IR 05000275/2019002

NRC Integrated Inspection Report 05000275/2019002 and 05000323/2019002

ML19214A279
Person / Time
Site:	Diablo Canyon
Issue date:	08/01/2019
From:	Jeffrey Josey NRC/RGN-IV/DRP/RPB-A
To:	Welsch J Pacific Gas & Electric Co
References
IR 2019002
Download: ML19214A279 (28)

Text

ust 1, 2019

SUBJECT:

DIABLO CANYON POWER PLANT, UNITS 1 AND 2 - NRC INTEGRATED INSPECTION REPORT 05000275/2019002 AND 05000323/2019002

Dear Mr. Welsch:

On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Diablo Canyon Power Plant, Units 1 and 2. On July 11, 2019, 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.

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.a of the Enforcement Policy.

If you contest the violation or 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 the 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 the 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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

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

Enclosure:

Inspection Report 05000275/2019002 and 05000323/2019002 with attachment 1. RFI Biennial Requalification

Inspection Report

Docket Numbers: 05000275 and 05000323 License Numbers: DPR-80 and DPR-82 Report Numbers: 05000275/2019002 and 05000323/2019002 Enterprise Identifier: I-2019-002-0001 Licensee: Pacific Gas & Electric Company Facility: Diablo Canyon Power Plant, Units 1 and 2 Location: Avila Beach, California Inspection Dates: April 01, 2019 to June 30, 2019 Inspectors: R. Bywater, Resident Inspector N. Hernandez, Operations Engineer C. Newport, Senior Resident Inspector J. Reynoso, Resident Inspector Approved By: Jeffrey E. Josey, Chief Project 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.

NRC-identified and self-revealed findings, violations, and additional items are summarized in the table below. Licensee-identified non-cited violations are documented in the Inspection Results at the end of this report.

List of Findings and Violations Human Performance Event Leads to Inadvertent Unit 2 Bus F Vital Bus Transfer Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.12] - Avoid 71111.15 NCV 05000275;05000323/2019002-01 Complacency Closed The inspectors reviewed a Green, self-revealed non-cited violation of Technical Specification (TS) 5.4.1.a, Procedures, because PG&E personnel failed to follow the requirements of procedure STP M-75F, 4 kV Vital Bus F Undervoltage Relay Calibration,

Revision 7. Specifically, on June 28, 2019, during restoration from STP M-75F, PG&E technicians inadvertently left a jumper in place resulting in an inadvertent transfer of the 4 kV vital bus F from the auxiliary power supply to the startup power supply. As part of this transfer, auxiliary saltwater pump 2-2 and containment fan cooler units 2-1 and 2-2 started.

Additionally, emergency diesel generator 2-3, which was out of service for maintenance at the time of the event, received a start signal.

Additional Tracking Items Type Issue Number Title Report Section Status LER 05000323/2018-001-00 LER 2018-001-00 for Diablo 71153 Closed Canyon Power Plant, Unit 2,

Automatic Reactor Trip of Unit 2 Following a Load Rejection.

LER 05000323/2018-001-01 LER 2018-001-01 for Diablo 71153 Closed Canyon Power Plant, Unit 2,

Automatic Reactor Trip of Unit 2 Following a Load Rejection.

PLANT STATUS

Units 1 and 2 began the inspection period at full power.

On April 1, 2019, Unit 2 reduced power to 50 percent to clean water boxes and condensers.

Unit 2 returned to full power on April 6, 2019.

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 (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. 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.

71111.01 - Adverse Weather Protection Impending Severe Weather Sample (IP Section 03.03)

The inspectors evaluated readiness for impending adverse weather conditions prior to the onset of seasonal heavy rains and winds on April 10, 2019.

Summer Readiness Sample (IP Section 03.01) (1 Sample)

The inspectors evaluated summer readiness of offsite and alternate alternating current power systems.

71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

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

(1) Unit 2, emergency diesel generator 2-3 on April 3, 2019

(2) Units 1 and 2, control room ventilation system on April 16, 2019

(3) Unit 1, component cooling water system train B on June 16, 2019

(4) Unit 2, auxiliary building ventilation system on June 17, 2019

(5) Unit 2, emergency diesel generator 2-1 on June 25, 2019

71111.04S - Equipment Alignment Complete Walkdown Sample (IP Section 03.02)

The inspectors evaluated system configurations during a complete walkdown of the Units 1 and 2 safety injection systems on May 8 - June 25, 2019.

71111.05A - Fire Protection (Annual) Annual Inspection (IP Section 03.02)

The inspectors evaluated fire brigade performance during a drill on June 13, 2019.

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Unit 1, component cooling water heat exchanger room on April 3, 2019

(2) Units 1 and 2, auxiliary building 115 foot elevation on April 15, 2019

(3) Unit 2, spent fuel building 100 foot elevation on May 3, 2019

(4) Unit 2, emergency diesel generator rooms 2-1 and 2-2 on June 25, 2019

71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04)

Biennial Requalification Written Examinations The inspectors evaluated the quality of the facility licensees biennial requalification written examination administered on May 28, 2019.

Annual Requalification Operating Tests The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.

Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.

Requalification Examination Security The inspectors evaluated the ability of the facility 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 facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.

Problem Identification and Resolution The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

The inspectors observed and evaluated operator performance during the following activities:

(1) Unit 2, unexpected plant process computer annunciator alarms on June 11, 2019

(2) Units 1 and 2, control room turnover and walkdowns on June 14, 2019

(3) Units 1 and 2, control room turnover and station production, work order, and corrective action program computer system outage on June 16, 2019

(4) Units 1 and 2, control room turnover on June 23, 2019 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

The inspectors observed and evaluated a crew of licensed operators in the plant's simulator during the licensed operator annual exam on May 8, 2019.

71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

Units 1 and 2, safety injection systems on June 20, 2019

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Unit 1, vital battery charger 132 out of service for maintenance on April 8, 2019

(2) Unit 2, control room ventilation system emergent maintenance on May 1, 2019

(3) Unit 2, vital battery charger 2-2 out of service for maintenance on May 6, 2019

(4) Unit 2, auxiliary saltwater pump 2-2 out of service for maintenance on June 6, 2019

(5) Unit 2, emergency diesel generator 2-3 out of service for maintenance on June 25-26, 2019

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Unit 1, elevated safety injection pump 1-1 shaft seal leakage on April 3, 2019

(2) Unit 1, control room ventilation motor operated damper MOD-3 sheared pin on April 17, 2019

(3) Unit 1, momentary reactor trip and safety injection initiate alarms on May 13, 2019

(4) Unit 2, turbine building high energy line break seized louvers on May 16, 2019

(5) Unit 2, emergency diesel generator 2-1 erratic speed control on May 29, 2019

(6) Unit 2, inadvertent transfer of 4 kV vital bus F on June 27, 2019

71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)

The inspectors evaluated the following temporary or permanent modifications:

Unit 1, turbine driven auxiliary feedwater pump 1-1 governor replacement on May 19, 2019

71111.19 - Post-Maintenance Testing Post Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the following post maintenance tests:

(1) Unit 1, centrifugal charging pump 2-1, anti-rotation pin replacement on April 1, 2019

(2) Unit 1, safety injection pump 1-1, mechanical seal maintenance on April 1, 2019

(3) Unit 2, auxiliary feedwater system valves LCV-106 and LCV-107, preventative maintenance on April 9, 2019

(4) Unit 1, auxiliary building ventilation system fan S-31, preventative maintenance and sheave replacement on April 25, 2019

(5) Unit 2, safety injection pump 2-1, lube oil cooler end bell replacement on April 30, 2019

(6) Units 1 and 2, diesel fuel oil transfer pump 0-1, preventative maintenance on June 10, 2019

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Inservice Testing (IP Section 03.01)

Unit 1, comprehensive testing of component cooling water pump 1-1, per procedure STP P-CCW-A11 on May 1, 2019

Surveillance Tests (other) (IP Section 03.01) (3 Samples)

(1) Unit 2, main turbine valve testing, per procedure STP M-21C on April 4, 2019

(2) Unit 2, solid state protection system train B actuation logic testing, per procedure STP I-38-B.1 on April 24, 2019

(3) Unit 1, vital battery charger 1-1 surveillance testing, per procedure STP M-12B on June 4, 2019

71114.06 - Drill Evaluation Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)

The inspectors evaluated an emergency preparedness drill on June 5,

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, date range: April 1, 2018 through March 31, 2019

(2) Unit 2, date range: April 1, 2018 through March 31, 2019 MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)

(1) Unit 1, date range: April 1, 2018 through March 31, 2019

(2) Unit 2, date range: April 1, 2018 through March 31, 2019 MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1, date range: April 1, 2018 through March 31, 2019

(2) Unit 2, date range: April 1, 2018 through March 31, 2019

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)

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

(1) Evaluation and corrective actions related to Units 1 and 2 emergency diesel generator fuel oil transfer piping compliance with technical specification testing and surveillance requirements on May 13, 2019

(2) Evaluation and corrective actions related to Unit 2 auxiliary saltwater pump 2-1 motor bearing degradation on May 13, 2019

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

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 human performance issues but also considered the results of daily corrective action program item screening and licensee trending efforts during the period of January 1, 2019 to June 30, 2019.

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

The inspectors evaluated the following licensee event reports (LERs) which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:

(1) LER 05000323/2-2018-001-00, Automatic Reactor Trip of Unit 2 Following a Load Rejection (ADAMS Accession No.: ML19030B857)

On December 1, 2018, Diablo Canyon Power Plant (DCPP), Unit 2, tripped from 100 percent power following a load rejection initiated from the 500 kV offsite power supply Special Protection Scheme (SPS) switch. The SPS switch is designed to detect abnormal grid conditions and preemptively initiate a load reject on one of the two reactor units at DCPP to avoid a grid overload condition that could potentially damage grid hardware and cause a dual unit reactor trip. The SPS switch load reject function is selected to either Unit 1 or Unit 2. At the time of the Unit 2 reactor trip, the load reject switch was selected to Unit 2 and Unit 1 was decreasing power to 50 percent power for unrelated reasons. This condition, coupled with prevailing grid conditions, reduced 500 kV line amperage flows to below the SPS switch remote outage detection logic trigger levels and initiated a load reject of Unit 2 per design.

The load reject occurred without any preliminary indications to DCPP plant operators.

Control room operators responded to the Unit 2 reactor trip in accordance with applicable procedures and stabilized the plant in Mode 3. No operator performance issues were identified. All safety systems functioned as designed. The initial event response and assessment was documented in NRC Inspection Report 05000275/2018004, 05000323/2018004 (ML19028A382). No performance deficiencies were identified during the review of the event or this licensee event report. The inspectors also concluded that no violation of NRC requirements occurred.

(2) LER 05000323/2-2018-001-01, Automatic Reactor Trip of Unit 2 Following a Load Rejection (ADAMS Accession No.: ML19101A435)

The inspectors reviewed the updated LER submittal which included results of the licensees causal evaluation of the event. The licensee conducted a root cause evaluation and determined that the root cause of event involved a latent design vulnerability with the SPS switch and inadequate required grid evaluations that could have identified the vulnerabilities of the SPS logic scheme. The root causes of the event occurred within the PG&E transmission and distribution organization and were outside of the cognizance of the DCPP, PG&E nuclear organization. As such, the causes of the load reject and reactor trip were not reasonably within the ability of the DCPP, PG&E nuclear organization to foresee and correct; therefore, no performance deficiency was identified. The inspectors also concluded that no violation of NRC requirements occurred.

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 - emergency preparedness, inservice inspection, and radiation protection - 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

Observation: Semi-Annual Trend Review 71152 The inspectors review was focused on human performance issues and considered the results of daily inspector corrective action program (CAP) item screening and licensee trending efforts. The inspectors review considered the 6-month period of January 2019 through June 2019, although some examples beyond those dates were considered when warranted.

The inspectors reviewed CAP notifications, trend reports, and performance indicator evaluations to address potential performance gaps at Diablo Canyon Power Plant. During the inspection period, the inspectors noted instances where low level human performance errors occurred in multiple departments, including operations, maintenance, and security.

Examples include: component mis-positioning events (including two that resulted in re-performance of surveillance tests), bumping valves out of position, fuses shorted out during maintenance, and two events associated with inadvertently working on the wrong component. Additionally, two human performance events associated with the performance of a routine surveillance test on the containment spray system and a routine surveillance test on the vital 4 kV bus F were noted that resulted in impacts on plant equipment and unplanned entries into technical specification LCOs. Both of these events were dispositioned as Green, non-cited violations and documented in NRC inspection reports.

The inspectors noted that the licensee appropriately entered these issues into the CAP and completed timely evaluations and self-assessments of these issues to determine their causes and actions to prevent recurrence. As a result, the licensee increased the oversight and observation of field activities and all maintenance and operations personnel will be provided training focused on improving work performance in the field to address mis-positioning errors.

Other corrective actions included training and plant communications with emphasis on pre-job briefs as well as procedure use and adherence with validation activities. At the end of this inspection period, some corrective actions were still open, and the effectiveness of the actions taken were still being assessed. However, the inspectors determined that the corrective actions taken to date appeared to be effective at addressing the identified gaps.

The inspectors noted that many of these low-level errors were 'near-miss' events and most were a result of a lack of focus and were preventable with proper use of human performance tools. Although these identified events were low level in nature and PG&E has taken actions to identify and correct the causes of the events, they may nonetheless indicate a decline in Diablo Canyon Power Plant human performance.

Human Performance Event Leads to Inadvertent Unit 2 Bus F Vital Bus Transfer Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.12] - Avoid 71111.15 NCV 05000275;05000323/2019002-01 Complacency Closed The inspectors reviewed a Green, self-revealed non-cited violation of Technical Specification (TS) 5.4.1.a, Procedures, because PG&E personnel failed to follow the requirements of procedure STP M-75F, 4 kV Vital Bus F Undervoltage Relay Calibration, Revision 7. Specifically, on June 28, 2019, during restoration from STP M-75F, PG&E technicians inadvertently left a jumper in place resulting in an inadvertent transfer of the 4 kV vital bus F from the auxiliary power supply to the startup power supply. As part of this transfer, auxiliary saltwater pump 2-2 and containment fan cooler units 2-1 and 2-2 started.

Additionally, emergency diesel generator 2-3, which was out of service for maintenance at the time of the event, received a start signal.

Description:

Procedure STP M-75F, 4 kV Vital Bus F Undervoltage Relay Calibration, Revision 7, step 7.7.3.n states, Remove all test equipment from relays 27HFB3, 27HFB4, 62HF3A, and 62HF3B. However, while performing this step of STP M-75F, on June 27, 2019, PG&E technicians inadvertently left two test equipment jumpers in place and moved on to the next step of the procedure which restored control power to the system. This resulted in an electrical short across two phases via the jumpers, and the subsequent actuation of a protection fuse which led to the drop out of multiple 4 kV bus protection relays. This resulted in an inadvertent transfer of the 4 kV vital bus F from the auxiliary power supply to the startup power supply. As part of this transfer, auxiliary saltwater pump 2-2 and containment fan cooler units 2-1 and 2-2 started. Additionally, emergency diesel generator 2-3, which was out of service for maintenance at the time of the event, received a start signal. Due to the light loading on 4 kV vital bus F and the transfer of only a single bus, the startup transformer automatic load tap changer was taken to manual by operators to lower bus voltage to within acceptable limits. This action, along with emergency diesel generator 2-3 already being out of service for unrelated maintenance, required entry into a 12-hour shutdown technical specification limiting condition of operation (TS LCO 3.8.1.D).

Corrective Actions: After troubleshooting and system configuration verification, PG&E personnel were able to successfully replace the fuses and restore the system to an operable condition prior to the expiration of the shutdown technical specification LCO. A cause evaluation to understand the causal factors that led to the event was also initiated.

Corrective Action References: Notification 51034990

Performance Assessment:

Performance Deficiency: The inspectors determined that PG&Es failure to follow procedure STP M-75F, 4 kV Vital Bus F Undervoltage Relay Calibration, Revision 7 was a performance deficiency within PG&Es ability to foresee and correct.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Equipment Performance attribute of the Initiating Events cornerstone. The performance deficiency was considered to be more than minor because it adversely impacted the equipment performance attribute of the Initiating Events cornerstone and its objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, the human performance event associated with execution of procedure STP M-75F, 4 kV Vital Bus F Undervoltage Relay Calibration, led to an inadvertent transfer of the 4 kV vital bus F from the auxiliary power supply to the startup power supply. As part of this transfer, auxiliary saltwater pump 2-2 and containment fan cooler units 2-1 and 2-2 started. Additionally, emergency diesel generator 2-3, which was out of service for maintenance at the time of the event, received a start signal. This action, along the with emergency diesel generator 2-3 already being out of service for unrelated maintenance, required entry into a 12-hour shutdown Technical Specification LCO (TS LCO 3.8.1.D).

Significance: The inspectors assessed the significance of the finding using Appendix A, Significance Determination of Reactor Inspection Findings for At - Power Situations. Using Exhibit 1 from Appendix A, the inspectors determined the issue was of very low safety significance (Green) since the inadvertent actuation of the 4 kV vital bus F bus transfer did not result in a plant trip and the loss of mitigation equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition.

Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, PG&E technicians failed to fully complete a procedural step using appropriate human error prevention tools requiring all testing equipment to be removed prior to moving on with the procedure which resulted in the inadvertent transfer of the 4 kV vital bus F.

Enforcement:

Violation: Technical Specification 5.4.1.a, Procedures, requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A. Regulatory Guide 1.33, Appendix A, Section 9, requires, in part, that maintenance that can affect the performance of safety-related equipment should be properly pre-planned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances. The licensee established procedure STP M-75F, "4 kV Vital Bus F Undervoltage Relay Calibration, Revision 7, as a procedure appropriate to the circumstances to support maintenance and testing of the safety-related 4 kV Vital Bus F. Contrary to the above, on June 28, 2019, PG&E personnel failed to follow the requirements of STP M-75F, 4 kV Vital Bus F Undervoltage Relay Calibration, Revision 7. Specifically, the human performance event associated with M-75F 4 kV bus F relay calibration procedure led to an inadvertent transfer of the 4 kV vital bus F from the auxiliary power supply to the startup power supply. As part of this transfer, auxiliary saltwater pump 2-2 and containment fan cooler units 2-1 and 2-2 started. Additionally, emergency diesel generator 2-3, which was out of service for maintenance at the time of the event, received a start signal. This action, along emergency diesel generator 2-3 already being out of service for unrelated maintenance, required entry into a 12-hour shutdown technical specification LCO.

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 May 31, 2019, the inspectors presented the biennial operator licensing requalification inspection results to Mr. J. Welsch, Senior Vice President, Generation and Chief Nuclear Officer, and other members of the licensee staff.

• On July 11, 2019, the inspectors presented the quarterly resident inspector 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 50981582, 51018665, 51027248, 51032504

Documents

71111.01 Procedures CP M-12 Stranded Plant 8

71111.01 Procedures CP M-16 Severe Weather 17

71111.01 Procedures OP AP SP-1 Loss of AC Power 22

71111.01 Procedures OP AP-26 Loss of Offsite Power, Unit 1/2 21A/20

71111.01 Procedures OP O-28 Operations Response to Storms or Biofouling 23

71111.04 Corrective Action Notifications 51012144, 51031355, 51031356, 51034157

Documents

71111.04 Drawings 106714 CCW OVID 73

71111.04 Drawings 107721 Starting Air System EDG 2-3 62

71111.04 Drawings 107723 Control Room HVAC Unit 2 105

71111.04 Drawings 57726 Aux., Containment, and Fuel Handling Buildings 12

71111.04 Procedures AD13.DC12 Control Room Envelop Habitability Program 4

71111.04 Procedures OP F-2:VI CCW system Alignment Verification 42

71111.04 Procedures OP H-1:I Auxiliary Building Safeguards Ventilation (ABVS) - Make 15

Available

71111.04 Procedures OP H-1:II Auxiliary Building Safeguards Ventilation - Normal 11

Operation

71111.04 Procedures OP H-5:II Control Room Ventilation System-Alignment Verification 22

71111.04 Procedures OP J-6B:I-A Diesel Generator 2-1 - Alignment Checklist 0

71111.04 Procedures OP J-6B:II-A Diesel Generator 2-2 - Alignment Checklist 0

71111.04 Procedures OP J-6B:III-A Diesel Generator 2-2 - Alignment Checklist 0

71111.04 Procedures OP J-6C:II Diesel Fuel Oil System - Alignment Verification for Plant 14

Startup

71111.04 Procedures OP K-10E1 Seal Valve Checklist for Component Cooling Water 73

71111.04 Work Order 641777113

71111.04S Corrective Action Notifications 50836988, 50888946, 50034848, 50925406, 50936644,

Documents 50967009, 50967030, 50967595, 50968643, 50549533

71111.04S Drawings 106709 Safety Injection, Unit 1, Sheet 4 69

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04S Drawings 107709 Safety Injection, Unit 2, Sheet 4 67

71111.04S Procedures DCPP A-30 Plant Labeling Program 1

71111.04S Procedures OP B-3A:11 Safety Injection System Alignment 23B

71111.04S Procedures OP K-10A12 Seal Components for Safety Injection 3

71111.04S Work Orders 60087891, 60004369, 60101584

71111.05A Corrective Action Notification 51026411

Documents

71111.05A Drawing RA-3 RCA Elev. 73' 4

71111.05A Procedure CP M-6 Casualty Procedure - Fire 39

71111.05Q Corrective Action Notifications 51026187, 50937062, 50622051, 50655050, 51026373,

Documents 51015502, 51002807, 50938102

71111.05Q Drawings 111805, Sheet 60 Fire Department 3

71111.05Q Drawings 111805, Sheet 61 Fire Department 1

71111.05Q Drawings RA-10 Pre-Fire plans; RCA and H-block, 115 foot elevation 3

71111.05Q Drawings RA-15 Radiological Control Area Elev. 100 3

71111.05Q Drawings TB-3 Turbine Building Elev. 85' 3

71111.05Q Work Orders 60116410, 60114723

71111.11B Corrective Action Notifications 50914432, 50937919, 50945261, 50945751, 50953015,

Documents 50954525, 50957474, 50965876, 50979165, 50979651,

50990860, 50991733, 50992512, 50992513, 50992514,

50943255, 50944990, 50951368, 50953221, 50953775,

50956899, 50958114, 50959130, 50966981, 50973710,

50907386, 50957614, 50959111, 51023738, 51004051,

51015231

71111.11B Miscellaneous 2019 Operations Crew Roster 3/12/2019

71111.11B Miscellaneous 2019 Operations Exam 3/29/2019

71111.11B Miscellaneous 2019 Written Exam RO/SRO Week 1 4/5/2019

71111.11B Miscellaneous 2018 Annual Operating Exams 5/24/2018

71111.11B Miscellaneous 71111.11 Self-Assessment Report 10/5/2018

71111.11B Miscellaneous 2018 Operations Training Self-Assessment Report 10/10/2018

71111.11B Miscellaneous ANSI/ANS-3.5-2009 9/4/2009

71111.11B Miscellaneous Simulator Plant Differences Report 4/1/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.11B Miscellaneous B3-2-1(1) ANSI-3.5 Simulator Test Manual Reactor Trip 2/13/2019

71111.11B Miscellaneous B3-2-1(3) ANSI-3.5 Simulator Test Closure of all MSIVs 2/13/2019

71111.11B Miscellaneous B3-2-1(5) ANSI-3.5 Simulator Test Trip of Single RCP 2/20/2019

71111.11B Miscellaneous B3-2-1(9) ANSI-3.5 Simulator Test Main Steam Line Rupture 2/25/2019

71111.11B Miscellaneous B3.1 (100) ANSI-3.5 Simulator 100% Steady State Power Test 3/25/2019

71111.11B Miscellaneous B3.1 (25) ANSI-3.5 Simulator 25% Steady State Power Test 3/21/2019

71111.11B Miscellaneous Form 69-2034 RO License Reactivation 2/12/2018

71111.11B Miscellaneous Form 69-2034 RO License Reactivation 6/29/2018

71111.11B Miscellaneous Form 69-2035 SRO License Reactivation 4/25/2018

71111.11B Miscellaneous Form 69-2035 SRO License Reactivation 7/7/2018

71111.11B Miscellaneous Form 69-2035 SRO License Reactivation 2/26/2019

71111.11B Miscellaneous Form 69-2035 SRO License Reactivation 9/9/2017

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record 1/31/2018

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record 2/9/2018

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record 1/5/2018

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record 1/12/2018

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record 6/4/2018

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record 8/7/2018

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record 9/28/2018

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record 10/31/2018

71111.11B Miscellaneous Form 69-20642 Crew Remediation Training Record 4/9/2019

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record (Student A) 9/8/2017

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record (Student B) 9/8/2017

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record 9/7/2017

71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record 12/5/2017

71111.11B Miscellaneous R1718SPRO.XLS RO Operating Test Quality Sample Methodology

71111.11B Miscellaneous R1718SPSRO.XLS SRO Operating Test Quality Sample Methodology

71111.11B Procedures B3-2-1(7) ANSI-3.5 Simulator Test Maximum Rate Power Ramp 2/20/2019

71111.11B Procedures B3.1 (100) ANSI-3.5 Simulator 100% Steady State Power Test 3/25/2019

71111.11B Procedures Form 69-2035 SRO License Reactivation 1/10/2018

71111.11B Procedures Form 69-20642 Individual Remediation Training Record 11/22/2017

71111.11B Procedures OM14.ID2 Medical Examinations 11

71111.11B Procedures OP1.DC10 Conduct of Operations 55

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.11B Procedures TQ2.DC 15 Licensed Operator Annual/Biennial Exam Development and 10

Administration

71111.11B Procedures TQ2.DC 3 Licensed Operator Continuing Training Program 31

71111.11B Procedures TQ2.ID 4 Training Program Implementation 47A

71111.11B Procedures TQ2.ID 9 Conduct of Training 17

71111.11Q Corrective Action Notification 51033211

Document

71111.11Q Procedures JSIM-507 Evaluator Skills 0

71111.11Q Procedures TQ2.DC3 Licensed Operator Continuing Training Program 29

71111.13 Corrective Action Notifications 51027990, 51028008, 51028376, 51027833, 51028007

Documents

71111.13 Drawing 107723 Control Room HVAC (south) 105

71111.13 Procedures AD13.DC12 Control Room Envelope Habitability Program 4

71111.13 Procedures AD7.DC6 On-Line Maintenance Risk Management 27

71111.13 Procedures AD7.DC6 On-Line Maintenance Risk Management 26

71111.13 Procedures AD7.ID14 Assessment of Integrated Risk 21

71111.13 Procedures OP O-36 Protected Equipment Postings 18

71111.13 Procedures OP O-36 Protected Equipment Postings 19

71111.13 Work Order 60114431

71111.15 Corrective Action Notifications 51027597, 51027678, 51027584, 51025593, 50595423,

Documents 50042226, 50042428, 50081646, 50503871, 50524751,

50945969, 50946204, 50946299, 50946368, 50946436,

51031744, 51034990, 50676578, 51031001, 51034990,

51030260, 51027610, 50913105

71111.15 Drawings 441286 4160 Volt Bus Section F Automatic Transfer 11

71111.15 Drawings 441340 Potential and Synchronizing Diagram 4160V Bus Sections 31

F, G, & H

71111.15 Drawings 6018227-16 Louver Schedule Turbine Building 5

71111.15 Drawings 663231 Reactor Protection System Vendor Manual 28

71111.15 Drawings 663231 Schematic Diagram - Isolation Card 137

71111.15 Drawings 663231 Solid State Protection System Interconnection Diagram 10

71111.15 Procedures AR PK02-02 Safety Injection Initiate Annunciator Response 11

71111.15 Procedures AR PK04-12 Reactor Trip Initiate 15

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.15 Procedures AR PK08-22 Auto S.I. Blocked 1

71111.15 Procedures AR PK18-19 4 kV Bus F Auto Transfer Annunciator Response 5

71111.15 Procedures CP M-16 Severe Weather 17

71111.15 Procedures OM7.ID1 Emerging Issue and Event Investigations 54

71111.15 Procedures OM7.ID12 Operability Determinations 39

71111.15 Procedures STP M-75F 4 kV Vital Bus F Undervoltage Relay Calibration 7

71111.15 Procedures STP P-SIP-11 Routine Testing of Safety Injection Pump Checks Required

by Licenses

71111.15 Work Orders 60023251, 64212870, 60105138, 60049371, 60105023,

60007325, 60120339, 60119104

71111.18 Corrective Action Notifications 51022989, 51023045, 51029356

Documents

71111.18 Miscellaneous DCP E-049490 Replacing Starter and Overload Relay TDAFW 0

71111.18 Procedures MP M-4.25 Auxiliary Feedwater Pump Turbine Governor Maintenance 18

71111.18 Work Order 64033834

71111.19 Corrective Action Notifications 50954692, 50993690, 50032499, 51029229, 50965742,

Documents 51029180, 50965347, 51028587, 51029500, 51033565,

51033619

71111.19 Miscellaneous RPE 211571 Fan & Motor Sheaves, Bushings, and Keys 4

71111.19 Procedures CF5.ID1 Receipt of Materials 13

71111.19 Procedures MP E-53.10A Preventative Maintenance of Limitorque Motor Operators 44

71111.19 Procedures MP E-8.1 Centrifugal Charging Pump Motor Overhaul 14

71111.19 Procedures MP M-23-FAN.4 Preventative Maintenance of Ventilation Fans With 9

Dampers and Inlet Vanes

71111.19 Procedures OP J-6C:1 DFO Alignment and Operations 15

71111.19 Procedures STP P-CCP-21 Routine Surveillance Test of Centrifugal Charging 26

Pump 2-1

71111.19 Procedures STP P-SIP 11 Routine Surveillance of Safety Injection Pump 25

71111.19 Procedures STP P-SIP-21 Routine Surveillance Testing of Safety Injection Pump 2-1 28

71111.19 Procedures STP V-3L2A Exercising Valve SI-2-8821A, Safety Injection Pump 0

Discharge to RCS Cold Legs

71111.19 Procedures STP V-3P5 Exercising Valves LCV-106, 107, 108, and 109 21

Auxiliary Feedwater Pump Discharge

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.19 Work Orders 60106782, 64165539, 64156641, 64206103, 60118888,

60118889, 64206104, 60108508, 64174611, 60118821,

64077390, 64129545

71111.22 Drawings 107722 Gland Steam Supply Main Turbine, Sheet 2 46

71111.22 Drawings EQP-626 Load Bank Constraints 2

71111.22 Procedures OP E-5:II Auxiliary Saltwater CCW Heat Exchanger Operation 19

71111.22 Procedures STP I-38-B.1 SSPS Train B Actuation Logic Test in MODES 1,2,3, or 4 12

71111.22 Procedures STP M-12B Battery Charger Performance Test 19

71111.22 Procedures STP M-21C Main Turbine Valve Testing 2

71111.22 Procedures STP P-CCW-A11 Comprehensive Pump Test of Component Cooling Water 6

Pump 1-1

71111.22 Work Orders 64168747, 64168976

71114.06 Procedures EP G-3 Emergency Notification of Off-Site Agencies 60

71114.06 Procedures R18-3 Simulator Event Sequence 0

71114.06 Procedures TQ2.DC3 Licensed Operator Training Program 31

71151 Corrective Action Notification 50974176

Document

71151 Miscellaneous CDE 4.0 UAI Unit 1/2, MSPI Derivation Reports MS05/ MS06 / MS07 06/10/2019

71151 Miscellaneous MSPI Self- Attachment 1; Calculation File C.10, DCPP PRA Model 12/01/2012

Assessment Technical Adequacy

71151 Work Orders 64201443, 60106784, 60110022

71152 Corrective Action Notifications 51021044, 51015768, 51026933, 51013123, 51012969,

Documents 51015353, 51012973, 51016307, 51015025, 51015362,

51016480, 51019481, 51020675, 51020974, 51022319,

51020443, 51026379, 51017815, 51019542, 51002648

71152 Drawings 102021 Diesel Generator, Sheet 2 67

71152 Drawings 108021 Diesel Fuel Oil System 40

71152 Miscellaneous 9000041674 Buried Piping and Tanks Program Asset Management Plan 2

71152 Miscellaneous ANSI/ANS-59.51- Fuel Oil Systems for Safety-Related Emergency Diesel

1997 Generators

71152 Procedures MP E-17.1 Westinghouse Auxiliary Saltwater Pump Motor Overhaul 22

71152 Procedures OM15.ID11 Human Performance Event Response 4

71152 Procedures OM15.ID8 Human Performance Error Prevention Tools 9

Inspection Type Designation Description or Title Revision or

Procedure Date

71152 Procedures OM4.ID14 Notification Review Team (NRT) 31

71152 Procedures OM7.ID1 Problem Identification and Resolution 53

71152 Procedures OM7.ID3 Root Cause Evaluation 47

71152 Procedures OP J-6C:VI DFO Transfer System - Pipe Leak Detection Operation 8

71152 Procedures OP1.DC40 Operations Equipment Deficiency and Adverse Condition 10

Monitoring

71152 Procedures OP1.ID6 Plant Status Control 16

71152 Procedures STP M-121 DFO Leak Detection System ANI-501 Functional Test 7

71152 Procedures STP M-122 Diesel Fuel Oil Underground Storage Tanks 0-1 and 0-2 6

Interstitial Test and Enhanced Leak Detection Test

71152 Procedures STP M-9A2 EDG Routine Surveillance Test 12A

BIENNIAL REQUALIFICATION INSPECTION DOCUMENT REQUEST

Inspection Report: 05000275/0219002, 05000323/2019002

Inspection Dates: April 8 to April 12, 2019

Inspection Procedure: IP 71111.11B, Licensed Operator Requalification Program

Lead Inspector: Nicholas Hernandez, Operations Engineer

A. The following information is requested in order to support inspection preparation

activities. These items are listed by section as they appear in the inspection module

(i.e. 2.02, 2.04, etc.). Requested materials should be sent either electronically or by

CD/DVD in order to arrive at the Region IV office no later than March 15, 2019. Do not

send USB flash drives.

• Electronically: To: Nicholas.Hernandez@nrc.gov (lead Inspector);

Cc: Clyde.Osterholtz@nrc.gov (inspector)

• CD/DVD: To: US Nuclear Regulatory Commission, Region IV

ATTN: Clyde Osterholtz

1600 E. Lamar Blvd

Arlington, TX 76011

General Requests:

• List of licensed operators (SRO & RO) by crew (operating & staff)

• Training and Operations Department organization charts (with qualified LOR

evaluators identified)

• Procedures that identify process for revising and maintaining LOR continuing training

program

• List of outstanding LOR program changes

• List of plant events and industry operating experience incorporated into LOR

program since last BRQ

• Audits and/or self-assessment reports addressing the LOR training program

• Last 2 years of simulator review committee (or equivalent) meeting minutes

• Last 2 years of Curriculum Review Committee (or equivalent) meeting minutes

Attachment

2.03: Biennial Requalification Written Examination Quality

• The current and approved biennial written examination schedule

• The current requalification cycle written examination results to date

• All written examinations that have been approved for administration up to the date of

submittal. Include password protection if e-mailed or double envelope protection if

mailed per NUREG-1021.

• The current requalification cycle examination methodology (sample plan)

2.04: Annual Requalification Operating Test Quality

• The schedule for the operating tests to be given the week of April 8, , 2019

• All operating tests (password protected) that have been approved for administration

up to and including the week of the onsite inspection

• All 2019 NRC-required annual operating tests

• Current requalification cycle operating test results

• Current requalification cycle operating test methodology (sample plan)

• List of time critical operator actions, including USAR references

2.05: Licensee Administration of Requalification Exams

• All procedures used to administer the annual operating test

• All procedures used to assess operator performance

• All procedures that describe conduct of simulator training

• All procedures used to test, operate, and maintain the simulator

2.06: Requalification Examination Security

• Tracking tools used to prevent excessive overlap on the written examinations and

ensure sampling of required topics on a periodic basis

• Tracking tools used to prevent excessive overlap on the operating tests and ensure

sampling of all required malfunctions (major events, instrument/component

malfunctions, TS calls, etc.) on a periodic basis.

• All procedures that describe examination security, including procedures used to

develop the examinations that include guidelines on overlap between examinations

in current exam cycle tests and prior year examinations

• List of all condition reports since the last biennial requalification inspection related to

examination security and overlap

2.07: Licensee Remedial Training Program

• List of remedial training conducted or planned since last biennial requalification

inspection (includes remedial training for exam failures and training to correct generic

or individual weaknesses observed during previous requalification exam cycle)

• Remediation plans (lesson plans, reference materials, and final documentation)

2.08: Conformance with Operator License Conditions

• All procedures and program documentation for maintaining active operator licenses,

tracking training attendance, and ensuring medical fitness of licensed operators

• All procedures and associated documentation that supports reactivation of any

SRO/RO license (operating or staff crew) since the last biennial inspection

2.09: Simulator Performance

• For the following cases, send the most recent transient test packages, which may be

electronic or in paper single test packages, and shall be complete with test procedures

for each test, the acceptance criteria, and results. For each transient

test, the reference chart should be included or an equivalent subject matter expert

review versus the simulator results with a write-up for any differences beyond the

ANSI 3.5 standard requirements.

o Transient test 3, Simultaneous closure of all main steam isolation valves

o Transient test 10, Slow primary system depressurization to saturated

condition with pressurizer relief or safety valve stuck open (inhibit activation of

high pressure emergency core cooling system)

o Steady State tests for low power test

• SBT packages for any three scenarios used for the 2018 annual requalification

operating test

• All simulator management and configuration procedures if not already provided for

Section 02.05 above

• Simulator discrepancy report (DR) summary list for all open DRs. For closed DRs,

summary list for those items closed between April 8, 2017

• Two examples of primary parameters tested in order to verify core physics

parameters. The applicable reference graphs from the plant physics data book

(electronic or other means as available) should also be included as well as the test

procedures used and the acceptance criteria with results.

• All simulator modification packages that are on hold, delayed, or just not completed

in the last 2-years

• A list of simulator modification packages completed in the last 2-year window

2.10: Problem Identification and Resolution

• A summary report of all condition reports related to licensed operator actions/errors

in the control room since April 8,2017

• Any revised requalification training that was based on licensed operator performance

issues since April 8,, 2017

B. The following information is requested in order to support the onsite inspection

activities. Requested materials should be available to the inspection team, either

electronically or hardcopy, upon site arrival on April 8, 2019.

2.02: Exam Results / 02.03 and 02.04: Written Exam and Op Test Quality

• All approved operating tests (password protected) to be administered subsequent to

the onsite inspection

• All results up to the day the team leaves the site.

2.08: Conformance with Operator License Conditions

• Access to licensed operators records

• Access to licensed operators training attendance records

• Access to licensed operators medical records

2.09: Simulator Performance

• Simulator discrepancies reports (DRs) since April 8, 2017. This should include all

open and closed DRs, with documentation / justification for closure

• Acceptance test documentation, including hardware and software model revisions at

the time of acceptance (as available)

• Documentation that validates current models, including the thermal-hydraulic and

neutronics models, to the actual plant

• All current model deficiencies, including USAR vs design differences in the simulator

• Summary list of plant modifications since April 8, 2017

• Plant modifications (both hardware and software) incorporated onto the simulator

since April 8, 2017.

• The complete book of all simulator annual performance test packages (either

hardcopy or electronic), complete with all transient tests, steady state tests, and

malfunction tests. This should also include the test procedures for each test, the

acceptance criteria, and results. For each transient test, the reference chart should

be included or an equivalent subject matter expert review versus the simulator

results with an analysis for any differences beyond the ANSI standard requirements

• Simulator reactor core performance test packages used to verify core physics

parameters (ANSI/ANS 3.5 sections 3.4.3.3 / 4.4.3.3), including applicable reference

graphs from the plant physics data book, test procedures, acceptance criteria, and

results

• All simulator test, configuration management, and related documents available in the

room for inspectors to review. This includes training needs analysis packages,

simulator review committee meeting minutes, etc.

• Current copy of ANSI 3.5 standard you are committed to for simulator testing

2.10: Problem Identification and Resolution

• All condition reports related to licensed operator actions/errors in the control room.

• All condition reports from the last initial license exam

C. Diablo Canyon Power Plant is required to send the final results and any remaining

written exams and operating tests to the lead inspector for final review and

comparison against the significance determination tools in order to communicate the

exit results for the inspection. Report results in the format below:

1. Total number of licensed operators.

2. Number of licensed operators administered a requalification examination

required by 10 CFR 55.59(a).

3. Number of individual licensed operators who failed any portion of a

requalification examination (written, JPM, or individual simulator scenario

failures).

3.a. Number of individual licensed operators who failed written exam

3.b. Number of individual licensed operators who failed JPM exam

3.c. Number of individual licensed operators who failed simulator

scenario exam individually

4. Divide line 3 by line 2 to obtain the individual requalification examination  %

failure rate

5. Number of crews administered simulator scenarios as part of a

requalification examination required by 10 CFR 55.59(a)

6. Number of crews who performed unsatisfactorily on the simulator

scenarios.

7. Divide line 6 by line 5 to obtain the crew simulator scenario failure rate. %

8. Describe the reason for each licensed operator who was not administered

an NRC-required requalification exam, or who did not pass an administered

requalification exam, and the stations plan to satisfy the requalification

exam requirement for each.

A-5