, the inspectors performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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 IMC 2515, Appendix D; and observed risk significant activities when warranted. In addition, resident and regional baseline inspections were evaluated to determine if all or portion 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 the cases where it was determined the objectives and requirements could not be performed remotely, management elected to postpone and reschedule the inspection to a later date.

71111.01 - Adverse Weather Protection

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

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather due to high winds on January 7, 2020.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

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

(1) Unit 1, turbine-driven auxiliary feedwater pump 1-1 on January 16, 2020

(2) Units 1 and 2, control room ventilation system on January 17, 2020

(3) Units 1 and 2, reactor trip breakers and motor generator set on February 3, 2020

(4) Unit 2, auxiliary feedwater and condensate system on February 4, 2020

(5) Units 1 and 2, auxiliary saltwater trains A and B on February 5, 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 85-foot elevation on January 15, 2020

(2) Units 1 and 2, 12 kV electrical switchgear rooms on February 3, 2020

(3) Units 1 and 2, auxiliary building rod control rooms 115-foot elevation on February 3, 2020

(4) Unit 2, auxiliary building battery rooms 115-foot elevation on February 12, 2020

(5) Unit 1, auxiliary building battery rooms 115-foot elevation on March 12, 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:

(1) Units 1 and 2, auxiliary feedwater pump rooms on February 13, 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)

The inspectors observed and evaluated licensed operator performance in the Control Room during the following activities:

(1) Unit 2, auxiliary feedwater pump 2-1 operation and main generator voltage regulator inconsistent function on February 11, 2020 Unit 2, return to power following unplanned technical specification required shutdown for control rod out of alignment on February 15, 2020 Units 1 and 2, high risk land management prescribed burn on February 29, 2020

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

(1) The inspectors observed and evaluated licensed operator requalification classroom training on the auxiliary feedwater system on February 6, 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) Unit 2, main feedwater regulating valve FCV-510 on January 4, 2020

(2) Units 1 and 2, control room and auxiliary building ventilation system on March 10, 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, vital battery charger 2-1 cleaning and maintenance on January 13, 2020

(2) Unit 1, emergency diesel generator 1-1 emergent lube oil heat exchanger oil repairs on January 23-24, 2020

(3) Unit 1, auxiliary feedwater valve LCV-110 plant computer analog output card troubleshooting on February 19, 2020

(4) Units 1 and 2, wildfire risk management activities on February 29, 2020

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, emergency diesel generator 1-1 heat exchanger lube oil leak on January 7, 2019

(2) Unit 2, steam generator 2-1 feedwater regulating valve FCV-510 flow oscillations on January 15, 2020

(3) Unit 2, nitrogen leak inside containment on January 26, 2020

(4) Unit 1, condensate storage tank loose resin on February 6, 2020

(5) Unit 1, plant computer system analog output circuit card safety-related classification on February 13, 2020

(6) Unit 2, emergency diesel generator 2-3 turbo air start pipe through wall leak on March 12, 2020

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for Title 10 of the Code of Federal Regulations (10 CFR) 50.59 from May 9-12, 2020:

(1) Licensing Basis Impact Evaluation (LBIE) Screen S-2017-004, Auxiliary Salt Water ASW2-2 Vault Room Conduit Replacement

(2) LBIE Screen S-2017-016, Partial Revision Calculation MP-6051

(3) LBIE Screen S-2017-024, Replace Pressurizer Struts with Snubber - Unit 2

(4) LBIE Screen S-2019-134, Task No. 134 Heating, Ventilation and Air Conditioning HVAC-83-14

(5) LBIE Screen S-2018-103, Task No. 103 Unit 2, Emergency Diesel Generator Governor Control Upgrade

(6) LBIE Screen S-2018-041, Task No. 41 DA Notification 50941685 Control Room Envelope (CRE) Floor Drain

(7) LBIE Screen S-2017-107, Pipe Support Repair

(8) LBIE Evaluation E-2018-002, Unit 1, Emergency Core Cooling System Valve Stem Mounted Limit Switch Interlocks

(9) LBIE Evaluation E-2017-005, Unit 1, Hydrogen Recombiner Electrical Penetration Protection

(10) LBIE Screen S-2017-011, Unit 2, Vital Battery and Battery Charger Unfused Non-Class 1E Ammeter Circuits modification

(11) LBIE Screen S-2017-015, DCP 1*25408, Unit 1 Nuclear Instrumentation System (NIS) Sensitivity Kits

(12) LBIE Screen S-2017-072, Temporary Modification Plant service Air Dryers (PAD) 03 04 Temporary Power

(13) LBIE Screen S-2018-032, Task No. 32 Temporary Modification 60108251 Unit 2 480 Volt Bus G Indication

(14) LBIE Screen S-2018-081, 91010-8219-AR_PK05-25u1r19e07-03-19, Pressurizer Relief Tank normal operating level is being lowered from 84 percent to a range of 60 percent-84 percent

(15) LBIE Screen S-2019-014, Task No. 14 LBIE DA 50823711 Engineered Safety Feature Delays

(16) LBIE Evaluation E-2017-019, UFSAR 3.2 for Class Breaks

(17) LBIE Evaluation E-2018-009, 480 Volt Switchgear Room Tornado Impacts

(18) LBIE Evaluation E-2018-010, DDP 1000025448, High Energy Line Break Analysis on 4 kV Switch Gear

(19) LBIE Evaluation E-2019-003, FSAR Engineered Safeguard Feature Non-LOOP Delays

(20) LBIE Evaluation 2017-004, DCN 2*1689, Unit 2 Hydrogen Recombiner Electrical Penetration Protection

(21) LBIE Evaluation 2017-023, Gas Decay Tank Rupture

(22) LBIE Evaluation 2017-026, Liquid Holdup Tank Rupture

(23) LBIE Evaluation 2018-001, Unit 2 Emergency Core Cooling System Valve Stem Mounted Limit Switch Interlocks, DCN-2000001823

(24) LBIE Screen OP _O -22u3r07e03-27- 17, Motor operated valves (MOVs) that may need local manual operation with motor contactors during emergency situations.

(25) LBIE Screen, OP B-3AIVu 1 r02e04-29-1 7, Venting pressure between the Safety Injection (SI) Pump discharge check valves and the Reactor Coolant System (RCS)loop injection check valves.

(26) LBIE Screen S-2017-030, Fisher regulators M98H is being evaluated to replace 98H regulators for PCV-410/411 in the Diesel Fuel Oil System.

(27) LBIE Screen STP P-AFW-A 1 1 u 1 r1 2-OTSC-06-25 - 1 7-S8B2, turbine-driven auxiliary feedwater (AFW) pump test procedure that performs the comprehensive flow surveillance be revised to allow a widened pump testing speed band.

(28) LBIE Screen S-2017-108, Modification installs a structural weld overlay (SWOL) on the existing weld containing the flaw at weld WIB-245.

(29) LBIE Screen S-2017-008, Unit 1 ICW Head Tank Nitrogen Cover Gas as permanent plant equipment and provides a more permanent tank lid hold-down device.

(30) LBIE Screen S-2017-129, The proposed activity will remove the interlocks associated with the stem-mounted Namco external limit switches.

(31) LBIE Screen 90120-1090-0P D-1 Vu 1 r25e05-23-18, Deleted closing of the FW-1 21 Auxiliary Feedwater Pump suction valve when aligned to the Condensate Storage Tank.

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 2, pressurizer relief tank operating procedure modifications on January 6, 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 2, Eagle 21 rack 4 board replacement on January 9, 2020

(2) Unit 1, control room air conditioner compressor CP-36 and condenser overhaul on January 21, 2020

(3) Unit 1, emergency diesel generator 1-1 heat exchanger repair on January 23, 2020

(4) Unit 1, condensate storage tank cleaning and inspection on February 4, 2020

(5) Units 1 and 2, control room ventilation backdraft damper BD-67 repairs on March 9, 2020

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Unit 2, vital battery charger 2-31 test per procedure STP M-12B on January 9, 2020

(2) Unit 2, main generator reactive power capability test per procedure TP TO-19005 on January 14, 2020

(3) Unit 1, emergency diesel generator 1-1 monthly surveillance test per procedure

STP M-9A1 on January 21, 2020 Inservice Testing (IP Section 03.01) (1 Sample)

(1) Unit 2, component cooling water fill check valve MU-2-971 in-service test per procedure STP V-18S on March 5, 2020

71114.06 - Drill Evaluation

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

(1) The inspectors evaluated an emergency preparedness drill on March 3,

OTHER ACTIVITIES - BASELINE

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

IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01) ===

(1) Unit 1 (01/01/2019-12/31/2019)

(2) Unit 2 (01/01/2019-12/31/2019)

IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)

(2 Samples)

(1) Unit 1 (01/01/2019-12/31/2019)

(2) Unit 2 (01/01/2019-12/31/2019)

IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)

(1) Unit 1 (01/01/2019-12/31/2019)

(2) Unit 2 (01/01/2019-12/31/2019)

71152 - Problem Identification and Resolution

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

(1) The inspectors reviewed the licensees corrective action program for trends that might be indicative of a more significant safety issue. The inspectors review was focused on fire damper issues during the period from January 1, 2019, to March 11, 2020.

Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Corrective actions associated with steam header pressure control and main steam safety valve RV-58 lifting while rolling main turbine generator on December 17, 2019

(2) Corrective actions associated with Units 1 and 2, auxiliary building ventilation system damper and supply fan failures on February 26, 2020

71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000323/2019-001-00, Unit 2, Containment Spray Inoperable in Mode 4 (ADAMS Accession No. ML20029E862). The circumstances surrounding this LER and an associated non-cited violation are documented in the Inspection Results section of this report.

Personnel Performance (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensee's performance during a Unit 2, controlled shutdown required by technical specifications due to control rod misalignment on February 13,

OTHER ACTIVITIES

- TEMPORARY INSTRUCTION, INFREQUENT, AND ABNORMAL Evaluation of Diablo Canyon Power Plant Safety Condition in Light of Financial Conditions Because Pacific Gas & Electric Corporation, and its subsidiary, Pacific Gas & 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

Failure to Follow Procedure Results in Inoperable Containment Spray Systems Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green [H.5] - Work 71153 NCV 05000323/2020001-01 Management Open The inspectors reviewed a self-revealed, Green, non-cited violation of 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," for failure to follow the requirements of procedure OP L-6, "Cold Shutdown/Refueling." Specifically, while preparing for a reactor plant mode transition, the licensee inadvertently rendered both trains of containment spray inoperable in Mode 4, a mode of operation with both containment spray trains required to be operable.

Description:

On November 30, 2019, at the start of Unit 2, Refueling Outage 21, the licensee began to transition the unit from Mode 4 to Mode 5 in accordance with OP L-6, Cold Shutdown/Refueling. While preparing for this transition, personnel from operations issued instructions to disable the containment spray pumps while the plant was still in Mode 4, a task that is required by OP L-6 only after the plant reaches Mode 5. This rendered both trains of containment spray inoperable as Technical Specification (TS) 3.6.6, "Containment Spray and Cooling Systems," requires two containment spray trains to be operable while in Modes 1, 2, 3, and 4. Approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> later, operations personnel identified that the two containment spray trains were inoperable while still in Mode 4. Operations personnel subsequently entered the applicable TS limiting condition for operation (LCO) 3.0.3 which states, in part, that when an LCO is not met, action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit in Mode 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />. Operations personnel restored power to the containment spray pumps, returned both trains of containment spray to operable status within the 37-hour requirement to place the unit in Mode 5, and exited the applicable TS LCOs.

Corrective Actions: Operations personnel returned both trains of containment spray to operable status and entered the issue into the corrective action program.

Corrective Action References: Notification 51057622

Performance Assessment:

Performance Deficiency: The inspectors determined that the licensee's failure to follow OP L-6, "Cold Shutdown/Refueling," by rendering both trains of containment spray inoperable while in a Mode of operation with containment spray required to be operable, was a performance deficiency.

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 licensee rendered both trains of containment spray inoperable while in Mode 4, a mode of operation in which both containment spray trains are required to be operable.

Significance: The inspectors assessed the significance of the finding using Appendix G, Shutdown Safety SDP. The inspectors determined the finding to be of very low safety significance (Green) because the finding did not degrade the ability to close or isolate the containment; the physical integrity of reactor containment; or involve an actual reduction in function of hydrogen control for a BWR Mark III containment, a PWR ice condenser containment, or an AP1000 containment.

Cross-Cutting Aspect: H.5 - Work Management: The organization implements a process of planning, controlling, and executing work activities such that nuclear safety is the overriding priority. The work process includes the identification and management of risk commensurate to the work and the need for coordination with different groups or job activities.

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," states, in part, that 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. Section 6.1.3 of OP L-6, "Cold Shutdown/Refueling," Revision 29, an activity affecting quality requires, in part, that containment spray pumps and control power are disabled after the unit reaches Mode 5 and before reaching Mode 6. Contrary to the above, on November 30, 2019, in anticipation of Mode 5 entry, the licensee inadvertently rendered both trains of containment spray inoperable while still in Mode 4, a mode of operation in which both containment spray pumps are required to be operable.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

• On March 12, 2020, the inspectors presented the Evaluations of Changes, Tests and Experiments inspection results to Mr. M. Hayes, Director, Learning Services, and other members of the licensee staff.

• On April 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

71111.01 Corrective Action Notifications 51061491, 51061412

Documents

Procedures CP M-16 Severe Weather 17

71111.04 Corrective Action Notifications 51051094, 51034153, 51041762, 51062395

Documents

Drawings 106703 Sheet 3 71

106704 Sheet 4 88

106723 Control Room Ventilation HVAC - Unit 1 133

107723 Control Room Ventilation HVAC - Unit 2 105

Procedures OP D-1:II Auxiliary Feedwater System - Alignment Verification for Plant 35B

Startup

OP H-5:II Control Room Ventilation System - Alignment Verification 23

71111.05 Corrective Action Notifications 51047792, 50937061, 51065375, 51065372, 50914543,

Documents 51069005, 51069558

Drawings 111805 RCA and H-Block Elev 115 3

111805 Radiological Control Area (RCA) & H Block Elev. 115 3

111805 Sheet 60 Fire Preplan Unit 2 Radiological Control Area 115' 17

111805 Sheets Turbine Building Elev. 115 ft 3

and 60

111805 TB-3 Fire Pre-Plan Drawing Turbine Building 85-foot elev. Sheet 3

111805 TB-5 Fire Pre-Plan Drawing Turbine Building 85-foot elev. Sheet 1

515221 Operational Requirement for Important to Safety Doors 29

663389 Hollow Door Vendor Drawing 17

RA-9 Fire Preplan Unit 1 Radiological Control Area 115' 9

Miscellaneous SAP Calc. No. NFPA 805 Design Basis Documents Units 1 and 2 43

9000041689-002-

TCP #12520 Transient Combustible Permit, 480 V temp power 12/22/2019

Work Orders 68058246, 64138828

71111.06 Corrective Action Notifications 50632943, 50636857, 50826609, 50591129

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents

Miscellaneous DCM No. T-12 Diablo Canyon Power Plant, Units 1 & 2, Design Criteria 24

Memorandum T-12 Pipe Break (HELB/MELB), Flooding, and

Missiles

71111.11Q Corrective Action Notifications 51066561, 51068223, 51065923, 51066632, 51066599,

Documents 50531403, 51058992, 51059240, 51057622, 51068868,

51066670, 51066564, 51066758, 51066640, 51069557,

51068235, 51068180, 51066545

Procedures AD7.DC8 Work Planning 53

AR PK05-08 RCS Valves Stem Leakage 12

CF2.DC1 Configuration Management Plan for the Operator Training 12

Simulator

OP1.DC10 Conduct of Operations 59

OP1.DC31 Dissemination of Operations Information 8

STP P-AFW-21 Routine Surveillance Test of Turbine-Driven Auxiliary 30

Feedwater Pump 20-1

STP R-1A Routine Control Rod Exercise 25

Work Orders 60120360, 60126079, 68055020

71111.12 Corrective Action Notification 51060172, 50980489, 51048745, 51048849, 51047760,

Documents 50997012, 51063460

Drawings 108036s4D Multivariable Instrument Systems 74

Miscellaneous DCM No. S-3C Main Feedwater & Steam Dump Control Systems 0

PC-23B-01 Main Auxiliary Building HVAC Maintenance Rule 5

Worksheet Performance Criteria

STP-V3P1 Valve Stroke Times for FCV-510

Procedures OM7.ID12 Operability Determination 40

STP M-6A Routine Surveillance Testing of Control Room Ventilation 58

System

71111.13 Corrective Action Notifications 51034877, 51063460, 51050796, 50984446, 51066561,

Documents 51066728, 51048684, 51032369

Procedures AD7.DC6 On-Line Maintenance Risk Management 28

AD7.ID15 On Line Maintenance Outage Window Execution 5

AD7.ID4 Assessment of integrated Risk 23

AWP WM-001 Integrated Risk Supplement Classification Guidance 12

Inspection Type Designation Description or Title Revision or

Procedure Date

B-40 Operations Response to Wildfire 1

CS1.ID15 Cyber Security Configuration Management 0

OP J-6B:IX Diesel Generator Extended On-Line Maintenance 17

OP O-36 Protected Equipment Posting 22

Work Orders 64129724, 60126079

71111.15 Corrective Action Notifications 51065420, 51066561, 51053146, 51053498, 51063165,

Documents 51063163, 51048609, 50985428, 51060172, 51061381,

51024543, 50985953, 50931403, 50828966, 51060220,

51063968, 51063831, 51069677

Drawings 107709 Mechanical Piping Gaseous System 63

108021-4B Turbo Charger Air Assist System 2-3 42

Procedures STP M-21-ENG.1 Diesel Engine Generator Inspection (Every Refueling 27

Outage)

STP M-9A1 Diesel Engine Generator 1-1 Routine Surveillance Test 12

Work Orders 60126079, 60123682, 60124189, 60111921, 64137989

71111.17T Calculations 14078110-MR- PG&E Design Class I Component Class Break Report 12/16/2016

001

SAP Calculation Unit 2 Electrical Penetration Protection Calculation. 6B

No. :

9000033734,

Legacy No. 364-

DC

SAP Calculation Gas Decay Tank/Gaseous Radwaste System 0

No. 9000012062,

Legacy No. RA-

93-9

WECTEC Site Boundary Doses for a Gas Decay Tank (GDT) Rupture. 0

14078110-C-M-

00003

Corrective Action 50870357, 50873211, 50881494, 50939612, 50946995,

Documents 50969368, 50969621, 51005934, 51005938, 51034727,

51053313, 51063468

Corrective Action 51069457, 51069490, 51069602, 51069620

Documents

Inspection Type Designation Description or Title Revision or

Procedure Date

Resulting from

Inspection

Drawings 102003 Diablo Canyon Power Plant - PG&E Co. - Feedwater 84

System

2008 Diablo Canyon Power Plant - PG&E Co., Chemical & 116

Volume Control System, Sheet 5B

2008 Diablo Canyon Power Plant - PG&E Co., Chemical & 102

Volume Control System, Sheet 9

2013 Diablo Canyon Power Plant - PG&E Co., Spend Fuel Pit 45

Cooling System, Sheet 2

2016 Diablo Canyon Power Plant - PG&E Co., Make-Up Water 86

System, Sheet 18

2016 Diablo Canyon Power Plant - PG&E Co., Make-Up Water 97

System, Sheet 16

2017 Diablo Canyon Power Plant - PG&E Co. Saltwater System, 96

Sheet 3B

2021 Diablo Canyon Power Plant - PG&E Co., Diesel Engine- 70

Generator Associated Systems, Sheet 7B

2021 Diablo Canyon Power Plant - PG&E Co., Diesel Engine- 73

Generator Associated Systems, Sheet 7

2021 Diablo Canyon Power Plant - PG&E Co., Diesel Engine- 73

Generator Associated Systems, Sheet 7A

106708 PG&E Co. Sheet 15A - Chemical & Volume Control System 133

OVID

106708 PG&E Co. Sheet 9 - Chemical & Volume Control System 150

OVID

106713 PG&E Co. Sheet 2 - Spend Fuel Pit Cooling System OVID 46

106716 PG&E Co. Sheet 18 - Make-Up Water System OVID 174

106716 PG&E Co. Sheet 16 - Make-Up Water System OVID 186

106717 PG&E Co. Sheet 8 - Saltwater System OVID 209

106717 PG&E Co. Sheet 7 - Saltwater System OVID 198

106721 PG&E Co. Sheet 16 - Diesel Engine-Generator Associated 61

Systems OVID

106721 PG&E Co. Sheet 6 - Diesel Engine-Generator Associated 60

Inspection Type Designation Description or Title Revision or

Procedure Date

Systems OVID

441368 Electrical Schematic Diagram 125 Volt D. C. System 24

Engineering DCN 2000001689 Replace the 3 existing Shawmut A23X125 fuses in the 0

Changes Hydrogen Recombiner Power Supply Panel with Shawmut

A50P125-4 and Install 3 more redundant A50P125-4 fuses

in series.

DDN 2000001912 Design Change Notice - 4kV Switchgear Room Ventilation 11/28/2018

System Modification (Unit 1)

DDN 2000001913 Design Change Notice - This design change will revise the 11/28/2018

licensing basis to explicitly credit manual operator actions to

ensure the cooling requirement for the electrical equipment

served by the 480VAC Switchgear Room and 125VDC

Inverter Room Ventilation System is met following a design

basis tornado that disables the ventilation system.

DDN 2000001927 Design Change Notice - This design change will revise the 2/15/2019

licensing basis to explicitly credit manual operator actions to

ensure the cooling requirement for the electrical equipment

served by the 480VAC Switchgear Room and 125VDC

Inverter Room Ventilation System is met following a design

basis tornado that disables the ventilation system.

DDP 1000025299 Replace the existing fuse and install a redundant fuse in 0

series in the Hydrogen Recombiner Power Supply Panel.

DDP 1000025506 Minor Design Change Package Summary - This design 2/15/2019

change will revise the licensing basis to explicitly credit

manual operator actions to ensure the cooling requirement

for the electrical equipment served by the 480VAC

Switchgear Room and 125VDC Inverter Room Ventilation

System is met following a design basis tornado that disables

the ventilation system.

EDT No. 4*1581 Engineering Drawing Transmittal: NMOD Convert TMOD 0

68012135 for U1 ICW Cover Gas to Permanent Equipment.

Engineering DDP 1000025448 Design Change Package Summary and Evaluation - This 1/4/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

Evaluations Design Change Package implements a physical change to

the vital 4.16-kV Switchgear room (SWGR) and Cable

Spreading Room (CSR) ventilation system by placing the

dampers in the normally closed position and disabling

(abandon in place) the associated HVAC exhaust fire

damper position switches.

Miscellaneous Y-3.2(10) UFSAR Change Request - The proposed activity is a change 1/31/2017

to the DCPP current licensing basis (CLB) for

the configuration of system boundaries as defined in UFSAR

Section 3.2.2.1. l(i).

Procedures CF3.ID22 Minor Modification Process 6

CF3.ID6 Drawing Change Transmittal Processing 28

CF3.ID9 Design Change Development 8

CF4.ID4 Field Change Process 26A

CF4.ID7 Temporary Alteration 30

CP M-16 Severe Weather 17

OM7.ID1 Problem Identification and Resolution 54

OM7.ID4 Cause Evaluations 39

OP B-3A:IV Safety Injection System - Off Normal Operation. 2

OP H-10:IV Auxiliary Building General Ventilation - Off Normal Operation 10

- (Unit 1)

OP H-10:IV Auxiliary Building General Ventilation - Off Normal Operation 9

- (Unit 2)

TS3.ID2 Licensing Basis Impact Evaluations 44A

Work Orders 60101343, 60108251

71111.18 Corrective Action Notifications 51060208, 50390780, 50673779, 50390622, 50673779,

Documents 51060449

Miscellaneous Temporary Unit 2 PRT Hydrogen Concentration Limit Increase 0

Modification

60076719

Procedures AD7.ID14 Assessment of Integrated Risk 23

OP A-4B:III Pressurizer Relief Tank - Remove From Service 21

OP A-4B:IV Pressurizer Relief Tank - Normal Operations 15

Inspection Type Designation Description or Title Revision or

Procedure Date

OP F-5:I Chemical Control Limits and Action Guidelines for the 48

Primary Systems

71111.19 Corrective Action Notifications 51058860, 51056200, 51062395, 51063795, 51053498,

Documents 50985428, 51063333, 50934425

Miscellaneous Unit 1 Diesel Generator 1-1 Lube Oil Leak Adverse 12/26/2019

Condition Monitoring Plan

Procedures MP M-21-HX.2 Diesel Generator Lube Oil Heat Exchanger 6

MPM M-23-BD.67 Preventive Maintenance of BD-67 1

OP H-5:I Control Room Ventilation Prepare for Service 21

OP H-5:III Control Room Ventilation System 22

STP I-36-R04 Eagle 21 Rack 4 Removal From Service and Return to 9

Service

STP M-21-ENG.1 Diesel Engine Generator Inspection (Every Refueling 27

Outage)

STP M6-A Routine Surveillance Testing of Control Room Ventilation 58

System

Work Orders 6010901, 60123967, 60124001, 60123682, 60111921,

64196335, 64174219

71111.22 Corrective Action Notifications 51053146, 51053498

Documents

Miscellaneous DCL-14-018 License Amendment Request 14-01, Revision to Technical 3/27/2014

Specifications 3.8.1, AC Sources - Operating

Procedures STP M-12B Battery Charger Performance Test 19

STP M-9A1 Diesel Engine Generator 1-1 Routine Surveillance Test 12

STP V-18S Nonintrusive Test of MU-02-971 7

TP TO-19005 Unit 2 Main Generator Reactive Power Capability Test 0

Work Orders 64230300, 60123682, 64153267, 64178148, 64178183

71114.06 Procedures EOP E-2 Faulted Steam Generator 23A

EOP E-3 Steam Generator Tube Rupture 40A

EP G-3 Emergency Notification of Off-Site Agencies 62

EP RB-10 Protective Actions Recommendations 21

71151 Procedures AWP L-001 NRC Performance Indicators Initiating Events, SSFFs, and 9

MOR

Inspection Type Designation Description or Title Revision or

Procedure Date

XI1.ID2 Regulatory Reporting Requirements 43

XI1.ID5 Collection and Submittal of NRC Performance Indicators

71152 Corrective Action Notifications 50980570, 51022441, 51023724, 51023903, 51024097,

Documents 51024146, 51024613, 51023931, 51023932, 51024092,

51024090, 51025122, 51025123, 51025124, 51025128,

51025129, 51025160, 51025161, 51025163, 51025164,

51025166, 51025167, 51025168, 51025169, 51025180,

51025181,51025182, 51025183, 51025184, 51025185,

51025186, 51025187, 51025188, 51025644, 51029223,

51029224, 51023930, 51029225, 51029389. 51032751,

51032866, 51032752, 51032865, 51032794, 51032795,

51032797, 51032851, 51032869, 51036160, 51037549,

51037687, 51037631, 51037736, 51038664, 51039380,

51041668, 51045183, 51045184, 51048745, 51048746,

51056345, 51056346, 51056347, 51056450, 51061194,

51062658, 51066257, 51066606, 51067284, 51067980,

51069986, 51068062, 51027584, 51032876, 51071321,

51067890, 51063444, 51067017, 51022978, 51057273,

51007668, 51070121, 51059901, 50652438, 50652617,

50643534, 50652093, 50657850, 50654950, 51049295,

51049291, 51050256

Drawings 107723 Auxiliary Building HVAC 94

Procedures MP M-23-BD.67 Preventive Maintenance of BD-67 1

NRC IN 97-09 Inadequate main steam safety valve (MSSV) Setpoints and 3/12/1997

Performance Issues

NUREG/CR-7037 Industry Performance of Relief Valves of U.S. Commercial 3/2011

Nuclear Power Plant Through 2007

OP C-3:II Main Unit Turbine - Startup 53

STP M-39B Routine Test of Cable Spreading Room CO2 Fire System 38

Operation

STP M-39B Routine Test of Cable Spreading Room CO2 Fire System 39

Operation

STP M-70B Inspection and Testing of Fire Dampers 22

STP V-3R1 Exercising 10% Atmospheric Dump Valves PCV-19, 20, 21, 57A

Inspection Type Designation Description or Title Revision or

Procedure Date

and Isolation Valves

Work Orders 60117800, 60118027, 60119941, 64190982, 60126407

71153 Corrective Action Notifications 51057622, 51057314, 51061381, 51067153, 51066758,

Documents 51058035, 51060562, 51065170, 51066241, 51060172,

51066640

Miscellaneous LER 2019-001-00 Containment Spray Inoperable in Mode 4 1/29/2020

Procedures OP AP-12B Control Rod Misalignment 19

OP AP-25 Rapid Load Rejection or Shutdown 13

OP L-4 Normal Operation at Power 82

OP L-6 Cold Shutdown/Refueling 29

OP1.DC1 Administrative Program to control The Return to Power after 12A

a Reactor Trip

STP R-19 Shutdown Margin Determination 32

STP R-1A Exercising Full Length Control Rod 25

20