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| =Text= | | =Text= |
| {{#Wiki_filter:September 09, 2021 | | {{#Wiki_filter: |
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| ==SUBJECT:==
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| WOLF CREEK GENERATING STATION - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000482/2021010
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| ==Dear Mr. Reasoner:==
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| On August 12, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Wolf Creek Generating Station and discussed the results of this inspection with Mr. J. McCoy, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
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| No findings or violations of more than minor significance were identified during this inspection.
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| 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.
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| Sincerely, Vincent G. Digitally signed by Vincent G.
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| Gaddy Gaddy Date: 2021.09.09 09:14:19-05'00'
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| Vincent G. Gaddy, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 05000482 License No. NPF-42 Enclosure:
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| As stated cc w/ encl: Distribution via LISTSERV
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| =SUMMARY=
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| The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) 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.
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| ===List of Findings and Violations===
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| No findings or violations of more than minor significance were identified.
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| ===Additional Tracking Items===
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| None.
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| =INSPECTION SCOPES=
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| 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 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.
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| 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 telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
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| ==REACTOR SAFETY==
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| ===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
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| Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (5 Samples 1 Partial)
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| : (1) 125 V DC Bus NK01
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| * Walkdown of 125 V DC system
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| * System health reports, component maintenance history, and corrective action program documents
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| * Calculations for electrical distribution, system load flow/voltage drop, short-circuit, and electrical protection
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| * Protective device settings and feeder circuit breaker ratings
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| * Procedures for preventive maintenance, inspection, and testing
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| * Results of completed preventative maintenance on the bus, load center, transformer, and feeder breakers
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| * Maintenance programs for batteries and battery chargers associated with the bus
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| * Calculations for the AC input to the battery chargers
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| : (2) 4.16 KV Class 1E Switchgear NB001
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| * Design basis calculations
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| * Corrective actions resulting from previous violations
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| * Infrared thermography procedures and completed work orders
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| * Vendor documents and recommendations
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| * Circuit breaker wiring diagrams
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| * Degraded voltage relaying setpoint calculations
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| * Component maintenance history
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| * Circuit breaker protective device settings
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| * Procedures for preventive maintenance, inspection, and testing
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| : (3) Main Steam Isolation Valve ABHV0011
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| * Component maintenance history and system health reports
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| * Corrective action documents
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| * Preventive maintenance bases
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| * Maintenance rule status and basis documents
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| * Main steam isolation valve actuation control system logic drawings and diagrams
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| * Procedures for inservice testing
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| * Acceptance criteria for actuation logic and slave relay surveillance testing
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| * Completed surveillance and inservice tests
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| * Calculations for valve stoke time adjustment
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| * Calculations of setpoints and uncertainty
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| * Environmental qualification of solenoid valves and limit switches
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| : (4) Non-Safety Auxiliary Feedwater Pump PAP01
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| * Walkdown of pump and applicable portions of the system
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| * Design calculations
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| * Vortex and air intrusion analysis
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| * Required operator actions
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| * Emergency operating procedures
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| * Maintenance and testing
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| * Surveillance acceptance criteria
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| * Net positive suction head calculations
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| * Pump curves
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| * System drawings and isometrics
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| * Vendor documents and recommendations
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| * Corrective action documents
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| : (5) Refueling Water Storage Tank TBN01
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| * Setpoint and total loop uncertainty calculations
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| * Calibration procedures and acceptance criteria calculations for level instrumentation
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| * Seismic calculations for refueling water storage tank anchor bolts
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| * Change packages for modifications to tank to support periodic tank inspections and repairs
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| : (6) Evaluation of Operator Procedures and Actions Related to Components
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| * Time sensitive action OPA-RHR, Control room operator action to secure residual heat removal pumps during a high-pressure event
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| * Time sensitive action OPA-SGOVERFL, Control room operator action to throttle auxiliary feedwater flow to the steam generators to prevent overfill of the steam generators
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| * Time sensitive action OPA-NSAFW-BF, Control room and field operator actions to initiate startup and align the non-safety auxiliary feedwater pump following failure of the safety-related auxiliary feedwater pumps Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) ===
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| {{IP sample|IP=IP 71111.21|count=1}}
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| : (1) 480 V Motor Control Center NG001B
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| * Design basis calculations
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| * Corrective actions resulting from previous violations
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| * Completed work orders
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| * Vendor documents and recommendations
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| * Circuit breaker/motor starter wiring diagrams
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| * Circuit breaker/circuit protector overload settings
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| * Circuit cable sizing
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| * Component maintenance history
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| * Procedures for preventive maintenance, inspection, and testing
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| ===Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)===
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| : (1) Change Package 20184, Replacement of ITT Barton Flow Indicator
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| * Critical design attributes
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| * Environmental qualification of indicator
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| : (2) Change Package 20297, Removal of CST Level Indicator APLI0008
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| * Regulatory Guide 1.97 commitments for accident monitoring
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| * Operator actions related to APLI0008
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| * Walkdown of condensate storage tank
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| * Piping and instrumentation drawings of tank and level instrumentation
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| : (3) Change Package 20316, NIS C-2 Setpoint Revision
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| * Surveillance test procedures and channel calibration acceptance criteria
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| * Alarm response procedures
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| * Post modification testing results
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| : (4) Change Package 20347, RCS Narrow Range RTD Lead Resistance Imbalance
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| * Change package modifications for critical design attributes
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| * Implementing work order
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| * Terminations for the RTD Leads
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| * Safety analysis of the narrow range RTD change
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| : (5) Change Package 20350, SGK05A/B Fuse Replacement
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| * Design package including drawings, analysis, and qualification of the fuses
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| * Schematic diagrams
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| * Calculations supporting fuse sizing
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| * Overload relay settings
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| * Corrective action documents and implementing work orders
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| * Motor data information for protective design information
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| * Vendor documentation for the replaced AJT20 amp fuse and the new AJT30 amp fuse
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| : (6) Change Package 20452, BBTY-441A RCS Loop 4 Narrow THOT Lead Resistance Imbalance
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| * Critical design attributes
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| * Affected electrical cable raceway and interconnection wiring drawings
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| * Surveillance test procedure
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| * Completed work order
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| ===Review of Operating Experience Issues (IP Section 02.06) (4 Samples)===
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| : (1) Wolf Creek Operating Experience 2018-0465, NRC Information Notice 2017-06, Battery and Battery Charger Short-Circuit Current Contributions to a Fault on the DC Distribution System
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| : (2) Wolf Creek Operating Experience 2018-0503, Loss of Ultimate Heat Sink Inventory Through Auxiliary Feedwater Minimum Flow Lines During a Loss of the Condensate Storage Tank
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| : (3) Wolf Creek Operating Experience 2018-0847, Discovery of a Condition that Could have Prevented Fulfillment of a Safety Function, Environmental Qualification Requirements for Atmospheric Steam Dumps
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| : (4) Wolf Creek Operating Experience 2019-0417, NRC Information Notice 2019-002, Emergency Diesel Generator Excitation System Diode Failures
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| ==INSPECTION RESULTS==
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| No findings were identified.
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| ==EXIT MEETINGS AND DEBRIEFS==
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| The inspectors verified no proprietary information was retained or documented in this report.
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| * On August 12, 2021, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. J. McCoy, Site Vice President, and other members of the licensee staff.
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| =DOCUMENTS REVIEWED=
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| Inspection Type Designation Description or Title Revision or
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| Procedure Date
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| 71111.21M Calculations 41-14.02-F RWST Displacements for New Seismic Analysis 0
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| 69466-M-001 Non-Safety Auxiliary Feedwater Pump Drawdown From the 1
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| Condensate Storage Tank
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| 69466-M-002 Non-Safety Auxiliary Feedwater Pump Net Positive Suction 1
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| Head
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| 69466-M-003 Non-Safety Auxiliary Feedwater Pump Analysis and System 1
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| Resistance Curve
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| 69466-M-004 Non-Safety Auxiliary Feedwater Pump Piping Vibration 0
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| Analysis
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| AN 98-001 Uncertainty for Refueling Water Storage Tank (RWST) 0
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| Level-Low, (Lo-Lo-1) Automatic Switchover Setpoint and
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| Technical Specification changes
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| AN-98-001-000- Uncertainty for Refueling Water Storage Tank (RWST) 0
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| CN-001 Level-Low, (Lo-Lo-1) Automatic Switchover Setpoint and
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| Technical Specification changes
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| AN-98-026 Determination of RWST Depletion prior to Completion of 0
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| Recirculation Switchover and ECCS Recirculation Flow
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| Requirement
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| BN-20 RWST Volumes and Level Set Points 3
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| BN-20-CN002 RWST Volume and Level Set Points 3
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| BN-J-001 RWST Level Transmitter Density Errors 01
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| BN-J-002 Total Loop Uncertainty Calculation - System BN, Loops 01
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| 0930, 0931, 0932, and 0933
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| BN-J-002-001- Total Loop Uncertainty Calculation - System BN, Loops 01
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| CN003 0930, 0931, 0932, and 0933
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| BN-J-002-01- Total Loop Uncertainty Calculation System BN, Loops 0930 01
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| CN001 0931 0932 0933
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| ECCS-47 SI Pumps - NPSH from RWST 0
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| EJ-30-003- RHR Pumps A & B NPSH 03
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| CN002
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| FL-08 Control Building Flooding 003
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| FL-18 Containment Flood Levels for LOCA and MSLB 03
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| Inspection Type Designation Description or Title Revision or
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| Procedure Date
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| H-08 NB System Protective Relays 5
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| KJ-M-017 Emergency Diesel Standby Generator (KKJOlB) Runtime 1
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| Without ESW Flow
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| NK-E-001-004- 125 VDC Class 1E Battery System Sizing, Voltage Drop and 005
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| 005 Short Circuit Studies.
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| SA-92-009 Calculation of RWST Depletion Rate and ECCS 0
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| Recirculation Switchover Time Following a Postulated
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| Primary/Secondary Pipe Rupture
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| WES-009-CALC- Wolf Creek/Callaway Post-LOCA Containment Water Level 1
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| 001 Calculation
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| XX-E-006 AC System Analysis 006
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| XX-E-006 AC System Analysis 8
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| XX-E-006 AC System Analysis 9
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| XX-E-009 System NB, NG, PG Undervoltage/Degraded Voltage Relay 1
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| Setpoints
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| Corrective Action Condition Report 2007-01786, 47791, 74322, 104253, 104389, 104390,
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| Documents (CR-) 128300, 133632, 135223, 66596, 66841, 103323, 104458,
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| 104515, 105136, 105564, 105741, 105744, 105969, 106015,
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| 114883, 118661, 124196, 129263, 130202, 10000916,
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| 10001446, 10002218, 10005090, 10007183, 10007246,
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| 100007975, 00124312, 00138042, 00145626, 00131142,
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| 10000792
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| Corrective Action Condition Report 10007140, 10007142, 10007145, 10007147, 10007163,
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| Documents (CR-) 10007662, 10007666, 10007668, 10007802, 10008018,
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| Resulting from 10007616, 10008023, 10008009, 10007407, 10007596,
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| Inspection 10007621, 10007625, 10007632, 10007633, 10007667,
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| 10007975, 10008021, 10008065, 10008092, 10008133
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| Drawings 8809D54 T HAVE Loop 4 (TEST) Protection IV Card Frame 08 5A
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| Cabinet 04 Interconnecting Wiring Diagram
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| C-0C0212 Refueling & Reactor Makeup Water Storage Tanks, 7
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| Concrete Neat Line & Reinforcing Plans and Sections
| |
| E-11001 Main Single Line Diagram 13
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| E-11NB01 Lower Medium Voltage Sys. Class 1E 4.16 kV Single Line 9
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| Meter and Relay Diagram
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| Inspection Type Designation Description or Title Revision or
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| Procedure Date
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| E-11NG01 Low Voltage System Class 1E 480V Single Line Meter & 16
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| Relay Diagram
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| E-11NG01 Low Voltage System Class 1E 480V Single Line Meter & 16
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| Relay Diagram
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| E-11NK01 Class 1E 125V DC System Meter & Relay Diagram 20
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| E-11NK02 CLASS IE 125V DC System, Meter & Relay Diagram 19
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| E-13EP02A Schematic Diagram Accumulator Isolation Valves 4
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| E-13GK04 Schematic Diagram Battery Rm. Hydrogen Alarm 00
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| E-13NB01 Lower Medium Class 1E Meter and Voltage System 4.16 kV 5
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| Three Line Relay Diagram
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| E-13NB02 Lower Medium Voltage Sys. Class 1E 4.16 KV Three Line 3
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| Meter & Relay Diagram
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| E-13NB03 Lower Medium Voltage Sys. Class 1E 4.16kv Meter and 8
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| Relay Three Line Diagram
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| E-13NB12 Schematic Diagram Class 1E Bus NB01 Feeder Brkr. 7
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| 2NB0112
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| E-13NB13 Schematic Diagram Class 1E Bus NB01 Feeder Brkr. 7
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| 2NB0109
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| E-13NE10 Schematic Diagram 4.16KV DG Feeder Breaker 152NB0111 22
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| E-13NG10 Schematic Diagram 4.16KV LC XFMR Feeder Breakers 5
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| 2NB0110 and 152NB0113
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| E-17000A Termination List Notes 20
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| J-14001 Control Room Equipment Arrangement. 12
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| KD-74-96, Sh. 1 One Line Diagram 73
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| KD-7496 One Line Diagram 73
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| KD-7496A Distribution System Equipment Lineup Limitations 11
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| M-12BN01 Piping & Instrumentation Diagram, Borated Refueling Water 1
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| Storage System
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| M-1H3311 HEATING VENTILATING & AIR COND. CONTROL 07
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| BUILDING EL. 2000'-0" AREA 1
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| M-1P3411 Drainage System (LE & LF) Control Building, EL. 2O16'- 0 01
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| Area 1
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| M-622.1-00036- Electrical Motor Data Sheet, Bahnson Ref: N-0027 Thru N- 1W
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| W03 003`
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| Inspection Type Designation Description or Title Revision or
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| Procedure Date
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| N1387-637A-B1 SGK05A & SGK05B Air Conditioner, Electrical Schematic 08
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| WIP-M-761- T HAVE Loop 1 (Test) Protection Card Frame 2/4 Cabinet 1 00
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| 2328-W01-A-1 Interconnecting Wiring Diagram.
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| Engineering 20452 BBTY-441A RCS LP4 Narrow THOT Lead Resistance 00
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| Changes Imbalance
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| CP 014426. Utilization of Spare RTD BBTE0430A1, 02
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| CP 20316 NIS C-2 Setpoint Revision 0
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| Document EC Engineering for SGK05A/B Fuse Replacement, Rev. 0 0
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| Number: 020350,
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| EC. 020347 RCS NARROW RANGE RTD LEAD RESISTANCE 0
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| IMBALANCE
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| Engineering LTR-SCS-19-17 Wolf Creek Nuclear Operating Corporation C-2 Interlock 0
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| Evaluations Setpoint Revision
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| PQE-J-601B-P01 Atmospheric Relief Valve 8005N I/P Converter w/ Metallic 0
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| Nozzle Cap
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| WCAP-11528 RCS Flow Anomaly Investigation Report 04/01/1988
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| WCAP-9917 Setpoint Study for Kansas Gas and Electric Co./Kansas City 06/01/1981
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| Power and Light Co. Wolf Creek Unit and Union Electric Co.
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| Callaway Units 1 and 2 (SNUPPS Projects)
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| Miscellaneous Technical Requirements Manual 72
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| 04-00383 WOLF CREEK GENERATING STATION - ISSUANCE OF 07/12/2004
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| AMENDMENT
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| RE: TECHNICAL SPECIFICATIONS 3.8.1 AND 3.8.4 - AC
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| AND DC SOURCES
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| (TAC NO. MB8763)
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| 50.59 for DECP 50.59 screening for RCS Narrow range RTD Lead 0
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| Resistance Imbalance engineering design change.
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| AD 20347 Applicability Determination for 50-59 for DCP 020347 0
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| ANSI/I EEE American National Standard - General requirements for dry- 11/30/1979
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| C57.12.01-1979 type distribution and power transformers
| |
| Bulletin 6.10-2C ITE Series 5600 Motor Control Centers - design and 02/1976
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| application guide
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| CJ16224-l Dedication Plan for MERSEN Fuse PIN: AJT30 2, 11/25/19
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| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
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| CP 20350 CP 20350 Attachment 2 for XX-E-006 REV 8 ETAP 10-31-2019
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| MODEL\XX-E-006 REV 8.O
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| CR 00145500 Level Of Effort Evaluation for NRC 3Q2020 Integrated N/A
| |
| Inspection Self-revealing Green NCV
| |
| E-009 Technical Specification for Metal-Clad Switchboard for the 8
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| Standardized Nuclear Unit Power Plant System
| |
| E-009-00342 Metal-Clad Switchgear - Types M26 and M36 for Magne- W09
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| (GEH-1802X) Blast Air Circuit Breakers
| |
| E-009B Design Specification for 4.16 KV and 13.8 KV Vertical Lift 1
| |
| Vacuum Circuit Breakers
| |
| E-009B-00009 Instruction Manual for Siemens Type 3AF-GER/GEU Vertical W06
| |
| Lift Direct Replacement Vacuum Circuit Breakers
| |
| E-00NG System Description Low Voltage System - 480 V (Class 1E 5
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| Power System)
| |
| E-018 Technical Specification for Motor Control Centers For The 13
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| Wolf Creek Generation Station
| |
| E-018A-00007 Instruction Manual For Molded Case Circuit Breaker W15
| |
| E-10NB System Description Lower Medium Voltage System - 4.16 00
| |
| kV (Class IE Power System)
| |
| E-11NG20 Low Voltage System Class 1E Motor Control Center 312
| |
| Summary
| |
| Frame Book 29- Westinghouse Series C Motor Circuit Protector 05/1986
| |
| 111
| |
| GEK-7310C Maintenance Manual - GE Power Circuit Breakers Types
| |
| AKR-3/3A-50 and AKRU-3/3A-50
| |
| LTAM WCNOC- 480 Volt Safety Related MCC Bucket Replacement 1/20/2021
| |
| 09-0152
| |
| LTR-SCS-16-59 Westinghouse Evaluation to Support 95% Probability/95% 0
| |
| Confidence Level Uncertainty Values for Non-Westinghouse
| |
| Supplied Instrumentation for the Wolf Creek Generating
| |
| Station Revised Thermal Design Procedure Uncertainty
| |
| Calculations in WCAP-18083-P.
| |
| M-10BN Borated Refueling Water Storage 1
| |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| MGE EOOP-11 Molded Case Circuit Breaker and Ground Fault Sensor 37A
| |
| Testing
| |
| N/A Maintenance Strategy - XNG01 8/5/201
| |
| NB SHR 2020 System Health Report - System NB (Low-Medium Voltage
| |
| Q3Q4 4.16 kV) Third and Fourth Quarter
| |
| PIR 2007-00368 Supplement to Condition Report 2008-002718 - DG Parallel 06/19/2008
| |
| CR Response with Scenario Table
| |
| PSA-05-0011 Probabilistic Risk Assessment System Notebook - Electrical 3
| |
| Power Systems
| |
| TS-19-0001 Fuse list Change for Fuses 109FU, 110FU, 111FU N/A
| |
| Procedures AI 12-002 FME Consideration and General Guidance for Major 0A
| |
| Components
| |
| AI 21-016 OPERATOR TIME CRITICAL ACTIONS VALIDATION 20
| |
| AI 29B-003 Guidance To Prevent Unacceptable Preconditioning Prior To 2
| |
| Testing
| |
| ALR 00-47D RWST Lev LoLo 1 Auto XFR 10B
| |
| ALR 00-82A PR Over PWR Rod Stop 11
| |
| ALR 301 125 VDC CLASS IE SWITCHBOARD NK01 10
| |
| AP 12-003 Foreign Material Exclusion 18
| |
| AP 14A-003 Scaffolding Construction 26
| |
| CNT-ME-507 Installation & Inspection of Cable Terminations 13
| |
| E-009Q-01 13.8 KV and 4.16 KV Switchgear Inspection and Testing 37A
| |
| E-017 Technical Specification for Load Center Unit Substations for 07
| |
| the Standardized Nuclear Unit Power Plant System
| |
| E-020 DC Distribution Switchboards 009
| |
| E-050A-00010 Installation Instructions for AT&T Lineage 2000 Round Cell W01
| |
| Batteries Racks and Seismic Bracing at Wolf Creek Nuclear
| |
| Power Plant
| |
| E-050A-00010 Installation Instructions for AT&T Lineage 2000 Round Cell W01
| |
| Batteries Racks and Seismic Bracing at Wolf Creek Nuclear
| |
| Power Plant
| |
| E-051B Electrically Operated Manually Controlled Transfer Switches 01
| |
| E-051B-0031 Instruction Manual for Transfer Switch Panels W04
| |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| E-075-00016 Instruction Manual for Installation, Operations, & W06
| |
| Maintenance of ESWS Transformers 225 KVA FOR
| |
| SNUPPS 10466
| |
| E-10NK System Description for 125-Volt DC System (Class 1E 007
| |
| Power System)
| |
| E-11013 Installation, Inspe49ction, and Testing Details for Electrical 49
| |
| Equipment and Cables.
| |
| EMG C-0 Loss of All AC Power 45
| |
| EMG ES-12 Transfer to Cold Leg Recirculation 24
| |
| EMG ES-12 Transfer to Cold Leg Recirculation 24
| |
| EMG FR-H1 Response to Loss of Secondary Heat Sink 37
| |
| I-ENG-005 Infrared Thermography 11
| |
| MGE EOOP-05 Insulation Resistance Testing 27
| |
| MGE EOOP-11 Molded Case Circuit Breaker and Ground Fault Sensor 37A
| |
| Testing
| |
| MGE TL-001 Wiring Termination and Lug/Connector Installation 26A
| |
| MPE E009Q-03 Inspection and Testing Of Siemens Vacuum Circuit Breakers 11
| |
| MPE E017Q-04 Circuit Breaker Test for AKR 50 and AKR 30 Breakers 31B
| |
| MPE E017Q-07 Load Center Transformer Inspection 17A
| |
| OE 2018-0465 NRC Information Notice 2017-06 06/14/2018
| |
| OFN NB-042 Loss Of Offsite Power To NB01 (NB02) With EDG Paralleled 15
| |
| STC-IC-441 Channel Calibration Nuclear Instrumentation System Power 16A
| |
| Range Channel N41
| |
| STN KU-010 Station Blackout Diesel and Non-Safety AFW Pump Test 13
| |
| STS CH-029 Refueling Water Storage Tank Boron Concentration 8A
| |
| Determination
| |
| STS EN-100A Containment Spray Pump A Inservice Test 31
| |
| STS IC-201A TAVG, Delta T and Pressurizer Pressure Channel 24
| |
| Operational Test-Protection Set 1
| |
| STS IC-442 Channel Calibration Nuclear Instrumentation System Power 16A
| |
| Range Channel N42
| |
| STS IC-443 Channel Calibration Nuclear Instrumentation System Power 16A
| |
| Range Channel N43
| |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| STS IC-444 Channel Calibration Nuclear Instrumentation System Power 17A
| |
| Range Channel N44
| |
| STS IC-500G Delta T/TAVG Instrumentation Loop 4 Channel Calibration 28B
| |
| STS IC-508A Refueling Water Storage Tank Level Transmitter Calibration 8
| |
| STS IC-508B Refueling Water Storage Tank Level Instrumentation 9
| |
| Channel Calibration
| |
| STS IC-803A 4KV Undervoltage - Grid Degraded Voltage Channel 8
| |
| Calibration of NB01 Bus
| |
| STS KJ-011A EDG NE01 24 Hour Run 38
| |
| STS MT-018 Weekly Inspection of 125 VDC Lead-Calcium Batteries 23B
| |
| STS MT-020 125 VDC Battery Charger Operational Test 26B
| |
| STS MT-020 125 VDC Battery Charger Operational Test 26B
| |
| STS MT-024A Functional Test of 480 and 120 Volt Molded Case Circuit 16A
| |
| Breakers
| |
| STS MT-024B Functional Test of 480 and 120 Volt Molded Case Circuit 17
| |
| Breakers
| |
| STS MT-024C Functional Test of 480 and 120 Volt Molded Case Circuit 16
| |
| Breakers
| |
| SYS AP-122 Non-Safety Auxiliary Feed Pump Operation 13
| |
| Work Orders Work Order (WO- 12-359863-000, 14-389904-000, 18-442405-001, 18-
| |
| ) 442406-001, 18-442408-001, 18-442426-001, 19-448418-
| |
| 000, 19-448418-002, 19-448418-004, 20-465688-000, 20-
| |
| 458894-000, 20-458895-000, 20-458896-000, 20-458898-
| |
| 000, 20-458900-000, 20-458901-000, 20-458905-002, 20-
| |
| 461085-000, 20-461085-001, 20-462400-000, 20-462400-
| |
| 001, 20-465688-000, 20-466586-000, 20-461440-000, 20-
| |
| 466529-000, 20-466528-000, 19-455924-000, 14-383742-
| |
| 000, 20-458317-001, 01-224289-000, 10-327766-000, 12-
| |
| 359819-000, 17-421614-000, 08-303906-000,. 04-259537-
| |
| 000, 13-372243-000, 15-405081-000, 18-444596-000, 17-
| |
| 21067-003, 18-437036 000, 20-467595-000, 20-458103-
| |
| 001
| |
| 16
| |
| }} | | }} |
