IR 05000482/2021011: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
 
Line 30: Line 30:
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.


Sincerely, Nicholas H. Digitally signed by Nicholas H. Taylor Taylor Date: 2021.12.01 14:16:08-06'00'
Sincerely, Nicholas H. Taylor, Chief Engineering Branch 2 Division of Reactor Safety
Nicholas H. Taylor, Chief Engineering Branch 2 Division of Reactor Safety Docket No. 05000482 License No. NPF-42
 
Docket No. 05000482 License No. NPF-42


===Enclosure:===
===Enclosure:===
Line 37: Line 38:


==Inspection Report==
==Inspection Report==
Docket Number: 05000482 License Number: NPF-42 Report Number: 05000482/2021011 Enterprise Identifier: I-2021-011-0029 Licensee: Wolf Creek Nuclear Operating Corporation Facility: Wolf Creek Generating Station Location: Burlington, Kansas Inspection Dates: October 18, 2021 to October 22, 2021 Inspectors: F. Thomas, Reactor Inspector R. Deese, Senior Reactor Analyst Approved By: Nicholas H. Taylor, Chief Engineering Branch 2 Division of Reactor Safety
Docket Number: 05000482
 
License Number: NPF-42
 
Report Number: 05000482/2021011
 
Enterprise Identifier: I-2021-011- 0029
 
Licensee: Wolf Creek Nuclear Operating Corporation
 
Facility: Wolf Creek Generating Station
 
Location: Burlington, Kansas
 
Inspection Dates: October 18, 2021 to October 22, 2021
 
Inspectors: F. Thomas, Reactor Inspector R. Deese, Senior Reactor Analyst
 
Approved By: Nicholas H. Taylor, Chief Engineering Branch 2 Division of Reactor Safety


=SUMMARY=
=SUMMARY=
Line 45: Line 64:


===List of Findings and Violations===
===List of Findings and Violations===
No findings or violations of more than minor significance were identified.
No findings or violations of more than minor significance were identified.


Line 55: Line 73:
Inspections were conducted using the appropriate portions of the Temporary Instruction (TI) in effect at the beginning of the inspection unless otherwise noted. Currently approved Temporary Instructions with their attached revision histories are located on the public website at https://www.nrc.gov/reading-rm/doc-collections/insp-manual/temp-instructions/index.html.
Inspections were conducted using the appropriate portions of the Temporary Instruction (TI) in effect at the beginning of the inspection unless otherwise noted. Currently approved Temporary Instructions with their attached revision histories are located on the public website at https://www.nrc.gov/reading-rm/doc-collections/insp-manual/temp-instructions/index.html.


Samples were declared complete when the TI 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 reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards. Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19),inspectors were directed to begin teleworking. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the TI could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable TI. In some cases, portions of a TI were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the TI.
Samples were declared complete when the TI 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 reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards. Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19),inspectors were directed to begin teleworking. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the TI could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable TI. In some cases, portions of a TI were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the TI.


==OTHER ACTIVITIES==
==OTHER ACTIVITIES==
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 2515/194 - Inspection of the Licensees Implementation of Industry Initiative Associated With The Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012-01)
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
 
2515/194 - Inspection of the Licensees Implementation of Industry Initiative Associated With The Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012- 01)
 
The inspectors reviewed the licensees implementation of Revision 3 to the Nuclear Energy Institute Voluntary Industry Initiative, (ADAMS Accession No. ML19163A176) dated June 6, 2019. This review included the licensee's application of risk screening techniques to determine that the risk associated with an open phase condition (OPC) event is significantly reduced through the implementation of detection circuits and the use of operator manual actions in lieu of automatic trip functions.
The inspectors reviewed the licensees implementation of Revision 3 to the Nuclear Energy Institute Voluntary Industry Initiative, (ADAMS Accession No. ML19163A176) dated June 6, 2019. This review included the licensee's application of risk screening techniques to determine that the risk associated with an open phase condition (OPC) event is significantly reduced through the implementation of detection circuits and the use of operator manual actions in lieu of automatic trip functions.


Sections 03.01.a, Detection, Alarms and General Criteria, and 03.01.b, Protective Actions, were previously inspected and documented in Inspection Report 05000482/2018011 with noted exceptions. Because the licensee has chosen to demonstrate compliance with Revision 3 of the Open Phase Condition Initiative using the Risk Informed Evaluation Method in lieu of the designs automatic protective functions, section 03.01.c, Use of Risk-Informed Evaluation Method is inspected in this report.
Sections 03.01.a, Detection, Alarms and General Criteria, and 03.01.b, Protect ive Actions, were previously inspected and documented in Inspection Report 05000482 /2018011 with noted exceptions. Because the licensee has chosen to demonstrate compliance with Revision 3 of the Open Phase Condition Initiative using the Risk Informed Evaluation Method in lieu of the designs automatic protective functions, section 03.01.c, Use of Risk-Informed Evaluation Method is inspected in this report.
 
Inspection of the Licensees Implementation of Industry Initiative Associated With the Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012- 01) (1 Sample)


Inspection of the Licensees Implementation of Industry Initiative Associated With the Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012-01) (1 Sample)
Wolf Creek Nuclear Operating Corporation selected the open phase detection system designed and manufactured by Power System Sentinel Technologies, LLC (PSSTech) as the design vendor for Wolf Creek Nuclear Operating Corporation. Wolf Creek Nuclear Operating Corporation has chosen to rely on risk-informed operator manual actions to isolate a power supply affected by an OPC in lieu of enabling the open phase isolation systems (OPIS) automatic functions.
Wolf Creek Nuclear Operating Corporation selected the open phase detection system designed and manufactured by Power System Sentinel Technologies, LLC (PSSTech) as the design vendor for Wolf Creek Nuclear Operating Corporation. Wolf Creek Nuclear Operating Corporation has chosen to rely on risk-informed operator manual actions to isolate a power supply affected by an OPC in lieu of enabling the open phase isolation systems (OPIS) automatic functions.


Line 73: Line 97:


==INSPECTION RESULTS==
==INSPECTION RESULTS==
Observation: Temporary Instruction 2515/194-03.01 - Voluntary Industry Initiative 2515/194 Based on discussions with Wolf Creek Generating Station staff, review of design and testing documentation, and walkdowns of installed equipment, the inspectors had reasonable assurance that Wolf Creek Nuclear Operating Corporation is appropriately implementing the voluntary industry initiative at Wolf Creek Generating Station. The inspectors verified the following criteria:
Observation: Temporary Instruction 2515/194-03.01 - Voluntary Industry Initiative 2515/194 Based on discussions with Wolf Creek Generating Station staff, review of design and testing documentation, and walkdowns of installed equipment, the inspectors had reasonable assurance that Wolf Creek Nuclear Operating Corporation is appropriately implementing the voluntary industry initiative at Wolf Creek Generating Station.
Detection, Alarms and General Criteria 1. [03.01(a)(1)] Open phase conditions are detected and alarmed in the control room.


2. [03.01(a)(2)] In scenarios where automatic detection may not be possible due to very low or no-load conditions, or when transformers are in a standby mode, automatic detection will occur as soon as loads are transferred to the standby source.
The inspectors verified the following criteria:
 
Detection, Alarms and General Criteria
 
[03.01(a)(1)] Open phase conditions are detected and alarmed in the control room.
 
[03.01(a)(2)] In scenarios where automatic detection may not be possible due to very low or no-load conditions, or when transformers are in a standby mode, automatic detection will occur as soon as loads are transferred to the standby source.


Additionally, where automatic detection is not reliable, Wolf Creek Nuclear Operating Corporation has established monitoring requirements on a per shift basis, to look for evidence of an open phase condition.
Additionally, where automatic detection is not reliable, Wolf Creek Nuclear Operating Corporation has established monitoring requirements on a per shift basis, to look for evidence of an open phase condition.


3. [03.01(a)(4)] No Class 1E circuits were being replaced with non-Class 1E circuits in this design.
[03.01(a)(4)] No Class 1E circuits were being replaced with non-Class 1E circuits in this design.


4. [03.01(a)(5)] The Final Safety Analysis Report was updated to discuss the design features and analyses related to the effects of any open phase condition design vulnerability.
[03.01(a)(5)] The Final Safety Analysis Report was updated to discuss the design features and analyses related to the effects of any open phase condition design vulnerability.


5. [03.01(a)(6)] The open phase condition detection and alarm components are maintained in accordance with Wolf Creek Nuclear Operating Corporation procedures or maintenance program, and periodic tests, calibrations setpoint verifications or inspections (as applicable) have been established.
[03.01(a)(6)] The open phase condition detection and alarm components are maintained in accordance with Wolf Creek Nuclear Operating Corporation procedures or maintenance program, and periodic tests, calibrations setpoint verifications or inspections (as applicable) have been established.


Use of Risk-Informed Evaluation Method 1. [03.01(c)(1)] The plant configuration matched the changes made to the probabilistic risk assessment model to address an open phase condition, and the logic of the probabilistic risk assessment model changes is sound.
Use of Risk-Informed Evaluation Method


2. [03.01(c)(2)] The procedures which validate that the open phase condition alarm would identify the proper indication to validate the open phase conditions at all possible locations.
[03.01(c)(1)] The plant configuration matched the changes made to the probabilistic risk assessment model to address an open phase condition, and the logic of the probabilistic risk assessment model changes is sound.
 
[03.01(c)(2)] The procedures which validate that the open phase condition alarm would identify the proper indication to validate the open phase conditions at all possible locations.


===3. [03.01(c)(3)] Observations associated with procedure(s) and operator actions required===
===3. [03.01(c)(3)] Observations associated with procedure(s) and operator actions required===
to respond to an open phase condition alarm and potential equipment trip match the Human Reliability
=====Analysis.=====
===4. [03.01(c)(4)] Assumptions listed in the NEI 19-02 Appendix A evaluation and the===
sensitivity analyses listed in Section 5 of the evaluation were verified.
[03.01(c)(5)] Assumptions, procedures, operator actions, and Wolf Creek Nuclear Operating Corporation analyses specified above are consistent with the plant-specific design and licensing basis, including:
a.


to respond to an open phase condition alarm and potential equipment trip match the           Human Reliability
Initiating events considered in the analysis b.


=====Analysis.=====
Boundary conditions specified in Attachment 1 of the NEI Voluntary Industry Initiative, Revision 3 c.


===4. [03.01(c)(4)] Assumptions listed in the NEI 19-02 Appendix A evaluation and the===
Operating procedures for steps taken to recover equipment from the effects of open phase conditions (or use of alternate equipment) was appropriate.


sensitivity analyses listed in Section 5 of the evaluation were verified.
d.


5. [03.01(c)(5)] Assumptions, procedures, operator actions, and Wolf Creek Nuclear Operating Corporation analyses specified above are consistent with the plant-specific design and licensing basis, including:
Where recovery was assumed in the probabilistic risk assessment analysis for tripped electric equipment, restoration of the equipment was based on analyses that demonstrate that automatic isolation trips did not result in equipment damage
a. Initiating events considered in the analysis b. Boundary conditions specified in Attachment 1 of the NEI Voluntary Industry Initiative, Revision 3 c. Operating procedures for steps taken to recover equipment from the effects of open phase conditions (or use of alternate equipment) was appropriate.


d. Where recovery was assumed in the probabilistic risk assessment analysis for tripped electric equipment, restoration of the equipment was based on analyses that demonstrate that automatic isolation trips did not result in equipment damage No findings or exceptions were identified.
No findings or exceptions were identified.


==EXIT MEETINGS AND DEBRIEFS==
==EXIT MEETINGS AND DEBRIEFS==
Line 112: Line 150:
=DOCUMENTS REVIEWED=
=DOCUMENTS REVIEWED=


Inspection Type             Designation   Description or Title                                         Revision or
Inspection Type Designation Description or Title Revision or
Procedure                                                                                               Date
Procedure Date
2515/194   Calculations     XX-E-039       Open Phase Analysis                                         0
2515/194 Calculations XX-E-039 Open Phase Analysis 0
H-11-002-CN003 System MR Protective Relay Settings                         10/23/2018
H-11-002-CN003 System MR Protective Relay Settings 10/23/2018
Corrective Action CR             00107717, 00108350, 00108708, 00108712, 00109066,
Corrective Action CR 00107717, 00108350, 00108708, 00108712, 00109066,
Documents                       00113077, 00113195, 00113853, 00114559, 00114648,
Documents 00113077, 00113195, 00113853, 00114559, 00114648,
00114730, 00115355, 00116834, 00116853, 00119905,
00114730, 00115355, 00116834, 00116853, 00119905,
00119950, 00120741, 00121737, 00123192, 00128627,
00119950, 00120741, 00121737, 00123192, 00128627,
00128907, 00135656, 00141087, 00143192, 10001997,
00128907, 00135656, 00141087, 00143192, 10001997,
10002131, 10002761, 10006086
10002131, 10002761, 10006086
Drawings         E-11005A       Emergency Diesel Generator Loading Data                     17
Drawings E-11005A Emergency Diesel Generator Loading Data 17
KD-7496       One Line Diagram                                             67
KD-7496 One Line Diagram 67
SK7458_DC06   Wolf Creek 345kV Substation No. 7 Transformer Primary       6
SK7458_DC06 Wolf Creek 345kV Substation No. 7 Transformer Primary 6
Diff. [Differential] Relaying
Diff. [Differential] Relaying
SK7458_DC07   Wolf Creek 345kV Substation No. 7 Transformer Secondary     6
SK7458_DC07 Wolf Creek 345kV Substation No. 7 Transformer Secondary 6
Diff. [Differential] Relaying
Diff. [Differential] Relaying
WIP-E-022-     Startup Transformer Protection, Control Panel Wiring         00
WIP-E-022-Startup Transformer Protection, Control Panel Wiring 00
00039-008-A-1
00039-008-A-1
WIP-E-12MR01- Startup Transformer Protection Logic Diagram                 00
WIP-E-12MR01-Startup Transformer Protection Logic Diagram 00
001-A-1
001-A-1
WIP-E-13MR12- Schematic Diagram 13.8KV Non-Class 1E Power System           00
WIP-E-13MR12-Schematic Diagram 13.8KV Non-Class 1E Power System 00
2-A-1       Start-Up XFMR [Transformer] XMR01 Alarming
2-A-1 Start-Up XFMR [Transformer] XMR01 Alarming
7458-B-5116   Wolf Creek Substation 345KV General Alarm Interface         4
7458-B-5116 Wolf Creek Substation 345KV General Alarm Interface 4
Elementary Diagram
Elementary Diagram
7458-D-7052   Wolf Creek Substation Annunciator Panel (No. 16)             10
7458-D-7052 Wolf Creek Substation Annunciator Panel (No. 16) 10
Connection Diagram
Connection Diagram
7458-D-7505   Wolf Creek Substation Terminal Board Cabinet No. 4           33
7458-D-7505 Wolf Creek Substation Terminal Board Cabinet No. 4 33
Connection Diagram
Connection Diagram
Miscellaneous     LO1506201     Lesson Plan, Site Electrical Distribution - Initial Licensed 004
Miscellaneous LO1506201 Lesson Plan, Site Electrical Distribution - Initial Licensed 004
Operator
Operator
LO1732435     Lesson Plan, OFN AF-025, Unit Limitations - Initial Licensed 019
LO1732435 Lesson Plan, OFN AF-025, Unit Limitations - Initial Licensed 019
Operator
Operator
Inspection Type             Designation       Description or Title                                     Revision or
 
Procedure                                                                                             Date
Inspection Type Designation Description or Title Revision or
LTR-RAM-20-15     Transmittal of the Final Plant Response to an Open Phase 0
Procedure Date
LTR-RAM-20-15 Transmittal of the Final Plant Response to an Open Phase 0
Condition (OPC) Package
Condition (OPC) Package
OP8206201         Switchyard ALR [Alarm] Response Seminar                 000
OP8206201 Switchyard ALR [Alarm] Response Seminar 000
PCR               74224                                                   10/20/2021
PCR 74224 10/20/2021
WCGS [Wolf       Transformer 7 OPD [Open Phase Detection] Interim Alarm   0
WCGS [Wolf Transformer 7 OPD [Open Phase Detection] Interim Alarm 0
Creek Generating Response
Creek Generating Response
Station] Standing
Station] Standing
Order 40
Order 40
89639             Scheduled Offering Roster - Switchyard ALR Response     01/16/2018
89639 Scheduled Offering Roster - Switchyard ALR Response 01/16/2018
Seminar
Seminar
Procedures       AI 23O-001       Functional Importance Determination                     7A
Procedures AI 23O-001 Functional Importance Determination 7A
ALR 00-14D       S/U [Start-Up] XFMR [Transformer] Trouble               14
ALR 00-14D S/U [Start-Up] XFMR [Transformer] Trouble 14
ALR 810           Startup XFMR XMR01                                       9
ALR 810 Startup XFMR XMR01 9
ALR 843           #7 Transformer Open Phase Detection Trouble             1
ALR 843 #7 Transformer Open Phase Detection Trouble 1
OFN AF-025       Unit Limitations                                         57
OFN AF-025 Unit Limitations 57
SYS NB-200       Transferring XNB01 Supply Between SL7 and #7             21
SYS NB-200 Transferring XNB01 Supply Between SL7 and #7 21
Transformer
Transformer
Self-Assessments PSA-20-002       Documentation of Vendor Provided Open Phase Condition   0
Self-Assessments PSA-20-002 Documentation of Vendor Provided Open Phase Condition 0
Evaluation
Evaluation
QH-2021-2143     Wolf Creek Installed Open Phase Detection System (OPDS) 02/15/2021
QH-2021-2143 Wolf Creek Installed Open Phase Detection System (OPDS) 02/15/2021
Assessment Report
Assessment Report
Work Orders                       13-378853-056, 15-403881-007, 20-457953-000
Work Orders 13-378853-056, 15-403881-007, 20-457953-000
 
8
8
}}
}}

Latest revision as of 04:16, 19 November 2024

Temporary Instruction 2515/194 Report 05000482/2021011
ML21326A296
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 12/01/2021
From: Nick Taylor
NRC/RGN-IV/DRS/EB-2
To: Reasoner C
Wolf Creek
References
IR 2021011
Download: ML21326A296 (9)
v • d • e


Text

December 01, 2021

SUBJECT:

WOLF CREEK GENERATING STATION - TEMPORARY INSTRUCTION 2515/194 REPORT 05000482/2021011

Dear Mr. Reasoner:

On October 21, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Nuclear Operating Corporation. On October 21, 2021, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Nicholas H. Taylor, Chief Engineering Branch 2 Division of Reactor Safety

Docket No. 05000482 License No. NPF-42

Enclosure:

As stated

Inspection Report

Docket Number: 05000482

License Number: NPF-42

Report Number: 05000482/2021011

Enterprise Identifier: I-2021-011- 0029

Licensee: Wolf Creek Nuclear Operating Corporation

Facility: Wolf Creek Generating Station

Location: Burlington, Kansas

Inspection Dates: October 18, 2021 to October 22, 2021

Inspectors: F. Thomas, Reactor Inspector R. Deese, Senior Reactor Analyst

Approved By: Nicholas H. Taylor, Chief Engineering Branch 2 Division of Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Temporary Instruction 2515/194 at Wolf Creek Generating Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors.

Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the Temporary Instruction (TI) in effect at the beginning of the inspection unless otherwise noted. Currently approved Temporary Instructions with their attached revision histories are located on the public website at https://www.nrc.gov/reading-rm/doc-collections/insp-manual/temp-instructions/index.html.

Samples were declared complete when the TI 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 reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards. Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19),inspectors were directed to begin teleworking. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the TI could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable TI. In some cases, portions of a TI were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the TI.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

2515/194 - Inspection of the Licensees Implementation of Industry Initiative Associated With The Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012- 01)

The inspectors reviewed the licensees implementation of Revision 3 to the Nuclear Energy Institute Voluntary Industry Initiative, (ADAMS Accession No. ML19163A176) dated June 6, 2019. This review included the licensee's application of risk screening techniques to determine that the risk associated with an open phase condition (OPC) event is significantly reduced through the implementation of detection circuits and the use of operator manual actions in lieu of automatic trip functions.

Sections 03.01.a, Detection, Alarms and General Criteria, and 03.01.b, Protect ive Actions, were previously inspected and documented in Inspection Report 05000482 /2018011 with noted exceptions. Because the licensee has chosen to demonstrate compliance with Revision 3 of the Open Phase Condition Initiative using the Risk Informed Evaluation Method in lieu of the designs automatic protective functions, section 03.01.c, Use of Risk-Informed Evaluation Method is inspected in this report.

Inspection of the Licensees Implementation of Industry Initiative Associated With the Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012- 01) (1 Sample)

Wolf Creek Nuclear Operating Corporation selected the open phase detection system designed and manufactured by Power System Sentinel Technologies, LLC (PSSTech) as the design vendor for Wolf Creek Nuclear Operating Corporation. Wolf Creek Nuclear Operating Corporation has chosen to rely on risk-informed operator manual actions to isolate a power supply affected by an OPC in lieu of enabling the open phase isolation systems (OPIS) automatic functions.

At the end of this inspection the OPIS system was monitoring and would initiate audible and visual alarms in the control room if a loss of phase condition is detected.

One offsite circuit consists of the #7 transformer feeding the ESF transformer XNB01, which, in turn powers the safety-related bus NB01. Transformer XNB01 may also be powered from the SL-7 supply. Another offsite circuit consists of the startup transformer (XMR01), which feeds ESF transformer XNB02, that provides power to the other safety-related bus, NB02. The licensees open phase condition design solution added redundant PSSTech systems to the start-up transformer XMR01 and to the #7 transformer.

Based on discussions with Wolf Creek Nuclear Operating Corporation staff, review of design and testing documentation, and walkdowns of installed equipment, the inspectors had reasonable assurance that Wolf Creek Nuclear Operating Corporation is appropriately implementing the voluntary industry initiative at Wolf Creek Generating Station.

INSPECTION RESULTS

Observation: Temporary Instruction 2515/194-03.01 - Voluntary Industry Initiative 2515/194 Based on discussions with Wolf Creek Generating Station staff, review of design and testing documentation, and walkdowns of installed equipment, the inspectors had reasonable assurance that Wolf Creek Nuclear Operating Corporation is appropriately implementing the voluntary industry initiative at Wolf Creek Generating Station.

The inspectors verified the following criteria:

Detection, Alarms and General Criteria

[03.01(a)(1)] Open phase conditions are detected and alarmed in the control room.

[03.01(a)(2)] In scenarios where automatic detection may not be possible due to very low or no-load conditions, or when transformers are in a standby mode, automatic detection will occur as soon as loads are transferred to the standby source.

Additionally, where automatic detection is not reliable, Wolf Creek Nuclear Operating Corporation has established monitoring requirements on a per shift basis, to look for evidence of an open phase condition.

[03.01(a)(4)] No Class 1E circuits were being replaced with non-Class 1E circuits in this design.

[03.01(a)(5)] The Final Safety Analysis Report was updated to discuss the design features and analyses related to the effects of any open phase condition design vulnerability.

[03.01(a)(6)] The open phase condition detection and alarm components are maintained in accordance with Wolf Creek Nuclear Operating Corporation procedures or maintenance program, and periodic tests, calibrations setpoint verifications or inspections (as applicable) have been established.

Use of Risk-Informed Evaluation Method

[03.01(c)(1)] The plant configuration matched the changes made to the probabilistic risk assessment model to address an open phase condition, and the logic of the probabilistic risk assessment model changes is sound.

[03.01(c)(2)] The procedures which validate that the open phase condition alarm would identify the proper indication to validate the open phase conditions at all possible locations.

3. [03.01(c)(3)] Observations associated with procedure(s) and operator actions required

to respond to an open phase condition alarm and potential equipment trip match the Human Reliability

Analysis.

4. [03.01(c)(4)] Assumptions listed in the NEI 19-02 Appendix A evaluation and the

sensitivity analyses listed in Section 5 of the evaluation were verified.

[03.01(c)(5)] Assumptions, procedures, operator actions, and Wolf Creek Nuclear Operating Corporation analyses specified above are consistent with the plant-specific design and licensing basis, including:

a.

Initiating events considered in the analysis b.

Boundary conditions specified in Attachment 1 of the NEI Voluntary Industry Initiative, Revision 3 c.

Operating procedures for steps taken to recover equipment from the effects of open phase conditions (or use of alternate equipment) was appropriate.

d.

Where recovery was assumed in the probabilistic risk assessment analysis for tripped electric equipment, restoration of the equipment was based on analyses that demonstrate that automatic isolation trips did not result in equipment damage

No findings or exceptions were identified.

EXIT MEETINGS AND DEBRIEFS

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

On October 21, 2021, the inspectors presented the integrated inspection results to Mr. C. Reasoner, Sr. Vice President and Chief Nuclear Officer, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

2515/194 Calculations XX-E-039 Open Phase Analysis 0

H-11-002-CN003 System MR Protective Relay Settings 10/23/2018

Corrective Action CR 00107717, 00108350, 00108708, 00108712, 00109066,

Documents 00113077, 00113195, 00113853, 00114559, 00114648,

00114730, 00115355, 00116834, 00116853, 00119905,

00119950, 00120741, 00121737, 00123192, 00128627,

00128907, 00135656, 00141087, 00143192, 10001997,

10002131, 10002761, 10006086

Drawings E-11005A Emergency Diesel Generator Loading Data 17

KD-7496 One Line Diagram 67

SK7458_DC06 Wolf Creek 345kV Substation No. 7 Transformer Primary 6

Diff. [Differential] Relaying

SK7458_DC07 Wolf Creek 345kV Substation No. 7 Transformer Secondary 6

Diff. [Differential] Relaying

WIP-E-022-Startup Transformer Protection, Control Panel Wiring 00

00039-008-A-1

WIP-E-12MR01-Startup Transformer Protection Logic Diagram 00

001-A-1

WIP-E-13MR12-Schematic Diagram 13.8KV Non-Class 1E Power System 00

2-A-1 Start-Up XFMR [Transformer] XMR01 Alarming

7458-B-5116 Wolf Creek Substation 345KV General Alarm Interface 4

Elementary Diagram

7458-D-7052 Wolf Creek Substation Annunciator Panel (No. 16) 10

Connection Diagram

7458-D-7505 Wolf Creek Substation Terminal Board Cabinet No. 4 33

Connection Diagram

Miscellaneous LO1506201 Lesson Plan, Site Electrical Distribution - Initial Licensed 004

Operator

LO1732435 Lesson Plan, OFN AF-025, Unit Limitations - Initial Licensed 019

Operator

Inspection Type Designation Description or Title Revision or

Procedure Date

LTR-RAM-20-15 Transmittal of the Final Plant Response to an Open Phase 0

Condition (OPC) Package

OP8206201 Switchyard ALR [Alarm] Response Seminar 000

PCR 74224 10/20/2021

WCGS [Wolf Transformer 7 OPD [Open Phase Detection] Interim Alarm 0

Creek Generating Response

Station] Standing

Order 40

89639 Scheduled Offering Roster - Switchyard ALR Response 01/16/2018

Seminar

Procedures AI 23O-001 Functional Importance Determination 7A

ALR 00-14D S/U [Start-Up] XFMR [Transformer] Trouble 14

ALR 810 Startup XFMR XMR01 9

ALR 843 #7 Transformer Open Phase Detection Trouble 1

OFN AF-025 Unit Limitations 57

SYS NB-200 Transferring XNB01 Supply Between SL7 and #7 21

Transformer

Self-Assessments PSA-20-002 Documentation of Vendor Provided Open Phase Condition 0

Evaluation

QH-2021-2143 Wolf Creek Installed Open Phase Detection System (OPDS) 02/15/2021

Assessment Report

Work Orders 13-378853-056, 15-403881-007, 20-457953-000

8

Retrieved from "https://kanterella.com/w/index.php?title=IR_05000482/2021011&oldid=3741147"