IR 05000454/2023003

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Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion
ML23312A317
Person / Time
Site: Byron  Constellation icon.png
Issue date: 11/13/2023
From: Hironori Peterson
NRC/RGN-III/DORS/RPB3
To: Rhoades D
Constellation Energy Generation
References
EA-23-086 IR 2023003
Download: ML23312A317 (1)


Text

SUBJECT:

BYRON STATION - INTEGRATED INSPECTION REPORT 05000454/2023003 AND 05000455/2023003 AND EXERCISE OF ENFORCEMENT DISCRETION

Dear David Rhoades:

On September 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Byron Station. On October 27, 2023, the NRC inspectors discussed the results of this inspection with H. Welt, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. One Severity Level IV violation without an associated finding is documented in this report. We are treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violations or the significance or severity of the violations documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Byron Station.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Byron Station.

November 13, 2023 This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Hironori Peterson, Chief Reactor Projects Branch 3 Division of Operating Reactor Safety Docket Nos. 05000454 and 05000455 License Nos. NPF-37 and NPF-66

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000454 and 05000455

License Numbers:

NPF-37 and NPF-66

Report Numbers:

05000454/2023003 and 05000455/2023003

Enterprise Identifier:

I-2023-003-0059

Licensee:

Constellation Energy Generation, LLC

Facility:

Byron Station

Location:

Byron, IL

Inspection Dates:

July 01, 2023 to September 30, 2023

Inspectors:

N. Bolling, Project Engineer

J. Cassidy, Senior Health Physicist

A. Demeter, Resident Inspector

R. Knutson, Illinois Emergency Management Agency

J. Masse, Project Engineer

V. Petrella, Resident Inspector

J. Robbins, Senior Resident Inspector

Approved By:

Hironori Peterson, Chief

Reactor Projects Branch 3

Division of Operating Reactor Safety

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Byron Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

0A Control Room Ventilation Inoperable due to Jumpers left on 0PR031J and 0PR032J (LER No. 454-2023-001-00 and 454-2023-001-01)

Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000454,05000455/2023003-01 Open/Closed

[H.3] - Change Management 71153 A self-revealed finding of very low safety significance (Green) and an associated non-cited violation (NCV) of Technical Specification (TS) 5.4.1.a, Administrative Controls - Procedures, was identified for the licensees failure to have station procedures appropriate for the circumstances to address defeating and restoring interlocks on radiation monitors 0PR31J, Control Room Outside Air Intake A, and 0PR32J, Control Room Outside Air Intake B. Additionally, a violation of TS LCO 3.3.7, Control Room Ventilation (VC)

Filtration System Actuation Instrumentation, was also identified.

0B Control Room Ventilation Supply Fan Failed to Start due to Erroneous Position Indication from the Closed Limit Switch for Charcoal Deluge Valve Interlock (LER No. 454-2022-001-00)

Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000454,05000455/2023003-02 Open/Closed Not Applicable 71153 A self-revealed, Severity Level (SL) IV, non-cited violation (NCV) of Technical Specification (TS) Limiting Condition for Operation (LCO) 3.7.10, Control Room Ventilation (VC) Filtration System, was self-revealed when it was discovered that one of the two trains of VC was inoperable.

Additional Tracking Items

Type Issue Number Title Report Section Status ED EA-23-086 Enforcement Action EA-23-086: Failure to Comply with 10 CFR Part 37 71124.08 Closed LER 05000455, 05000454/2022-001-00 LER 2022-001-00 for Byron Station, Units 1 and 2,

OB Control Room Ventilation Supply Fan Failed to Start due to Erroneous Position Indication from the Closed Limit Switch for Charcoal Deluge Valve Interlock 71153 Closed LER 05000454, 05000455/2023-001-00 LER 2023-001-00 for Byron Station, Units 1 and 2, 0A Control Room Ventilation Inoperable due to Jumpers left on 0PR031J and 0PR032J 71153 Closed LER 05000454, 05000455/2023-001-01 LER 2023-001-01 for Byron Station, Units 1 and 2, 0A Control Room Ventilation Inoperable Due to Jumpers Left on 0PR031J and 0PR32J 71153 Closed

PLANT STATUS

Unit 1 began the inspection period operating at full power. Apart from minor reductions in power to support scheduled testing activities or small load changes requested by the transmission dispatcher, Unit 1 remained at or near full power for the duration of the inspection period, except for the following: In the early morning hours of September 16, Unit 1 began reducing power to 25 percent to support the replacement of a failed flow instrument (1FT-0415, RC Flow Loop 1A DP Cell Transmitter). The unit returned to full power in the early morning hours of September 17.

Unit 2 began the inspection period operating at full power. Apart from minor reductions in power to support scheduled testing activities or small load changes requested by the transmission dispatcher, Unit 2 remained at or near full power until September 20, 2023.

On September 20, the unit reached the end of the fuel cycle, and power coast down operations commenced in preparation for its planned B2R24 Refuel Outage. The unit continued to reduce power in accordance with the licensees approved reactivity management plan and was operating at approximately 95 percent power at the end of the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 2 Component Cooling Water (CCW) and 2B Diesel Generator (DG) systems during a 2A Component Cooling Pump work window, as documented in Work Order (WO) 53070877 on July 7, 2023
(2) Common Fire Protection System during 0B Fire Pump replacement work window, as documented in WO 5370877 on July 20, 2023
(3) Unit 2 Train A DG restoration of standby lineup following monthly run, on August 2, 2023

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Fire Zones 11.2A-D, Unit 1 and 2 Auxiliary Building (AB) 346' elevation, prior to a 1B Residual Heat Removal (RH) pump work window on July 10, 2023
(2) Fire Zone 3.3A-1, AB 463' elevation, Unit 1 Upper Cable Spreading Room on July 13, 2023
(3) Fire Zones 18.12-0 and 18.13-0, Circulating Water Pump House / 0B Fire Pump Room on July 19, 2023
(4) Fire Zones 11.6 and 12.1, AB 426' elevation and Fuel Handling Building during hourly fire watch as a result of a non-functional security door on July 31, 2023
(5) Review of engineering evaluations of combustible floor loading in permanent storage areas on August 14, 2023

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the on-site fire brigade training and performance during an unannounced fire drill on September 12, 2023.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance involving on-watch operations crews in the control room during various activities on September 16, 2023.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)

The inspectors observed and evaluated the following licensed operator training activities, which included the administration of the annual requalification operating test required by 10 CFR 55.59(a)(2) in the facilitys control room simulator:

(1) The inspectors observed and evaluated Licensed Operator Requalification Training/Examination OBE 23-4-1, Revision 0, on August 8, 2023.
(2) A complex casualty graded scenario involving a crew of licensed operators was observed in the facility's simulator during the conduct of the annual requalification operating test (BY-89, Revision 1), on August 23, 2023.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 Samples)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Maintenance effectiveness review associated with the Unit 1 1B Diesel-Driven Auxiliary Feedwater (AF) Pump following discovery of a hose being installed opposite of work instructions on July 10, 2023
(2) Maintenance effectiveness and performance history review of WOs containing quality control hold points, commercial grade dedications, and item equivalency evaluations on August 3, 2023
(3) Maintenance effectiveness review associated with the 0A Essential Service Water Makeup Pump following the pump trips on September 29, 2023

Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:

(1) Maintenance effectiveness review associated with the 0VA86Y, Non-accessible Filter Plenum Inlet Isolation Damper, following the discovery of the damper being failed open, as documented in Issue Report (IR) 4692039

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Review and evaluation of the planning for emergent work, including potential License Amendment Request/Notice of Enforcement Discretion actions associated with the 1SI8875 leakby, as documented in IR 4682829 on July 26, 2023
(2) Review and evaluation of the emergent work associated with the 2A Feedwater Pump Auxiliary Oil Pump following signs of degradation, as documented in IR 4691555 on August 14, 2023
(3) Review and evaluation of the planned work associated with new fuel receipt and inspection in preparation for Refueling Outage B2R24, as documented in WO 5288259 on August 23, 2023
(4) Verification of select risk mitigating actions implemented in the plant during planned work on the 1A DG on August 29 and 30, 2023
(5) Review and evaluation of planned work following the failure of 1A Reactor Coolant System (RCS) Loop Flow transmitter, 1FT-415, and the associated Risk-Informed Completion Time (RICT) implementation on September 5 and 6, 2023

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

The inspectors evaluated the licensees justifications and actions associated with the following operability determinations and functionality assessments:

(1) Evaluation of the operability of the Unit 1 Safety Injection (SI) Accumulators following regulator drift, as documented in IR 4666851 on July 19, 2023
(2) Evaluation of the operability of the 1B Emergency Diesel Starting Air System following issues eliminating a system leak, as documented in IR 4666851 on July 27, 2023
(3) Evaluation of the operability of the Unit 2 Turbine Generator/Exciter following terminal point failure during testing, as documented in IR 4694183 on August 9, 2023
(4) Evaluation of the operability of the Unit 1 Power Distribution Monitoring System following instrumentation spiking, as documented in IR 4693490 on September 12, 2023
(5) Evaluation of the operability of the unit common CCW system following the discovery of missed relief valve testing on 0CC9432, as documented in IR 4692423 on September 18, 2023
(6) Evaluation of the operability of the Unit 1, Train A, Emergency Diesel Generator following the discovery of degraded coating and internal corrosion/wall thinning, as documented in IR 4699483 on September 18, 2023

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) Review of a permanent plant modification per Engineering Change (EC) 637998, Unit 2 SI Accumulator Nitrogen Supply Line Additional Isolation Valve on September 13, 2023
(2) Review of a temporary modification per EC 394524, Plant Barrier Impairment Permit Number 23-270, Door Fire/Security RS TB1 to 1DG01KA on September 19, 2023

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:

Post-Maintenance Testing (PMT) (IP Section 03.01) (7 Samples)

(1) Functional and operational testing of the 1A Emergency Diesel Generator (EDG) Start-up Air Compressor following maintenance, as documented in WOs 5221703,

===5221704, and 5221703 on July 10, 2023

(2) Functional and operational testing of the 1B RH pump following maintenance, as documented in WO 5279058 on July 17, 2023
(3) Functional and operational testing of the 1B SI Pump following maintenance, as documented in WO 5336258 on August 8, 2023
(4) Functional and operational testing of 1A EDG following maintenance described in multiple WOs on September 2, 2023
(5) Functional and operational testing of 1FT-0415, 1A Reactor Coolant Loop Flow Transmitter, as documented in WO 5386483 on September 25, 2023
(6) Functional and operational testing of the 0B Fire Pump following maintenance, as documented in WO 5315760 on August 18, 2023
(7) Functional and operational testing of the 2SX033 Valve following maintenance, as documented in WO 5230551 Surveillance Testing (IP Section 03.01)===

(1)1BOSR 7.5.4-2, Unit One Diesel-Driven AF Pump Monthly Surveillance, as documented in WO 5377336 on July 19, 2023

(2) MA-BY-723-054, Nickel Cadmium Battery Bank Surveillance for the AF System Batteries, as documented in WO 5356990 on August 16, 2023 (3)2BOSR 5.5.8.CS.5-2C, 2B CS Pump Comprehensive, as documented in WO 5370661 on August 17, 2023

Inservice Testing (IST) (IP Section 03.01) (1 Sample)

(1) Inservice Testing of the 1B Component Cooling Pump as documented in WO 5378814 on September 22, 2023

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) A Drill/Training Evolution on September 28,

RADIATION SAFETY

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling,

Storage, & Transportation

Radioactive Material Storage (IP Section 03.01)

The inspectors evaluated the licensees performance in controlling, labeling and securing the following radioactive materials:

(1) Energy Solutions dry active waste seavans
(2) Waste liners and filter drums in the radwaste building

Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)

The inspectors walked down the following accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality:

(1) Radioactive waste building 401' elevation

Waste Characterization and Classification (IP Section 03.03) (3 Samples)

The inspectors evaluated the following characterization and classification of radioactive waste:

(1) Dry Active Waste
(2) Spent Resin Storage Tank
(3) Radwaste Resin

Shipping Records (IP Section 03.05) (4 Samples)

The inspectors evaluated the following non-excepted radioactive material shipments through a record review:

(1) RWS22-06; Resin Cask; LSA-II
(2) RWS22-10; Resin Cask; LSA-II
(3) RWS23-02; Resin Cask; LSA-II
(4) RWS23-16; 20' Oil Pan Sealand of Oil; LSA-II

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS08: Heat Removal Systems (IP Section 02.07)===

(1) Unit 1 (July 1, 2022 through June 30, 2023)
(2) Unit 2 (July 1, 2022 through June 30, 2023)

MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)

(1) Unit 1 (July 1, 2022 through June 30, 2023)
(2) Unit 2 (July 1, 2022 through June 30, 2023)

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)

(1) Unit 1 (October 1, 2022 through June 30, 2023)
(2) Unit 2 (October 1, 2022 through June 30, 2023)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) June 1, 2022 through June 30, 2023 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
(1) June 1, 2022 through June 30, 2023

71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Review and assessment of the stations corrective actions following multiple battery voltage drops in the AF System, as documented in various IRs on August 7, 2023
(2) Review and assessment of the stations corrective actions following the failure to start of the 1B AF Pump during a monthly surveillance, as documented in IR 4679424 on September 25, 2023

71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 454-2022-001-00, 0B Control Room Ventilation Supple Fan Failed to Start due to Erroneous Position Indication from the Closed Limit Switch for Charcoal Deluge Valve Interlock, (ADAMS Accession No. ML22252A138). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER, therefore no performance deficiency was identified. The inspectors did identify a violation of NRC requirements. The inspection conclusions associated with this LER are documented in this report under Inspection Results Section 71153. This LER is Closed.
(2) LER 454-2023-001-00 for Byron Station, Units 1 and 2, 0A Control Room Ventilation Inoperable due to Jumpers left on 0PR031J and 0PR032J, (ADAMS Accession No. ML23135A079). The inspection conclusions associated with this LER are documented in this report under Inspection Results Section 71153. This LER is Closed.
(3) LER 454-2023-001-01 for Byron Station, Units 1 and 2, 0A Control Room Ventilation Inoperable Due to Jumpers Left on 0PR031J, and 0PR32 (ADAMS Accession No. ML23135A079). The inspection conclusions and associated with this LER are documented in this report under Inspection Results Section 71153. This LER is Closed.

INSPECTION RESULTS

Enforcement Discretion Enforcement Action EA-23-086: Failure to Comply with 10 CFR Part 37 71124.08

Description:

On April 27, 2016, the licensee was issued NRC Inspection Report Nos. 05000454/2016406 and 05000455/2016406, which documented a licensee identified violation of 10 CFR Part 37, Physical Protection of Category 1 and Category 2, Quantities of Radioactive Material at Facilities with a 10 CFR Part 73, Physical Protection Program. The violation met the criteria for Enforcement Discretion as described in Enforcement Guidance Memorandum (EGM)14-001, Interim Guidance for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Material at Power Reactor Facilities Licensed Under 10 CFR Parts 50 and 52.

Subsequently, the inspectors re-evaluated this activity and found that while a violation of regulatory requirements continues to exist, the conditions remain within the criteria for enforcement discretion established within EGM 14-001.

Corrective Actions: As specified in EGM 14-001, the application of discretion is authorized until the underlying technical issue is dispositioned through rulemaking or other regulatory action.

Corrective Action References: Not Applicable

Enforcement:

Violation: On April 27, 2016, a violation of 10 CFR Part 37 was documented in Byron Inspection Report Nos. 05000454/2016406 and 05000455/2016406. The inspectors determined that the previously identified violation remains.

Basis for Discretion: This violation met the criteria for Enforcement Discretion as described in Enforcement Guidance Memorandum (EGM) 14-001, Interim Guidance for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Material at Power Reactor Facilities Licensed Under 10 CFR Parts 50 and 52.

Observation: Tracking and Trending of Auxiliary Feedwater System Battery Surveillance Results 71152A The inspectors performed a detailed review of Issue Report (IR) 4690928, 1AF01EA-B Battery Surveillance. On July 17, 2023, the station began performing the Auxiliary Feedwater (AF) System quarterly surveillance tests on Unit 1, under Work Order (WO) 5356990. The Unit 1 AF system batteries were tested on July 17, 2023, and the Unit 2 AF system batteries were tested on July 18, 2023, using procedure MA-BY-723-054, Nickel Cadmium Battery Bank Surveillance. Inspectors selected this issue, in part, because several cells between the two units were found to have voltages below the administrative voltage of 1.35 VDC (Volts Direct Current).

Step 4.4.1.4 of MA-BY-723-054 states, in part, that if battery cell voltage is less than 1.35 VDC, an IR is to be initiated. Individual cells had voltages that were below the administrative level with the charger on, but overall battery voltage with the charger off was 26.9 VDC, above the minimum required voltage of 26 VDC. Engineering determined that no further action was necessary as all values were within acceptance criteria and that trending should continue. IRs for the applicable cells with low voltages were written.

The inspectors reviewed 3 years of AF battery surveillance data and performed a corrective action program (CAP) search to determine the frequency of AF batteries reading below the administrative level of 1.35 VDC. The CAP items were then compared to trending data provided by the stations engineering department to determine the consistency between the two methods of tracking and trending. The inspectors did not identify any issues with the licensees CAP actions taken. Actions targeting low voltages included placing the batteries on an equalizing charge and proactive replacement of battery cells and banks as appropriate.

While no issues with the actions taken were identified, inspectors observed that there were several instances where battery cells were below the administrative level, but no associated IR could be located that documented this condition for trending purposes. Additional inconsistencies were found between the surveillance record, engineering trending data, and IRs attributed to typos or transcription errors.

No findings or violations of NRC requirements of more than minor safety significance were identified by the inspectors in the course of this review.

Observation: Review of Similar Pump Failures Following the Failure to Start of the 1B Auxiliary Feedwater Pump 71152A The inspectors performed a detailed review of IR 4679424, 1B AF Pp failed to start. The licensee determined foreign material (FM) in the fuel shutoff solenoid valve, 1AF01PB-K-L1, caused the failure. The inspectors chose this issue for an indepth review of the licensees actions within their corrective action program (CAP) because of the inherent safety significance associated with the potential inability to remove heat from the reactor coolant system during a design-basis accident.

Both the Essential Service Water (SX) makeup pumps and the AF pumps utilize the same type of components within their governor oil systems. Because of these similarities, the inspectors examined the licensees corrective actions related to previous SX makeup pump and AF pump failures caused by FM. Additional pump failures selected for review share characteristics to the 1B AF pump failure: the presence of foreign material was, at least in part, the cause of the failure, and the pumps had previous successful runs prior to the failure.

Several observations by the inspectors were made with regards to the IRs:

  • Several failures of pumps and associated concerns were captured across various IRs.

The inspectors concluded that titles of the IRs do not always fully indicate the scope of the issues discussed within the IR, thus making the failures and their associated corrective actions more difficult to track and trend.

  • IR 4029120, 0A SX M/U Pump Failed to Start, created a corrective action to include a step in the upcoming engine oil change to perform a filter analysis and visual/borescope inspection of the oil reservoir and lines following a failure to start of the 0A SX Makeup Pump due to FM in the shutdown solenoid valve. The associated WO contains steps for both actions, but the licensee could not find records for the results. The inspectors concluded that the absence of this potentially useful information represented a missed opportunity to either contribute to subsequent evaluations or prevent subsequent failures.

No findings or violations of NRC requirements of more than minor safety significance were identified by the inspectors in the course of this review.

0A Control Room Ventilation Inoperable due to Jumpers left on 0PR031J and 0PR032J (LER No. 454-2023-001-00 and 454-2023-001-01)

Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000454,05000455/2023003-01 Open/Closed

[H.3] - Change Management 71153 A self-revealed finding of very low safety significance (Green) and an associated non-cited violation (NCV) of Technical Specification (TS) 5.4.1.a, Administrative Controls - Procedures, was identified for the licensees failure to have station procedures appropriate for the circumstances to address defeating and restoring interlocks on radiation monitors 0PR31J, Control Room Outside Air Intake A, and 0PR32J, Control Room Outside Air Intake B. Additionally, a violation of TS LCO 3.3.7, Control Room Ventilation (VC)

Filtration System Actuation Instrumentation, was also identified.

Description:

On March 16, 2023, as reported in LER No. 454-2023-001-00 and 454-2023-001-01, following the failure of the 0A Control Room Ventilation (VC) to actuate during the 1A Diesel Generator (DG) sequencer testing, the licensee determined they had operated in a condition prohibited by TS. The licensee concluded that jumpers installed to support a Unit 1 bus outage had not been removed during the completion and restoration of the bus. Therefore, the 0A train of Control Room Ventilation Filtration System Actuation Instrumentation was inoperable for approximately 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />. The failure to remove the jumpers was attributed to changes made to work instructions outside of the change/revision process as defined in MA-AA-716-010, Maintenance Planning, Attachment 1, Example of Work Package Revision Guidelines. A latent error (typographical error in equipment identification nomenclature (EPN) in the restoration instructions) also contributed to this event.

Specifically, licensee staff made multiple changes/revisions to work instructions located in WO 5188331-01, Support Rad Monitor Shutdown/Startup Bus 141/131X Outage, but failed to recognize that the changes made were not minor as defined in MA-AA-716-010, Maintenance Planning, Attachment 1, Example of Work Package Revision Guidelines, and therefore required review and approval by a qualified planner prior to implementation. At Steps 7.4.2 and 7.4.3, licensee staff revised the work package to install jumpers in place of lifting leads. Staff failed to make corresponding changes to Steps 7.7.2 and 7.7.3, the section that would have restored the actuation instrumentation interlocks by removing jumpers installed in Steps 7.4.2 and 7.4.3. Additionally, licensee staff revised Steps 7.7.2 and 7.7.3 by marking them as not applicable (N/A) due to an error in the WO that identified the equipment of interest as 0AR031J and 0AR032J, vs 0PR31J and 0PR32J.

While in Mode 1, 2, 3, 4, 5, 6, and during movement of irradiated fuel assemblies, TS LCO 3.3.7, Control Room Ventilation (VC) Filtration System Actuation Instrumentation, requires that instrumentation for each function in Table 3.3.7-1 be operable. Table 3.3.7-1 states that, for the function of Control Room Radiation-Gaseous, two channels per train are required. TS LCO 3.3.7 Action statement, Condition A requires that, with one or more channels on one train inoperable, place the redundant VC Filtration System train in normal mode or place one VC Filtration System train in emergency mode. The completion time for this action is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. When Condition A is not met, Condition C requires the unit be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The jumpers installed on 0PR31J and 0PR32J caused both channels of Control Room Radiation-Gaseous detection on the 0A train to be inoperable while the 0A train was in-service in the normal mode and the 0B train was secured. This resulted in the TS, Condition A, and part of Condition C not being met.

For approximately 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />, the 0A Train of VC was in-service and the 0A train of Actuation Instrumentation was inoperable and actions were not taken to restore the 0A train to operable status or to place the redundant VC Filtration System train in normal mode or place one VC Filtration System train in emergency mode, and no actions were taken to place the unit in hot standby, therefore a violation of TS LCO 3.3.7 occurred.

Corrective Actions: Once identified, the jumpers were removed, restoring the 0A Train of VC to operable.

Corrective Action References: AR 4562629, Issue During DG Sequence Testing

Performance Assessment:

Performance Deficiency: The inspectors determined that the failure to follow the change/revision process as described in MA-AA-716-010, Maintenance Planning, 1, Example of Work Package Revision Guidelines, was a performance deficiency and was within the licensees ability to foresee and correct.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Procedure Quality attribute of the Mitigating Systems cornerstone and adversely affected the cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. (i.e., core damage).

Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power.

Exhibit 3, Barrier Integrity Screening Questions, and determined that this finding was of very low safety significance (Green).

Cross-Cutting Aspect: H.3 - Change Management: Leaders use a systematic process for evaluating and implementing change so that nuclear safety remains the overriding priority.

(LA 5).

Enforcement:

Violation: Technical Specification Section 5.4.1.a requires, in part, that written procedures be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978.

NRC Regulatory Guide 1.33, Revision 2, Appendix A, Section 9 addresses Procedures for Performing Maintenance and Section 9.a, addresses Maintenance that can affect the performance of safety-related equipment should be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.

The licensee established Work Order (WO) 5188331, Support RAD Monitor Shutdown/Startup Bus 141/131X Outage, Revision 0, in part, to address defeating and restoring interlocks on 0PR31J, Control Room Outside Air Intake A, and 0PR32J, Control Room Outside Air Intake B. WO 5188331, Step 7.7.2 requires: restore interlocks to 0AR031J by reconnecting field lead TB1-11, TB1-12, TB1-7, and TB1-10. Step 7.7.3 requires: restore interlocks to 0AR032J by reconnecting field lead TB1-11, TB1-12, TB1-7, and TB1-10.

While in Mode 1, 2, 3, 4, 5, 6, and during movement of irradiated fuel assemblies, TS LCO 3.3.7, Control Room Ventilation (VC) Filtration System Actuation Instrumentation, requires that instrumentation for each function in Table 3.3.7-1 be operable. Table 3.3.7-1 states that, for the function of Control Room Radiation-Gaseous, two channels per train are required.

LCO 3.3.7 Action statement, Condition A requires that, with one or more channels on one train inoperable, place the redundant VC Filtration System train in normal mode or place one VC Filtration System train in emergency mode. The completion time for this action is 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

LCO 3.3.7 Action statement, Condition C requires that, when Condition A is not met, the unit be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Contrary to the above, on March 15 and 16, 2023, for approximately 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />, while Unit 1 was in Mode 6 and Unit 2 was in Mode 1, the licensee failed to implement Steps 7.7.2 and 7.7.3 of WO 5188331 and restore interlocks on 0PR31J and 0PR32J. Specifically, at Steps 7.4.2 and 7.4.3, licensee staff revised the work package to install jumpers in place of lifting leads. Staff failed to make corresponding changes to Steps 7.7.2 and 7.7.3, the section that would have restored the actuation instrumentation interlocks by removing jumpers installed in Steps 7.4.2 and 7.4.3. Additionally, licensee staff revised Steps 7.7.2 and 7.7.3 by marking them as not applicable (N/A) due to an error in the WO that identified the equipment of interest as 0AR031J and 0AR032J vs 0PR31J and 0PR32J.

Additionally, on March 15 and 16, 2023, for approximately 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />, while Unit 1 was in Mode 6 and Unit 2 was in Mode 1, actions were not taken to restore the 0A train to operable status or to place the redundant VC Filtration System train in normal mode or place one VC Filtration System train in emergency mode, and no actions were taken to place the unit in hot standby.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

0B Control Room Ventilation Supply Fan Failed to Start due to Erroneous Position Indication from the Closed Limit Switch for Charcoal Deluge Valve Interlock (LER No. 454-2022-001-00)

Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000454,05000455/2023003-02 Open/Closed Not Applicable 71153 A self-revealed, Severity Level (SL) IV, non-cited violation (NCV) of Technical Specification (TS) Limiting Condition for Operation (LCO) 3.7.10, Control Room Ventilation (VC) Filtration System, was self-revealed when it was discovered that one of the two trains of VC was inoperable.

Description:

On July 12, 2022, as reported in LER No. 454-2022-001-00, following the failure of the 0B Control Room Ventilation (VC) Supply Fan (0VC01CB) to Start on demand, the licensee determine they had operated in a condition prohibited by TS. The licensee conclude that the last successful operation of the supply fan was on May 23, 2022. Therefore, the 0B train of VC was inoperable between May 23, 2022, and July 12, 2022. The cause of the 0B VC supply fan failure to start was a limit switch operating lever rolling under the limit switch finger which caused a fire protection valve (0FP432B) to appear to be in the intermediate or open position. This caused the supply fan shunt trip coil to remain energized, thereby preventing the fan breaker from remaining closed after the start command.

The VC system has two full capacity redundant equipment trains that perform the same function. The VC HVAC (heating, ventilation, and air conditioning) system is designed to ensure control of environmental conditions within specified maximum and minimum limits which are conducive to personnel habitability and prolonged service life of Safety Category I components under all normal and abnormal station operating conditions. The 0A Train of VC remained operable during this event (i.e., between May 23, 2022, and July 12, 2022).

While in Mode 1, TS LCO 3.7.10, Control Room Ventilation (VC) Filtration System, requires that two VC Filtration System trains be operable. The loss of the 0B VC supply fan causes the 0B train to be inoperable and resulted in this TS LCO not being met.

Corrective Actions: The actuator arm was replaced with a longer actuator arm, and the limit switch was adjusted to properly make up the closed limit, then the supply fan was started, restoring the 0B train of VC to operable.

Corrective Action References: AR 4510429, 0VC01CB Failed to Start AR 4511202, 0B VC Recirculation Charcoal Deluge Valve Limit Switch

Performance Assessment:

The NRC determined this violation was not reasonably foreseeable and preventable by the licensee, and therefore is not a performance deficiency. Specifically, the switch in question was installed for more than a decade, the system was routinely tested and no performance issues had previously been identified. Additionally, the failure did not cause any abnormal indications or alarms while in a standby configuration.

Enforcement:

Enforcement Policy Section 2.2.4 states, in part, that violations not associated with Reactor Oversight Process (ROP) findings be dispositioned using traditional enforcement. Therefore, operating reactor violations with no associated performance deficiencies should be assigned a severity level as long as the violation meets the criteria described in Section 2.3.2 of the Policy for disposition as an NCV.

Severity: Traditional Enforcement is being used to disposition this violation with no associated Reactor Oversight Process finding, per NRC Enforcement Manual, dated January 14, 2022, Section 2.2, Assessment of Violations, item 2.2.4.d, violations not associated with ROP findings. The inspectors determined the severity of the violation using Section 6 of the NRC Enforcement Policy and determined this issue was a Severity Level IV (SL IV) because it was similar to the examples in Section 6.1.d.

Violation: Technical Specification LCO 3.7.10 requires that while the plant is in Mode 1, 2, 3, 4, 5, and 6, during movement of irradiated fuel assemblies, two Control Room Ventilation Filtration System trains be operable. TS LCO 3.7.10 Action statements require that, with one VC Filtration System train inoperable for reasons other than Condition B, which did not apply, restore VC Filtration System train to operable status in 7 days or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Contrary to the above, between May 23, 2022 and July 12, 2022, while both units were in Mode 1, the 0B train of VC was inoperable due to the failure of the 0B VC Supply Fan to start on July 12, 2002, due to erroneous position indication from the closed limit switch for the Charcoal Deluge Valve Interlock, and action was not taken to either restore the system train to operable status within 7 days or place the unit in cold shutdown within the following 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

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

  • On October 27, 2023, the inspectors presented the integrated inspection results to H. Welt, Site Vice President, and other members of the licensee staff.
  • On July 13, 2023, the inspectors presented the radiation protection inspection results to J. Burton, Radiation Protection Operations Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

22355

EOC - @A EDG Intake Bolt Proof Torque

09/14/2022

26716

2A DG NGT Ground Resistor Outside Acceptance Criteria

10/04/2022

26853

2A DG Taken Apart with 2B Not Functioning Correctly

10/04/2022

4558767

0FP03PB Leak at Oil Filter Connection to Crankcase

03/02/2023

4680207

Fire Pump Battery Cells Below SG Acceptance Criteria

05/22/2023

4686508

0FP03PB 0B FP Leaking Coolant

06/23/2023

4686514

0TI-FP8023 0B FP Jacket Water Temp Gauge

06/23/2023

4688979

0B FP Pump Unexpected Alarm

07/06/2023

4690382

0B Fire Pump Surveillance Issues

07/13/2023

Corrective Action

Documents

4691325

Removed 0FP775B Failed Testing

07/19/2023

2BOSR 8.1.2-1

Unit Two, 2A Diesel Generator Operability Surveilance

BOP CC-E2A

Unit 2 Component Cooling System Train A Electrical Lineup

BOP CC-E2B

Unit 2 Component Cooling System Train B Electrical Lineup

BOP CC-E2C

Unit 2 Component Cooling System Train C Electrical Lineup

BOP CC-M2A

Unit 2 Component Cooling System Train A Valve Lineup

(Train A Safety Loop and Seal Water HX)

BOP CC-M2B

Unit 2 Component Cooling System Train B Valve Lineup

(Train B Safety Loop and Seal Water HX)

BOP CC-M2C

Unit 2 Component Cooling System Train C Valve Lineup

BOP DG-E2B

Unit 2 Diesel Generator Train B Electrical Lineup

BOP DG-M2B

Unit 2 Train B Diesel Generator System Valve Lineup

BOP FP-E1

Unit 1 Fire Protection System Electrical Lineup

BOP FP-E2

Unit 2 Fire Protection System Electrical Lineup

BOP FP-E3

Unit 0 Fire Protection System Electrical Lineup

Procedures

BOP FP-M1

Fire Protection System Valve Lineup

28088

Run Time Meter Not Working on 2A CC PP Breaker

07/05/2023

232069

Remove Relief Valve to Support Op Surv 0BOSR 3.10.B.12-1

07/19/2023

238289

CC Pump 2A Suct Press Indicator

07/05/2023

239042

(Sample/Change) Component Cooling Pump 2A - Increased

Freque

07/05/2023

71111.04

Work Orders

296948

0FP03PB Oil Leak

07/17/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

5303068

4KV Relay Routine Calibration (2A CC Pump)

07/05/2023

5307197

(Sample/Change) Component Cooling Pump 2A

07/05/2023

5370877

NEIL - Perform 2Y PM on Diesel Driven Fire Pump

07/17/2023

4685508

Quarterly Review of Fire Brigade Drill Performance

06/19/2023

4690186

Fire Protection Water Sample Collection

07/12/2023

4690201

Chemistry Sample in 0BOSR 10.c.2-1

07/12/2023

4691321

1C CW Pump Coupling Housing Pump Is Not Working

07/19/2023

4691360

FP Program Health Cornerstone Yellow for 1P2023

07/19/2023

4691485

0A FP Green Light Is Broke in The Socket

07/19/2023

4691497

Fire Protection Test Header Piping Leak

07/19/2023

4691772

0FP5118 Alarm Shut Off Left Closed

07/21/2023

4691810

PM Hold Applied on 0BSOR FP-A3

07/21/2023

4691886

WSA/DSA WO#5058994-01

07/21/2023

4692781

Unexpected MCR Fire Alarm for 1D-11

07/26/2023

4692864

Unexpected Alarm-CWPH Fire Alarm. Zone 1D-22

07/27/2023

4693215

0FP222E Issue

07/28/2023

4693220

Unexpected MCR Fire Alarm (1D-17 & 1D-40),

364 Aux Building

07/28/2023

4693269

Unexpected MCR Fire Alarm (1D-20), 1B CS/RH Pp Rooms

07/28/2023

4693357

0DSD725 Upper Flush Bolt Not Working

07/29/2023

4693420

0B FP FO Tank Level Below Rounds Min

07/30/2023

4693440

0B Fire Pump Speed Adjustment Needed

07/29/2023

4693487

0FP0775A Removed Relief Valve Failed Testing

07/30/2023

4693578

Fire Protect Pull Switches Found Failed During Surveillance

07/31/2023

4693869

Fire Protection Test Header Degraded

07/31/2023

4693875

Play Pipes Below Minimum for Future FP Surveillances

08/01/2023

4694166

0FP042A Valve Handle Spinning Free

08/02/2023

4694619

Trng Bldg Fire Protection Surveillance Unsat

07/31/2023

4694817

Godwin HL110M B.5.B Pump Needs to be Cleaned After Each

Run

08/05/2023

4694819

Low Head FLEX Pump Needs to be Cleaned After Each Run

08/05/2023

4694843

ETL on 1VD24YB is Delaminating

08/05/2023

71111.05

Corrective Action

Documents

4694960

Missing Items from FLEX Inventory Surveillance

08/06/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

4695446

Permanent Storage Areas

08/08/2023

4695457

0FS-FP203 May Need Calibration or Repair

08/08/2023

4699458

0FPJ3A - UT Reading is Below the 87.5% Acceptance Criteria

08/30/2023

4700136

0FP5013 Missing Handwheel Needs to Have Priority

Re-Evaluated

09/02/2023

4700689

0BOSR 10.B.10-1 FP Flush and Flow Test Not Completed

09/06/2023

4700939

Acceptance Criteria/Data Sheet Discrepancy

09/06/2023

340168

Permanent Storage of Refueling Outage Related Materials

Inside Unit 1 Containment

345057

Permanent Storage of Refueling Outage Related Materials

Inside Unit 1 Containment

Engineering

Evaluations

347429

Permanent Storage of Additional Refueling Outage Related

Materials Inside Unit 2 Containment

Pre-Fire Plan

Fire Zone 11.6-0 Auxiliary Building 426'-0" Elevation Auxiliary

Building General Area - North

Pre-Fire Plan 103

Fire Zone 11.2A-1 Aux. Bldg. 346'-0" Elev. 1A RHR Pump

Room

Pre-Fire Plan 104

Fire Zone 11.2A-2 Aux. Bldg. 346'-0" Elev. 2A RHR Pump

Room

Pre-Fire Plan 105

Fire Zone 11.2B-1 Aux. Bldg. 346'-0" Elev. 1A Containment

Spray Pump Room

Pre-Fire Plan 106

Fire Zone 11.2B-2 Aux. Bldg. 346'-0" Elev. 2A Containment

Spray Pump Room

Pre-Fire Plan 107

Fire Zone 11.2C-1 Aux. Bldg. 346'-0" Elev. 1A Containment

Spray Pump Room

Pre-Fire Plan 108

Fire Zone 11.2C-2 Aux. Bldg. 346'-0" Elev. 2B Containment

Spray Pump Room

Pre-Fire Plan 109

Aux. Bldg. 346'-0" Elev. 1B RHR Pump Room

Pre-Fire Plan 110

Fire Zone 11.2D-2 Aux. Bldg. 346'-0" Elev. 1B RHR Pump

Room

Pre-Fire Plan 155

Fire Zone 11.6-0 and 11.6C-0 Auxiliary Building 426'-0"

Elevation Auxiliary Building General Area - South & MMD

MOV Room

Fire Plans

Pre-Fire Plan 156

Fire Zone 11.6-0, 11.6D-0, and 11.5E-0 Auxiliary Building

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

26'-0" Elevation Auxiliary Building General Area - West,

Old Mens Changing Room & Hot Shop

Pre-Fire Plan 176

Fire Zone 12.1-0 Fuel Handling Building 401'-0" Elevation

Fuel Handling Building

Pre-Fire Plan 177

Fire Zone 12.1-0 Fuel Handling Building 426'-0" Elevation

Fuel Handling Building

Pre-Fire Plan 206

Fire Zone 18.12-0 and 18.13-0 Circulating Water Pump

House / 0B Fire Pump Room

Pre-Fire Plan 29

Fire Zone 3.3A-1 Aux. Bldg. 463 Elevation, Upper Cable

Spreading Room

MA-AA-716-026

Station Housekeeping/Material Condition Program

OP-AA-201-009

Control of Transient Combustible Material

OP-AA-201-012-

1001

Operations On-Line Fire Risk Management

Procedures

SA-AA-129-2118

Management and Control of Temporary Power

Work Orders

279058

PM Inspection, In-Service Diag Test, PIT

07/10/2023

1BGP 100-4

Power Descension

OP AA 101 111

1001

Operations Standards and Expectations

OP AA 101 113

Operator Fundamentals

OP AA 103 102

Watch Standing Practices

OP AA 103 103

Operation of Plant Equipment

71111.11Q

Procedures

OP AA 104 101

Communications

2589491

0B SX Makeup Pump Failed to Start

11/18/2015

4056789

0B SX Makeup Pump Tripped During Run, No Alarms

Received

09/28/2017

4104858

0B SX Makeup Pump Tripped during Monthly Surveillance

Run

2/16/2018

4106225

0B SX Makeup Pump Abnormal Alarm

2/20/2018

219925

Relay May Need Replacement

2/14/2019

4416626

0B SX Makeup Pump Engine Water Temperature RTD

Indicating OVER+

04/14/2021

71111.12

Corrective Action

Documents

4490482

0A SX Makeup Pump Trip

04/05/2022

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

4539770

0A SX Makeup Pump Trip

11/30/2022

4561338

NOS QV ID Incorrect Pre Heat on Weld Docs

03/12/2023

4561346

NOS QV ID Undersize Weld

03/12/2023

4562779

B1R25 LL LP Heater Manway Covers

03/17/2023

4672083

0VA86Y Failed Open

04/21/2023

4679424

1B AF Pp Failed to Start

05/19/2023

4685344

0VA086Y Found Failed

06/18/2023

4685821

MMD: Stop Work Criteria Entered on 1B AF PP Work Window

06/19/2023

4687057

0A SX Makeup Pump Trip

06/27/2023

4692039

0VA86Y Found Failed

07/23/2023

4701020

0A SX Makeup Pump Trip

09/07/2023

4701152

Potential Trend in 0A SX Makeup Pump Trips

09/08/2023

Engineering

Changes

B-91-003-0157-00

Parts Evaluation and Commercial Grade Dedication for Aux

Feedwater Diesel Governor Hoses and Fittings

09/27/1991

BYR-59609

Failure Analysis of Valve, Solenoid, 1/4" NPT, 2 Way Normally

Open

07/07/2023

Commercial

Grade Dedication

276896

Rebuild/Repair Kit, Intercooler, for Detroit Diesel 16V149TI

05/23/2023

Commercial

Grade Dedication

277338

CPE: Method 2 Detroit Diesel

2/12/2023

Commercial

Grade Dedication

277478

Fitting, Hose, Straight, 1-5/8 IN.-12, Steel, SAE 37 Degree

(JIC) Swivel, for Detroit Diesel 16V149TI

03/09/2023

Commercial

Grade Dedication

277653

Assembly, Plunger and Bushing, Injector, Fuel

01/30/2023

Commercial

Grade Dedication

277654

Kit, Rebuild, Seat, Spring, Without Cage, Injector, Fuel

04/10/2023

Miscellaneous

Commercial

Grade Dedication

278662

Injector, Fuel, Refurbished, 165 MM, for Series 146 Diesel En

04/06/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Commercial

Grade Dedication

279328

Fitting, Hose, Elbow, 45 Degree, 1-5/8 in.-12, Steel, SAE 37

Degree (JIC) Swivel, For

03/21/2023

Commercial

Grade Dedication

281303

Rebuild/Repair Kit, Injector, Fuel, Engine, Diesel

05/12/2023

Item Equivalency

Evaluation

268040

Hose, Metal, Braided, Single, 0.75 in.ID., 15.25 in. Overall

Length, Type 321 SS

04/03/2023

Item Equivalency

Evaluation

2210

Spacer, Seal, for Westinghouse Reactor Coolant Pump,

Model V11001-A1

06/22/2023

Item Equivalency

Evaluation

2928

Valve, Globe, 3/4 in., 1700 ANSI Class, Repair Report, Heat

Treat Report, and CMTR To

07/14/2023

Item Equivalency

Evaluation

2960

Assembly, Bowl, Pump, Model 16HXBF, 4 Stages, 39.7 Inch

Min. Submergence

01/10/2023

Item Equivalency

Evaluation

281741

Switch, Pressure, 1-40 PSIG Range, SPDT, Adjustable

Differential, NEMA 1 Enclosure

06/23/2023

OP-AA-101-113-

1004

Prompt Investigation Following the Failure to Start of the

1B AF Pp

05/20/2023

BMP 3100-84

Fabrication of Aeroquip Hoses

BMP 3100-86

Auxiliary Feedwater Flex Hose Replacements

000

CC-AA-204

Control Of Vendor Equipment Manuals

CC-AA-501-1003

Exelon Nuclear Welding Program Visual Weld Acceptance

Criteria

ER-AA-310-1002

Maintenance Rule Functions - Safety Significance

Classification

ER-AA-310-1008

Maintenance Rule Process Map

ER-AA-320

Maintenance Rule Implementation Per NEI 18-10

MA-AA-716-008

Foreign Material Exclusion Program

Procedures

NISP-EN-02

Standard Item Equivalency Process

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

NO-AA-10

Quality Assurance Topical Report (QATR)

NO-AA-300-1001

Nuclear Oversight Independent Inspection Plan

NO-AA-300-1002

Logging Quality Verification Inspections

NO-AA-50

Nuclear Oversight Vendor Audit (NOVA) Process Description

SM-AA-300

Procurement Engineering Support Activities

SM-AA-300-1001

Procurement Engineering Process and Responsibilities

SM-AA-3019

Parts Quality Initiative (PQI)

22384

Support Eddy Current Testing for 14A LP Heater

05/17/2023

5157042

Replacement of the Fuel Shutoff Solenoid

03/23/2023

5190636

1CB140B Replace Valve

05/25/2023

5190980

MVR - 1SX168 - Open/Inspect & Rebuild AOV

03/20/2023

20650

CM 1WS29AB-Disconnect/Reconnect Piping 1B Stator

WTR CLR

03/19/2023

237710

Diesel Drive AF Pump Insp Per BMP 3203-1

03/28/2023

5367243

1B AF Pp Failed to Start

05/20/2023

Work Orders

5373526

Emergent Work Window for 1AF01PB-K-L1

06/19/2023

4517766

A FW Pp Aux Oil Pp Making Rubbing Noise

08/19/2022

4552333

Activities Associated with EC 637903

2/03/2023

4679638

2A FW Pp Oil Filter High DP

05/21/2023

4681110

Change Out 2A FW Pump #2 Lube Oil Filter

05/28/2023

4682829

1SI8875A Leaking By

06/05/2023

4688165

2A FW Pp Aux Lube Oil Pp2FW01PA-B Motor Hot to Touch

07/01/2023

4691555

Debris Around Coupling Guard for 2A FW PP AOP

07/19/2023

4693308

2FW36J-HVA Filter Dirty

07/29/2023

4693309

2FW37J-HVA Filter Dirty

07/29/2023

Corrective Action

Documents

4697102

Westinghouse Reports Instances of Lock Tubes Out of

Position

08/17/2023

Engineering

Changes

637903

Unit 1 SI Accumulator Nitrogen Supply Line Additional

Isolation Valve

000

1FW01PA-B Vibration Data

07/21/2023

ER-AA-320-1004

Engage Health A1 Determination for the Safety Injection

System

07/22/2023

71111.13

Miscellaneous

NF-AP-209

By2C25 NF Receipt Shipment 1

08/08/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

TSTF-370-A

Technical Specification Task Force Improved Standard

Technical Specifications Change Traveler for Increasing

Accumulator Completion Time from 1 Hour to 24 Hours

BMP 3229-1

Preventive Maintenance Of Miscellaneous Pump Couplings

NF-AP-309

PWR Special Nuclear Material and Core Component Move

Sheet Development

OP-BY-108-117-

1000

Byron Protected Equipment Program

OU-AP-200

Administrative Controls During Fuel Handling Activities for

Byron and Braidwood

OU-AP-201

New Fuel Receipt and Inspection for Byron, Braidwood,

and Ginna

OU-AP-203

Operation of the New Fuel Elevator for Byron and Braidwood

OU-AP-204

Fuel Movement in the Spent Fuel Pool for Byron and

Braidwood

Procedures

OU-AP-4001

PWR Fuel and Core Component Handling Practices

5115240

One Time Preventative Replacement Of 2FW01PA-B Bearings

07/31/2023

287443

A FW Pp Aux Oil Pp Making Rubbing Noise

08/25/2022

288259

U-2 Receive & Inspect New Fuel

07/24/2023

288259

U-2 Receive & Inspect New Fuel

07/24/2023

288260

U-2 Download of New Fuel

06/02/2023

288260

U-2 Download of New Fuel

06/02/2023

5311565

U1 SI Accumulator Fill and Vent Line Additional Isol Valve

03/16/2023

5346216

New Motor for 1FW01PA-B Doesnt Fit Existing Mount

05/09/2023

5372647

FNE 1SI8875A Solenoid Porting Air

06/20/2023

5384837

EWP EM ~Contingent~ Determ / Reterm 2A MDFW AOP

Motor

07/20/2023

Work Orders

5384837

Abnormal Sounds/Vibes From Coupling 2A FW PP AOP

07/20/2023

4492642

U1 Thermocouple Spike, 1TE-IT8001H

04/12/2023

4499612

Reading Not Within Acceptance Criteria U1 Generator

05/13/2022

4500355

U-2 Main Generator Test Point BGE1 Low Resistance to

Ground

05/17/2022

71111.15

Corrective Action

Documents

4510441

U1 CETC #5 Spiking

07/12/2022

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

4548879

Unexpected Level and Press Loss in 2D SI Accum

01/17/2023

4666851

1A, 1C, and 1D SI Accumulator Pressure Rising

04/01/2023

4670112

Generator/Exciter Surveillance Issue

04/14/2023

4677782

1B DG Trip

05/12/2023

4685682

1B DG Non-Essential Control Air Lines Are Making Noise

06/20/2023

4691896

Abbreviated Maintenance 1SA142D Packing Adjustment

07/21/2023

4692423

0CC9432 Missed IST Relief Valve Test

07/25/2023

4693490

U1 CETC #5 Spiking 1TE-IT8001H

07/30/2023

4694183

U2 Gen/Exctr Terminal Point Failed Testing

08/02/2023

4699483

1A Diesel Oil Storage Tank Coating Degradation

08/30/2023

M-139, Sheet 2

Diagram of Component Cooling

AI

M-152, Sheet 10

Manufacturers Supplemental Diagram of Diesel Generator

Fuel Oil Schematic

AF

M-50, Sheet 1B

Diagram of Diesel Fuel Oil

AP

Drawings

M-66, Sheet 3A

Diagram of Component Cooling

AY

1BOL 8.1

LCOAR AC Sources - Operating Tech Spec LCO # 3.8.1

1BOSR 3.h.1-1

Unit One PDMS Instrumentation Channel Checks

1BVSR 3.1.6-1

Unit One Incore-Excore Axial Flux Quarterly Calibration

1BVSR 3.a.1-1

Unit One Moveable Incore Detectors Operability Check

BOP DG-21

Diesel Generator Air Receiver Pressure Control

Procedures

MA-BY-723-057

Maintenance Testing of Turbine Generator/Exciter

Drawings

Auxiliary Building Ground Floor Area 1

AN

394524

Evaluation of Miscellaneous Penetrations Subject to Affects of

Turbine Building High Energy Line Breaks (HELB)

637903

Unit 1 SI Accumulator Nitrogen Supply Line Additional

Isolation Valve

000

Engineering

Changes

637998

Unit 2 SI Accumulator Nitrogen Supply Line Additional

Isolation Valve

000

Engineering

Evaluations

EC 396376

MR90 Evaluation - Temporary Barrier for EDG Roll-Up Doors

to Facilitate Routing of Hoses and Cables for Maintenance

Activities

71111.18

Miscellaneous

Plant Barrier

Impairment

Door Fire/Security RS TB1 to 1DG01KA

08/29/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Permit 23-270

ER-AA-335-015-

2013

VT-2 Visual Examination in Accordance with ASME 2013

Edition

ER-AA-335-1008

Code Acceptance & Recording Criteria For Nondestructive

(NDE) Surface Examination

Procedures

ER-BY-330-1001

ISI Program Plan Fourth Ten-Year Inspection Interval

Work Orders

5311564

U2 SI Accumulator Fill and Vent Line Additional Isol Valve

08/11/2023

4370138

Inactive Leak Found on 1B SI Oil Cooler

09/17/2020

4407338

OTI Results for NDE Inspection of 1SI01Pa Lube Oil Pipe

03/08/2021

23399

1SI01SB (1B SI Pp Oil Cooler) GL 89-13 Results

05/13/2021

4435209

LR OTI Results 2SI01PB - 3/4" Lube Oil Line

07/15/2021

4446652

1B SI Pump Shaft Oil Pump Bearing Temperatures

09/15/2021

4451447

NOS ID: Grease Leak from 2SX033

10/07/2021

4459560

Failed 89-13 Inspection 1B SI Lube Oil Cooler

11/09/2021

4459560

Failed 89-13 Inspection 1B SI Lube Oil Cooler

11/09/2021

4463522

Follow-up for 1B SI Pump Bearing Oil Cooler

11/29/2021

4464401

OTI Results for 1SI01PA Lube Oil Pipe

2/02/2021

4548371

1RH01PB Nearing Run Time Alert Limit, WR to Replace

Bearings

01/12/2023

4550405

1A DG JW Leak

01/25/2023

4665685

1A Diesel Generator 1B Air Compressor Relief Valve Lifting

03/29/2023

4671026

Replace 1A DG Exhaust Fan MTR

03/06/2023

4674092

1A DG - 6R Cylinder Oil Leak

04/30/2023

4678723

Large Oil Leak and Accumulation of Oil on 1A DG

05/17/2023

4678859

2CS009B Repack Required at Next PVT

05/17/2023

4679999

1RH01PB Nearing Run Time Alert Limit, WR to Replace

Bearings

05/22/2023

4685024

Need WR/WO to Clean 1B RH Pump Boal During Next

Work Window

06/15/2023

4689931

1SI8812B Stripped MOV Actuator Motor Mount Bolt

07/11/2023

4690368

1SI8812B Motor Mounting Bolts Not Long Enough

07/12/2023

71111.24

Corrective Action

Documents

4692312

Unexpected Annun.,1-13-A3, RCP 1A Brkr Open/Flow Low

Alert

07/25/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

4696631

NRC ID: IRs Not Written for Abnormal Conditions

08/15/2023

4699305

1FT-0415 Continuing to Degrade

08/30/2023

4699427

Unexpected Entry into 1BOL 3.1 and 1BOA INST-2

(1RC-0415)

08/30/2023

4700170

Unexpected Entry into 1BOL 3.1 and 1BOA INST-2

(1RC-0415)

09/02/2023

1RHR-1-ISI

Inspection Identification DWG. For ISI Residual Heat Removal

Pumps 1RH01PA-1-1A & 1RH01PB-2-1B & CHGG Pumps

07/14/2000

6E-1-4031RC10

Loop Schematic Diagram Loop 1A and 1B Reactor

09/15/1977

M-2062 Sheet 2

P&ID/C&I Diagrams Heat Removal System - RH

2/15/2008

Drawings

M-62

Diagram of Residual Heat Removal

2/16/1997

4685024

Need WR/WO to Clean 1B RH Pump Boal During Next Work

Window

06/15/2023

ER-AP-331-1002

Evaluation of Leakage from ASME Section XI Class 2 Bolted

Connection at Flange Downstream of 1RH8739B

06/13/2023

Miscellaneous

OP-AA-101-113-

1004

Prompt Investigation Following Failure of 1FT-0415

09/05/2023

1BOSR 0.1-1, 2,

Unit One, Mode 1, 2, 3, Technical Specification Data Sheet

D4, Reactor Coolant Loops & S/G Level Channel Checks

1BOSR

0.5.2.SI.1-2

Unit One 1SI8821B, 1SI8812B, 1SI8804B and 1SI8920

Exercise Test

1BOSR 7.5.4-2

Unit One Diesel Driven Auxiliary Feedwater Pump Monthly

Surveillance

BISR 3.1.10-201

Surveillance Calibration of Reactor Coolant Flow Loop

Procedures

MA-AA-723-300

Diagnostic Testing of Motor Operated Valves

4937459

Re-Tube Lower DG Jacket Water Heat Exchanger During Next

ECT PM Window

09/02/2023

5162054

Diesel Generator Electrical Inspection

09/02/2023

5174460

MOV Thermal Overload Surveillance

(MCC 132X1-C4 1RH611)

07/11/2023

5177898

Replace Solenoid and Valve

09/02/2023

209550

Position Indication Tests of 2SX033

09/25/2023

211750

RHR PMP 1B Suction Press IND

07/11/2023

Work Orders

213330

Retorque Stationary End Flange per ER99011292

09/02/2023

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

21703

Replace Filter and Housing O-Ring

07/07/2023

21705

(CHANGE) Diesel Generator Starting Air Compressor 1A-B

07/07/2023

230551

Thermal O.L. Surveillance (MCC-231X1-A4) - 2AP21E-A4

09/25/2023

269986

4KV Breaker Swap (Bus 141 Cub 06)

09/02/2023

269986

4KV Breaker Swap, OPS PMT - Cycle Breaker and Verify

Operation

08/25/2023

279058

PM Inspection, In-Service Diag Test, PIT

07/11/2023

5302761

(Change) RHR Pump 1B

07/11/2023

5305468

RHR PMP 1B Mini Flow Indicator Switch

07/11/2023

5305469

Flow Loop 1RH-0619 Selected Instrument Calibration

07/11/2023

5330510

Residual HT Removal Low Press 1B Return Bypass Flow

Loop 1RH

07/11/2023

5336258

LR-1SI01SB - Heat Exchanger Inspection Per Generic Letter 89-13

08/07/2023

5338332

Clean 1HS-DG271, Starting Air Dryer No. 2

07/06/2023

5363131

1A DG - 6R Cylinder Oil Leak

09/02/2023

5366354

1SI01PB Group A IST Requirements for Safety Injection

08/07/2023

5377336

(NEIL)- 1B AF Pump Surv

07/18/2023

5385876

NEIL - Diesel Driven 0B Fire Pump Surveillance

08/18/2023

5386483

EWP FNI Troubleshoot 1RC-0415 Momentary Drop to 85 PE

09/13/2023

Byron Generating Station Part 37 Security Plan for the

Protection of Category 1 and Category 2 Quantities of

Radioactive Material

RP-AA-605

Trending for Shifts in Scaling Factors

various

SRRS 2B.127

Semi-Annual Source Leak Test

06/08/2023

SRRS 2B.127

Semi-Annual Source Leak Test

07/07/2022

TBE Sample ID

L94189-1

Waste Stream Analysis - DAW

10/01/2021

TBE Sample ID

L96182-1

10CFR61 Waste Stream Analysis - Radwaste Resin

04/01/2021

71124.08

Miscellaneous

TBE Sample ID

L99826-2

Waste Stream Analysis - Spent Resin Storage Tank

PO7088809-11

11/29/2022

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

RP-AA-600

Radioactive Material/Waste Shipments

RP-AA-605

CFR 61 Program

RP-AA-800

Control, Inventory, and Leak Testing of Radioactive Sources

Procedures

RW-AA-100

Process Control Program for Radioactive Wastes

Self-Assessments

AR 04378875

Radioactive Solid Waste Processing and Radioactive Material

Handling, Storage, and Transportation

2/08/2021

RWS22-06

Shipping Papers; Metal Cask of Dewatered Resin

07/28/2022

RWS22-10

Shipping Papers; Metal Cask of Dewatered Resin

10/13/2022

RWS23-02

Shipping Papers; Cask with Resin Liner

2/16/2023

Shipping Records

RWS23-16

Shipping Papers; 20' Oil Sealand

03/22/2023

LS-AA-2090

Monthly Data Elements for NRC ROP Indicator - Reactor

Coolant System (RCS) Specific Activity

various

LS-AA-2140

Monthly Data Elements for NRC ROP Indicator - Occupational

Exposure Control Effectiveness

various

71151

Miscellaneous

LS-AA-2150

Monthly Data Elements for NRC ROP Indicator - RETS/ODCM

Radiological Effluent Occurrences

various

4311738

Cell Voltage Low

01/22/2020

4318469

Corrosion On Battery Stand (1AF01EA-A)

2/16/2020

4318470

Corrosion On Battery Stand (1AF01EB-A)

2/16/2020

4318473

Corrosion On Battery Rack (1AF01EB-B)

2/16/2020

20256

Residue Build Up on 1AF01EA-B Batteries

2/22/2020

4337981

1AF01EB-A Battery Surveillance WO 5002735-01

04/23/2020

4363946

Voltage Reading Not Obtained for 1B AF Pump Start

08/18/2020

4384065

Battery Surveillance Results Above Admin Limit

11/10/2020

4402107

Aux Feed Battery Surveillance Results Below Admin Limit

2/12/2021

4417492

Battery Surveillance Results Below Admin Limit

04/19/2021

4436231

AF Battery Surveillance Results Below Admin Limit

07/21/2021

4450220

1AF01EB-B Battery Cells Found Below Admin Level

10/01/2021

4466422

NOS ID: Discolored Residue on 1AF01EA Battery

2/13/2021

4468553

Battery 2AF01EB-B Cells Below Voltage Admin Limit

2/10/2022

4473103

AF Battery Surveillance Results Below Admin Limit

01/20/2022

4477179

Battery 2AF01EA-B Cells Below Voltage Admin Limit

2/10/2022

71152A

Corrective Action

Documents

4483742

Residue Build Up On 2AF01EA-A Battery Cells

03/09/2022

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

4483743

Residue Build Up On 2AF01EA-B Battery Cells

03/09/2022

4483744

Residue Build Up On 2AF01EB-A Battery Cells

03/09/2022

4483745

Residue Build Up On 2AF01EB-B Battery Cells

03/09/2022

4483746

Residue Build Up On 2AF01EA-A Battery Cells

03/09/2022

4483747

Residue Build Up On 2AF01EA-B Battery Cells

03/09/2022

4483748

Residue Build Up On 2AF01EB-A Battery Cells

03/09/2022

4483749

Residue Build Up On 2AF01EB-B Battery Cells

03/09/2022

4501056

Battery Cell 20 Below Admin Limits for 2AF01EB-A

05/10/2022

4511235

2B Aux Feed Battery Cell Voltages Below Acceptance Criteria

07/15/2022

4513412

2AF01EA-A Battery Cell Low Voltage

07/28/2022

4514787

1AF01EA-A Battery Cell 19 Level Hi

08/03/2022

4536856

Voltage Reading Not Obtained for 2B AF Pp Start

11/14/2022

4537716

Move AF Battery Cap Test to Online 5Y Freq, Prep

Contingency

11/17/2022

4669080

1AF01EB-B Low Voltage Charger On

04/11/2023

4671045

AF Battery Surveillance Results Below Admin Limit

04/18/2023

4671047

AF Battery Surveillance Results Below Admin Limit

04/18/2023

4671140

2AF01EA-B Low Voltage Readings

04/19/2023

4671145

2AF01EB-B Aux Feed Battery Surveillance

04/19/2023

4685399

1B AF Battery Electrolyte Levels Low

06/18/2023

4685683

1B AF Pump Battery 1AF01EB-B Cells 5 & 7 Below Admin

Voltage

06/20/2023

4690928

1AF01EA-B Battery Surveillance

07/17/2023

4691106

2AF01EB-B Battery Voltage Below Acceptance Criteria

07/18/2023

4691109

2AF01EA-B Battery Low Voltage Readings

07/18/2023

4691111

2AF01EA-A Low Voltage Readings

07/18/2023

4691113

2AFO1EB-A Low Battery Voltage

07/18/2023

Miscellaneous

BYR-44134

PowerLabs Failure Analysis of a Solenoid Valve from a Byron

SX Make-Up Pump

08/29/2017

Procedures

MA-BY-723-054

Nickel Cadmium Battery Bank Surveillance

4734618

(Change) Essential Service Water Make-Up Pump 0A

06/09/2019

5111188

Bank B BATT A NiCad Battery Surv Aux Fee

03/22/2021

Work Orders

20746

Bank A BATT B NiCad Battery Surv Aux Fee

2/09/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

24686

Bank A BATT B NiCad Battery Surv Aux Fee

04/22/2021

5173533

AF Battery Surveillance Results Below Admin Limit

10/12/2022

204740

Bank B BATT A NiCad Battery Surv Aux Fee

04/22/2022

24943

Bank B BATT A NiCad Battery Surv Aux Fee

05/13/2022

280813

Bank A BATT A NiCad Battery Surv Aux Fee

10/12/2022

5301696

Bank A BATT B NiCad Battery Surv Aux Fee

01/11/2023

5305802

Bank A BATT B NiCad Battery Surv Aux Fee

01/17/2023