IR 05000266/2024002
| ML24225A232 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  (DPR-024, DPR-027) |
| 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:
Report Numbers:
05000266/2024002 and 05000301/2024002
Enterprise Identifier:
I-2024-002-0064
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
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 Aspect Report Section Mitigating Systems Green NCV 05000266,05000301/2024002-01 Open/Closed None (NPP)71111.18 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.
REACTOR SAFETY
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,
RADIATION SAFETY
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 Aspect Report Section Mitigating Systems Green NCV 05000266,05000301/2024002-01 Open/Closed None (NPP)71111.18 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
Procedure
Type
Designation
Description or Title
Revision or
Date
110E017 Sheet 1
P&ID Safety Injection System
110E017 Sheet 2
P&ID Safety Injection System
110E018 Sheet 1
P&ID Auxiliary Coolant System
110E035 Sheet 1
P&ID Safety Injection System
Drawings
110E035 Sheet 2
P&ID Safety Injection System
2486448
AR to Purchase Aerating Nozzles for FBG Foam Use
05/16/2024
Corrective Action
Documents
2486449
FB Foam Cart Needs Rails
05/16/2024
2478188
PFP-0-CB - Pre-Frie Plan Control Building ELE
- V. 8 ft, 26 ft
2/02/2024
2478468
PBC-218 Sheet 2,3,6,8 VS PFP-0-CB - Identified
by NRC PT 1
2/06/2024
2478470
PBC-218 Sheet 2,3,6,8 VS PFP-0-CB - Identified by
NRC PT 2
2/06/2024
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
FP DWGS
04/09/2024
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
Corrective Action
Documents
Resulting from
Inspection
2487711
OM 3.27 - Control of Fire Protection and NFPA 805 Equipment
06/04/2024
PBC-218, Sheet 2
Fire Protection for Turbine Building, AUX Building &
Containment ELEV. 8'-0" Point Beach N.P. Units 1 & 2
PBC-218, Sheet
Fire Barrier Locations for Turbine Building,
Aux Building & Containment Elev 8 ft
PBC-218, Sheet 3
Fire Protection for Turbine Building, Aux Building &
Containment ELEV. 26'-0" Point Beach N.P. Units 1 & 2
Drawings
PBC-218, Sheet 8
Fire Protection for Control Room ELEV. 44'-0" & Computer
Room ELEV. 60'-0 Point Beach Nuclear Plant Unit 1 & 2
Pre-Fire Plan Control Building Elev 8 ft, 26 ft, 44 ft, and 66 ft
Fire Plans
PFP-0-PAB-8
Pre-Fire Plan Primary Auxiliary Building Elevations 8 ft and
Below
Miscellaneous
Fire Drill Scenario
Crew C: 2nd Quarter 2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NP 1.9.13
Ignition Control Procedure
NP 1.9.14
Fire Protection Plan
Procedures
OM 3.27
Control of Fire Protection and NFPA 805 Equipment
Work Orders
40802652-23
K-003B / Install Service Air Test Conn. North Aux Feed
05/03/2024
Calculations
2014-0007
Allowable Flood Levels
E-100, Sheet 1
Electrical Plot Plan Details
Drawings
PBE-816
Cable Vault Locations
Corrective Action
Documents
2485848
2B-41 MCC Breaker 2B52-42D, the 2B02 to 2B41, Tripped
05/07/2024
Miscellaneous
PBN LOC24C
003S
CPE Style Scenario
AOP-17A Unit 2
Rapid Power Reduction
MDB 3.2.6 2B41
480 V AC Motor Control Centers
Procedures
OP-2A Unit 2
Normal Power Operation Unit 2
2470986
1CS-232A Will Not Adjust in Band, Causing Accumulator
Hi Pres
10/28/2023
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
Corrective Action
Documents
2486411
Inspect/Replace 1CS-242A to Support 1K-29A
Troubleshooting
05/15/2024
Drawings
M-209 Sheet 5
P&ID Instrument Air
Miscellaneous
EVT-480V-2024-
20106
Maintenance Rule Functional Failure Determination
05/22/2024
CMP 2.3
Relief/Safety Valves
Maintenance Rule Program Administration
RMP 9303
DB-50 Breaker Routine Maintenance
Procedures
RMP 9369-1
Westector/Amptector Overload SerpointC Heck on Low
Voltage Breakers
Work Orders
40785650-01
B52-DB50-018; Breaker Maint per RMP 9303 and
11/21/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RMP 9369-1
40954962-01
Gas Leakage from 1CS-3126A MFIV Accumulator/Operator
2/04/2023
40954962-06
1CS-03126A / Perform As-left Testing Prior to Installation
01/05/2024
40954966-01
1CS-232A - Bench Check Regulator and Replace if Necessary
10/29/2023
40956122-01
1K-29A Cycling Excessively
2/01/2024
2488806
Z-015 Pre-Lift Inspection
06/18/2024
Corrective Action
Documents
2489023
Z-015 Pre-Lift Inspection
06/20/2024
Guarded Equipment Log
06/25/2024
Miscellaneous
Rigging Lift Plans
06/21/2024
1ICP 03.016
Independent Overspeed Protection System Analog and
Train A and B Logic Test
2ICP 02.008-1
Nuclear Instrumentation Power Range Axial Offset Calibration
Rigging Handbook and Inspection Procedure
Rigging and Material Handling
Guarded Equipment
SLP 4
Safe Load Path and Rigging Manual
Procedures
Work Activity Risk Management
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
Work Orders
40908448-03
(Contingency) Unit 2 NIs Power Range Axial Offset Cal
05/31/2024
2461599
Validate Tavg/Tref Deviation Meter
07/05/2023
2467128
Unexpected 1C04 1A 3-10 Reactor Coolant T AVG Deviation
Alarm
09/17/2023
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
Lowered
04/26/2024
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
Corrective Action
Documents
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
Resulting from
Inspection
Issues
207034-H Sheet 1
30in. Main Steam Non-return Valve CV-2017A & CV-2018A
207034-H Sheet 2
30in Main Steam Isolation Check Valve
Drawings
M-2201 Sheet 1
P&ID Main & Reheat Steam System
Engineering
Changes
258496
EPU - MSIV and NRV Valve Disc Upgrades (U2)
2RMP 9306-1
Main Steam Non-Return Check Valve Inspection Without
Removing Cover (Unit 2)
NP 7.7.28
Cable Condition Monitoring Program
and 8
NP 7.7.37
Surveillance Frequency Control Program Manual
OM 3.42
Control of WR SFP Level Instrumentation and Credited
FLEX Equipment
Procedures
PBF-2034
Control Room Log U1
105
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
Work Orders
40955496
Investigate Reason for U1 White Channel Temperature Offset
04/04/2024
Calculations
2005-0054
Control Building GOTHIC Temperature Calculation
Corrective Action
Documents
2486793
2W-001A2-A Second Blade Disconnected from Damper Shaft
05/21/2024
2489616
Calc 2005-0054 Error
06/27/2024
2490407
Clarity of Basis for A Train EDG Room Heat Up Parameters
07/10/2024
Corrective Action
Documents
Resulting from
Inspection
2490693
Potential Green NCV, 10 CFR Appendix B, Criterion III
07/15/2024
297502
1CW-3 Seal Well Outlet MOV Temporary Configuration
Alignment
298378
1CW-3 Seal Well Outlet MOV TCC Conversion to
Permanent Mod
Engineering
Changes
299709
2W-1A2-A Backdraft Damper Temporary Duct Blank
Engineering
Evaluations
2015-0017
G-01 and G-02 Air Temperature Limit
Miscellaneous
SCR 2013-0043-
Revise OI 168 Emergency Diesel Generator Operability,
TS B 3.8.1 and PBF-2035
08/21/2013
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Circulating Water System Malfunction
Severe Weather Conditions
Service Water System Malfunction
OI 168
Emergency Diesel Generator Operability
Procedures
OI 38
Circulating Water System Operation
2486703
CR Vent Failed to Shift from Mode 5 to Mode 1
05/20/2024
2486861
Potentially Inadequate PMT on DAM 7 Restoration
05/22/2024
2486927
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
Corrective Action
Documents
2486793
2W-001A2-A Second Blade Disconnected from Damper Shaft
05/21/2024
Corrective Action
Documents
Resulting from
Inspection
2490694
Potential Minor PD - IT Series Procedures Signoffs Not
Consistent
07/15/2024
036032
2"-16" 150 Pound Swing Check Valve
BD-4
Block Diagram-Instrument Reactor Protection System
Delta T - T Average - Loop B-1
CD-6 JOB 10668
Sheet 1
Wiring Diagram-Interconnect Reactor Protection System Rack
1-1B (1C116) Top
Drawings
CD1-22
Connection Diagram Rack 1C173A-F
0-SOP-FLEX-004
FLEX Portable Diesel Steam Generator Injection Pump
Operation
1ICP-13.004B
Spec 200, Reactor Vessel Level and Subcooling Post Accident
Monitoring Instruments 18 Month Calibration
Procedure and Work Instruction Use and Adherence
Inservice Testing Procedure
HPIP 7.51.7
DAM/SPING Post-Startup Operational Verification
IT 01 Train A
High Head Safety Injection Pumps and Valves Train A Unit 1
IT 02 Train A
High Head Safety Injection Pumps and Valves Train A Unit 2
IT 03 Train A
Low Head Safety Injection Pumps and Valves Train A Unit 1
IT 04 Train A
Low Head Safety Injection Pumps and Valves Train A Unit 2
Procedures
IT 04 Train B
Low Head Safety Injection Pumps and Valves Train B Unit 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
IT 05 Train A
Train A Containment Spray Pump and Valves Unit 1
IT 45 Train B
Safety Injection Valves Train B Unit 2
Maintenance Testing
MI 32.13
Belts and Pulleys
OI 81
RMS Troubleshooting and Startup
OI 81
RMS Troubleshooting and Startup
Conduct of Operations
PC-29
Gas Turbine and Auxiliary Diesel Load Test
Procedure
Writer's Guide
Procedure Writers Guide
RMP 9328
SW-32A-F Service Water Pump Discharge Check Valve
Inspection
TS 34
Containment Accident Recirculation Fan-Cooler Units Unit 2
TS 84
Emergency Diesel Generator G-04 Monthly
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
Work Orders
40978994-06
2W-001A2-A, OPS PMT/RTS
05/22/2024
Miscellaneous
2Q24 CEP
Installation
Practice Drill
Drill Spreadsheet
04/25/2024
Procedures
Seismic Event
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Calculations
HP-100-012623
Basis for GEM-5 Portal Monitor Alarm Setpoint Change
01/27/2023
27020-0610-
231219
Calibration Certificate for Telepole II SN 427020-061 and
28020-061
2/19/2023
PBF-4020
Low Volume Air Sampler Maintenance and Calibration Record
for SN 330785
2/07/2023
PBF-4020d
Escort ELF Air Sampling Pump Calibration Record for
SN A2-41247
11/09/2023
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
Calibration
Records
RP-AA-110-1000-
F01
Cronos Calibration Data Sheet for SN 1511-197
09/07/2023
2465046
MSL Rad Monitor Calculation 99-0106 Not Updated for New
Source Term
08/21/2023
2465471
Documents Have Different MSL LLD Values
08/24/2023
2473296
Calibration Constant for MSL Radiation Detectors May Be
Incorrect
11/29/2023
Corrective Action
Documents
2473308
RMS Background Subtract Not Performed IAW Vendor
Instruction
11/29/2023
HPCAL 1.33
Maintenance and Calibration of Low Volume Air Samplers
HPCAL 1.49
Calibration of Portable Dose Rate Instruments
HPCAL 2.23
Portable Scaler Calibrations
HPCAL 2.24
Calibration of the ARGOS 5AB Alpha/Beta Whole Body
Contamination Monitor
HPCAL 2.25
Calibration of the GEM Whole Body Contamination Monitor
Procedures
Operation and Calibration of the Cronos Contamination
Monitors
Work Orders
40869430
1RE-229/229B Calibration
01/25/2024
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
40873521
2RM-SPING-22 Calibration
01/19/2024
2432491
Potential Adverse Trend for Environmental Air Sampling
04/08/2024
Corrective Action
Documents
2465121
08/22/2023
Offsite Dose Calculation Manual
22 Annual Monitoring Report
04/10/2023
Miscellaneous
21 Annual Monitoring Report
04/14/2022
HPIP 3.58.1
Radiological Environmental Sampling
Procedures
NP 3.4.7
Groundwater Protection Program
Self-Assessments
L1A 02419352
Year GWPP Self-Assessment
2/21/2022
2005-0049
Primary Auxiliary Building (PAB) and Control Building (CB)
Mechanical Heat Load Calculation
Calculations
2005-0054
Control Building GOTHIC Temperature Calculation
2450093
1K-29B Continuous Air Bleed Coming from Weep Hole
03/04/2023
2464991
G-01 Room Temperature Outside Band 50-105 F While
Running
08/20/2023
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
SFP Cell SS-21
04/17/2024
2486044
1K-29A Haskel not Controlling Pressure as Set
05/10/2024
2486411
Inspect/Replace 1CS-242A to Support 1K-29A
Troubleshooting
05/15/2024
2488284
1K-29A Cycling ~30 Times per Minute
06/11/2024
Corrective Action
Documents
2488322
ACMP: Check for Operator Challenge
06/11/2024
Corrective Action
Documents
Resulting from
Inspection
2489967
TI-6616A Contributing to Questions on G-01 Room Heat Up
07/03/2024
Miscellaneous
Letter from Engine System, Inc. to Point Beach
2/23/2007
0-SOP-FH-001
Fuel/Insert/Component Movement in the Spent Fuel Pool or
New Fuel Vault
Procedures
Part 21 Reporting
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PBTP 259
G01 EDG Air Flow Measurement Test
09/20/2014
QI-7-NSC-1
Warehouse Receipt, Storage, Issuance and Maintenance
2A
Work Orders
40476004
Z-25A&B/Repair SFP Racks
06/05/2023