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| {{#Wiki_filter:May 7, 2021 | | {{#Wiki_filter: |
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| ==SUBJECT:==
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| COLUMBIA GENERATING STATION - INTEGRATED INSPECTION REPORT 05000397/2021001
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| ==Dear Mr. Sawatzke:==
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| On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Columbia Generating Station. On April 15, 2021, the NRC inspectors discussed the results of this inspection with Mr. A. Javorik, Site Vice President, Engineering Projects, and other members of your staff. The results of this inspection are documented in the enclosed report.
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| 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.
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| 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:
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| Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspectors at Columbia Generating Station.
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| 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 Inspectors at Columbia 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 (10CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
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| Sincerely, Jeffrey Digitally signed by Jeffrey Josey Josey Date: 2021.05.07 08:02:18 -05'00'
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| Jeffrey E. Josey, Chief Reactor Projects Branch A Division of Reactor Projects Docket No. 05000397 License No. NPF-21
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| ===Enclosure:===
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| As stated
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| ==Inspection Report==
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| Docket Number: 05000397 License Number: NPF-21 Report Number: 05000397/2021001 Enterprise Identifier: I-2021-001-0004 Licensee: Energy Northwest Facility: Columbia Generating Station Location: Richland, Washington Inspection Dates: January 1, 2021 to March 31, 2021 Inspectors: N. Hernandez, Senior Resident Inspector L. Merker, Senior Resident Inspector W. Cullum, Reactor Inspector L. Flores, Reactor Inspector J. Melfi, Project Engineer W. Sifre, Senior Reactor Inspector Approved By: Jeffrey E. Josey, Chief Reactor Projects Branch A Division of Reactor Projects Enclosure
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| =SUMMARY=
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| The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Columbia Generating Station, in accordance with the Reactor Oversight Process (ROP). The ROP 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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| Inadequate Operability Evaluations for American Society of Mechanical Engineers (ASME)
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| Code Pipe Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.1] - 71111.15 Systems NCV 05000397/2021001-01 Resources Open/Closed The inspectors identified a Green, non-cited violation (NCV) of 10 CFR 50, Appendix B,
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| Criterion V, Instructions, Procedures, and Drawings, associated with the licensees failure to establish adequate procedural guidance for operability determinations. Specifically, Plant Procedures Manual (PPM) 1.3.66, Operability Determination, Revisions 35 and 36, failed to include guidance identifying the need to also evaluate structural integrity in accordance with the ASME Code for code class piping systems when flaws are identified. This resulted in an incomplete operability determination on September 18, 2020, and loss of the presumption of operability of the reactor core isolation cooling (RCIC) system on December 11, 2020.
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| Failure to Perform Preservice Testing as Required by American Society of Mechanical Engineers (ASME) Code Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green [H.1] - 71152 NCV 05000397/2021001-02 Resources Open/Closed The team identified a Green, non-cited violation (NCV) of 10 CFR 50.55a(f), Preservice and inservice testing requirements, subsection (4), Inservice testing standards requirement for operating plants, because the licensee did not implement the Inservice Test (IST) Program in accordance with the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM) of Record for the control room chilled water system 1A and 1B pumps. Specifically, the licensee did not perform preservice testing of the 1A and 1B control room chilled water (CCH)pumps as required by ASME OM Code, Paragraph ISTB-3100 Preservice Testing, before scoping the pumps into their IST program. This resulted in CCH operability surveillance procedures with inaccurate IST information that could not be used to determine the pumps met technical specification requirements.
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| ===Additional Tracking Items===
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| Type Issue Number Title Report Section Status URI 05000397/2020004-02 Reactor Core Isolation 71111.15 Closed Cooling Drainpipe Steam Leak
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| =PLANT STATUS=
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| Columbia Generating Station began the inspection period at 100 percent power. On January 16, 2021, reactor power was reduced to 80 percent to perform a control rod sequence exchange before returning to rated thermal power. On February 20, 2021, reactor power was reduced to 65 percent to perform a control rod pattern adjustment and repair a leak on condensate booster pump 2C before returning to 100 percent power. On February 27, 2021, reactor power was reduced to 80 percent to perform a control rod pattern adjustment and turbine bypass valve testing before returning to 100 percent power. On March 23, 2021, the plant began power coastdown for refueling outage R25 and ended the inspection period at approximately 96 percent power.
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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 Disease 2019 (COVID-19),resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions 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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| ==71111.01 - Adverse Weather Protection==
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| ===Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)===
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| : (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal extreme cold temperatures for standby service water system A, standby service water system B, diesel generator 1, and diesel generator 2 on
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| ===February 3, 2021.
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| Impending Severe Weather Sample (IP Section 03.02) (1 Sample)===
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| : (1) The inspectors verified the adequacy of the overall preparations to protect risk-significant systems from impending severe weather during sustained high wind conditions on January 13, 2021.
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| ===External Flooding Sample (IP Section 03.03) (1 Sample)===
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| : (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on March 3, 2021.
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| ==71111.04 - Equipment Alignment==
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| ===Partial Walkdown Sample (IP Section 03.01) (3 Samples)===
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| The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
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| : (1) control room emergency chilled water system B during planned maintenance on January 12, 2021
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| : (2) control room emergency chilled water system A during planned maintenance on January 25, 2021
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| : (3) diesel generator 3 during planned maintenance, week of January 25, 2021
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| ===Complete Walkdown Sample (IP Section 03.02) (1 Sample)===
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| : (1) The inspectors performed a complete system alignment of diesel generator 2 on March 26, 2021.
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| ==71111.05 - Fire Protection==
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| ===Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)===
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| 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:
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| : (1) Fire Area RC-13/2; chiller, communications, instrumentation and control area; on January 11, 2021
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| : (2) Fire Areas RC-11/1 and RC-12/2; heating, ventilation, and air conditioning equipment rooms A and B; on January 22, 2021
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| : (3) Fire Areas DG-1/4, DG-6/#, and DG-7/#; high-pressure core spray diesel generator room, storage tank access area, and day tank room; on January 25, 2021
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| : (4) Fire Area R-3, high-pressure core spray pump room, on March 11, 2021
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| : (5) Fire Areas DG-3, DG-5, and DG-9; diesel generator 2, diesel oil tank pump room, and diesel day tank room; on March 16, 2021
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| ==71111.06 - Flood Protection Measures==
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| ===Cable Degradation (IP Section 03.02) (1 Sample)===
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| : (1) The inspectors evaluated manholes E-MH-E11, E-MH-E13, and E-MH-E15 for cable submergence protection in the protected area on March 31, 2021.
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| ===71111.07T - Heat Sink Performance Triennial Review (IP Section 03.02) ===
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| {{IP sample|IP=IP 71111.07|count=4}}
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| : (1) RHR-HX-1A, Residual Heat Removal Train A
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| : (2) RHR-HX-2A, RHR-P-2A Seal Injection Water Cooler
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| : (3) DCW-HX-1C, Cooling Water to Division 3 Diesel
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| : (4) RRA-CC-12, Division I Motor Control Center Room Cooler
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| ==71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance==
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| Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
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| (1 Sample)
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| : (1) The inspectors observed and evaluated licensed operator performance in the control room during a reactor downpower to perform maintenance on condensate pump C on February 20, 2021.
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| ===Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)===
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| : (1) The inspectors observed and evaluated the licensed operator requalification training drill (Crew B) on February 1, 2021.
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| ==71111.12 - Maintenance Effectiveness==
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| ===Maintenance Effectiveness (IP Section 03.01) (1 Sample)===
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| : (1) The inspectors evaluated the effectiveness of diesel generator 2 maintenance on March 25, 2021 to ensure structures, systems, and components remained capable of performing their intended function.
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| ===Quality Control (IP Section 03.02) (1 Sample)===
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| : (1) The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the commercial dedication of the control room emergency chiller 1A rupture disk remained capable of performing its intended function on January 15, 2021.
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| ==71111.13 - Maintenance Risk Assessments and Emergent Work Control==
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| ===Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)===
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| 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:
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| : (1) high risk for transformer E-TR-8A/2 replacement on January 19, 2021
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| : (2) yellow risk for diesel generator 3 maintenance, week of January 25, 2021
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| : (3) yellow risk for standby service water system A, circuit breaker S/1, and turbine oil vapor extractors 1A and 1B maintenance, week of February 1, 2021
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| : (4) yellow risk for RCIC system surveillance testing, week of March 8, 2021
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| : (5) yellow risk for diesel generator 2 planned maintenance outage, week of March 15, 2021
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| ==71111.15 - Operability Determinations and Functionality Assessments==
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| ===Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)===
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| The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
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| : (1) control room emergency chilled water pump 1B differential pressure beyond action range on February 12, 2021
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| : (2) aging effects on electrical contactors on February 24, 2021
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| : (3) diesel generator 3 high jacket water temperature shutdown switch out of calibration on March 9, 2021
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| : (4) standby service water pump 1B oil sample found elevated water level in the upper bearing oil reservoir on March 12, 2021
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| ==71111.18 - Plant Modifications==
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| Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
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| (2 Samples)
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| The inspectors evaluated the following temporary or permanent modifications:
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| : (1) control room emergency chilled water system A check valve replacement on January 27, 2021
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| : (2) electrical bus SM-1 undervoltage relay E-RLY-27/1 removal on March 9, 2021
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| ==71111.19 - Post-Maintenance Testing==
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| ===Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)===
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| The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
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| : (1) control room emergency chiller system A on January 22, 2021
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| : (2) control room emergency chiller system B on January 29, 2021
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| : (3) diesel generator 3 maintenance on January 29, 2021
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| : (4) standby service water system A on February 8, 2021
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| : (5) diesel generator 2 on March 26, 2021
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| ==71111.22 - Surveillance Testing==
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| The inspectors evaluated the following surveillance tests:
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| ===Surveillance Tests (other) (IP Section 03.01)===
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| {{IP sample|IP=IP 71111.22|count=2}}
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| : (1) ISP-SGT-B101, standby gas treatment system A flow and filter pressure drop test (once per 24 months), on January 7, 2021
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| : (2) OSP-CRD-C703, control rod settle time test, on February 20, 2021
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| ===Inservice Testing (IP Section 03.01) (1 Sample)===
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| : (1) OST-SLC/IST-Q701, standby liquid control pump 1A quarterly, on March 4, 2021
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| ===FLEX Testing (IP Section 03.02) (1 Sample)===
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| : (1) FLEX diesel quarterly testing on February 23, 2021
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| ==71114.06 - Drill Evaluation==
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| Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)
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| (1 Sample)
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| : (1) The inspectors evaluated the emergency planning drill (Emergency Response Organization Team C) on March 9,
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| ==OTHER ACTIVITIES - BASELINE==
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| ===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
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| IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 03.01) ===
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| {{IP sample|IP=IP 71151|count=1}}
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| : (1) January 1, 2020, through December 31, 2020 IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 03.02) (1 Sample)
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| : (1) January 1, 2020, through December 31, 2020
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| ===IE04: Unplanned Scrams with Complications Sample (IP Section 03.03) (1 Sample)===
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| : (1) January 1, 2020, through December 31, 2020
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| ==71152 - Problem Identification and Resolution==
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| ===Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)===
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| The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
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| : (1) evaluation of the control room chilled water system addition to the IST program on March 9, 2021
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| : (2) evaluation of the electrical power panel E-PP-8AF low voltage on March 22,
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| ==INSPECTION RESULTS==
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| Inadequate Procedural Guidance for Operability Determinations for American Society of Mechanical Engineers (ASME) Code Pipe Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.1] - 71111.15 Systems NCV 05000397/2021001-01 Resources Open The inspectors identified a Green, non-cited violation (NCV) of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, associated with the licensees failure to establish adequate procedural guidance for operability determinations. Specifically, Plant Procedures Manual (PPM) 1.3.66, Operability Determination, Revisions 35 and 36, failed to include guidance identifying the need to also evaluate structural integrity in accordance with the ASME Code for code class piping systems when flaws are identified. This resulted in an incomplete operability determination on September 18, 2020, and loss of the presumption of operability of the RCIC system on December 11, 2020.
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| =====Description:=====
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| On September 18, 2020, the licensee discovered a steam leak on the RCIC system turbine steam inlet valve drain line during recovery from planned RCIC maintenance. This issue was entered into the corrective action program under Action Request (AR) 410929. The licensee performed an operability determination that stated the RCIC system was operable with the steam leak because the leak would not impact the required steam flow to the RCIC turbine. The licensee restored the RCIC system to the normal standby lineup (which isolated the steam leak) on September 18, 2020. On December 9, 2020, engineering entered a concern into the corrective action program (AR 414023) that the operability determination from AR 410929 failed to evaluate the steam leak against ASME Code requirements as the drain line was an ASME Section III, Class 2, high-energy pipe. Operations requested additional operability information from engineering to further evaluate operability of the RCIC system. Engineering provided the requested additional operability information on December 11, 2020. The inspectors identified weaknesses in the additional operability information and determined the licensee needed to perform an ASME Code repair on the pipe and submit an ASME Code relief request to the NRC. On December 17, 2020, the licensee declared the RCIC system inoperable. On December 19, 2020, the licensee declared the RCIC system unavailable in order to perform the ASME Code repair. The licensee restored the RCIC system to operable status on December 20, 2020.
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| The licensee completed an event investigation and entered AR 414343 into the corrective action program to evaluate past operability of the RCIC system. The inspectors independently reviewed the licensees past operability analyses, evaluated the licensee's event investigation, and determined the licensee had demonstrated reasonable assurance of past operability of the RCIC system.
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| On April 30, 2020, the licensee updated PPM 1.3.66 to Revision 35 to reflect updated industry guidance on operability determinations. ASME Code requirements and their relationship to operability of structures, systems, and components were unknown by licensee personnel throughout the organization and were not included in the operability determination process update. This omission was carried through in the August 18, 2020, update to Revision 36. The licensee updated PPM 1.3.66 to Revision 37 to include guidance identifying the need to also evaluate structural integrity in accordance with the ASME Code for code class piping systems when flaws are identified on March 4, 2021.
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| Corrective Actions: The licensee performed an ASME Code repair on the turbine steam inlet valve drain line, entered the condition into the corrective action program, performed a failure analysis of the drain line, conducted an event investigation, performed extensive past operability analyses, and updated the operability procedure to include guidance identifying the need to also evaluate structural integrity in accordance with the ASME Code for code class piping systems when flaws are identified.
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| Corrective Action References: ARs 410929, 414023, and 414343
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| =====Performance Assessment:=====
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| Performance Deficiency: The failure to establish adequate procedural guidance for operability determinations was a performance deficiency.
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| 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, Plant Procedures Manual (PPM) 1.3.66, Operability Determination, Revisions 35 and 36, failed to include guidance identifying to evaluate structural integrity in accordance with the ASME Code for code class piping system when flaws are identified. This resulted in an incomplete operability determination on September 18, 2020, and the loss of the presumption of operability of the RCIC system on December 11, 2020.
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| Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined this finding is of very low safety significance (Green) because all of the screening questions were answered in the negative.
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| Cross-Cutting Aspect: H.1 - Resources: Leaders ensure that personnel, equipment, procedures, and other resources are available and adequate to support nuclear safety. The finding has a cross-cutting aspect in the area of human performance, resources, in that the licensee did not ensure that personnel, equipment, procedures, and other resources were available and adequate to support nuclear safety. Specifically, ASME Code requirements and their relationship to operability of structures, systems, and components were unknown by licensee personnel throughout the organization and were not included in the operability determination process update on April 30, 2020.
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| =====Enforcement:=====
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| Violation: Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires, in part, that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances. The licensee established PPM 1.3.66, Operability Determination, as the implementing procedure for conducting operability determinations.
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| Contrary to the above, from April 30, 2020, through March 4, 2021, the licensee failed to ensure that operability determinations, activities affecting quality, were prescribed by a documented procedure of a type appropriate to the circumstances. Specifically, PPM 1.3.66, Operability Determination, Revisions 35 and 36, failed to include guidance to evaluate structural integrity in accordance with the ASME Code for code class piping systems when flaws are identified. This resulted in an incomplete operability determination on September 18, 2020, and the loss of the presumption of operability of the RCIC system on December 11, 2020, due to a steam leak on the turbine steam inlet valve drain line.
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| Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
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| The disposition of this finding and associated violation closes URI: 05000397/2020004-02.
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| URI Reactor Core Isolation Cooling Drainpipe Steam Leak 71111.15 (Closed) URI 05000397/2020004-02
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| =====Description:=====
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| This unresolved item (URI) is closed. The basis for the URI closure is discussed in this report under NCV 05000397/2021001-01 in the above Inspection Results associated with Report Section 71111.15.
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| Failure to Perform Preservice Testing as Required by American Society of Mechanical Engineers (ASME) Code Cornerstone Significance Cross-Cutting Report Aspect Section Barrier Integrity Green [H.1] - 71152 NCV 05000397/2021001-02 Resources Open The team identified a Green, non-cited violation (NCV) of 10 CFR 50.55a(f), Preservice and inservice testing requirements, subsection (4), Inservice testing standards requirement for operating plants, because the licensee did not implement the IST program in accordance with the ASME OM Code of Record for the control room chilled water system 1A and 1B pumps. Specifically, the licensee did not perform preservice testing of the 1A and 1B control room chilled water (CCH) pumps as required by ASME OM Code, Paragraph ISTB-3100 Preservice Testing, before scoping the pumps into their IST program. This resulted in CCH operability surveillance procedures with inaccurate IST information that could not be used to determine the pumps met technical specification requirements.
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| =====Description:=====
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| On February 6, 2020, Columbia Generating Station received approval from the NRC for a license amendment request (LAR) to allow the use of either the CCH system or the emergency service water system (SW) as acceptable cooling sources in support of the main control room (MCR) air conditioning (AC) system. The safety-related function of the MCR AC system is to maintain the MCR temperature less than or equal to the 104°F equipment qualification temperature limit during and following design basis events, and maintaining the long term, steady state MCR design condition temperature less than or equal to 85°F that supports 30 days continuous MCR occupancy. The change would utilize the CCH system as the preferred cooling source in support of the MCR AC system due to SW heat removal capability limitations. The LAR implementation included expanding the scope of the IST program to include applicable components in the CCH and SW systems utilized for CCH system operation not previously included in the program and updating all relevant documentation to reflect the change. On May 4, 2020, Columbia Generating Station received approval to extend the LAR implementation date to February 6, 2021, due to unforeseen circumstances associated with the COVID-19 pandemic. The licensee completed full implementation of the LAR on February 4, 2021.
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| The inspectors reviewed several ARs that documented issues with implementing the LAR and establishing required test conditions for the CCH pumps. On February 4, 2021, the licensee created AR 415919 to document that the newly updated CCH operability surveillance procedures contained inaccurate IST information that could not to be used to determine the pumps met technical specification requirements; the inaccurate IST information would be corrected by March 12, 2021, after the licensee performed additional testing. The inspectors identified that this was not in compliance with the ASME OM Code.
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| Corrective Actions: The licensee entered the condition into the corrective action program, performed preservice testing of the 1A and 1B control room chilled water pumps and established initial sets of reference values in accordance with the ASME OM Code, and completed an investigation.
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| Corrective Action References: ARs 415619, 415919, and 417741
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| =====Performance Assessment:=====
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| Performance Deficiency: The failure to perform required testing set forth in the ASME OM Code for the control room chilled water system 1A and 1B pumps was a performance deficiency.
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| Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Procedure Quality attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, the licensee did not perform preservice testing of the 1A and 1B CCH pumps as required by ASME OM Code, Paragraph ISTB-3100 Preservice Testing, before scoping the pumps into their IST program. This resulted in CCH operability surveillance procedures with inaccurate IST information that could not be used to determine the pumps met technical specification requirements.
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| Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined this finding is of very low safety significance (Green) because the finding did not represent a degradation of the radiological barrier function provided for the control room, auxiliary building, spent fuel pool, SBGT system (BWR), or EGTS system (PWR ice condenser) and did not represent a degradation of the barrier function of the control room against smoke or a toxic atmosphere.
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| Cross-Cutting Aspect: H.1 - Resources: Leaders ensure that personnel, equipment, procedures, and other resources are available and adequate to support nuclear safety. This finding had a cross-cutting aspect in the area of human performance, resources, in that the licensee did not ensure that personnel, equipment, procedures, and other resources are available and adequate to support nuclear safety. Specifically, the licensee did not understand the full scope of testing requirements required by the ASME Code and did not have adequate testing procedures available to support preservice testing.
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| =====Enforcement:=====
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| Violation: Title 10 CFR 50.55a(f), Preservice and inservice testing requirements, states, in part, that systems and components of boiling and pressurized water-cooled nuclear power reactors must meet the requirements for preservice and inservice testing (referred to in this paragraph
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| : (f) collectively as inservice testing) of the ASME BPV Code and ASME OM Code. Subsection (4), Inservice testing standards requirement for operating plants, further states, in part, that throughout the service life of a boiling or pressurized water-cooled nuclear power facility, pumps and valves that are within the scope of the ASME OM Code must meet the inservice test requirements set forth in the ASME OM Code and addenda. Paragraph ISTB-3100 of ASME OM Code 2004, 2006 Addenda, states, in part, before implementing inservice testing, an initial set of reference values shall be established for each pump. These tests shall be conducted under conditions as near as practicable to those expected during subsequent inservice testing Contrary to the above, the licensee did not meet the requirements for preservice and inservice testing of the ASME OM Code, in that they did not establish an initial set of reference values for each pump before implementing inservice testing, and did not conduct these tests under conditions as near as practicable to those expected during subsequent inservice testing. Specifically, the licensee did not perform preservice testing of the 1A and 1B control room chilled water (CCH) pumps as required by ASME OM Code, Paragraph ISTB-3100 Preservice Testing, before scoping the pumps into their IST program. This resulted in CCH operability surveillance procedures with inaccurate IST information that could not be used to determine the pumps met technical specification requirements.
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| | |
| Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
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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 February 18, 2021, the inspectors presented the triennial heat sink inspection results to R. Shultz, Site Vice President and other members of the licensee staff.
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| * On April 15, 2021, the inspectors presented the integrated inspection results to Mr. A.
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| | |
| Javorik, Site Vice President, Engineering Projects, and other members of the licensee staff.
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| | |
| =DOCUMENTS REVIEWED=
| |
| | |
| Inspection Type Designation Description or Title Revision or
| |
| Procedure Date
| |
| 71111.01 Calculations CE-02-13-18 Probable Maximum Flood Analysis for Columbia Generating 000
| |
| Station
| |
| CE-02-13-22 Effects of Local Intense Probable Maximum Precipitation 000
| |
| Analysis for Columbia Generating Station
| |
| ME-02-92-41 Calculation for Ultimate Heat Sink Analysis 008
| |
| ME-02-92-43 Room Temperature Calculation for DG Building, Reactor 013
| |
| Building, Radwaste Building and Service Water
| |
| Corrective Action Action Requests 403246, 404534, 415728, 396990, 025319, 400176,
| |
| Documents (ARs) 389796
| |
| Miscellaneous G02-16-143, Response to NRC Request for Information Pursuant to 10
| |
| Columbia CFR 50.54(f) Regarding Recommendation 2.1 of the
| |
| Generating Near-term Task Force Review of Insights from the
| |
| Station, Docket Fukushima Dai-ichi Accident
| |
| No. 50-397
| |
| Flooding Hazard
| |
| Reevaluation
| |
| Report
| |
| MOT-HT-1-1 Freeze Protection Heat Trace 004
| |
| Procedures 4.840.A5 840.A5 Annunciator Panel Alarms 029
| |
| ABN-FLOODING Flooding 022
| |
| ABN-WIND Tornado/High Winds 034
| |
| SOP- Cold Weather Operations 034, 035
| |
| COLDWEATHER-
| |
| OPS
| |
| SOP- Hot Weather Operations 007
| |
| HOTWEATHER-
| |
| OPS
| |
| SOP- Warm Weather Operations 016
| |
| WARMWEATHER-
| |
| OPS
| |
| 71111.01 Work Orders 02135244
| |
| 71111.04 Corrective Action Action Requests 0415611
| |
| Documents (ARs)
| |
| Drawings M512-1 Flow Diagram Diesel Oil and Miscellaneous Systems Diesel 048
| |
| Generator Building
| |
| M512-4 Flow Diagram Diesel Oil and Miscellaneous Systems Diesel 015
| |
| Generator Building
| |
| M775 Flow Diagram Emergency Chilled Water Piping System 029
| |
| Control Room
| |
| Procedures 1.3.29 Locked Valve Checklist 087
| |
| OSP-CCH/IST- Control Room Emergency Chiller System A Operability 049
| |
| M701
| |
| OSP-CCH/IST- Control Room Emergency Chiller System B Operability 047, 048
| |
| M702
| |
| SOP-DG2-LU Emergency Diesel Generator (Div 2) Valve and Power 007
| |
| Supply Lineup
| |
| SOP-DG2-START Emergency Diesel Generator (Div 2) Start 031
| |
| SOP-DG2-STBY Emergency Diesel Generator (Div 2) Standby Lineup 023
| |
| SOP-DG3-LU High Pressure Core Spray Diesel Generator Valve and 009
| |
| Power Supply Lineup
| |
| SOP-DG3-STBY High Pressure Core Spray Diesel Generator Standby 020
| |
| Lineup
| |
| SOP-HVAC/CR- Control, Cable, and Critical Switchgear Rooms HVAC 001
| |
| LU Lineup
| |
| SOP-SW-LU Standby Service Water System Valve and Breaker Lineup 014
| |
| Work Orders 02172385
| |
| 71111.05 Calculations FP-02-85-03 Combustible Loading Calculation 011
| |
| Fire Plans PFP-DG- Diesel Generator Building 004
| |
| BUILDING
| |
| PFP-RW-525 Radwaste 525 006
| |
| Procedures 1.3.10 Plant Fire Protection Program Implementation 036
| |
| 1.3.10A Control of Ignition Sources 017
| |
| 1.3.10C Control of Combustibles 022
| |
| 71111.06 Corrective Action Action Requests 417530, 417568, 417604, 417615, 417852
| |
| Documents (ARs)
| |
| Drawings E823 Manhole Print Underground Duct Banks Plans and Profiles 027
| |
| Sheet 1
| |
| Miscellaneous Video of E-MH-E15 Inspection 03/31/2021
| |
| BIP 20-0559 Barrier Impairment Permit for E-MH-E11 30 east of bldg. 88 03/25/2021
| |
| (north end)
| |
| BIP 20-0560 Barrier Impairment Permit for E-MH-E13 60 east of bldg. 88 03/25/2021
| |
| (north end)
| |
| BIP 20-0561 Barrier Impairment Permit for E-MH-E15 east of bldg. 88 03/25/2021
| |
| BIP 21-0097 Barrier Impairment Permit for E-MH-E15 east of bldg. 88 03/31/2021
| |
| Procedures 1.3.57 Barrier Impairment 040
| |
| Work Orders 02139272
| |
| 71111.07T Calculations ME-02-05-05 Calculation for Projecting RHR Heat Exchanger Thermal 000
| |
| Performance
| |
| ME-02-09-03 Test Data Evaluation and Uncertainty Analysis for the RHR 04/21/2009
| |
| Heat Exchangers
| |
| ME-02-85-70 Seal Coolers for RHR-P-2A, 2B, and 2C 000
| |
| ME-02-92-41 Calculation for Ultimate Heat Sink Analysis 007
| |
| ME-02-92-43 Room Temperature Calculation for DG Building, Reactor 013
| |
| Building, Radwaste Building and Service Water
| |
| ME-02-96-03 Potential Effect of SW Fouling on RHR Seal Cooler 000
| |
| Performance
| |
| Corrective Action Action Requests 387462, 404282, 372892, 387484, 240323, 385702,
| |
| Documents (ARs) 399102, 398565, 392171, 413335, 412987
| |
| Drawings CVI DWG 215-11 Seal Injection Water Coolers 006
| |
| M524-1 Flow Diagram Standby Service Water System Reactor, 140
| |
| Radwaste, D.G. Buildings and Yard
| |
| M587 General Arrangement Plan and Section Diesel Generator 040
| |
| Building
| |
| M777 Composite Piping Plans at EL.441'-0", 455'-0", 472'-9" 054
| |
| Diesel Generator Building
| |
| M778 Composite Piping Sections and Details Diesel Generator 041
| |
| Building
| |
| Engineering EC 17500 Minimum Wall Thickness Requirement for RHR-HX-2A 002
| |
| Changes EC14774 Replace RHR-P-2A 007
| |
| Miscellaneous Columbia Generating Station Service Water Reliability 004
| |
| Program
| |
| AED SPC 15F.2 Design Specification for Division 15 Section 15F.2 Essential 002
| |
| Fan Coil Units
| |
| AED SPC 309 Design Basis Document Division 300 Section 309 - Standby 018
| |
| Service Water System
| |
| AED SPC 310 Design Basis Document Standby Power Systems 015
| |
| DCW-HX-1C DCW-HX-1C Plugged Tubes List 000
| |
| Plugged Tubes
| |
| List
| |
| DCW-HX-1C DCW-HX-1C Plugged Tubes Map 000
| |
| Plugged Tubes
| |
| Map
| |
| Procedures 1.5.11 Maintenance Rule Program 015
| |
| 2.14.1 Chemical Treatment of Standby Service Water 020
| |
| 4.820.B1 820.B1 Annunciator Panel Alarms 041
| |
| ABN-SW Service Water Trouble 015
| |
| SOP-SW-DRAIN Standby Service Water Drain 008
| |
| SOP-SW-FILL Standby Service Water System Fill 007
| |
| SOP-SW-OPS Standby Service Water Operations 009
| |
| SWP-CHE-02 Chemical Process Management and Control 030
| |
| SYS-4-23 Maintenance Rule Structural Baseline Inspections 001
| |
| Self-Assessments 404096 Self-assessment is to assess Columbias performance in 10/01/2020
| |
| the area of Service Water Reliability and GL 89-13 in
| |
| preparation for the triennial NRC ultimate heat sink
| |
| inspection
| |
| Work Orders 02100975, 02117561, 02134259, 02131491, 02131518,
| |
| 2103774, 02077068, 02111141, 02076064, 29135328,
| |
| 2041703, 02076064, 02134638, 02134639, 02134640,
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| 2143199, 02143200, 02143201, 02163358, 02136601,
| |
| 2085391, 02085671, 02114521, 02134951, 02145562,
| |
| 2165498, 02100975, 02117561, 02095968, 02135019,
| |
| 2147556, 02147572, 02111141, 02128173, 01178727,
| |
| 29135328, 29151758
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| 71111.11Q Corrective Action Action Requests 0415789
| |
| Documents (ARs)
| |
| Miscellaneous LR002510 Columbia Generating Station Simulator Cycle 21-1
| |
| Evaluated Scenario
| |
| Procedures 13.1.1 Classifying the Emergency 049
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| 3.2.6 Power Maneuvering 015
| |
| 3.3.1 Reactor Scram 066
| |
| 5.1.1 RPV Control 022
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| 5.1.2 RPV Control - ATWS 026
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| 5.5.11 Alternate Control Rod Insertions 010
| |
| 9.3.12 Plant Power Maneuvering 037
| |
| 9.3.9 Control Rod Withdrawal Sequence Development and 030
| |
| Control
| |
| ABN-CORE Unplanned Core Operating Conditions 018
| |
| OI-09 Operations Standards and Expectations 079
| |
| OSP-CRD-M704 Control Rod Exercise (week 4) 000
| |
| SOP-CR- Control Rod Movement 004, 005
| |
| MOVEMENT
| |
| Work Orders 02146078
| |
| 71111.12 Corrective Action Action Requests 404914, 415069, 415085, 415094, 415233, 415125,
| |
| Documents (ARs) 417213, 417232, 417233, 417234, 417235, 417236,
| |
| 417238, 417242, 417266, 417275, 417291, 417297,
| |
| 417308, 417360, 417364, 417366, 417376, 417390,
| |
| 417406, 417423, 417426, 417429, 417435, 417441,
| |
| 417449, 417450, 417237, 417241
| |
| Miscellaneous Commercial Grade Dedication Package for Continental 01/11/2021
| |
| Rupture Discs
| |
| ISP 20-0216 Ignition Source Permit for DG2 Room 03/17/2021
| |
| ISP 20-0217 Ignition Source Permit for DG2 01/20/2021
| |
| MOT-CHILL-1-1- MOT for Chillers 010
| |
| 9.1
| |
| Procedures 1.3.10A Control of Ignition Sources 017
| |
| 1.3.56 Conduct of Maintenance 012
| |
| 1.3.64 Plant Clearance Order 044
| |
| 1.5.11 Maintenance Rule Program 016
| |
| 10.2.13 Approved Lubricants 077
| |
| 10.20.19 Diesel Generator Alternative Refuel Cycle (2 Year & 4 Year) 010
| |
| Preventative Maintenance (Division 1 and 2)
| |
| ECP-DG2/INSP- Diesel Generator DG2 Electrical Inspection 020
| |
| B101
| |
| OQAPD-01 Operational Quality Assurance Program Description 056
| |
| (EN-QA-004)
| |
| SWP-ENV-01 Refrigerant Compliance Program 005
| |
| SWP-INS-01 Quality Control Inspection and Peer Verification 008
| |
| SYS-4-31 System and Equipment Performance Monitoring and 012
| |
| Trending Program
| |
| WCI-2 Standard Operating Cycle Schedule Development 006
| |
| Work Orders 02136926, 02155988, 02165100, 02159685, 02152933,
| |
| 2155807, 02128138, 02129026, 02127872, 02127930,
| |
| 2127931, 02121189
| |
| 71111.13 Corrective Action Action Requests 412066, 412131, 414328, 414384, 414642, 415479,
| |
| Documents (ARs) 415528, 415781, 414350, 417009, 398152
| |
| Miscellaneous Paragon Snapshot of week of March 8 03/09/2021
| |
| Paragon Snapshot of week of March 15 03/15/2021
| |
| BIP 20-0471 Barrier Impairment Permit: ISP-MS-Q923 (Calibrate MS- 03/08/2021
| |
| LIS-38A)
| |
| Procedures 1.3.76 Integrated Risk Management 060
| |
| 1.3.83 Protected Equipment Program 031, 032,
| |
| 033
| |
| 1.5.14 Risk Assessment and Management for 043
| |
| Maintenance/Surveillance Activities
| |
| OSP-ELEC-W102 Electrical Distribution Subsystem Breaker Alignment and 032
| |
| Power Availability Verification
| |
| SOP-ELEC-AC- AC Electrical Distribution System Breaker Lineup 077
| |
| LU
| |
| SOP-HPCS- HPCS RPV Injection 007
| |
| INJECTION
| |
| Work Orders 02163349, 02160962, 02162477, 02171486, 02172898,
| |
| 2169318, 02120074, 02157617, 02163796, 02164284,
| |
| 2151273, 02168694, 02129026, 02107861, 02153181
| |
| 71111.15 Calculations 9.32.02 HVAC Control Room Emergency Chiller System 002
| |
| E/I-02-91-1096 Setting Range Determination for Instrument Loop DCW-TS- 000
| |
| ME-02-92-43 Room Temperature Calculation for DG Building, Reactor 013
| |
| Building, Radwaste Building and Service Water
| |
| Corrective Action Action Requests 415639, 415798, 415855, 415892, 415935, 416136,
| |
| Documents (ARs) 415566, 413121, 414214, 396335
| |
| Drawings EWD-7E-004C High Pressure Core Spray System HPCS Diesel Engine 004
| |
| DG-ENG-1C Controls
| |
| EWD-7E-005C High Pressure Core Spray System HPCS Diesel Engine 005
| |
| DG-ENG-1C Controls
| |
| M775 Flow Diagram: Emergency Chilled Water Piping System 029, 030
| |
| Control Room
| |
| Engineering 16619 Credit CCH for MCR Equipment Operability 002
| |
| Changes
| |
| Engineering Failure Evaluation Failure Evaluation of Aux contact from WMA-42-8F2C
| |
| Evaluations
| |
| Miscellaneous AED SPC 309 Design Basis Document Division 300 Section 309 - Standby 018
| |
| Service Water System
| |
| Procedures 1.10.11 Technical Assessments Supporting Reportability and 002
| |
| Reportability Evaluations
| |
| 1.3.66 Operability Determination 036, 037
| |
| OSP-CCH/IST- Control Room Emergency Chiller System A Operability 047, 048,
| |
| M701 049, 050,
| |
| 051, 052
| |
| OSP-CCH/IST- Control Room Emergency Chiller System B Operability 045, 046,
| |
| M702 047, 048,
| |
| 049
| |
| OSP-SW-M101 Standby Service Water Loop A Valve Position Verification 043, 044
| |
| OSP-SW-M102 Standby Service Water Loop B Valve Position Verification 044, 045
| |
| Work Orders 02159687, 02139086, 02120123, 02134259
| |
| 71111.18 Calculations 8.42.0241 Pipe Stress Analysis CCH A Piping 003
| |
| Corrective Action Action Requests 415249, 408430
| |
| Documents (ARs)
| |
| Drawings 215-00,14008,1 Chilled Water Surge Pipe to CCH-P-1A 005
| |
| M775 Flow Diagram Emergency Chilled Water Piping System 029
| |
| Control Room
| |
| Engineering 16619 CCH-V-14A Replacement Check Valve 002A.FCR
| |
| Changes 16619 Credit CCH for MCR Equipment Operability 002
| |
| 18415 TMOD Remove SM-1 UV Relay E-RLY-27/1 000
| |
| Miscellaneous 5059EVAL-18- EC 16619 000
| |
| 0002
| |
| 696-00,4 Vendor Manual Y-type Check Valve with Soft Mainseat 002
| |
| SPC 1 Design Specification for Division 100, Section 1, ASME 024
| |
| Piping Systems
| |
| Procedures 1.3.30 Repair, Replacement, and Alteration of ASME Items 029
| |
| 1.3.9 Temporary Modifications 057
| |
| 10.2.28 Installation, Modification and Inspection of Piping Systems 023
| |
| 10.25.23 Testing and Setting Time Voltage Relays 016
| |
| DES-2-15 Engineering Change Revisions 013
| |
| ENG-DES-50 Interface Procedure for IP-ENG-001 Standard Design 002
| |
| Process
| |
| IP-ENG-001 Standard Design Process 002
| |
| Work Orders 02173116, 02164829
| |
| 71111.19 Corrective Action Action Requests 415125, 415249, 415251, 415253, 415254, 415264,
| |
| Documents (ARs) 415385, 415428, 415448, 415426, 415443, 415619,
| |
| 415639, 415640, 415566, 415784, 417360, 417364
| |
| Procedures 1.3.16 Issue Management 002
| |
| 10.20.19 Diesel Generator Alternative Refuel Cycle (2 Year & 4 Year) 010
| |
| Preventative Maintenance (Division 1 and 2)
| |
| 10.25.207 Testing and Setting Agastat 7000 Series and Agastat ETR 007
| |
| Series Time Delay Relays
| |
| ECP-DG2/INSP- Diesel Generator DG2 Electrical Inspection 020
| |
| B101
| |
| MI-1.22 Maintenance Planning Program 025
| |
| OSP-CCH/IST- Control Room Emergency Chiller System A Operability 048, 049
| |
| M701
| |
| OSP-CCH/IST- Control Room Emergency Chiller System B Operability 046, 047,
| |
| M702 048
| |
| OSP-DO-Q703 DO-P-2 Operability 001
| |
| OSP-ELEC-M102 DO-TK-3B Operability Test 005
| |
| OSP-ELEC-S703 HPCS Diesel Generator Semi-Annual Operability Test 064
| |
| OSP-LPCS/IST- LPCS System Operability Test 045
| |
| Q702
| |
| OSP-SW/IST- Standby Service Water Loop A Operability 032
| |
| Q701
| |
| QAP-ASU-07 Peer Verification Program Planning 006
| |
| SWP-TST-01 Post Maintenance Testing Program 017
| |
| TSP-DG2-B502 Standby Diesel Generator DG2 Load Testing 026
| |
| Work Orders 02163484, 02136926, 02159685, 02152933, 02159687,
| |
| 2138414, 02160255, 02168523, 02153328, 02150242,
| |
| 2152214, 02152211, 02139086, 02128619, 02143355,
| |
| 2155806, 02157633, 02157844, 02153328, 02167414,
| |
| 2153540, 02155511, 02165185, 02138671, 02129026,
| |
| 2127872, 02121189, 02176181, 02168090
| |
| 71111.22 Corrective Action Action Requests 414973, 416341, 416689, 416475, 416474
| |
| Documents (ARs)
| |
| Miscellaneous Reactivity Control Plan, Rod Set 02/13/2021
| |
| Control Rod Withdrawal Deviation Sheet, pages 28, 29, 30 02/20/2021
| |
| and 31
| |
| NRC Information FLEX Diesel Generator Operational Challenges 09/15/2020
| |
| Notice 2020-02
| |
| Procedures 1.5.1 Surveillance Testing Program 045
| |
| ISP-SGT-B101 Standby Gas Treatment - System A - Flow and Filter 007
| |
| Pressure Drop Test
| |
| OSP-CRD-C703 Control Rod Settle Time Test 002
| |
| OSP-FLEX-Q704 Diesel Generator 4 Quarterly Surveillance 000
| |
| OSP-SLC/IST- Standby Liquid Control Pumps Operability Test 029
| |
| Q701
| |
| 71111.22 Procedures SOP-DG4- Diesel Generator 4 Shutdown 003
| |
| SHUTDOWN
| |
| SOP-DG4-START Diesel Generator 4 Start 010
| |
| SOP-DG4-STBY Diesel Generator 4 Standby 002
| |
| Work Orders 02136245, 02163210, 02163209, 02158719, 02126801,
| |
| 2123201, 02168152
| |
| 71114.06 Corrective Action Action Requests 416984, 416986, 416996
| |
| Documents (ARs)
| |
| Miscellaneous Columbia Generating Station ERO Team C Drill Report: 000
| |
| March 9, 2021 After Action Report / Improvement Plan
| |
| Procedures 13.1.1 Classifying the Emergency 049
| |
| 13.1.1A Classifying the Emergency - Technical Bases 034
| |
| 13.10.2 TSC Manager Duties 035
| |
| 13.10.9 Operations Support Center Manager and Staff Duties 050
| |
| 13.11.1 EOF Manager Duties 044
| |
| 13.11.12 EOF Engineering Manager and Staff Duties 032
| |
| 13.11.2 Assistant EOF Manager Duties 010
| |
| 13.11.3 Site Support Manager and Staff Duties 033
| |
| 71151 Corrective Action Action Requests 403173, 404225, 404429, 407724, 412859, 416468
| |
| Documents (ARs)
| |
| Miscellaneous Operations Logs 01/01/2020 -
| |
| 2/31/2020
| |
| Operational Decision Making Issue Evaluation 002, 003,
| |
| 004, 005
| |
| Timeline and Discussion of Second Turbine Balance Shot in 03/08/2021
| |
| June 2020 White Paper
| |
| Procedures 1.10.10 Consolidated Data Entry Process Description 008
| |
| ABN-FWH- Feedwater Heater High Level Trip 007
| |
| HILEVEL/TRIP
| |
| ABN-POWER Unplanned Reactor Power Change 016
| |
| Work Orders 02147004, 02145898
| |
| 71152 Corrective Action Action Requests 415619, 415795, 415640, 415892, 415919, 415955,
| |
| Documents (ARs) 419957, 419958, 415999, 409590, 409591, 409937,
| |
| 2066, 412131, 412465, 414328, 414384, 414642,
| |
| 415308, 415383, 415384, 415575, 417741
| |
| Drawings EWD-46E-252 Electrical Wiring Diagram AC Electrical Distribution System 021
| |
| Power Panel E=PP-8AF
| |
| Engineering 16619 Credit CCH for MCR Equipment Operability 002
| |
| Changes
| |
| Miscellaneous FA-PR20001875-1 Failure Analysis Report for Regulating Transformers SOLA 000
| |
| P/N 63-28-315-8
| |
| IST-4 Inservice Testing Program Plan Fourth Ten-Year Inspection 004, 005
| |
| Interval
| |
| Procedures 18.1.19 CCH-P-1A Pre-service Test 000, 001
| |
| 18.1.21 CCH-P-1B Pre-service Test 000
| |
| SOP-ELEC-AC-LU AC Electrical Distribution System Breaker Lineup 077
| |
| Work Orders 02167660, 02171486, 02157840
| |
| 25
| |
| }} | | }} |
