IR 05000275/2019002: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:August 1, 2019 Mr. James Senior Vice President, Generation and Chief Nuclear Officer Pacific Gas & Electric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 SUBJECT: DIABLO CANYON POWER PLANT, UNITS 1 AND 2
{{#Wiki_filter:ust 1, 2019
- NRC INTEGRATED INSPECTION REPORT 05000275/2019002 AND 05000323/2019002
 
==SUBJECT:==
DIABLO CANYON POWER PLANT, UNITS 1 AND 2 - NRC INTEGRATED INSPECTION REPORT 05000275/2019002 AND 05000323/2019002


==Dear Mr. Welsch:==
==Dear Mr. Welsch:==
On June 30, 2019
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.
, 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.
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.


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 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
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.
, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcem ent; 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
Sincerely,
. 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
/RA/
."
Jeffrey E. Josey, Chief Project Branch A Division of Reactor Projects Docket Nos.: 05000275 and 05000323 License Nos.: DPR-80 and DPR-82


Sincerely,
===Enclosure:===
/RA/ Jeffrey E. Josey, Chief Project Branch A Division of Reactor Projects Docket No s.: 05000275 and 05000323 License No s.: DPR-80 and DPR-82 Enclosure:
Inspection Report 05000275/2019002 and 05000323/2019002 with attachment 1. RFI Biennial Requalification
Inspection Report 05000275/2019002 and 05000323/2019002 with attachment 1. RFI Biennial Requalification cc w/ enclosure: Distribution via LISTSERV
 
==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=
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensee's performance by conducting a n integrated inspection at Diablo Canyon Power Plant, Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more informati on. NRC-identified and self-revealed findings, violations, and additional items are summarized in the table below.
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.


Licensee-identified non-cited violations are documented in the Inspection Results at the end of this report.
Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.


List of Findings and Violatio ns  Human Performance Event Leads to Inadvertent Unit 2 Bus F Vital Bus Transfer Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 0 5000275;05000323/2019002
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.
-01  Closed [H.12] - Avoid Complacency 71111.15 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
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,
-2 and containment fan cooler units 2
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.
-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
Additionally, emergency diesel generator 2-3, which was out of service for maintenance at the time of the event, received a start signal.
-001-00 LER 2018-001-00 for Diablo Canyon Power Plant, Unit 2, Automatic Reactor Trip of Unit 2 Following a Load Rejection.


71153 Closed LER 05000323/2018
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,
-001-01 LER 2018-001-01 for Diablo Canyon Power Plant, Unit 2, Automatic Reactor Trip of Unit 2 Following a Load Rejection.
Automatic Reactor Trip of Unit 2 Following a Load Rejection.


71153 Closed 3
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=
=PLANT STATUS=


Units 1 and 2 began the inspection period at full power.
===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.
On April 1, 2019, Unit 2 reduced power to 50 percent to clean water boxes and condensers.
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==INSPECTION SCOPES==
==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
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.
-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.


==REACTOR SAFETY==
==REACTOR SAFETY==
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===Impending Severe Weather Sample (IP Section 03.03)===
===Impending Severe Weather Sample (IP Section 03.03)===
{{IP sample|IP=IP 71111.01|count=1}}
{{IP sample|IP=IP 71111.01|count=1}}
The inspectors evaluated readiness for impending adverse weather conditions prior to the onset of seasonal heavy rains and winds on April 10, 2019.
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)
Summer Readiness Sample (IP Section 03.01) (1 Sample)===
(1 Sample) The inspectors evaluated summer readiness of offsite and alternate alternating current power systems.
The inspectors evaluated summer readiness of offsite and alternate alternating current
 
===power systems.


==71111.04 - Equipment Alignment==
==71111.04 - Equipment Alignment==


===Partial Walkdown Sample (IP Section 03.01)
===Partial Walkdown Sample (IP Section 03.01)===
(5 Sample s) The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
{{IP sample|IP=IP 71111.04|count=5}}
: (1) Unit 2, emergency diesel generator 2
 
-3 on April 3, 2019
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
: (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
: (3) Unit 1, component cooling water system train B on June 16, 2019
: (4) Unit 2, auxiliary building ventilation system on June 17, 2019
: (4) Unit 2, auxiliary building ventilation system on June 17, 2019
: (5) Unit 2, emergency diesel generator 2
: (5) Unit 2, emergency diesel generator 2-1 on June 25, 2019
-1 on June 25, 2019 71111.04S  
 
- Equipment Alignment Complete Walkdown Sample (IP Section 03.02)===
===71111.04S - Equipment Alignment Complete Walkdown Sample (IP Section 03.02) ===
{{IP sample|IP=IP 71111.04|count=1}}
{{IP sample|IP=IP 71111.04|count=1}}
The inspectors evaluated system configurations during a complete walkdown of the Units 1 and 2 safety injection systems on May 8  
The inspectors evaluated system configurations during a complete walkdown of the Units 1 and 2 safety injection systems on May 8 - June 25, 2019.
- June 25, 2019.


==71111.05A - Fire Protection (Annual)==
==71111.05A - Fire Protection (Annual)==
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===Annual Inspection (IP Section 03.02)===
===Annual Inspection (IP Section 03.02)===
{{IP sample|IP=IP 71111.05A|count=1}}
{{IP sample|IP=IP 71111.05A|count=1}}
The inspectors evaluated fire brigade performance during a drill on June 13, 2019.
The inspectors evaluated fire brigade performance during a drill on June 13, 2019.


==71111.05Q - Fire Protection==
==71111.05Q - Fire Protection==


===Quarterly Inspection (IP Section 03.01)
===Quarterly Inspection (IP Section 03.01)===
(4 Sample s) The inspectors evaluated fire protection program implementation in the following selected areas:
{{IP sample|IP=IP 71111.05Q|count=4}}
 
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
: (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
: (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
: (3) Unit 2, spent fuel building 100 foot elevation on May 3, 2019
: (4) Unit 2, emergency diesel generator rooms 2
: (4) Unit 2, emergency diesel generator rooms 2-1 and 2-2 on June 25, 2019
-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)===
===71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Program (IP Section 03.04) ===
{{IP sample|IP=IP 71111.05Q|count=1}}
{{IP sample|IP=IP 71111.11|count=1}}
Biennial Requalification Written Examinations The inspectors evaluated the quality of the facility licensee's biennial requalification written examination administered on May 28, 2019
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 licensee's annual requalification operating test.
 
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.
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.
Line 136: Line 131:
Requalification Examination Security The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
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
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.
-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 licensee's program for ensuring that licensed operators meet the conditions of their licenses. Control Room Simulator The inspectors evaluated the adequacy of the facility licensee's control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.


Problem Identification and Resolution The inspectors evaluated the licensee's ability to identify and resolve problems associated with licensed operator performance.
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==
==71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance==
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===Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)===
===Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)===
{{IP sample|IP=IP 71111.11Q|count=1}}
{{IP sample|IP=IP 71111.11Q|count=1}}
The inspectors observed and evaluated operator performance during the following activities:
The inspectors observed and evaluated operator performance during the following activities:
: (1) Unit 2, unexpected plant process computer annunciator alarms on June 11, 2019
: (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
: (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
: (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)
: (4) Units 1 and 2, control room turnover on June 23, 2019 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)===
(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.
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==
==71111.12 - Maintenance Effectiveness==
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===Routine Maintenance Effectiveness Inspection (IP Section 02.01)===
===Routine Maintenance Effectiveness Inspection (IP Section 02.01)===
{{IP sample|IP=IP 71111.12|count=1}}
{{IP sample|IP=IP 71111.12|count=1}}
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
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
Units 1 and 2, safety injection systems on June 20, 2019
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==71111.13 - Maintenance Risk Assessments and Emergent Work Control==
==71111.13 - Maintenance Risk Assessments and Emergent Work Control==


===Risk Assessment and Management Sample (IP Section 03.01)
===Risk Assessment and Management Sample (IP Section 03.01)===
(5 Sample s) The inspectors evaluated the risk assessments for the following planned and emergent work activities:
{{IP sample|IP=IP 71111.13|count=5}}
 
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
: (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
: (2) Unit 2, control room ventilation system emergent maintenance on May 1, 2019
: (3) Unit 2, vital battery charger 2
: (3) Unit 2, vital battery charger 2-2 out of service for maintenance on May 6, 2019
-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
: (4) Unit 2, auxiliary saltwater pump 2
: (5) Unit 2, emergency diesel generator 2-3 out of service for maintenance on June 25-26, 2019
-2 out of service for maintenance on June 6, 2019
 
: (5) Unit 2, emergency diesel generator 2
==71111.15 - Operability Determinations and Functionality Assessments==
-3 out of service for maintenance on June 25-26, 2019


==71111.15 - Operability Determinations and Functionality Assessment==
===Operability Determination or Functionality Assessment (IP Section 02.02)===
{{IP sample|IP=IP 71111.15|count=6}}


s Operability Determination or Functionality Assessment (IP Section 02.02)
The inspectors evaluated the following operability determinations and functionality assessments:
(6 Sample s) 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
: (1) Unit 1, elevated safety injection pump 1
: (2) Unit 1, control room ventilation motor operated damper MOD-3 sheared pin on April 17, 2019
-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
: (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
: (4) Unit 2, turbine building high energy line break seized louvers on May 16, 2019
: (5) Unit 2, emergency diesel generator 2
: (5) Unit 2, emergency diesel generator 2-1 erratic speed control on May 29, 2019
-1 erratic speed control on May 29, 2019
: (6) Unit 2, inadvertent transfer of 4 kV vital bus F on June 27, 2019
: (6) Unit 2, inadvertent transfer of 4 kV vital bus F on June 27, 2019


==71111.18 - Plant Modifications==
==71111.18 - Plant Modifications==


Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)===
===Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)===
{{IP sample|IP=IP 71111.13|count=1}}
{{IP sample|IP=IP 71111.18|count=1}}
 
The inspectors evaluated the following temporary or permanent modifications:
The inspectors evaluated the following temporary or permanent modifications:
Unit 1, turbine driven auxiliary feedwater pump 1
Unit 1, turbine driven auxiliary feedwater pump 1-1 governor replacement on May 19, 2019
-1 governor replacement on May 19, 2019


==71111.19 - Post-Maintenance Testi==
==71111.19 - Post-Maintenance Testing==


===ng Post Maintenance Test Sample (IP Section 03.01)
===Post Maintenance Test Sample (IP Section 03.01)===
(6 Sample s) The inspectors evaluated the following post maintenance tests:
{{IP sample|IP=IP 71111.19|count=6}}
: (1) Unit 1, centrifugal charging pump 2
 
-1, anti-rotation pin replacement on April 1, 2019
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
: (2) Unit 1, safety injection pump 1-1, mechanical seal maintenance on April 1, 2019
: (3) Unit 2, auxiliary feedwater system valves LCV
: (3) Unit 2, auxiliary feedwater system valves LCV-106 and LCV-107, preventative maintenance on April 9, 2019
-106 and LCV
: (4) Unit 1, auxiliary building ventilation system fan S-31, preventative maintenance and sheave replacement on April 25, 2019
-107, preventative maintenance on April 9, 2019
: (5) Unit 2, safety injection pump 2-1, lube oil cooler end bell replacement on April 30, 2019
: (4) Unit 1, auxiliary building ventilation system fan S
: (6) Units 1 and 2, diesel fuel oil transfer pump 0-1, preventative maintenance on June 10, 2019
-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:==
==71111.22 - Surveillance Testing==


===The inspectors evaluated the following surveillance tests:
Inservice Testing (IP Section 03.01)===
Inservice Testing (IP Section 03.01)===
{{IP sample|IP=IP 71111.19|count=1}}
{{IP sample|IP=IP 71111.22|count=1}}
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 Sample s)
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
: (1) Unit 2, main turbine valve testing, per procedure STP M-21C on April 4, 2019
-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
===(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
: (3) Unit 1, vital battery charger 1-1 surveillance testing, per procedure STP M-12B on June 4, 2019
-12B on June 4, 2019


==71114.06 - Drill Evaluation==
==71114.06 - Drill Evaluation==
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===Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)===
===Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)===
{{IP sample|IP=IP 71114.06|count=1}}
{{IP sample|IP=IP 71114.06|count=1}}
The inspectors evaluated an emergency preparedness drill on June 5, 2019.
The inspectors evaluated an emergency preparedness drill on June 5, 2019.


==OTHER ACTIVITIES  
==OTHER ACTIVITIES - BASELINE==
- 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)
(2 Sample s)
: (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 Sample s)
: (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 Sample s)
: (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==
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) ===
{{IP sample|IP=IP 71151|count=2}}
: (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


===Annual Follow
===(2)    Unit 2, date range: April 1, 2018 through March 31, 2019 MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)===
-up of Selected Issues (IP Section 02.03)
: (1) Unit 1, date range: April 1, 2018 through March 31, 2019
(2 Sample s) The inspectors reviewed the licensee's 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)===
{{IP sample|IP=IP 71152|count=1}}
The inspectors reviewed the licensee's 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.
===(2)    Unit 2, date range: April 1, 2018 through March 31, 2019


71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
==71152 - Problem Identification and Resolution==
(1 Sample) 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.
===Annual Follow-up of Selected Issues (IP Section 02.03)===
{{IP sample|IP=IP 71152|count=2}}


The SPS switch load reject function is selected to either Unit 1 or Unit 2.
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.


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.
===71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) ===
 
{{IP sample|IP=IP 71153|count=1}}
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 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.
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.
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)
All safety systems functioned as designed.
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.
 
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 licensee's 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 identifi ed. The inspectors also concluded that no violation of NRC requirements occurred.


==OTHER ACTIVITIES==
==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.
- 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:
 
Using the flexibilities in the baseline inspection program, the inspectors evaluated several aspects of the licensee's operations to determine whether the financial condition of the licensee impacted plant safety.
 
The factors reviewed during this period included:
: (1) impact on staffing,
: (1) impact on staffing,
: (2) corrective maintenance backlog,
: (2) corrective maintenance backlog,
: (3) changes to the planned maintenance schedule,
: (3) changes to the planned maintenance schedule,
: (4) corrective action program implementation, and
: (4) corrective action program implementation, and
: (5) any reduction in outage scope, including risk-significant modifications.
: (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.


Considering the licensee's 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 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.
 
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 licensee's financial circumstances were adversely affecting plant performance and safety.


==INSPECTION RESULTS==
==INSPECTION RESULTS==
Observation
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.
: 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 k V bus F were noted that resulted in impacts on plant equipment and unplanne d 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
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.
-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
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.
-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.
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.


However, the inspectors determined that the corrective actions taken to date appeared to be effective at addressing the identified gaps.
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
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.
-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 Aspect Report Section Initiating Events Green NCV 05000275;05000323/2019002
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.
-01  Closed  [H.12] - Avoid Complacency 71111.15 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
Additionally, emergency diesel generator 2-3, which was out of service for maintenance at the time of the event, received a start signal.
-3, which was out of service for maintenance at the time of the event, received a start signal.


=====Description:=====
=====Description:=====
Procedure STP M
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).
-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.
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.


This resulted in an inadvertent transfer of the 4 kV vital bus F from the auxiliary power supply to the startup power supply.
Corrective Action References: Notification 51034990


As part of this transfer, auxiliary saltwater pump 2
=====Performance Assessment:=====
-2 and containment fan cooler units 2
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.
-1 and 2-2 started.


Additionally, emergency diesel generator 2
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).
-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.
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.


This action, along with emergency diesel generator 2
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.
-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 Action s: 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.
=====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.


A cause evaluation to understand the causal factors that led to the event was also initiated.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
 
Corrective Action Reference s:  Notification 51034990 Performance Assessment
:  Performance Deficiency:  The inspectors determined that PG&E's failure to follow procedure STP M-75F, "4 k V Vital Bus F Undervoltage Relay Calibration," Revision 7 was a performance deficiency within PG&E's 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==
==EXIT MEETINGS AND DEBRIEFS==
The inspectors verified no proprietary information was retained or documented in this report.
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 May 31, 201 9 , the inspectors presented the biennial operator licensing requalification inspection results to Mr. J. Welsch, Senior Vice President
* 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.
, 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=
=DOCUMENTS REVIEWED=


Inspection Procedure Type Designation
Inspection Type             Designation   Description or Title                                     Revision or
Description or Title
Procedure                                                                                            Date
Revision or Date 71111.01 Corrective Action Documents Notifications
71111.01   Corrective Action Notifications 50981582, 51018665, 51027248, 51032504
50981582 , 51018665 , 51027248 , 51032504 71111.01 Procedures
Documents
CP M-12 Stranded Plant
71111.01   Procedures       CP M-12       Stranded Plant                                           8
71111.01 Procedures
71111.01   Procedures       CP M-16       Severe Weather                                           17
CP M-16 Severe Weather
71111.01   Procedures       OP AP SP-1   Loss of AC Power                                         22
71111.01 Procedures
71111.01   Procedures       OP AP-26     Loss of Offsite Power, Unit 1/2                           21A/20
OP AP SP-1 Loss of AC Power
71111.01   Procedures       OP O-28       Operations Response to Storms or Biofouling               23
71111.01 Procedures
71111.04   Corrective Action Notifications 51012144, 51031355, 51031356, 51034157
OP AP-26 Loss of Offsite Power, Unit 1/2
Documents
21A/20 71111.01 Procedures
71111.04   Drawings         106714       CCW OVID                                                 73
OP O-28 Operations Response to Storms or Biofouling
71111.04   Drawings         107721       Starting Air System EDG 2-3                               62
71111.04 Corrective Action Documents Notifications
71111.04   Drawings         107723       Control Room HVAC Unit 2                                 105
51012144, 51031355, 51031356, 51034157
71111.04   Drawings         57726         Aux., Containment, and Fuel Handling Buildings           12
71111.04 Drawings 106714 CCW OVID 73 71111.04 Drawings 107721 Starting Air System EDG 2
71111.04   Procedures       AD13.DC12     Control Room Envelop Habitability Program                 4
-3 62 71111.04 Drawings 107723 Control Room HVAC Unit 2
71111.04   Procedures       OP F-2:VI     CCW system Alignment Verification                         42
105 71111.04 Drawings 57726 Aux., Containment, and Fuel Handling Buildings
71111.04   Procedures       OP H-1:I     Auxiliary Building Safeguards Ventilation (ABVS) - Make   15
71111.04 Procedures
Available
AD13.DC12 Control Room Envelop Habitability Program
71111.04   Procedures       OP H-1:II     Auxiliary Building Safeguards Ventilation - Normal       11
71111.04 Procedures
Operation
OP F-2:VI CCW system Alignment Verification
71111.04   Procedures       OP H-5:II     Control Room Ventilation System-Alignment Verification   22
71111.04 Procedures
71111.04   Procedures       OP J-6B:I-A   Diesel Generator 2-1 - Alignment Checklist               0
OP H-1:I Auxiliary Building Safeguards Ventilation (ABVS)  
71111.04   Procedures       OP J-6B:II-A Diesel Generator 2-2 - Alignment Checklist               0
- Make Available 15 71111.04 Procedures
71111.04   Procedures       OP J-6B:III-A Diesel Generator 2-2 - Alignment Checklist               0
OP H-1:II Auxiliary Building Safeguards Ventilation  
71111.04   Procedures       OP J-6C:II   Diesel Fuel Oil System - Alignment Verification for Plant 14
- Normal Operation 11 71111.04 Procedures
Startup
OP H-5:II Control Room Ventilation System
71111.04   Procedures       OP K-10E1     Seal Valve Checklist for Component Cooling Water         73
-Alignment Verification
71111.04   Work Order                     641777113
71111.04 Procedures
71111.04S Corrective Action Notifications 50836988, 50888946, 50034848, 50925406, 50936644,
OP J-6B:I-A Diesel Generator 2
Documents                      50967009, 50967030, 50967595, 50968643, 50549533
-1 - Alignment Checklist
71111.04S Drawings         106709       Safety Injection, Unit 1, Sheet 4                         69
71111.04 Procedures
Inspection Type             Designation     Description or Title                               Revision or
OP J-6B:II-A Diesel Generator 2
Procedure                                                                                        Date
-2 - Alignment Checklist
71111.04S Drawings         107709           Safety Injection, Unit 2, Sheet 4                   67
71111.04 Procedures
71111.04S Procedures       DCPP A-30       Plant Labeling Program                             1
OP J-6B:III-A Diesel Generator 2
71111.04S Procedures       OP B-3A:11       Safety Injection System Alignment                   23B
-2 - Alignment Checklist
71111.04S Procedures       OP K-10A12       Seal Components for Safety Injection               3
71111.04 Procedures
71111.04S Work Orders                       60087891, 60004369, 60101584
OP J-6C:II Diesel Fuel Oil System  
71111.05A Corrective Action Notification     51026411
- Alignment Verification for Plant Startup 14 71111.04 Procedures
Documents
OP K-10E1 Seal Valve Checklist for Component Cooling Water
71111.05A Drawing           RA-3             RCA Elev. 73'                                       4
71111.04 Work Order
71111.05A Procedure         CP M-6           Casualty Procedure - Fire                           39
641777113  71111.04S Corrective Action Documents Notifications
71111.05Q Corrective Action Notifications   51026187, 50937062, 50622051, 50655050, 51026373,
50836988, 50888946, 50034848, 50925406, 50936644, 50967009, 50967030, 50967595, 50968643, 50549533
Documents                          51015502, 51002807, 50938102
71111.04S Drawings 106709 Safety Injection, Unit 1, Sheet 4
71111.05Q Drawings         111805, Sheet 60 Fire Department                                     3
Inspection Procedure Type Designation
71111.05Q Drawings         111805, Sheet 61 Fire Department                                     1
Description or Title
71111.05Q Drawings         RA-10           Pre-Fire plans; RCA and H-block, 115 foot elevation 3
Revision or Date 71111.04S Drawings 107709 Safety Injection, Unit 2, Sheet 4
71111.05Q Drawings         RA-15           Radiological Control Area Elev. 100               3
71111.04S Procedures
71111.05Q Drawings         TB-3             Turbine Building Elev. 85'                         3
DCPP A-30 Plant Labeling Program
71111.05Q Work Orders                       60116410, 60114723
71111.04S Procedures
71111.11B Corrective Action Notifications   50914432, 50937919, 50945261, 50945751, 50953015,
OP B-3A:11 Safety Injection System Alignment
Documents                          50954525, 50957474, 50965876, 50979165, 50979651,
23B 71111.04S Procedures
50990860, 50991733, 50992512, 50992513, 50992514,
OP K-10A12 Seal Components for Safety Injection
50943255, 50944990, 50951368, 50953221, 50953775,
71111.04S Work Orders
50956899, 50958114, 50959130, 50966981, 50973710,
60087891, 60004369, 60101584
50907386, 50957614, 50959111, 51023738, 51004051,
71111.05A Corrective Action Documents Notification
51015231
51026411  71111.05A Drawing RA-3 RCA Elev. 73'
71111.11B Miscellaneous                     2019 Operations Crew Roster                         3/12/2019
71111.05A Procedure CP M-6 Casualty Procedure  
71111.11B Miscellaneous                     2019 Operations Exam                               3/29/2019
- Fire 39 71111.05Q Corrective Action Documents Notifications
71111.11B Miscellaneous                     2019 Written Exam RO/SRO Week 1                     4/5/2019
51026187, 50937062, 50622051, 50655050, 51026373, 51015502, 51002807, 50938102 71111.05Q Drawings 111805, Sheet 60
71111.11B Miscellaneous                     2018 Annual Operating Exams                         5/24/2018
Fire Department
71111.11B Miscellaneous                     71111.11 Self-Assessment Report                     10/5/2018
71111.05Q Drawings 111805, Sheet 61
71111.11B Miscellaneous                     2018 Operations Training Self-Assessment Report     10/10/2018
Fire Department
71111.11B Miscellaneous                     ANSI/ANS-3.5-2009                                   9/4/2009
71111.05Q Drawings RA-10 Pre-Fire plans; RCA and H
71111.11B Miscellaneous                     Simulator Plant Differences Report                 4/1/2019
-block, 115 foot elevation
Inspection Type         Designation   Description or Title                               Revision or
71111.05Q Drawings RA-15 Radiological Control Area Elev. 100'
Procedure                                                                                  Date
71111.05Q Drawings TB-3 Turbine Building Elev. 85'
71111.11B Miscellaneous B3-2-1(1)     ANSI-3.5 Simulator Test Manual Reactor Trip       2/13/2019
71111.05Q Work Orders
71111.11B Miscellaneous B3-2-1(3)     ANSI-3.5 Simulator Test Closure of all MSIVs      2/13/2019
60116410, 60114723
71111.11B Miscellaneous B3-2-1(5)     ANSI-3.5 Simulator Test Trip of Single RCP         2/20/2019
71111.11B Corrective Action Documents Notifications
71111.11B Miscellaneous B3-2-1(9)     ANSI-3.5 Simulator Test Main Steam Line Rupture   2/25/2019
50914432, 50937919, 50945261, 50945751, 50953015, 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
71111.11B Miscellaneous B3.1 (100)     ANSI-3.5 Simulator 100% Steady State Power Test   3/25/2019
2019 Operations Crew Roster
71111.11B Miscellaneous B3.1 (25)     ANSI-3.5 Simulator 25% Steady State Power Test     3/21/2019
3/12/2019 71111.11B Miscellaneous
71111.11B Miscellaneous Form 69-2034   RO License Reactivation                           2/12/2018
2019 Operations Exam
71111.11B Miscellaneous Form 69-2034   RO License Reactivation                           6/29/2018
3/29/2019 71111.11B Miscellaneous
71111.11B Miscellaneous Form 69-2035   SRO License Reactivation                           4/25/2018
2019 Written Exam RO/SRO Week 1
71111.11B Miscellaneous Form 69-2035   SRO License Reactivation                           7/7/2018
4/5/2019 71111.11B Miscellaneous
71111.11B Miscellaneous Form 69-2035   SRO License Reactivation                           2/26/2019
2018 Annual Operating Exams
71111.11B Miscellaneous Form 69-2035   SRO License Reactivation                           9/9/2017
5/24/2018 71111.11B Miscellaneous
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record             1/31/2018
71111.11 Self-Assessment Report
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record             2/9/2018
10/5/2018 71111.11B Miscellaneous
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record             1/5/2018
2018 Operations Training Self
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record             1/12/2018
-Assessment Report
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record             6/4/2018
10/10/2018
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record             8/7/2018
71111.11B Miscellaneous
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record             9/28/2018
ANSI/ANS-3.5-2009 9/4/2009 71111.11B Miscellaneous
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record             10/31/2018
Simulator Plant Differences Report
71111.11B Miscellaneous Form 69-20642 Crew Remediation Training Record                   4/9/2019
4/1/2019
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record (Student A) 9/8/2017
Inspection Procedure Type Designation
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record (Student B) 9/8/2017
Description or Title
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record             9/7/2017
Revision or Date 71111.11B Miscellaneous
71111.11B Miscellaneous Form 69-20642 Individual Remediation Training Record             12/5/2017
B3-2-1(1) ANSI-3.5 Simulator Test Manual Reactor Trip
71111.11B Miscellaneous R1718SPRO.XLS RO Operating Test Quality Sample Methodology
2/13/2019 71111.11B Miscellaneous
71111.11B Miscellaneous R1718SPSRO.XLS SRO Operating Test Quality Sample Methodology
B3-2-1(3) ANSI-3.5 Simulator Test Closure of all MSIV's
71111.11B Procedures   B3-2-1(7)     ANSI-3.5 Simulator Test Maximum Rate Power Ramp   2/20/2019
2/13/2019 71111.11B Miscellaneous
71111.11B Procedures   B3.1 (100)     ANSI-3.5 Simulator 100% Steady State Power Test   3/25/2019
B3-2-1(5) ANSI-3.5 Simulator Test Trip of Single RCP
71111.11B Procedures   Form 69-2035   SRO License Reactivation                           1/10/2018
2/20/2019 71111.11B Miscellaneous
71111.11B Procedures   Form 69-20642 Individual Remediation Training Record             11/22/2017
B3-2-1(9) ANSI-3.5 Simulator Test Main Steam Line Rupture
71111.11B Procedures   OM14.ID2       Medical Examinations                               11
2/25/2019 71111.11B Miscellaneous
71111.11B Procedures   OP1.DC10       Conduct of Operations                             55
B3.1 (100)
Inspection Type             Designation   Description or Title                                   Revision or
ANSI-3.5 Simulator 100% Steady State Power Test
Procedure                                                                                        Date
3/25/2019 71111.11B Miscellaneous
71111.11B Procedures       TQ2.DC 15     Licensed Operator Annual/Biennial Exam Development and 10
B3.1 (25) ANSI-3.5 Simulator 25% Steady State Power Test
Administration
3/21/2019 71111.11B Miscellaneous
71111.11B Procedures       TQ2.DC 3     Licensed Operator Continuing Training Program         31
Form 69-2034 RO License Reactivation
71111.11B Procedures       TQ2.ID 4     Training Program Implementation                       47A
2/12/2018 71111.11B Miscellaneous
71111.11B Procedures       TQ2.ID 9     Conduct of Training                                   17
Form 69-2034 RO License Reactivation
71111.11Q Corrective Action Notification  51033211
6/29/2018 71111.11B Miscellaneous
Document
Form 69-2035 SRO License Reactivation
71111.11Q Procedures         JSIM-507     Evaluator Skills                                       0
4/25/2018 71111.11B Miscellaneous
71111.11Q Procedures         TQ2.DC3       Licensed Operator Continuing Training Program         29
Form 69-2035 SRO License Reactivation
71111.13   Corrective Action Notifications 51027990, 51028008, 51028376, 51027833, 51028007
7/7/2018 71111.11B Miscellaneous
Documents
Form 69-2035 SRO License Reactivation
71111.13   Drawing           107723       Control Room HVAC (south)                             105
2/26/2019 71111.11B Miscellaneous
71111.13   Procedures       AD13.DC12     Control Room Envelope Habitability Program             4
Form 69-2035 SRO License Reactivation
71111.13   Procedures       AD7.DC6       On-Line Maintenance Risk Management                   27
9/9/2017 71111.11B Miscellaneous
71111.13   Procedures       AD7.DC6       On-Line Maintenance Risk Management                   26
Form 69-20642 Individual Remediation Training Record
71111.13   Procedures       AD7.ID14     Assessment of Integrated Risk                         21
1/31/2018 71111.11B Miscellaneous
71111.13   Procedures       OP O-36       Protected Equipment Postings                           18
Form 69-20642 Individual Remediation Training Record
71111.13   Procedures       OP O-36       Protected Equipment Postings                           19
2/9/2018 71111.11B Miscellaneous
71111.13   Work Order                     60114431
Form 69-20642 Individual Remediation Training Record
71111.15   Corrective Action Notifications 51027597, 51027678, 51027584, 51025593, 50595423,
1/5/2018 71111.11B Miscellaneous
Documents                      50042226, 50042428, 50081646, 50503871, 50524751,
Form 69-20642 Individual Remediation Training Record
50945969, 50946204, 50946299, 50946368, 50946436,
1/12/2018 71111.11B Miscellaneous
51031744, 51034990, 50676578, 51031001, 51034990,
Form 69-20642 Individual Remediation Training Record
51030260, 51027610, 50913105
6/4/2018 71111.11B Miscellaneous
71111.15   Drawings         441286       4160 Volt Bus Section F Automatic Transfer           11
Form 69-20642 Individual Remediation Training Record
71111.15   Drawings         441340       Potential and Synchronizing Diagram 4160V Bus Sections 31
8/7/2018 71111.11B Miscell aneous Form 69-20642 Individual Remediation Training Record
F, G, & H
9/28/2018 71111.11B Miscellaneous
71111.15   Drawings         6018227-16   Louver Schedule Turbine Building                       5
Form 69-20642 Individual Remediation Training Record
71111.15   Drawings         663231       Reactor Protection System Vendor Manual               28
10/31/2018
71111.15   Drawings         663231       Schematic Diagram - Isolation Card                     137
71111.11B Miscellaneous
71111.15   Drawings         663231       Solid State Protection System Interconnection Diagram 10
Form 69-20642 Crew Remediation Training Record
71111.15   Procedures       AR PK02-02   Safety Injection Initiate Annunciator Response         11
4/9/2019 71111.11B Miscellaneous
71111.15   Procedures       AR PK04-12   Reactor Trip Initiate                                 15
Form 69-20642 Individual Remediation Training Record (Student A)
Inspection Type             Designation   Description or Title                                     Revision or
9/8/2017 71111.11B Miscellaneous
Procedure                                                                                            Date
Form 69-20642 Individual Remediation Training Record (Student B)
71111.15   Procedures       AR PK08-22   Auto S.I. Blocked                                         1
9/8/2017 71111.11B Miscellaneous
71111.15   Procedures       AR PK18-19   4 kV Bus F Auto Transfer Annunciator Response             5
Form 69-20642 Individual Remediation Training Record
71111.15   Procedures       CP M-16       Severe Weather                                           17
9/7/2017 71111.11B Miscellaneous
71111.15   Procedures       OM7.ID1       Emerging Issue and Event Investigations                   54
Form 69-20642 Individual Remediation Training Record
71111.15   Procedures       OM7.ID12     Operability Determinations                               39
2/5/2017 71111.11B Miscellaneous
71111.15   Procedures       STP M-75F     4 kV Vital Bus F Undervoltage Relay Calibration           7
R1718SPRO.XLS
71111.15   Procedures       STP P-SIP-11 Routine Testing of Safety Injection Pump Checks Required
RO Operating Test Quality Sample Methodology
by Licenses
71111.11B Miscellaneous
71111.15   Work Orders                     60023251, 64212870, 60105138, 60049371, 60105023,
R1718SPSRO.XLS
60007325, 60120339, 60119104
SRO Operating Test
71111.18   Corrective Action Notifications 51022989, 51023045, 51029356
Quality Sample Methodology
Documents
71111.11B Procedures
71111.18   Miscellaneous     DCP E-049490 Replacing Starter and Overload Relay TDAFW               0
B3-2-1(7) ANSI-3.5 Simulator Test Maximum Rate Power Ramp
71111.18   Procedures       MP M-4.25     Auxiliary Feedwater Pump Turbine Governor Maintenance     18
2/20/2019 71111.11B Procedures
71111.18   Work Order                     64033834
B3.1 (100)
71111.19   Corrective Action Notifications 50954692, 50993690, 50032499, 51029229, 50965742,
ANSI-3.5 Simulator 100% Steady State Power Test
Documents                      51029180, 50965347, 51028587, 51029500, 51033565,
3/25/2019 71111.11B Procedures
51033619
Form 69-2035 SRO License Reactivation
71111.19   Miscellaneous     RPE 211571   Fan & Motor Sheaves, Bushings, and Keys                   4
1/10/2018 71111.11B Procedures
71111.19   Procedures       CF5.ID1       Receipt of Materials                                     13
Form 69-20642 Individual Remediation Training Record
71111.19   Procedures       MP E-53.10A   Preventative Maintenance of Limitorque Motor Operators   44
11/22/2017
71111.19   Procedures       MP E-8.1     Centrifugal Charging Pump Motor Overhaul                 14
71111.11B Procedures
71111.19   Procedures       MP M-23-FAN.4 Preventative Maintenance of Ventilation Fans With         9
OM14.ID2 Medical Examinations
Dampers and Inlet Vanes
71111.11B Procedures
71111.19   Procedures       OP J-6C:1     DFO Alignment and Operations                             15
OP1.DC10 Conduct of Operations
71111.19   Procedures       STP P-CCP-21 Routine Surveillance Test of Centrifugal Charging         26
Inspection Procedure Type Designation
Pump 2-1
Description or Title
71111.19   Procedures       STP P-SIP 11 Routine Surveillance of Safety Injection Pump             25
Revision or Date 71111.11B Procedures
71111.19   Procedures       STP P-SIP-21 Routine Surveillance Testing of Safety Injection Pump 2-1 28
TQ2.DC 15 Licensed Operator Annual/Biennial Exam Development and Administration
71111.19   Procedures       STP V-3L2A   Exercising Valve SI-2-8821A, Safety Injection Pump       0
71111.11B Procedures
Discharge to RCS Cold Legs
TQ2.DC 3 Licensed Operator Continuing Training Program
71111.19   Procedures       STP V-3P5     Exercising Valves LCV-106, 107, 108, and 109             21
71111.11B Procedures
TQ2.ID 4 Training Program Implementation
47A 71111.11B Procedures
TQ2.ID 9 Conduct of Training
71111.11Q Corrective Action Document Notification
51033211  71111.11Q Procedures
JSIM-507 Evaluator Skills
71111.11Q Procedures
TQ2.DC3 Licensed Operator Continuing Training Program
71111.13 Corrective Action Documents Notifications
51027990, 51028008, 51028376, 51027833, 51028007
71111.13 Drawing 107723 Control Room HVAC (south)
105 71111.13 Procedures
AD13.DC12 Control Room Envelope Habitability Program
71111.13 Procedures
AD7.DC6 On-Line Maintenance Risk Management
71111.13 Procedures
AD7.DC6 On-Line Maintenance Risk Management
71111.13 Procedures
AD7.ID14 Assessment of Integrated Risk
71111.13 Procedures
OP O-36 Protected Equipment Postings
71111.13 Procedures
OP O-36 Protected Equipment Postings
71111.13 Work Order
60114431  71111.15 Corrective Action Documents Notifications
51027597, 51027678, 51027584, 51025593, 50595423, 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
71111.15 Drawings 441340 Potential and Synchronizing Diagram 4160V Bus Sections F, G, & H 31 71111.15 Drawings 6018227-16 Louver Schedule Turbine Building
71111.15 Drawings 663231 Reactor Protection System Vendor Manual
71111.15 Drawings 663231 Schematic Diagram  
- Isolation Card
137 71111.15 Drawings 663231 Solid State Protection System Interconnection Diagram
71111.15 Procedures
AR PK02-02 Safety Injection Initiate Annunciator Response
71111.15 Procedures
AR PK04-12 Reactor Trip Initiate
Inspection Procedure Type Designation
Description or Title
Revision or Date 71111.15 Procedures
AR PK08-22 Auto S.I. Blocked
71111.15 Procedures
AR PK18-19 4 kV Bus F Auto Transfer Annunciator Response
71111.15 Procedures
CP M-16 Severe Weather
71111.15 Procedures
OM7.ID1 Emerging Issue and Event Investigations
71111.15 Procedures
OM7.ID12 Operability Determinations
71111.15 Procedures
STP M-75F 4 kV Vital Bus F Undervoltage Relay Calibration
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 Documents Notifications
51022989, 51023045, 51029356
71111.18 Miscellaneous
DCP E-049490 Replacing Starter and Overload Relay TDAFW
71111.18 Procedures
MP M-4.25 Auxiliary Feedwater Pump Turbine Governor Maintenance
71111.18 Work Order
64033834  71111.19 Corrective Action Documents Notifications
50954692, 50993690, 50032499, 51029229, 50965742, 51029180, 50965347, 51028587, 51029500, 51033565, 51033619 71111.19 Miscellaneous
RPE 211571
Fan & Motor Sheaves, Bushings, and Keys
71111.19 Procedures
CF5.ID1 Receipt of Materials
71111.19 Procedures
MP E-53.10A Preventative Maintenance of Limitorque Motor Operators
71111.19 Procedures
MP E-8.1 Centrifugal Charging Pump Motor Overhaul
71111.19 Procedures
MP M-23-FAN.4 Preventative Maintenance of Ventilation Fans With Dampers and Inlet Vanes
71111.19 Procedures
OP J-6C:1 DFO Alignment and Operations
71111.19 Procedures
STP P-CCP-21 Routine Surveillance Test
of Centrifugal Charging Pump 2-1 26 71111.19 Procedures
STP P-SIP 11 Routine Surveillance of Safety Injection Pump
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 Discharge to RCS Cold Legs
71111.19 Procedures
STP V-3P5 Exercising Valves LCV
-106, 107, 108, and 109
Auxiliary Feedwater Pump Discharge
Auxiliary Feedwater Pump Discharge
Inspection Procedure Type Designation
Inspection Type             Designation     Description or Title                                   Revision or
Description or Title
Procedure                                                                                          Date
Revision or Date 71111.19 Work Orders
71111.19   Work Orders                       60106782, 64165539, 64156641, 64206103, 60118888,
60106782, 64165539, 64156641, 64206103, 60118888, 60118889, 64206104, 60108508, 64174611, 60118821, 64077390, 64129545
60118889, 64206104, 60108508, 64174611, 60118821,
71111.22 Drawings 107722 Gland Steam Supply Main Turbine, Sheet 2
64077390, 64129545
71111.22 Drawings EQP-626 Load Bank Constraints
71111.22   Drawings         107722         Gland Steam Supply Main Turbine, Sheet 2               46
71111.22 Procedures
71111.22   Drawings         EQP-626         Load Bank Constraints                                 2
OP E-5:II Auxiliary Saltwater CCW Heat Exchanger Operation
71111.22   Procedures       OP E-5:II       Auxiliary Saltwater CCW Heat Exchanger Operation       19
71111.22 Procedures
71111.22   Procedures       STP I-38-B.1   SSPS Train B Actuation Logic Test in MODES 1,2,3, or 4 12
STP I-38-B.1 SSPS Train B Actuation Logic Test in MODES 1,2,3, or 4
71111.22   Procedures       STP M-12B       Battery Charger Performance Test                       19
71111.22 Procedures
71111.22   Procedures       STP M-21C       Main Turbine Valve Testing                             2
STP M-12B Battery Charger Performance Test
71111.22   Procedures       STP P-CCW-A11   Comprehensive Pump Test of Component Cooling Water     6
71111.22 Procedures
Pump 1-1
STP M-21C Main Turbine Valve Testing
71111.22   Work Orders                       64168747, 64168976
71111.22 Procedures
71114.06   Procedures       EP G-3         Emergency Notification of Off-Site Agencies           60
STP P-CCW-A11 Comprehensive Pump Test of Component Cooling Water Pump 1-1 6 71111.22 Work Orders
71114.06   Procedures       R18-3           Simulator Event Sequence                               0
64168747, 64168976
71114.06   Procedures       TQ2.DC3         Licensed Operator Training Program                     31
71114.06 Procedures
71151     Corrective Action Notification    50974176
EP G-3 Emergency Notification of Off
Document
-Site Agencies
71151     Miscellaneous     CDE 4.0 UAI     Unit 1/2, MSPI Derivation Reports MS05/ MS06 / MS07   06/10/2019
71114.06 Procedures
71151     Miscellaneous     MSPI Self-     Attachment 1; Calculation File C.10, DCPP PRA Model   12/01/2012
R18-3 Simulator Event Sequence
Assessment      Technical Adequacy
71114.06 Procedures
71151     Work Orders                       64201443, 60106784, 60110022
TQ2.DC3 Licensed Operator Training Program
71152     Corrective Action Notifications   51021044, 51015768, 51026933, 51013123, 51012969,
71151 Corrective Action Document Notification
Documents                        51015353, 51012973, 51016307, 51015025, 51015362,
50974176  71151 Miscellaneous
51016480, 51019481, 51020675, 51020974, 51022319,
CDE 4.0 UAI
51020443, 51026379, 51017815, 51019542, 51002648
Unit 1/2, MSPI Derivation Reports MS05/ MS06 / MS07
71152     Drawings         102021         Diesel Generator, Sheet 2                             67
06/10/2019
71152     Drawings         108021         Diesel Fuel Oil System                                 40
71151 Miscellaneous
71152     Miscellaneous     9000041674     Buried Piping and Tanks Program Asset Management Plan 2
MSPI Self-Assessment
71152     Miscellaneous     ANSI/ANS-59.51- Fuel Oil Systems for Safety-Related Emergency Diesel
1; Calculation File C.10, DCPP PRA Model Technical Adequacy
1997            Generators
2/01/2012
71152     Procedures       MP E-17.1       Westinghouse Auxiliary Saltwater Pump Motor Overhaul   22
71151 Work Orders
71152     Procedures       OM15.ID11       Human Performance Event Response                       4
201443, 60106784, 60110022
71152     Procedures       OM15.ID8       Human Performance Error Prevention Tools               9
71152 Corrective Action Documents Notifications
Inspection Type       Designation Description or Title                                 Revision or
51021044, 51015768, 51026933, 51013123, 51012969, 51015353, 51012973, 51016307, 51015025, 51015362, 51016480, 51019481, 51020675, 51020974, 51022319, 51020443, 51026379, 51017815, 51019542, 51002648
Procedure                                                                              Date
71152 Drawings 102021 Diesel Generator, Sheet 2
71152     Procedures OM4.ID14   Notification Review Team (NRT)                       31
71152 Drawings 108021 Diesel Fuel Oil System
71152     Procedures OM7.ID1     Problem Identification and Resolution                 53
71152 Miscellaneous
71152     Procedures OM7.ID3     Root Cause Evaluation                                 47
9000041674
71152     Procedures OP J-6C:VI DFO Transfer System - Pipe Leak Detection Operation   8
Buried Piping and Tanks Program Asset Management Plan
71152     Procedures OP1.DC40   Operations Equipment Deficiency and Adverse Condition 10
71152 Miscellaneous
Monitoring
ANSI/ANS-59.51-1997 Fuel Oil Systems for Safety
71152     Procedures OP1.ID6     Plant Status Control                                 16
-Related Emergency Diesel Generators
71152     Procedures STP M-121   DFO Leak Detection System ANI-501 Functional Test     7
71152 Procedures
71152     Procedures STP M-122   Diesel Fuel Oil Underground Storage Tanks 0-1 and 0-2 6
MP E-17.1 Westinghouse Auxiliary Saltwater Pump Motor Overhaul
Interstitial Test and Enhanced Leak Detection Test
71152 Procedures
71152     Procedures STP M-9A2   EDG Routine Surveillance Test                         12A
OM15.ID11 Human Performance Event Response
71152 Procedures
OM15.ID8 Human Performance Error Prevention Tools
Inspection Procedure Type Designation
Description or Title
Revision or Date 71152 Procedures
OM4.ID14 Notification Review Team (NRT)
71152 Procedures
OM7.ID1 Problem Identification and Resolution
71152 Procedures
OM7.ID3 Root Cause Evaluation
71152 Procedures
OP J-6C:VI DFO Transfer System  
- Pipe Leak Detection Operation
71152 Procedures
OP1.DC40 Operations Equipment Deficiency and Adverse Condition Monitoring
71152 Procedures
OP1.ID6 Plant Status Control
71152 Procedures
STP M-121 DFO Leak Detection System ANI
-501 Functional Test
71152 Procedures
STP M-122 Diesel Fuel Oil Underground Storage Tanks 0
-1 and 0-2 Interstitial Test and Enhanced Leak Detection Test
71152 Procedures
STP M-9A2 EDG Routine Surveillance Test
2A
Attachment
BIENNIAL REQUALIFICATION INSPECTION DOCUMENT REQUEST
BIENNIAL REQUALIFICATION INSPECTION DOCUMENT REQUEST
Inspection Report:
Inspection Report:             05000275/0219002, 05000323/2019002
05000275/0219002, 05000323/2019002
Inspection Dates:               April 8 to April 12, 2019
Inspection Dates:
Inspection Procedure:           IP 71111.11B, Licensed Operator Requalification Program
April 8 to April 12, 2019
Lead Inspector:                 Nicholas Hernandez, Operations Engineer
Inspection Procedure:
A. The following information is requested in order to support inspection preparation
IP 71111.11B, "Licensed Operator Requalification Program"
activities. These items are listed by section as they appear in the inspection module
Lead Inspector:
    (i.e. 2.02, 2.04, etc.). Requested materials should be sent either electronically or by
Nicholas Hernandez, Operations Engineer
CD/DVD in order to arrive at the Region IV office no later than March 15, 2019. Do not
: [[contact::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
send USB flash drives.
. Electronically:
    *    Electronically:       To:     Nicholas.Hernandez@nrc.gov (lead Inspector);
To: Nicholas.Hernandez@nrc.gov
Cc:     Clyde.Osterholtz@nrc.gov (inspector)
(lead Inspector);
    *    CD/DVD:               To:     US Nuclear Regulatory Commission, Region IV
Cc: Clyde.Osterholtz@nrc.gov
ATTN: Clyde Osterholtz
(inspector)
CD/DVD: To: US Nuclear Regulatory Commission, Region IV
ATTN: Clyde Osterholtz
1600 E. Lamar Blvd
1600 E. Lamar Blvd
Arlington, TX 76011
Arlington, TX 76011
General Requests:
General Requests:
List of licensed operators (SRO & RO) by crew (operating & staff)
    *    List of licensed operators (SRO & RO) by crew (operating & staff)
Training and Operations Department organization charts (with qualified LOR
    *    Training and Operations Department organization charts (with qualified LOR
evaluators identified)
evaluators identified)
Procedures that identify process for revising and maintaining LOR continuing training
    *    Procedures that identify process for revising and maintaining LOR continuing training
program List of outstanding LOR program changes
program
List of plant events and industry operating experience incorporated into LOR
    *    List of outstanding LOR program changes
    *    List of plant events and industry operating experience incorporated into LOR
program since last BRQ
program since last BRQ
Audits and/or self
    *    Audits and/or self-assessment reports addressing the LOR training program
-assessment reports addressing the LOR training program
    *    Last 2 years of simulator review committee (or equivalent) meeting minutes
Last 2 years of simulator review committee (or equivalent) meeting minutes
    *    Last 2 years of Curriculum 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
02.03: Biennial Requalification Written Examination Quality
* The current and approved biennial written examination schedule
* The current and approved biennial written examination schedule
* The current requalification cycle written examination results to date
* The current requalification cycle written examination results to date
* All written examinations that have been approved for administration up to the date of
* 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
submittal. Include password protection if e
mailed per NUREG-1021.
-mailed or double envelope protection
* The current requalification cycle examination methodology (sample plan)
if mailed per NUREG
-1021. * The current requalification cycle examination methodology (sample plan)
2.04: Annual Requalification Operating Test Quality
2.04: Annual Requalification Operating Test Quality
* The schedule for the operating tests to be given the week of April 8, , 2019
* 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
* All operating tests (password protected) that have been approved for administration
up to and including the week of the onsite inspection
up to and including the week of the onsite inspection
  * All 2019 NRC
* All 2019 NRC-required annual operating tests
-required annual operating tests
* Current requalification cycle operating test results
* Current requalification cycle operating test results
* Current requalification cycle operating test methodology (sample plan)
* Current requalification cycle operating test methodology (sample plan)
* List of time critical operator actions, including USAR references
* List of time critical operator actions, including USAR references
2.05: Licensee Administration of Requalification Exams
2.05: Licensee Administration of Requalification Exams
* All procedures used to administer the annual operating test
* 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 assess operator performance
* All procedures used to test, operate, and maintain the simulator
* All procedures that describe conduct of simulator training
* All procedures used to test, operate, and maintain the simulator
2.06: Requalification Examination Security
2.06: Requalification Examination Security
* Tracking tools used to prevent excessive overlap on the written examinations a
* Tracking tools used to prevent excessive overlap on the written examinations and
nd ensure sampling of required topics on a periodic basis
ensure sampling of required topics on a periodic basis
* Tracking tools used to prevent excessive overlap on the operating tests and ensure
* Tracking tools used to prevent excessive overlap on the operating tests and ensure
sampling of all required malfunctions (major events, instrument/component
sampling of all required malfunctions (major events, instrument/component
malfunctions, TS calls, etc.) on a periodic basis.
malfunctions, TS calls, etc.) on a periodic basis.
* All procedures that describe examination security, including procedures used to
* All procedures that describe examination security, including procedures used to
develop the examinations that include guidelines on overlap between examinations
develop the examinations that include guidelines on overlap between examinations
in current exam cycle tests and prior year examinations
in current exam cycle tests and prior year examinations
* List of all condition reports since the last biennial requalification inspection related to
* List of all condition reports since the last biennial requalification inspection related to
examination security and overlap
examination security and overlap
2.07: Licensee Remedial Training Program
2.07: Licensee Remedial Training Program
* List of remedial training conducted or planned since last biennial requalification
* List of remedial training conducted or planned since last biennial requalification
inspection (includes remedial training for exam failures and training to correct generic
inspection (includes remedial training for exam failures and training to correct generic
or individual weaknesses observed during previous requalification exam cycle)
or individual weaknesses observed during previous requalification exam cycle)
* Remediation plans (lesson plans, reference materials, and final documentation)
* Remediation plans (lesson plans, reference materials, and final documentation)
2.08: Conformance with Operator License Conditions
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 program documentation for maintaining active operator licenses,
* All procedures and associated documentation that supports reactivation of any
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
SRO/RO license (operating or staff crew) since the last biennial inspection
 
2.09: Simulator Performance
02.09: Simulator Performance
  * For the following cases, send the most recent transient test packages, which may be
* 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
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
test, the reference chart should be included or an equivalent subject matter expert
review versus the simulator results with a write
review versus the simulator results with a write-up for any differences beyond the
-up for any differences beyond the
ANSI 3.5 standard requirements.
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
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
condition with pressurizer relief or safety valve stuck open (inhibit activation of
high pressure emergency core cooling system)
high pressure emergency core cooling system)
o Steady State tests for low power test
o Steady State tests for low power test
* SBT packages
  * SBT packages for any three scenarios used for the 2018 annual requalification
for any three scenarios used for the 2018 annual requalification
operating test
operating test
* All simulator management and configuration procedures if not already provided for
  * All simulator management and configuration procedures if not already provided for
Section 02.05 above
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
  * Simulator discrepancy report (DR) summary list for all open DRs. For closed DRs,
* Two examples of primary parameters tested in order to verify core physics
summary list for those items closed between April 8, 2017
parameters.
  * Two examples of primary parameters tested in order to verify core physics
The applicable reference graphs from the plant physics data book
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
      (electronic or other means as available) should also be included as well as the test
procedures used and the acceptance criteria with results.
procedures used and the acceptance criteria with results.
* All simulator modification packages that are on hold, delayed, or just not completed
  * All simulator modification packages that are on hold, delayed, or just not completed
in the last 2
in the last 2-years
-years * A list of simulator modification packages completed in the last 2
  * A list of simulator modification packages completed in the last 2-year window
-year window
2.10: Problem Identification and Resolution
2.10: Problem Identification and Resolution
* A summary report of all condition reports related to licensed operator actions/errors
  * A summary report of all condition reports related to licensed operator actions/errors
in the control room since April 8,2017
in the control room since April 8,2017
* Any revised requalification training that was based on licensed operator performance
  * Any revised requalification training that was based on licensed operator performance
issues since April 8,, 2017
issues since April 8,, 2017
B. The following information is requested in order to support the onsite inspection activities.
B. The following information is requested in order to support the onsite inspection
Requested materials should be available to the inspection team, either electronically or hardcopy, upon site arrival on April 8, 2019.
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
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
  * All approved operating tests (password protected) to be administered subsequent to
the onsite inspection
the onsite inspection
* All results up to the day the team leaves the site. 02.08: Conformance with Operator License Conditions
  * All results up to the day the team leaves the site.
* Access to licensed operators' records
2.08: Conformance with Operator License Conditions
* Access to licensed operators' training attendance records
  * Access to licensed operators records
* Access to licensed operators' medical records
  * Access to licensed operators training attendance records
  * Access to licensed operators medical records
2.09: Simulator Performance
2.09: Simulator Performance
* Simulator discrepancies
  * Simulator discrepancies reports (DRs) since April 8, 2017. This should include all
reports (DRs) since April 8, 2017.
This should include all
open and closed DRs, with documentation / justification for closure
open and closed DRs, with documentation / justification for closure
 
  *   Acceptance test documentation, including hardware and software model revisions at
* Acceptance test documentation, including hardware and software model revisions at
the time of acceptance (as available)
the time of acceptance (as available)
* Documentation that validates current models, including the thermal
  *   Documentation that validates current models, including the thermal-hydraulic and
-hydraulic and
neutronics models, to the actual plant
neutronics models, to the actual plant
* All current model deficiencies, including USAR vs design differences in the simulator
  *   All current model deficiencies, including USAR vs design differences in the simulator
* Summary list of plant modifications since April 8, 20
  *   Summary list of plant modifications since April 8, 2017
* Plant modifications (both hardware and software) incorporated onto the simulator
  *   Plant modifications (both hardware and software) incorporated onto the simulator
since April 8, 2017.
since April 8, 2017.
* The complete book of all simulator annual performance test packages (either
  *   The complete book of all simulator annual performance test packages (either
hardcopy or electronic), complete with all transient tests, steady state tests, and
hardcopy or electronic), complete with all transient tests, steady state tests, and
malfunction tests.
malfunction tests. This should also include the test procedures for each test, the
This should also include the test procedures for each test, the
acceptance criteria, and results. For each transient test, the reference chart should
acceptance criteria, and results.
be included or an equivalent subject matter expert review versus the simulator
For each transient test, the reference chart should
results with an analysis for any differences beyond the ANSI standard requirements
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
* 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
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
graphs from the plant physics data book, test procedures, acceptance criteria, and
results * All simulator test, configuration management, and related documents available in the
results
room for inspectors to review.
  *   All simulator test, configuration management, and related documents available in the
This includes training needs analysis packages, simulator review committee meeting minutes, etc.
room for inspectors to review. This includes training needs analysis packages,
* Current copy of ANSI 3.5 standard you are committed to for simulator testing
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
2.10: Problem Identification and Resolution
* All condition reports related to licensed operator actions/errors in the control room.
  * All condition reports related to licensed operator actions/errors in the control room.
* All condition reports from the last initial license exam
  * 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.
C. Diablo Canyon Power Plant is required to send the final results and any remaining
Report results in the format below:
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.
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
2. Number of licensed operators administered a requalification examination
any portion of a requalification examination (written, JPM, or individual simulator scenario failures).
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.a. Number of individual licensed operators who failed written exam
3.b. Number of individual licensed operators who failed JPM 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
3.c. Number of individual licensed operators who failed simulator
4. Divide line 3 by line 2 to obtain the individual requalification examination failure rate
scenario exam individually
% 5. Number of crews administered simulator scenarios as part of a requalification examination required by 10 CFR 55.59(a)
4. Divide line 3 by line 2 to obtain the individual requalification examination     %
 
failure rate
6. Number of crews who performed unsatisfactorily on the simulator scenarios.
5. Number of crews administered simulator scenarios as part of a
7. Divide line 6 by line 5 to obtain the crew simulator scenario failure rate.
requalification examination required by 10 CFR 55.59(a)
% 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 station's plan to satisfy the requalification exam requirement for each.
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
}}
}}

Revision as of 11:39, 19 October 2019

NRC Integrated Inspection Report 05000275/2019002 and 05000323/2019002
ML19214A279
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
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)
v • d • e


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.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Impending Severe Weather Sample (IP Section 03.03)

Main article: IP 71111.01

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)

Main article: IP 71111.04

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)

Main article: IP 71111.04

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)

Main article: IP 71111.05A

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

71111.05Q - Fire Protection

Quarterly Inspection (IP Section 03.01)

Main article: IP 71111.05Q

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)

Main article: IP 71111.11

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)

Main article: IP 71111.11Q

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)

Main article: IP 71111.12

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)

Main article: IP 71111.13

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)

Main article: IP 71111.15

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)

Main article: IP 71111.18

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)

Main article: IP 71111.19

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)===

Main article: IP 71111.22

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)

Main article: IP 71114.06

The inspectors evaluated an emergency preparedness drill on June 5, 2019.

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) ===

Main article: IP 71151
(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)

Main article: IP 71152

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)

Main article: IP 71153

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)

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

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