IR 05000482/2024001
| ML24107A888 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/17/2024 |
| From: | Greg Werner NRC/RGN-IV/DORS/PBB |
| To: | Reasoner C Wolf Creek |
| References | |
| IR 2024001 | |
| Download: ML24107A888 (33) | |
Text
April 17, 2024
SUBJECT:
WOLF CREEK GENERATING STATION - INTEGRATED INSPECTION REPORT 05000482/2024001
Dear Cleve Reasoner:
On March 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station. On April 4, 2024, the NRC inspectors discussed the results of this inspection with R. Bayer, General Manager, Plant Operations, and other members of your staff. The results of this inspection are documented in the enclosed report.
Two findings of very low safety significance (Green) are documented in this report. Both of these findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs) consistent with section 2.3.2 of the Enforcement Policy.
If you contest the violations or the significance or severity of the violations 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 Wolf Creek Generating Station.
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 Wolf Creek Generating Station.
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, Gregory E. Werner, Chief Reactor Projects Branch B Division of Operating Reactor Safety Docket No. 05000482 License No. NPF-42
Enclosure:
As stated
Inspection Report
Docket Number:
05000482
License Number:
Report Number:
Enterprise Identifier:
I-2024-001-0010
Licensee:
Wolf Creek Nuclear Operating Corp.
Facility:
Wolf Creek Generating Station
Location:
Burlington, KS
Inspection Dates:
January 1 to March 31, 2024
Inspectors:
C. Henderson, Senior Resident Inspector
R. Kopriva, Senior Project Engineer
J. Melfi, Project Engineer
D. Proulx, Senior Project Engineer
Approved By:
Gregory E. Werner, Chief
Reactor Projects Branch B
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection 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
Failure to Maintain Surveillance Testing Procedure in Accordance with the Fire Protection Program Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000482/2024001-01 Open/Closed None (NPP)71111.24 The inspectors identified a Green finding and associated non-cited violation of Technical Specification 5.4.1.d, for the licensees failure to maintain a fire protection program procedure.
Specifically, the licensee failed to maintain procedure STN RP-002H, Essential Service Water Train B to Component Cooling Water Heat Exchanger B Isolation Switch, revision 2, to perform the required 18-month post-fire safe shutdown normal/bypass (isolation) switch surveillance testing for train B essential service water from component cooling water heat exchanger isolation valve, EFHV0060.
Failure to Perform Post-Maintenance Testing Following Maintenance and Installation of the Bypass Reactor Trip Breaker Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000482/2024001-02 Open/Closed
[H.5] - Work Management 71111.24 The inspectors identified a Green finding and associated non-cited violation of Technical Specification 5.4.1.a for the licensee failure to perform appropriate post-maintenance testing following reactor trip breaker maintenance and installation to verify full technical specification operability.
Additional Tracking Items
None.
PLANT STATUS
Wolf Creek Generating Station began the inspection period at full power. On March 24, 2024, the unit commenced power coast down. On March 28, 2024, the unit was shut down to begin refueling outage (RF)
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 activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed onsite portions of IPs. 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 03.02) (1 Sample)
(1)winter weather advisory with wind gusts of approximately 45 mph and extreme cold weather temperatures on January 16, 2024
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)operator action to isolate a faulted steam generator on February 8, 2024 (2)reactor protection system and anticipated transient without scram actions on February 15, 2024 (3)turbine-driven auxiliary feedwater pump and motor-driven auxiliary feedwater pump A to steam generator D on February 28, 2024 (4)train B class 1E recirculation system for planned maintenance of train A class 1E air conditioning system on March 12, 2024
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the 480 volt AC distribution system on March 14, 2024.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
(1)missed 18-month fire protection surveillance for the isolation/bypass switch for train B essential service water from component cooling water heat exchanger isolation valve, fire area C-27, on January 16, 2024 (2)diesel-driven fire pump area, fire area circulating water screen house, on January 31, 2024 (3)auxiliary building, 2026-foot elevation, fire area A-16, on February 2, 2024 (4)auxiliary feedwater valve compartment number one, fire area A-29, on February 9, 2024 (5)auxiliary panel shutdown room, fire area A-28, on February 14, 2024 (6)reactor protection system motor generator set room, fire area A-27, on February 28, 2024
Fire Brigade Drill Performance Sample (IP Section 03.02) (2 Samples)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill turbine building north 2032-foot elevation, 480 volt motor control center PG-015 on February 14, 2024.
- (2) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill auxiliary building elevation 2026-foot, south electrical penetration room 480 volt load center XPG22 on March 8, 2024.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections for a feedwater line break inside containment, main steam enclosure, and turbine building on February 15, 2024.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during end of core life moderator temperature coefficient measurement and plant shut down for RF 26 on March 28, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated just-in-time training for plant shutdown for RF 26 on March 18, 2024.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)480 volt distribution system maintenance and testing on February 21, 2024 (2)reactor protection system and anticipated transient without scram actions maintenance and testing on February 28, 2024
Quality Control (IP Section 03.02) (1 Sample)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:
(1)class 1E motor-operated valve thermal overload maintenance and testing on March 4, 2024
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (9 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
(1)train A safety injection equipment outage January 11, 2024 (2)emergency diesel generator B and train B essential service water equipment outage on January 23, 2024 (3)train B motor-driven feedwater equipment outage on January 29, 2024 (4)circulating water bay C diving activities and unavailability for the diesel and motor-driven fire protection pumps on January 31, 2024 (5)train A essential service water system equipment outage and emergency diesel generator A in maintenance lockout on February 6, 2024 (6)emergency work activities of unplanned nitrogen and instrument air leak for steam generator A atmospheric relief valve and turbine-driven auxiliary feedwater flow control valve accumulator on March 10, 2024 (7)train A class 1E air conditioning system and residual heat removal equipment outage on March 13, 2024 (8)emergent work activities for troubleshooting of a step change in nitrogen leakage for the steam generator D atmospheric relief valve and turbine-driven auxiliary feedwater flow control valve accumulator on March 14, 2024 (9)emergent work activities for emergency diesel generator B failure to manual start on March 29, 2024.
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)chemical and volume control valve to safety injection pump A valve, EMHV8924, closed with safety injection pump A unavailable and 100 percent emergency core cooling system flow equivalent from both trains operability determination on January 17, 2024 (2)train B class 1E air conditioning system, SGK05B, tripped on high pressure discharge past operability determination on January 22, 2024 (3)feedwater line D flow accelerated corrosion design pressure requirement operability determination on February 6, 2024 (4)failure to isolate a faulted steam generator with a single failure of the remotely operated valve operability determination on February 27, 2024 (5)emergency diesel generator B governor control load decrease while increasing load during surveillance testing operability determination on February 27, 2024
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
(1)large break loss of coolant accident dose analysis re-evaluation on February 6, 2024 (2)steam generator A atmospheric relief valve gauge block removal on March 13, 2024
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors evaluated RF 26 activities from March 28 - 31, 2024. The inspectors completed inspection procedure sections 03.01.a and 03.01.b.
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (8 Samples)
(1)containment cooler D 480 volt breaker fast and slow speed mechanical interlock replacement post-maintenance testing on January 3, 2024 (2)train A containment spray system room cooler belt replacement on January 25, 2024 (3)train A swing inverter, NN15, post-maintenance testing on January 25, 2024 (4)train B essential service water travelling screen post-maintenance testing on January 25, 2024 (5)emergency diesel generator B post-maintenance testing on February 20, 2024 (6)turbine-driven auxiliary feedwater equipment outage post-maintenance testing on February 21, 2024 (7)train B essential service water travel screen motor-operated valve, EFHV0092, corrective and preventative maintenance post-maintenance testing on February 29, 2024 (8)emergent repairs for steam generator A atmospheric relief valve on March 13, 2024
Surveillance Testing (IP Section 03.01) (3 Samples)
(1)train B essential service water motor-operated valve fire protection isolation switch surveillance testing on January 5, 2024 (2)inservice testing requirements for auxiliary feedwater discharge isolation valves ALV032, ALV047, ALV044, ALV035, ALV056, ALV066, ALV071, and ALV061 on February 9, 2024 (3)reactor trip and bypass breaker response time testing and maintenance on February 27, 2024
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)turbine-driven auxiliary feedwater discharge to steam generator air operated valve, ALHV0006, on February 27, 2024
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
(1)simulated reactor coolant pump A shaft shear and failure of automatic reactor trip and manual trip from the control room on January 31,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) January 1, 2023, through December 31, 2023 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (1 Sample)
- (1) January 1, 2023, through December 31, 2023
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
- (1) January 1, 2023, through December 31, 2023
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)failure to perform essential service water motor-operated valve 18-month isolation/bypass surveillance extent of condition (2)failure to perform adequate reactor trip breaker work planning, and post-maintenance testing
INSPECTION RESULTS
Failure to Maintain Surveillance Testing Procedure in Accordance with the Fire Protection Program Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000482/2024001-01 Open/Closed None (NPP)71111.24 The inspectors identified a Green finding and associated non-cited violation of Technical Specification 5.4.1.d, for the licensees failure to maintain a fire protection program procedure. Specifically, the licensee failed to maintain procedure STN RP-002H, Essential Service Water Train B to Component Cooling Water Heat Exchanger B Isolation Switch, revision 2, to perform the required 18-month post-fire safe shutdown normal/bypass (isolation) switch surveillance testing for train B essential service water from component cooling water heat exchanger isolation valve, EFHV0060.
Description:
The inspectors reviewed the licensees Updated Safety Analysis Report (USAR),off normal procedures, and surveillance procedures for the normal/bypass (isolation) switches for the train B essential service water system motor-operated valves that are credited for post-fire safe shutdown to determine the required surveillance testing. Specifically, the inspectors reviewed three off normal procedures including: procedure OFN RP-017, Control Room Evacuation, revision 56; procedure AP 10-100, Fire Protection Program, revision 26; and procedure STN RP-002H, Essential Service Water Train B to Component Cooling Water Heat Exchanger B Isolation Switch, revision 2, and identified the following:
- Procedure AP 10-100, step 6.3.12.3, stated, in part that all STN RP-002 series of procedures are performed at least once per 18-months to verify the operability of normal/bypass (isolation) switches credited for post-fire safe shutdown that are used to bypass circuits that could be affected by a fire.
- Off normal procedure OFN RP-017 was used to determine the operability of credited post-fire safe shutdown B essential service water motor-operated valves that are operated by normal/bypass (isolation) switches located at the 480 volt motor control centers, which included train B essential service water from component cooling water heat exchanger motor-operated isolation valve, EFHV0060. The required position of EFHV0060 for post-fire safe shutdown was maintain/close to ensure adequate essential service water flow to all train B components required for post-fire safe shutdown.
- Procedure STN RP-002H was utilized to verify the operability of train B essential service water to and from the component cooling water heat exchanger B. However, EFHV0060 isolation switch, that was used to bypass circuits that could be affected by a fire in the control room, was not being testing every 18 months.
From the above, the inspectors determined that the licensee failed to perform the 18-month surveillance testing to verify the operability of the normal/bypass (isolation) switch credited for postfire safe shutdown for valve EFHV0060 in accordance with procedure AP 10-100, step 6.3.12.3. The inspectors informed the licensee of the issue. The licensee then entered it into their corrective action program as condition report 10029354. The licensee confirmed valve EFHV0060 normal/bypass (isolation) switch was not being testing every 18 months and was last tested March 2014. Valve EFHV0060 normal/bypass (isolation) switch was installed in 2013 at its 480 volt motor control center in accordance with change package 13898, and the licensee failed to identify that procedure STN PR-002H was required to be updated to ensure valve EFHV0060 normal/bypass (isolation) switch was tested every 18 months.
Corrective Action: The licensee performed an extent of condition review, established an hourly fire watch for the control room, and revised procedure STN RP-002H to perform 18-month surveillance testing for valve EFHV0060 normal/bypass (isolation) switch during RF 26.
Corrective Action Reference: Condition reports 10029354 and 10031492
Performance Assessment:
Performance Deficiency: The licensees failure to maintain procedure STN RP-002H to perform required fire protection program 18-month isolation/bypass surveillance testing for valve EFHV0060 normal/bypass (isolation) switch, was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the procedural quality attribute of the Mitigating Systems Cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, the licensees failure to maintain procedural guidance to perform required 18-month isolation/bypass surveillance testing for valve EFHV0060 normal/bypass (isolation) switch prevented the licensee from verifying the valve was capable of being/maintained closed from the motor control center in a case of a fire in the control room.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix F, Fire Protection Significance Determination Process. The inspectors assigned the finding a fire category 1.4.7, because the finding involved post-fire safe shutdown. The inspectors determined that the finding had very low safety significance (Green) because the finding did not adversely affect the ability to reach and maintain hot shutdown/hot standby or safe and stable conditions using the credited safe shutdown success path.
Cross-cutting Aspect: Not present performance. Specifically, the performance deficiency occurred in 2013 when the licensee modified the motor control center for EFHV0060 to provide the isolation/bypass circuit to allow for local operation and failed to update procedure STN RP-002H.
Enforcement:
Violation: Technical Specification 5.4.1.d requires that written procedures shall be established, implemented, and maintained covering fire protection program implementation.
Procedure STN RP-002H, Essential Service Water Train B to Component Cooling Water Heat Exchanger B Isolation Switch, revision 2, verified the operability of train B essential service water motor-operated valves for the component cooling water heat exchanger B isolation switch used to bypass circuits that could be affected by a fire.
Contrary to the above, from March 2014 to January 2024, the licensee failed to maintain a procedure covering the fire protection program implementation. Specifically, the licensee failed to maintain procedure STN RP-002H to perform the required 18-month isolation/bypass switch surveillance testing for train B essential service water from component cooling water heat exchanger isolation valve, EFHV0060.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with section2.3.2 of the Enforcement Policy.
Failure to Perform Post-Maintenance Testing Following Maintenance and Installation of the Bypass Reactor Trip Breaker Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000482/2024001-02 Open/Closed
[H.5] - Work Management 71111.24 The inspectors identified a Green finding and associated non-cited violation of Technical Specification 5.4.1.a for the licensee failure to perform appropriate post-maintenance testing following reactor trip breaker maintenance and installation to verify full technical specification operability.
Description:
On August 18, 2020, while the plant was in Mode 1, in accordance with work order (WO) 18-444075-000, the licensee installed a vendor overhauled reactor trip breaker as train B reactor trip bypass breaker (BYB), and during RF 24 (March 25 - May 9, 2021) the breaker was moved to train A reactor trip breaker (RTA) in accordance with WO 20-459184-000. Following being placed in the RTA position, on April 28, 2021, the breaker failed surveillance procedure STS IC-215, Trip Actuating Device Operational Test, Trip and Bypass Breaker UV/Shunt Trip, Turbine Trip on Reactor Trip and P4, revision 17. Specifically, the reactor trip breaker failed to generate the turbine trip signal associated with the P-4 interlock upon a reactor trip, because the interlock was not wired into the circuit when the breaker was overhauled. Additionally, surveillance procedure STS IC-215 can only be performed in Modes 4, 5, 6, and defueled. The licensee corrected this deficiency during RF 24 and initiated condition reports (CR) 10004991 and 10005013 and performed a past operability review and equipment performance evaluation.
The inspectors reviewed WO 18-444075-000, WO 20-259184-000, CR 10004991, CR 10005013, the past operability and equipment performance evaluation, technical specifications and identified the following:
- The reactor trip P-4 interlock requirements to meet Technical Specification 3.3.2, Engineering Safety Feature Actuation System (ESFAS) Instrumentation, limited condition of operation (LCO) F are two operable trains of reactor trip P-4 interlock. The functions of the reactor trip P-4 interlock was to prevent excessive cool down of the reactor coolant system following a reactor trip and the following was required to meet the LCO:
- (1) trip the main turbine - Modes 1 and 2,
- (2) isolate main feedwater with coincident low reactor coolant average temperature - Modes 1 and 2,
- (3) allows manual block of the automatic re-actuation of safety injection after a manual reset of safety injection - Modes 1, 2, and 3,
- (4) prevents opening of the main feedwater isolation valves if closed on safety injection and steam generator water level high-high - Modes 1, 2, and 3.
- The equipment performance evaluation and the past operability determined the turbine trip did not function because two wires connecting the trip contact, as seen on drawing M-766-01045, to the test points and TB4 terminals 1 and 4, as seen on drawing M-766-1043, were not installed during the breakers overhaul performed by a vendor. This issue was identified during the performance of surveillance procedure STS IC-215 The function of the trip contact was to produce a turbine trip signal from the P-4 interlock upon a reactor trip breaker opening. Additionally, between August 18, 2020, and RF 24, BYB was racked to connect for testing of RTB on October 10, 2020, and February 4, 2021, for approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the 48-hour completion time for LCO 3.3.2 condition F in support of train B reactor trip breaker quarterly testing.
During these periods, if a reactor trip occurred by BYB, no turbine trip signal would have been generated from the P-4 interlock, however, RTA was fully capable of generating the required turbine trip, so no complete loss of safety function occurred.
The equipment performance evaluation and past operability documented in CRs 10004991 and 10005013 did not review the maintenance practice of installing and performing maintenance on reactor trip breakers in Mode 1, nor did it contain corrective actions associated with the maintenance practice.
- The installation WO 18-445075-000 stated to perform maintenance on the spare reactor trip breaker in accordance with maintenance procedure MPE M766Q-03, Reactor Trip Switchgear Breaker, revision 24, and perform as found and as left testing in accordance with surveillance procedure STS IC-746, Reactor Trip and Bypass Breaker Response Time Testing, revision 2C. The purpose of surveillance procedure STS IC-746 was to perform response time testing on train A and B reactor trip breakers and bypass reactor trip breakers which does not test all the technical specification design functions, including the reactor trip P-4 interlocks.
The inspectors concluded the licensee did not properly pre-plan maintenance and installation of overhauled reactor trip breakers in Mode 1 to ensure adequate post-maintenance testing was performed to demonstrate full technical specification operability.
Corrective Actions: The licensee initiated actions to review what modes of operation are appropriate for performing maintenance, installation, and testing of reactor trip breakers.
Corrective Action References: Condition reports 10031001 and 10031493
Performance Assessment:
Performance Deficiency: The licensees failure to perform appropriate post-maintenance testing following reactor trip breaker maintenance and installation to verify full technical specification operability was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the equipment performance attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Specifically, failure to perform the appropriate post-maintenance testing prevented the licensee from identifying the train B bypass reactor trip breaker P-4 interlock was inoperable.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The finding was determined to be of very low safety significance (Green) because it
- (1) was not a deficiency affecting design or qualification of a mitigating system,
- (2) does not represent a loss of the probability risk analysis (PRA) function of a single train technical specification system for greater than allowed outage time,
- (3) does not represent a loss of PRA function of one train of a multi-train technical specification for greater than its allowed outage time, (4)does not represent a loss of the PRA function of two separate technical specification systems for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- (5) does not represent a loss of PRA system and/or function as defined by the plant risk information e-book or licensees PRA for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
- (6) does not result in the loss of a high safety-significant, nontechnical specification train for greater than 3 days.
Cross-Cutting Aspect: H.5 - Work Management: The organization implements a process of planning, controlling, and executing work activities such that nuclear safety is the overriding priority. The work process includes the identification and management of risk commensurate to the work and the need for coordination with different groups or job activities. Specifically, inappropriately planning the installation of vendor overhauled reactor trip breakers in Mode 1 prevented the licensee from performing adequate post-maintenance testing to verify proper operation of the reactor trip breaker in the bypass location to ensure it was fully operable.
Enforcement:
Violation: Technical Specification 5.4.1.a, requires, in part, that written procedures be established, implemented, and maintained covering applicable procedures recommended in appendix A to Regulatory Guide 1.33, Quality Assurance Program Requirements, revision 2, dated February 1978. Regulatory Guide 1.33, appendix A, section 9.a, requires, in part, 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. Work order 18-445075-000 pre-planned the maintenance and installation of reactor trip bypass breaker B.
Contrary to the above, between August 2020 to March 2021, the licensee failed to properly pre-plan and perform maintenance that affected safety-related equipment. Specifically, WO 18-445075-000 failed to provide appropriate instructions for safety-related bypass reactor trip breaker post-maintenance testing following maintenance and installation to verify the breaker was fully operable, by testing the technical specification required P-4 interlock.
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 April 4, 2024, the inspectors presented the integrated inspection results to R. Bayer, General Manager, Plant Operations, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Condition Reports
10029393, 10029523, 10029546
Drawings
M-12BN01
Piping and Instrumentation Diagram Borated Refueling
Water Storage Tank
Drawings
M-12EC02
Piping and Instrumentation Diagram Fuel Pool Cooling and
Clean-Up System
Procedures
AI 14-006
Severe Weather
Procedures
ALR 00-055F
FRZ Prot Trouble
Procedures
Spent Fuel Pool Boron Concentration Determination
9A
Procedures
SYS EC-121
Recirc of the RWST Through the Fuel Pool Cleanup System
Procedures
SYS EF-205
ESW/CIRC Water Cold Weather Operations
Work Orders
Calculations
XX-E-004
AC Motor Operated Valve Minimum Terminal Voltage
Calculations
XX-E-009
System NB, NG, PG Undervoltage/Degraded Voltage Relay
Setpoints
Corrective Action
Documents
Condition Reports
10009424, 10028903, 10028925
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10030450
Drawings
E-018-0852
MMC Cubicles SZ 5 2SP-1WD Schematic
W12
Drawings
E-018-0853
Wiring Diagram 2SP IWD (Size 5)
W12
Drawings
E-11NG01
Low Voltage System Class 1E 480V Single Line Meter and
Relay Diagram
Drawings
E-11NG02
Low Voltage System Class 1E 480 V. Single Line Meter and
Relay Diagram
Drawings
E-11NG20
Low Voltage System Class 1E Motor Control Center
Summary
318
Drawings
E-13EF09A
Schematic Diagram ESW To/From Containment Air Coolers
Isolation Valve
Drawings
E-13GN02A
Schematic Diagrams Containment Cooler B and D
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
E-13NG01A
Low Voltage System Class 1E 480 V Three Line Meter and
Relay Diagram
Drawings
E-1F9915
Design Basis Document for OFN RP-017, Control Room
Evacuation
Drawings
KD-7496
One Line Diagram
Drawings
M-12AB01
Piping and Instrumentation Diagram Main Steam System
Drawings
M-12AB02
Piping and Instrumentation Diagram Main Steam System
Drawings
M-12AE02
Piping and Instrumentation Diagram Feedwater System
Drawings
M-12AL
Piping and Instrumentation Diagram Auxiliary Feedwater
System
Drawings
M-12AL01
Piping and Instrumentation Diagram Auxiliary Feedwater
System
Drawings
M-12BM01
Piping and Instrumentation Diagram Steam Generator
Blowdown Sys.
Miscellaneous
WCRE-34
Fourth 10-Year Interval Inservice Testing Basis Document
Procedures
AI 21-016
Operator Time Critical Actions Validation
Procedures
ALR 00-025E
NG02 Bus Trouble
Procedures
AP 21-004
Operator Response Time Program
5A
Procedures
BD-EMG E-0
Reactor Trip or Safety Injection
Procedures
BD-EMG E-2
Faulted Steam Generator Isolation
Procedures
CKL AL-120
Auxiliary Feedwater Normal Lineup
44A
Procedures
EMG E-0
Reactor Trip or Safety Injection
Procedures
EMG E-2
Faulted Steam Generator Isolation
24A
Procedures
EMG FR-S1
Response to Nuclear Power Generation/ATWS
Procedures
OFN RP-17
Control Room Evacuation
Procedures
STN RP-002G
ESW Train B to CTMT Air Cooler ISO Switch
Procedures
SYS GK-201
Mitigating Actions for Inoperable SGK05 Train
21D
Procedures
SYS NG-332
Deenergized NG02 NG04 and NG06E
29A
Work Orders
WO 15194, 21-475048-000, 21-475048-001
Calculations
XX-X-004
Combustible Fire Loading for Each in the Various Fire Areas
at WCNOC
Corrective Action
Documents
Condition Reports
10009424, 10029354
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10030120, 10030121
Drawings
E-11NG20
Low Voltage System Class 1E Motor Control Center
Summary
318
Drawings
M-12EF02
Piping and Instrumentation Diagram Essential Service Water
System
Miscellaneous
E-1F9905
Fire Hazard Analysis
Miscellaneous
E-1F9910
Post Fire Safe Shutdown Area Analysis
Miscellaneous
PT12386
Post Fire Safe Shutdown Issue
Miscellaneous
WCRE-35
Boundary Matrix
Procedures
ALR KC-888
Fire Protection Panel KC-008 Alarm Response
Procedures
AP 10-100
Procedures
AP 10-101
Control of Transient Ignition Sources
Procedures
AP 10-102
Control of Combustible Materials
Procedures
AP 10-103
Fire Protection Impairment Control
Procedures
AP 10-104
Breach Authorization
Procedures
AP 10-105
Fire Protection Training and Drills
24B
Procedures
AP 10-106
Fire Preplan
Procedures
Operability Determination and Functionality Assessments
Procedures
OFN KC-016
Fire Responses
Calculations
XX-M-069
FAC Program Minimum Wall Thickness Calculation for
Large Bore Piping and Components
Corrective Action
Documents
Condition Reports
10019400, 10020468, 10021613, 10021652, 10027094,
10028389, 10029850
Drawings
M-12AE01
Piping and Instrumentation Diagram Feedwater System
Drawings
M-12AE02
Piping and Instrumentation Diagram Feedwater System
Drawings
M-12AL01
Piping and Instrumentation Diagram Auxiliary Feedwater
System
Drawings
M-13AE05
Piping Isometric Main Feedwater Reactor and Auxiliary
Building
Miscellaneous
MS-02
Pipe Class Sheets
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
EMG E-2
Faulted Steam Generator Isolation
24A
Procedures
EMG E-0
Reactor Trip or Safety Injection
Procedures
EMG ES-02
Reactor Trip Response
Procedures
GEN 00-004
Power Operation
2
Procedures
GEN 00-005
Minimum Load to Hot Standby
Procedures
STS RE-006
EOL Core MTC Measurement
Calculations
XX-E-004
AC Motor Operated Valve Minimum Terminal Voltage
Calculations
XX-E-042
Class 1E 480V AC and 208/120V AC System Coordination
Corrective Action
Documents
Condition Reports
73120, 73421, 81790, 10004991, 10005001, 10005013,
10007665, 10013896, 10014094, 10018253, 10019416,
10020251, 10020290, 10023534, 10023559, 10024112,
10024908, 10026422, 10026451, 10026459, 10026498,
10027058, 10027518, 10027877, 10028066, 10028432,
10028903, 10028925, 10029210, 10029729, 10029830,
10029484
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10030449
Drawings
E-025-00007
sheet 201
ESW Screen B Spray EFHV0092
W14
Drawings
E-11NG20
Low Voltage System Class 1E Motor Control Center
Summary
318
Drawings
E-13NG02
Schematic Diagram Containment Cooler Fans A and C
Drawings
M-12AB01
Piping and Instrumentation Diagram Main Steam System
Drawings
M-766-01043
05W
Engineering
Changes
CP 14923
Restore Regulatory Compliance for Ten 480V MOVs
Miscellaneous
2013-049
USAR Change Request
2/12/2013
Miscellaneous
E-018A-00007
Instruction Manual for Molded Case Circuit Breaker
W15
Miscellaneous
QL-AB
System AB Main Steam System
Miscellaneous
WCLR-33
Electrical Cable Connections Not Subject to 10 CFR 50.49
Environmental Qualification Requirements B2.1.36
NUREG-1801 Program XLE6 Aging Management Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
WCNOC-76
Medium Low Voltage AC and Low Voltage DC Overcurrent
Protection Coordination for Wolf Creek Generating Station
Miscellaneous
WCQPM
Wolf Creek Quality Program Manual
Procedures
AI 16B-002
Preventive Maintenance Change Process
Procedures
Planning and Scheduling Preventive Maintenance
8B
Procedures
Post Maintenance Testing Development
21B
Procedures
Receipt Inspection
Procedures
I-ENG-005
Infrared Thermography
Procedures
MGE EOOP-11
Molded Case Circuit Breaker and Ground Fault Sensor
Testing
Procedures
STS IC-211A
Actuation Logic Test Train A Solid State Protection System
37A
Procedures
STS IC-211B
Actuation Logic Test Train B Solid State Protection System
38A
Procedures
STS IC-215
TADOT of Manual Reactor Trip, Trip and Bypass Breaker
UV/Shunt Trip, Turbine Trip on Reactor Trip and P4
Procedures
STS MT-024A
Functional Test of 480 and 120 Volt Molded Case Circuit
Breakers
16A
Work Orders
WO 2580, 14-385283-000, 14-385283-001, 15-406874-000,
18-439151-000, 18-445075-000, 19-452140-026,
20-458342-000, 20-460120-000, 20-460914-000,
2-480055-000, 22-477183-000, 22-477957-001,
23-486740-000, 23-486740-001, 23-488067-000
Corrective Action
Documents
Condition Reports
10029736, 10030624, 10030630, 10030631, 10030667,
10030732, 10030733, 10030734, 10030736, 10030739,
10031127
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10029882
Drawings
M-12AB01
Piping and Instrumentation Diagram Main Steam System
Drawings
M-12AL01
Piping and Instrumentation Diagram Auxiliary Feedwater
System
Drawings
M-12BG03
Piping and Instrumentation Diagram Chemical and Volume
Control System
Drawings
M-12EM01
Piping and Instrumentation Diagram High Pressure Coolant
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Injection System
Drawings
M-12FC02
Piping and Instrumentation Diagram Auxiliary Turbines
Auxiliary Feedwater Pump Turbine
Drawings
M-12KA05
Piping and Instrumentation Diagram Compressed Air
System
Miscellaneous
E-1F9910
Post-Fire Safe Shutdown Area Analysis
Procedures
AI 16C-006
Troubleshooting
2A
Procedures
AI 22C-013
Protected Equipment Program
Procedures
AI 22C-014
TSEO Management
7A
Procedures
On-Line Nuclear Safety and Generation Risk Assessment
Procedures
EMG ES-12
Transfer to Cold Leg Recirculation
Procedures
OFN RP-017
Control Room Evacuation
Procedures
STS KA-010
N2 Accumulator Inservice Check Valve Test
Procedures
SYS EM-003
Operation of EM HV-8924
Procedures
SYS KJ-200
Inoperable Emergency Diesel
Procedures
SYS NB-202
Transferring NB02 Power Sources
Work Orders
WO 50424, 50426, 50948
Calculations
AN-05-016
Wolf Creek MSLB Containment Pressure and Temperature
Response Analyses with GOTHIC for the MSIV/MFIV
Replacement Project
Calculations
SA-91-016
ECCS Design Basis Injection Flowrates Re-analysis in
Supporting of the WCGS Power Re-Rate Project
Calculations
XX-M-069
FAC Program Minimum Wall Thickness Calculation for
Large Bore Piping and Components
Corrective Action
Documents
Condition Reports
99-3942, 10019400, 10021613, 10028389, 10028779,
10029850, 10030351
Drawings
M-12BG03
Piping and Instrumentation Diagram Chemical and Volume
Drawings
M-12EM01
Piping and Instrumentation Diagram High Pressure Coolant
Injection System
Drawings
M-622.1A-00001
SGK05A and SGK05B Air Conditioner Refrigeration
Schematic
W13
Engineering
Changes
DCP 09488
Governor Replacement of Emergency Diesel Generators
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
M-018B-00009
Woodward Governor Failure Analysis and Test Report
Review
W01
Miscellaneous
M-10AE
Feedwater System
Miscellaneous
MS-02
Pipe Class Sheets
Procedures
Operability Determinations and Functionality Assessments
Procedures
DB-EMG E-0
Reactor Trip or Safety Injection
Procedures
EMG E-0
Reactor Trip or Safety Injection
Procedures
EMG E-2
Faulted Steam Generator Isolation
24A
Procedures
EMG E-3
Steam Generator Tube Rupture
Procedures
EMG ES-12
Transfer to Cold Leg Recirculation
Procedures
MPE GK-004
GK Unit Preparation for Work
Procedures
STS KJ-005B
Manual/Auto Start, Sync and Loading of EDG NE02
Procedures
SYS EM-003
Operation of EM HV-8924
Work Orders
WO 285, 33185, 48154, 22-482755-000
Calculations
BN-20
RWST Volumes and Level Set Points
Calculations
BN-M-013
Time Available for Injection, ECCS, and Containment Spray
Pumps Transfer and Evaluation of Air Entrainment at Empty
Alarm
Calculations
EJ-30
Calculations
EN-33
Containment Spray Pump NPSH
Calculations
FL-18
Containment Flood Levels for LOCA and MSLB
Calculations
WES-009-CALC-
001
Wolf Creek/Callaway Post-LOCA Containment Water Level
Calculation
Corrective Action
Documents
Condition Reports
21822, 137915, 142204, 10014808, 10015112, 10015262,
10017090, 10017620, 10019464, 10019626, 10030624,
10030630, 10030361, 10030650, 10030662, 10030663,
10030664,
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10029963
Engineering
Changes
DECP 020631
System Descriptions M-10BN and M-10EN Update
Engineering
DRE 20456
AV1 Positioner Gauge Block Removal
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes
Miscellaneous
DB-EMG ES-12
Transfer to Cold Leg Recirculation
Miscellaneous
SQTS-01-GSQTP
Seismic Functional Procedure
Procedures
ALR 00-047C
RWST LOLO2
Procedures
AP 05-021
Direct Replacement Equivalency
6A
Procedures
Operability Determination and Functionality Assessments
Procedures
DB-EMG ES-03
SI Termination
Procedures
SI Termination
Procedures
EMG E-0
Reactor Trip or Safety Injection
Procedures
EMG ES-12
Transfer to Cold Leg Recirculation
Corrective Action
Documents
Condition Report
10030086, 10030789, 10031067
Miscellaneous
Interoffice
Correspondence
Refuel 26 Risk Assessment Team Report - Schedule Rev.
C 1/12/2024
2/22/2024
Procedures
Outage Risk Management
Procedures
GEN 00-006
Hot Standby to Cold Shutdown
106
Procedures
STS BB-011
Reactor Coolant System and Pressurizer Heatup/Cooldown
Surveillance
Procedures
STS IC-901
Channel Operational Test Reactor Coolant Cold
Overpressure Protection Instrumentation
23A
Procedures
SYS NB-202
Transferring NB02 Power Sources
Work Orders
WO 53004, 20-466498-000, 21-474062-000, 23-487901-000
Calculations
XX-M-080
Wolf Creek Generating Station Pump Room Heat-Up
Analysis
Corrective Action
Documents
Condition Reports
20559, 10001214, 10004589, 10005013, 10007337,
10019205, 10024045, 10024821, 10028295, 10028635,
10028649, 10029512, 10029662, 10029726, 10029748,
10030191, 10030273, 10030274, 10030624, 10030630,
10030361
Corrective Action
Documents
Resulting from
Inspection
Condition Reports
10029354, 10029485, 10029495, 100300455, 10031001,
10031492, 10031493
Drawings
E-13EF09A
Schematic Diagram ESW To/From Containment Air Coolers
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Isolation Valve
Drawings
E-13NN01
Class 1E Instrument AC Schematic
Drawings
M-12AB01
Piping and Instrumentation Diagram Main Steam System
Drawings
M-12AL01
Piping and Instrumentation Diagram Auxiliary Feedwater
System
Drawings
M-12EF01
Piping and Instrumentation Diagram Essential SVC Water
System
Drawings
M-12EF02
Piping and Instrumentation Diagram Essential Service Water
System
Drawings
M-12KA05
Piping and Instrumentation Diagram Compressed Air
System
Miscellaneous
E-1F9915
Design Basis Document for OFN RP-017, Control Room
Evacuation
Miscellaneous
WCRE-34
Fourth 10-Year Interval Inservice Testing Bases Document
Procedures
AP 10-100
Procedures
Post Maintenance Testing Development
21B
Procedures
Operability Determination and Functionality Assessments
Procedures
Operability Determination and Functionality Assessments
26C
Procedures
ASME Code Testing of Pumps and Valves
2A
Procedures
Surveillance Testing
Procedures
EMG E-0
Reactor Trip or Safety Injection
Procedures
EMG E-2
Faulted Steam
24A
Procedures
EMG E-3
Steam Generator Tube Rupture
Procedures
MPE 766Q-008
Cleaning and Inspection of Class 1E Inverters
Procedures
MPE RC-001
Room Cooler Maintenance
Procedures
OFN RP-017
Control Room Evacuation
Procedures
STN AL-201
Auxiliary Feedwater System Valve Test
Procedures
STN RP-001E
3A
Procedures
STN RP-001F
2A
Procedures
STN RP-002G
ESW TRN B to CTMT Air Coolers ISO Switch
Procedures
STN RP-002H
ESW TRN B to CCW HX B ISO Switch
Procedures
STN RP-011E
ESW to SW SYS VLV ISO Switch 10 YR
Procedures
STN RP-011F
ESW to UHS VLV ISO Switch 10 YR
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
STN RP-012H
ESW To/From CCW HX B ISO Switches 10 year
Procedures
STN TCA-001
Manual Time Critical Action Timing
Procedures
STS AB-201D
Atmospheric Relief Valve Inservice Valve Test
Procedures
STS AL-103
TDAFW Pump Inservice Pump Test
Procedures
STS AL-201C
Turbine Driven Auxiliary Feedwater System Inservice Valve
Test
Procedures
STS EF-100B
ESW System Inservice B and ESW Check Valve B Test
51A
Procedures
STS GN-001
CTMT Cooling Fan Operability Test
Procedures
STS IC-746
Reactor Trip and Bypass Breaker Response Time Testing
2C
Procedures
STS KA-010
N2 Accumulator Inservice Check Valve Test
Procedures
STS PE-007
Periodic Verification of Motor Operated Valves
5A
Procedures
SYS KJ-124
Post Maintenance Run of Emergency Diesel Generator B
Procedures
SYS NN-131
Energizing NN Buses
Procedures
SYS NN-200A
Transferring NN01 and NN03 Buses Between Power
Sources
Work Orders
WO 15194, 15202, 15925, 16321, 16774, 16776, 16778, 16790,
16794, 16800, 16880, 16886, 17423, 17435, 17442, 17549,
17553, 26620, 27203, 29104, 30569, 32367, 32797, 32392,
38854, 44708, 45373, 50424, 50426, 50431, 17-430071-
003, 18-444963-000, 18-444964-000, 18-445168-000,
18-445169-000, 19-448878-000, 19-488879-000,
19-448880-000, 19-448882-000, 22-480055-000,
23-146046-000, 23-485690-000, 23-486898-000,
23-486898-001, 23-489131-005
71152A
Corrective Action
Documents
Condition Reports
14364, 45434, 50217, 1996-0015, 1995-3074, 10029354,
10004991, 10004995, 10005013, 10017445
71152A
Corrective Action
Documents
Resulting from
Inspection
Condition Report
10030907
71152A
Drawings
M-766-01043
W05
71152A
Drawings
M-766-01045
W04
71152A
Miscellaneous
EPR NS30650022
06/05/2009
71152A
Miscellaneous
WCQPM
Wolf Creek Quality Program Manual
13, 14
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71152A
Procedures
AP 24-002
Requisition and Procurement Process
30E
71152A
Procedures
Receipt Inspection
71152A
Procedures
OFN RP-013
Control Room Not Habitable
71152A
Procedures
OFN RP-017
Control Room Evacuation
71152A
Procedures
STN RP 002D
71152A
Procedures
STN RP-001C
VCT Outlet Isolation VLV ISO Switch
71152A
Procedures
STN RP-001D
CCP B Suct from RWST VLV ISO Switch
2B
71152A
Procedures
STN RP-001N
71152A
Procedures
STN RP-002C
RWST to RHR B Suction ISO Switch
71152A
Procedures
STN RP-002F
71152A
Procedures
STN RP-002I
CCW TRN B SPLY/Return VLV ISO Switch
71152A
Procedures
STN RP-011C
VCT Outlet Isolation VLV ISO Switch 10 YR
71152A
Procedures
STN RP-011D
CCP B Suct from RWST VLV ISO Switch 10 YR
71152A
Procedures
STN RP-011N
SGL15B Control RM ISO Switch 10 YR
71152A
Procedures
STN RP-012C
RWST to RHR Pump B Suction ISO Switch 10 YR
71152A
Procedures
STN RP-012D
BIT Inlet VLV B ISO Switch 10 YR
71152A
Procedures
STN RP-012F
CCP B Recirc VLV ISO Switch 10 YR
71152A
Procedures
STN RP-012I
CCW TRN B SPLY/Return VLV ISO Switch 10 YR
71152A
Procedures
STS IC-211B
Actuation Logic Test Train B Solid Sate Protection System
38A
71152A
Procedures
STS IC-215
TADOT of Manual Reactor Trip, Trip and Bypass Breaker
UV/Shunt Trip, Turbine Trip on Reactor Trip and P4
71152A
Procedures
STS IC-610B
Slave Relay Test K610 Train B Safety Injection
71152A
Work Orders
13-378440-000, 15-406873-002, 21-469167-000,
21-472626-000, 21-474139-000, 22-483407-000,
2-477183-000