IR 05000266/2024002

Integrated Inspection Report 05000266/2024002 and 05000301/2024002

ML24225A232
Person / Time
Site:	Point Beach
Issue date:	08/13/2024
From:	Hartman T NRC/RGN-III/DORS/RPB2
To:	Durbin M Point Beach
References
IR 2024002
Download: ML24225A232 (1)

Text

SUBJECT:

POINT BEACH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000266/2024002 AND 05000301/2024002

Dear Michael Durbin:

On June 30, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear Plant. On July 15, 2024, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation or the significance or severity of the violation 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 Point Beach Nuclear Plant.August 13, 2024 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, Thomas C. Hartman, Acting Branch Chief Reactor Projects Branch 2 Division of Operating Reactor Safety Docket Nos. 05000266 and 05000301 License Nos. DPR-24 and DPR-27

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000266 and 05000301

License Numbers: DPR-24 and DPR-27

Report Numbers: 05000266/2024002 and 05000301/2024002

Licensee: NextEra Energy Point Beach, LLC

Facility: Point Beach Nuclear Plant

Location: Two Rivers, WI

Inspection Dates: April 01, 2024 to June 30, 2024

Inspectors: J. Masse, Resident Inspector V. Myers, Senior Health Physicist V. Petrella, Project Manager J. Robbins, Senior Resident Inspector M. Stafford, Senior Resident Inspector

Approved By: Thomas C. Hartman, Acting Branch Chief Reactor Projects Branch 2 Division of Operating Reactor Safety

Enclosure

SUMMARY

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

List of Findings and Violations

Failure to Translate Design Basis for Diesel Generator Operability Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green None (NPP) 71111.18 Systems NCV 05000266,05000301/2024002-01 Open/Closed The inspectors identified a Green finding and associated Non-cited Violation (NCV) of Title 10 CFR, Part 50, Appendix B, Criterion III, Design Control, when the licensee failed to assure that the applicable design basis was correctly translated into instructions. Specifically, the licensee failed to translate the maximum allowable outside air temperature to maintain emergency diesel generator operability into Operating Instruction 168, Emergency Diesel Generator Operability.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period at rated thermal power and remained at or near full power throughout the remainder of the inspection period.

Unit 2 began the inspection period at rated thermal power and remained at or near full power throughout the remainder 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.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (2 Samples)

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

(1) Unit 2 train B safety injection system on May 9, 2024

(2) Unit 1 train A residual heat removal system on June 27, 2024

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (10 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 318, 326, 333, 334, 335, 336, and 337 on April 9, 2024

(2) Fire zones 305, 306, 307, 308, 309, and 310 on April 9, 2024

(3) Fire zones 304N, 304S, and 311 on April 9, 2024

(4) Fire zones 106, 110, 115, 119, 141, 142A, 143, 144, 145, and 147 on April 22, 2024

(5) Fire zones 113, 114, and 118 on April 22, 2024

(6) Fire zones 137, 138, 139, and 140 on April 22, 2024

(7) Fire zones 142, 149, 150, and 151 on April 22, 2024

(8) Fire zones 152, 153, 154, 155, 156, 156A, 158, and 159 on April 23, 2024

(9) Fire zones 162, 163, 164, 165, and 166 on April 23, 2024

(10) Fire zones 304N and 304S during hot work on May 8, 2024

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

(1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on May 16, 2024.

71111.06 - Flood Protection Measures

Flooding Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated internal flooding mitigation protections in the cable vaults in manholes 1, 2, 66A, 66B, and 67B on April 29, 2024, April 30, 2024, and May 2, 2024.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

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

(1) The inspectors observed and evaluated licensed operator performance in the control room during a power reduction following the loss of power to the 2B-41 480V motor control center on May 7, 2024.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operator simulator training on May 15, 2024.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

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

(1) Air accumulator, 1T-223A, for main feedwater isolation valve 1CS-3124

(2) Unit 2 480 volt alternating current system following the temporary loss of power to distribution bus 2B-41

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (4 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) Unit 1 elevated risk due to independent overspeed protection system analog and train A and B logic test on May 8, 2024

(2) Unit 2 elevated risk due to nuclear instrumentation power range axial offset channel calibration on June 20, 2024

(3) Elevated risk due to rigging and lifting activities over the spent fuel pool on June 24, 2024

(4) Elevated risk due to maintenance on the D-09 battery charger and D-305 125-volt battery on June 26, 2024

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

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

(1) Operability determination for the Unit 2 main steam non-return check valve, 2MS-2017A, following a packing leak on April 11, 2024

(2) Operability determination for the SW-2977, HX-98 residual heat removal pump area cooling coil inlet control, not opening on May 17, 2024

(3) Operability determination for the Unit 1 white channel temperature average, Tavg, indication on May 31, 2024

(4) Functionality determination for reactor coolant system makeup portable diesel driven pumps on June 17, 2024

(5) Operability determination for underground cabling after a manhole was found full of water on June 20, 2024

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (3 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) Removal of the seal well outlet motor operated valve and the impact to circulating water and service water ice melt lineups

(2) Temporary modification to address containment accident recirculation fan operability

(3) Emergency diesel generator rooms for G-01 and G-02 temperature limit change

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) Unit 1 wide range reactor vessel level indicator after module lug replacement on April 16, 2024

(2) Service water pump discharge check valve, SW-32D, after replacement of the valve disc on April 19, 2024

(3) Unit 1 blue channel average temperature after 1TM-403BB module replacement on May 1, 2024

(4) Unit 2 containment accident recirculation fan, 2W-1A1, after flange installation over containment cooling fan backdraft damper on May 23, 2024

(5) Station blackout gas turbine generator, G-05, after various mechanical and electrical maintenance activities on May 30, 2024

(6) Emergency diesel generator, G-03, exhaust fan post-maintenance test, on June 10, 2024

(7) Radiation monitor post-maintenance testing, on June 10, 2024

Surveillance Testing (IP Section 03.01) (1 Sample)

(1) TS-84, G-04 emergency diesel generator run on June 18, 2024

Inservice Testing (IST) (IP Section 03.01) (2 Samples)

(1) IT 45 Train B, safety injection valve tests, on April 12, 2024

(2) IT 04 Train A, low head safety injection pump test, on May 29, 2024

Diverse and Flexible Coping Strategies (FLEX) Testing (IP Section 03.02) (1 Sample)

(1) Steam generator injection portable diesel driven pump surveillance, on June 17, 2024

71114.06 - Drill Evaluation

Additional Drill and/or Training Evolution (1 Sample)

The inspectors evaluated:

(1) Emergency preparedness drill conducted to practice the new combined emergency plan implementation on April 30,

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (9 Samples)

The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:

(1) AMP 50 for the demineralizer valve gallery

(2) AMP 50 for the unit 1 demineralizer cubicle

(3) AMS 4 for the unit 2 charging pump cubicles

(4) Cronos 4 at the radiologically controlled area exit

(5) SAM at the radiation protection release station

(6) iSolos in the counting room

(7) MGP Telepole staged for use

(8) Ludlum 9-3 staged for use

(9) Ludlum 3 staged for use

Calibration and Testing Program (IP Section 03.02) (12 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) AMS-4, SN 330692

(2) Low Volume Air Sampler, SN 330785

(3) iSolo, SN 361202

(4) Ludlum 9-3, SN 333119

(5) Thermo RO-20, SN 472971

(6) Telepole II, SN 427020-061 and 428020-061

(7) Ludlum 3, SN 327581

(8) Ludlum 177, SN 348303

(9) Escort ELF, SN A2-41247

(10) ARGOS 5AB, SN 712-048/0480461

(11) Cronos-4, SN 1511-197

(12) GEM 5, SN 480458

Effluent Monitoring Calibration and Testing Program Sample (IP Section 03.03) (2 Samples)

The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:

(1) Unit 1 Service Water Monitor, 1RE-229

(2) Unit 2 Containment SPING, SPING-22

71124.07 - Radiological Environmental Monitoring Program

Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.

Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.

GPI Implementation (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative (GPI) program to identify incomplete or discontinued program elements.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===

(1) Unit 1 (April 1, 2023 through March 31, 2024)

(2) Unit 2 (April 1, 2023 through March 31, 2024)

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (April 1, 2023 through March 31, 2024)

(2) Unit 2 (April 1, 2023 through March 31, 2024)

===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) Fuel assembly grid strap damaged during fuel moves.

(2) Emergency diesel generator, G-01, temperature outside normal band while running

(3) Main feed isolation valve air accumulator Part 21 applicability

INSPECTION RESULTS

Failure to Translate Design Basis for Diesel Generator Operability Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green None (NPP) 71111.18 Systems NCV 05000266,05000301/2024002-01 Open/Closed The inspectors identified a Green finding and associated Non-cited Violation (NCV) of Title 10 CFR, Part 50, Appendix B, Criterion III, Design Control, when the licensee failed to assure that the applicable design basis was correctly translated into instructions. Specifically, the licensee failed to translate the maximum allowable outside air temperature to maintain emergency diesel generator operability into Operating Instruction 168, Emergency Diesel Generator Operability.

Description:

During an endurance run for the G-01 emergency diesel generator (EDG) in August of 2023, the licensee noted elevated temperatures in the diesel generator room. The highest recorded readings in this room were 113.4 degrees Fahrenheit (°F), taken from TI-6616A, a digital thermometer located in this room. This value was within 6.6 F of the operability limit of 120 °F for equipment in the room. This led the inspectors to investigate the maximum allowable room temperatures and outside air temperatures to maintain diesel generator operability.

The licensee maintains calculation 2005-0054, Control Building GOTHIC Temperature Calculation. Revision 9, Section 9.2, calculates the maximum allowable outside air temperature to maintain the G-01 and G-02 diesel generator room temperatures below 120 °F to be 97.4 °F. The calculation assumes two room exhaust fans are running and three open fire dampers.

The licensee also has Operating Instruction 168, Emergency Diesel Generator Operability, Revision 31, which discusses when to consider the EDGs operable or inoperable. The inspectors noted that step 5.1.3 states, When outside air temperature is greater than 97.5 F, then G-01 and G-02 are to be considered INOPERABLE. The value of 97.5 °F does not match the calculated design value of 97.4 °F from calculation 2005-0054.

Further, if the value of 97.5 °F were utilized in the calculation it would result in a required air flow that would exceed the available air flow assumed in the calculation. Based on Operating Instruction 168, the licensee would not declare G-01 or G-02 inoperable until outside temperatures exceeded 97.5 °F, which could have resulted in the licensee operating outside of their design requirements.

Corrective Actions: The licensee has entered this issue into their corrective action program to determine changes needed in their required procedures.

Corrective Action References: AR 02490693

Performance Assessment:

Performance Deficiency: The inspectors determined the licensees failure to properly translate the emergency diesel generator air temperature limits into procedures was contrary to 10 CFR Part 50, Appendix B, Criterion III Design Control, and was a performance deficiency. Specifically, the licensee failed to translate the design value for maximum outside air temperature into Operating Instruction 168, Emergency Diesel Generator Operability.

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, if the Operating Instruction is followed, between 97.4 °F and 97.5 °F, the licensee would not declare the equipment inoperable, but the G-01 and G-02 emergency diesel generators might not be capable of performing their safety function.

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

Specifically, the inspectors determined the finding was of very low safety significance (Green)because the inspectors answered no to all of the screening questions in Exhibit 2.

Cross-Cutting Aspect: Not Present Performance. No cross-cutting aspect was assigned to this finding because the inspectors determined the finding did not reflect present licensee performance.

Enforcement:

Violation: Title 10 CFR Part 50, Appendix B, Criterion III, Design Control, requires in part that measures be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and instructions.

Contrary to the above, since June 16, 2016, the licensee failed to assure that applicable regulatory requirements and the design basis were correctly translated into specifications, drawings, procedures, and instructions. Specifically, the licensee failed to correctly translate the maximum allowable outside air temperature to maintain emergency diesel generator operability into Operating Instruction 168, Emergency Diesel Generator Operability.

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 July 15, 2024, the inspectors presented the integrated inspection results to Michael Durbin, Site Vice President, and other members of the licensee staff.

• On April 11, 2024, the inspectors presented the radiation protection inspection results to Michael Durbin, Site Vice President, and other members of the licensee staff.

• On June 6, 2024, the inspectors presented the radiation protection inspection results to Michael Durbin, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Drawings 110E017 Sheet 1 P&ID Safety Injection System 61

110E017 Sheet 2 P&ID Safety Injection System 68

110E018 Sheet 1 P&ID Auxiliary Coolant System 71

110E035 Sheet 1 P&ID Safety Injection System 56

110E035 Sheet 2 P&ID Safety Injection System 61

71111.05 Corrective Action 02486448 AR to Purchase Aerating Nozzles for FBG Foam Use 05/16/2024

Documents 02486449 FB Foam Cart Needs Rails 05/16/2024

Corrective Action 02478188 PFP-0-CB - Pre-Frie Plan Control Building ELE

V. 8 ft, 26 ft 02/02/2024

Documents 02478468 PBC-218 Sheet 2,3,6,8 VS PFP-0-CB - Identified 02/06/2024

Resulting from by NRC PT 1

Inspection 02478470 PBC-218 Sheet 2,3,6,8 VS PFP-0-CB - Identified by 02/06/2024

NRC PT 2

2482008 (P) PFP-0-CB - Pre-Fire Plan Control Building (In Review) 03/21/2024

2483596 Potential Minor Violation Related to Pre-Fire Plans 04/09/2024

2483599 Potential Minor Violation Related to PBC 218 Series 04/09/2024

FP DWGS

2484697 Red Lock Improperly Installed on Entrance to Fire Zone 146 04/22/2024

2487710 Clarify OM 3.27 Verbiage to NP 1.9.14 Regarding CMFWS 06/04/2024

2487711 OM 3.27 - Control of Fire Protection and NFPA 805 Equipment 06/04/2024

Drawings PBC-218, Sheet 2 Fire Protection for Turbine Building, AUX Building & 39

Containment ELEV. 8'-0" Point Beach N.P. Units 1 & 2

PBC-218, Sheet Fire Barrier Locations for Turbine Building, 19

Aux Building & Containment Elev 8 ft

PBC-218, Sheet 3 Fire Protection for Turbine Building, Aux Building & 23

Containment ELEV. 26'-0" Point Beach N.P. Units 1 & 2

PBC-218, Sheet 8 Fire Protection for Control Room ELEV. 44'-0" & Computer 10

Room ELEV. 60'-0 Point Beach Nuclear Plant Unit 1 & 2

Fire Plans PFP-0-CB Pre-Fire Plan Control Building Elev 8 ft, 26 ft, 44 ft, and 66 ft7

PFP-0-PAB-8 Pre-Fire Plan Primary Auxiliary Building Elevations 8 ft and 7

Below

Miscellaneous Fire Drill Scenario Crew C: 2nd Quarter 2024 0

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures NP 1.9.13 Ignition Control Procedure 33

NP 1.9.14 Fire Protection Plan 27

OM 3.27 Control of Fire Protection and NFPA 805 Equipment 83

Work Orders 40802652-23 K-003B / Install Service Air Test Conn. North Aux Feed 05/03/2024

71111.06 Calculations 2014-0007 Allowable Flood Levels 5

Drawings E-100, Sheet 1 Electrical Plot Plan Details 45

PBE-816 Cable Vault Locations 1

71111.11Q Corrective Action 02485848 2B-41 MCC Breaker 2B52-42D, the 2B02 to 2B41, Tripped 05/07/2024

Documents

Miscellaneous PBN LOC24C CPE Style Scenario 0

003S

Procedures AOP-17A Unit 2 Rapid Power Reduction 28

MDB 3.2.6 2B41 480 V AC Motor Control Centers 20

OP-2A Unit 2 Normal Power Operation Unit 2 22

71111.12 Corrective Action 2470986 1CS-232A Will Not Adjust in Band, Causing Accumulator 10/28/2023

Documents Hi Pres

2470991 Gas Leakage from 1CS-3124 MFIV Accumulator/Operator 10/28/2023

2471106 Air Leak on 1CS-257A 10/30/2023

2471208 Contingency - Troubleshoot and Repair 1CS-03124 10/31/2023

2485848 2B-41 MCC Breaker 2B52-42D, 2B02 to 2B41, Tripped 05/07/2024

2486044 1K-29A Haskel Not Controlling Pressure as Set 05/10/2024

2486253 Received a 2B-03 Ground Fault Alarm 05/14/2024

2486411 Inspect/Replace 1CS-242A to Support 1K-29A 05/15/2024

Troubleshooting

Drawings M-209 Sheet 5 P&ID Instrument Air 41

Miscellaneous EVT-480V-2024-Maintenance Rule Functional Failure Determination 05/22/2024

20106

Procedures CMP 2.3 Relief/Safety Valves 34

ER-AA-100-2002 Maintenance Rule Program Administration 13

RMP 9303 DB-50 Breaker Routine Maintenance 34

RMP 9369-1 Westector/Amptector Overload SerpointC Heck on Low 44

Voltage Breakers

Work Orders 40785650-01 B52-DB50-018; Breaker Maint per RMP 9303 and 11/21/2023

Inspection Type Designation Description or Title Revision or

Procedure Date

RMP 9369-1

40954962-01 Gas Leakage from 1CS-3126A MFIV Accumulator/Operator 12/04/2023

40954962-06 1CS-03126A / Perform As-left Testing Prior to Installation01/05/2024

40954966-01 1CS-232A - Bench Check Regulator and Replace if Necessary 10/29/2023

40956122-01 1K-29A Cycling Excessively 02/01/2024

71111.13 Corrective Action 2488806 Z-015 Pre-Lift Inspection 06/18/2024

Documents 2489023 Z-015 Pre-Lift Inspection 06/20/2024

Miscellaneous Guarded Equipment Log 06/25/2024

Rigging Lift Plans 06/21/2024

Procedures 1ICP 03.016 Independent Overspeed Protection System Analog and 22

Train A and B Logic Test

2ICP 02.008-1 Nuclear Instrumentation Power Range Axial Offset Calibration28

MA-AA-110-1000 Rigging Handbook and Inspection Procedure 11

MA-AA-212-1000 Rigging and Material Handling 25

OP-AA-102-1003 Guarded Equipment 47

SLP 4 Safe Load Path and Rigging Manual 17

WM-AA-100-1000 Work Activity Risk Management 26

Work Orders 40905559-01 D-305/D-09; Bat Disch & Charger Maint and SR Tests 06/26/2024

40906507-01 1ICP 0.016 - IOPS Quarterly Trip and Logic Tests 05/07/2024

40908448-03 (Contingency) Unit 2 NIs Power Range Axial Offset Cal 05/31/2024

71111.15 Corrective Action 02461599 Validate Tavg/Tref Deviation Meter 07/05/2023

Documents 02467128 Unexpected 1C04 1A 3-10 Reactor Coolant T AVG Deviation 09/17/2023

Alarm

2484255 White Channel Tavg Reads 577 Degrees Hot, Tech Spec Limit 04/17/2024

2485060 SW-2977 Did Not Open When TIC-2977 Setpoint was 04/26/2024

Lowered

2485200 Z-2005B Failed to Turn Over 04/29/2024

2485201 Z-2005C Failed to Turn Over 04/29/2024

2485250 Z-66A Manhole Full of Water and Cables Under Water 04/30/2024

2485547 FLEX Equipment Battery Low Electrolyte Level (Trend) 05/03/2024

2485971 WR Needed to Replace Sump Pump in Z-66A 05/09/2024

2483008 Packing Leakage on 2MS-2017A Non-Return Valve 04/02/2024

Corrective Action 2485342 MS-2017A/2018A Non-Return Check Valves Documentation 05/01/2024

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents Issues

Resulting from

Inspection

Drawings 207034-H Sheet 1 30in. Main Steam Non-return Valve CV-2017A & CV-2018A 1

207034-H Sheet 2 30in Main Steam Isolation Check Valve 1

M-2201 Sheet 1 P&ID Main & Reheat Steam System 58

Engineering 258496 EPU - MSIV and NRV Valve Disc Upgrades (U2) 2

Changes

Procedures 2RMP 9306-1 Main Steam Non-Return Check Valve Inspection Without 2

Removing Cover (Unit 2)

NP 7.7.28 Cable Condition Monitoring Program 7 and 8

NP 7.7.37 Surveillance Frequency Control Program Manual 15

OM 3.42 Control of WR SFP Level Instrumentation and Credited 11

FLEX Equipment

PBF-2034 Control Room Log U1 105

Work Orders 40886741-01 PC-21.6 B.5.B Miscellaneous and FLEX Checks 04/11/2024

40888638 Yearly (Spring) Electrical Manhole Sump Inspections 05/09/2024

40955496 Investigate Reason for U1 White Channel Temperature Offset 04/04/2024

71111.18 Calculations 2005-0054 Control Building GOTHIC Temperature Calculation 9

Corrective Action 02486793 2W-001A2-A Second Blade Disconnected from Damper Shaft 05/21/2024

Documents

Corrective Action 02489616 Calc 2005-0054 Error 06/27/2024

Documents 02490407 Clarity of Basis for A Train EDG Room Heat Up Parameters 07/10/2024

Resulting from 02490693 Potential Green NCV, 10 CFR Appendix B, Criterion III 07/15/2024

Inspection

Engineering 297502 1CW-3 Seal Well Outlet MOV Temporary Configuration 0

Changes Alignment

298378 1CW-3 Seal Well Outlet MOV TCC Conversion to 3

Permanent Mod

299709 2W-1A2-A Backdraft Damper Temporary Duct Blank 0

Engineering 2015-0017 G-01 and G-02 Air Temperature Limit 0

Evaluations

Miscellaneous SCR 2013-0043-Revise OI 168 Emergency Diesel Generator Operability, 08/21/2013

TS B 3.8.1 and PBF-2035

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures AOP-13A Circulating Water System Malfunction 26

AOP-13C Severe Weather Conditions 53

AOP-9A Service Water System Malfunction 39

OI 168 Emergency Diesel Generator Operability 31

OI 38 Circulating Water System Operation 82

71111.24 Corrective Action 02486703 CR Vent Failed to Shift from Mode 5 to Mode 1 05/20/2024

Documents 02486861 Potentially Inadequate PMT on DAM 7 Restoration 05/22/2024

2486927 RMS Procedures and PMT 05/22/2024

2487042 Z-2004B FLEX Inj. Pump Failed to Start 05/23/2024

2483107 1LT-495 (RV Level, Wide Range) Failed Channel Check 04/03/2024

2486793 2W-001A2-A Second Blade Disconnected from Damper Shaft 05/21/2024

Corrective Action 02490694 Potential Minor PD - IT Series Procedures Signoffs Not 07/15/2024

Documents Consistent

Resulting from

Inspection

Drawings 036032 2"-16" 150 Pound Swing Check Valve 4

BD-4 Block Diagram-Instrument Reactor Protection System 12

Delta T - T Average - Loop B-1

CD-6 JOB 10668 Wiring Diagram-Interconnect Reactor Protection System Rack 18

Sheet 1 1-1B (1C116) Top

CD1-22 Connection Diagram Rack 1C173A-F 8

Procedures 0-SOP-FLEX-004 FLEX Portable Diesel Steam Generator Injection Pump 7

Operation

1ICP-13.004B Spec 200, Reactor Vessel Level and Subcooling Post Accident 19

Monitoring Instruments 18 Month Calibration

AD-AA-100-1006 Procedure and Work Instruction Use and Adherence 26

ER-AA-113-1000 Inservice Testing Procedure 11

HPIP 7.51.7 DAM/SPING Post-Startup Operational Verification 10

IT 01 Train A High Head Safety Injection Pumps and Valves Train A Unit 1 12

IT 02 Train A High Head Safety Injection Pumps and Valves Train A Unit 2 15

IT 03 Train A Low Head Safety Injection Pumps and Valves Train A Unit 1 16

IT 04 Train A Low Head Safety Injection Pumps and Valves Train A Unit 2 19

IT 04 Train B Low Head Safety Injection Pumps and Valves Train B Unit 2 19

Inspection Type Designation Description or Title Revision or

Procedure Date

IT 05 Train A Train A Containment Spray Pump and Valves Unit 1 8

IT 45 Train B Safety Injection Valves Train B Unit 2 10

MA-AA-203-1000 Maintenance Testing 20

MI 32.13 Belts and Pulleys 2

OI 81 RMS Troubleshooting and Startup 25

OI 81 RMS Troubleshooting and Startup 26

OP-AA-100-1000 Conduct of Operations 41

PC-29 Gas Turbine and Auxiliary Diesel Load Test 77

Procedure Procedure Writers Guide 33

Writer's Guide

RMP 9328 SW-32A-F Service Water Pump Discharge Check Valve 15

Inspection

TS 34 Containment Accident Recirculation Fan-Cooler Units Unit 249

TS 84 Emergency Diesel Generator G-04 Monthly 48

Work Orders 40824334-01 SW-00032D Disassemble/Visually Inspect Check Valve 03/28/2024

40824334-02 SW-00032D Ops PMT/RTS 03/29/2024

40849151-01 1ICP 13.4 -- Spec 200 Tech Spec - Train B 04/05/2024

40862003-01 PC-29; G-05 Gas Turbine Generator Load Testing 05/17/2024

40882213-01 IT 04 Train A 03/13/2024

40886696-01 IT 45 Train B 04/15/2024

40905557 W-183A - Grease Fan Bearings 05/30/2024

40933119-01 0-SOP-FLEX-004/Z-2004A and B Quarterly Run 06/13/2024

40933123-01 TS-84, G-04 Emergency Diesel Generator Operability Test 06/03/2024

40951650 RE-214 Spikes When Source Checking RE-218 05/23/2024

40966458-08 D-500; Battery Charger Maint and Testing 05/13/2024

40973263-01 1LM-495-1 Replace Lugs 04/04/2024

40976153-02 1TM-403BB - Bench Check Replacement Module 04/27/2024

40976153-04 1TM-403BB - Replace Module with Bench Checked Spare 04/30/2024

40978994-06 2W-001A2-A, OPS PMT/RTS 05/22/2024

71114.06 Miscellaneous 2Q24 CEP Drill Spreadsheet 04/25/2024

Installation

Practice Drill

Procedures AOP-28 Seismic Event 9

Inspection Type Designation Description or Title Revision or

Procedure Date

71124.05 Calculations HP-100-012623 Basis for GEM-5 Portal Monitor Alarm Setpoint Change 01/27/2023

Calibration 427020-0610- Calibration Certificate for Telepole II SN 427020-061 and 12/19/2023

Records 20231219 428020-061

PBF-4020 Low Volume Air Sampler Maintenance and Calibration Record 12/07/2023

for SN 330785

PBF-4020d Escort ELF Air Sampling Pump Calibration Record for 11/09/2023

SN A2-41247

PBF-4055a ARGOS 5AB Calibration Worksheet for SN 712/048/0480461 06/16/2023

PBF-4055b Calibration Data Sheet for GEM 5 SN 480458 04/30/2024

PBF-4085ff Calibration Data Sheet for iSolo SN 361202 06/04/2023

PBF-4085j Calibration Data Sheet for Ludlum 3 SN 327581 11/13/2023

PBF-4085J Calibration Data Sheet for Ludlum 177 SN 348303 08/02/2023

PBF-4085u Calibration Data Sheet for AMS-4 SN 330692 01/09/2024

PBF-4085y Calibration Data Sheet for Thermo RO-20 SN 472971 05/23/2023

PBF-4085y Calibration Data Sheet for Ludlum 9-3 SN 333119 03/05/2024

RP-AA-110-1000- Cronos Calibration Data Sheet for SN 1511-197 09/07/2023

F01

Corrective Action 02465046 MSL Rad Monitor Calculation 99-0106 Not Updated for New 08/21/2023

Documents Source Term

2465471 Documents Have Different MSL LLD Values 08/24/2023

2473296 Calibration Constant for MSL Radiation Detectors May Be 11/29/2023

Incorrect

2473308 RMS Background Subtract Not Performed IAW Vendor 11/29/2023

Instruction

Procedures HPCAL 1.33 Maintenance and Calibration of Low Volume Air Samplers 23

HPCAL 1.49 Calibration of Portable Dose Rate Instruments 17

HPCAL 2.23 Portable Scaler Calibrations 16

HPCAL 2.24 Calibration of the ARGOS 5AB Alpha/Beta Whole Body 8

Contamination Monitor

HPCAL 2.25 Calibration of the GEM Whole Body Contamination Monitor 11

RP-AA-110-1000 Operation and Calibration of the Cronos Contamination 1

Monitors

Work Orders 40869430 1RE-229/229B Calibration 01/25/2024

Inspection Type Designation Description or Title Revision or

Procedure Date

40873521 2RM-SPING-22 Calibration 01/19/2024

71124.07 Corrective Action 02432491 Potential Adverse Trend for Environmental Air Sampling 04/08/2024

Documents 02465121 ODCM Reviews Against TS 5.6.2 08/22/2023

Miscellaneous Offsite Dose Calculation Manual 25

L-2023-058 2022 Annual Monitoring Report 04/10/2023

NRC 2022-0014 2021 Annual Monitoring Report 04/14/2022

Procedures HPIP 3.58.1 Radiological Environmental Sampling 16

NP 3.4.7 Groundwater Protection Program 17

Self-Assessments L1A 02419352 5 Year GWPP Self-Assessment 02/21/2022

71152A Calculations 2005-0049 Primary Auxiliary Building (PAB) and Control Building (CB) 0

Mechanical Heat Load Calculation

2005-0054 Control Building GOTHIC Temperature Calculation 9

Corrective Action 02450093 1K-29B Continuous Air Bleed Coming from Weep Hole 03/04/2023

Documents 02464991 G-01 Room Temperature Outside Band 50-105 F While 08/20/2023

Running

2471076 1K-29A Air Intensifier not Working Properly 10/29/2023

2471978 1K-29A Cycling Excessively 11/09/2023

2484218 Load Deflection during Fuel Moves at SFP 04/16/2024

2484271 Fuel Assembly 2D06 has Torn Grid Straps from 04/17/2024

SFP Cell SS-21

2486044 1K-29A Haskel not Controlling Pressure as Set 05/10/2024

2486411 Inspect/Replace 1CS-242A to Support 1K-29A 05/15/2024

Troubleshooting

2488284 1K-29A Cycling ~30 Times per Minute 06/11/2024

2488322 ACMP: Check for Operator Challenge 06/11/2024

Corrective Action 02489967 TI-6616A Contributing to Questions on G-01 Room Heat Up 07/03/2024

Documents

Resulting from

Inspection

Miscellaneous Letter from Engine System, Inc. to Point Beach 02/23/2007

Procedures 0-SOP-FH-001 Fuel/Insert/Component Movement in the Spent Fuel Pool or 34

New Fuel Vault

LI-AA-102-1002 Part 21 Reporting 19

Inspection Type Designation Description or Title Revision or

Procedure Date

PBTP 259 G01 EDG Air Flow Measurement Test 09/20/2014

QI-7-NSC-1 Warehouse Receipt, Storage, Issuance and Maintenance 12A

Work Orders 40476004 Z-25A&B/Repair SFP Racks 06/05/2023

19