IR 05000266/2024001
| ML24100A790 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/11/2024 |
| From: | Billy Dickson NRC/RGN-III/DORS/RPB2 |
| To: | Durbin M Point Beach |
| References | |
| IR 2024001 | |
| Download: ML24100A790 (1) | |
Text
SUBJECT:
POINT BEACH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000266/2024001 AND 05000301/2024001
Dear Michael Durbin:
On March 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear Plant. On April 4, 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.
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 Point Beach Nuclear Plant.
April 11, 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, Billy C. Dickson, Jr., 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:
05000266/2024001 and 05000301/2024001
Enterprise Identifier:
I-2024-001-0077
Licensee:
NextEra Energy Point Beach, LLC
Facility:
Point Beach Nuclear Plant
Location:
Two Rivers, WI
Inspection Dates:
January 01, 2024 to March 31, 2024
Inspectors:
J. Masse, Resident Inspector
V. Petrella, Resident Inspector
M. Stafford, Senior Resident Inspector
Approved By:
Billy C. Dickson, Jr., 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 Account for Instrument Uncertainty Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000266,05000301/2024001-01 Open/Closed
[P.3] -
Resolution 71111.24 The inspectors identified a Green finding and an associated non-cited violation (NCV) of Title 10 CFR, Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, when the licensee failed to prescribe an instruction or procedure with the appropriate qualitative or quantitative acceptance criteria for determining that important activities have been satisfactorily accomplished. Specifically, the licensee failed to account for instrument uncertainty when calculating the technical specification value of sodium hydroxide in the spray additive tank.
Additional Tracking Items
Type Issue Number Title Report Section Status URI 05000266,05000301/20 23004-03 Potential Failure to Correct an
NRC Identified
Violation 71152A Closed
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
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the overall preparations to protect risk-significant systems from impending severe weather with a blizzard moving through the area on January 12, 2024.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 motor driven auxiliary feedwater pump on January 23, 2024 (2)125 volt direct current station batteries and switchgear on February 2, 2024
- (3) G-01 emergency diesel generator starting air system and fuel oil system on February 12, 2024
- (4) G-04 emergency diesel generator starting air system, fuel oil system, and the glycol cooling system on February 13, 2024
- (5) Unit 1 train A and B component cooling water loops on March 8, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (2 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 552 and 553 on January 19, 2024
- (2) Fire zones 225, 226, 227, and 228 on January 24, 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 announced fire drill on February 22, 2024.
71111.06 - Flood Protection Measures
Flooding Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the: Unit 1 and Unit 2 residual heat removal pump cubicles
71111.07A - Heat Exchanger/Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) HX-13B spent fuel pool heat exchanger on March 28, 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 the response to a plant process computer system indication failure on January 29, 2024, and during minor power changes to support turbine-driven auxiliary feedwater pump testing on February 8, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated an operator simulator evaluation on January 22, 2024.
71111.12 - Maintenance Effectiveness
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) Fire protection foam used in barrier penetrations between fire areas
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 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 the TS 3A, Turbine Trip Test Unit 1, on January 24, 2024
- (2) Unit 1 elevated risk due to 1ICP 02.013, 4.16 KV Undervoltage Matrix Relays Surveillance Test, on January 2, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Operability determination for boric acid found inside 2W-1B1 fan cubicle, Containment Accident Recirculation Fan, on January 22, 2024
- (2) Operability determination for the seal leakage on 1P-11B, Component Cooling Water Pump, on January 24, 2024
- (3) Operability determination for voids found in piping for the 1P-10A and 1P-10B residual heat removal pumps on February 1, 2024
- (4) Operability determination for elevated temperatures on 1P-11A, component cooling water pump, on March 8, 2024
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Battery and inverter room cooler modifications
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) (2 Samples)
- (1) OI 70, Service Water System Operation after a strainer backwash arm replacement on February 29, 2024
- (2) Post-maintenance testing after various preventative maintenance activities on the G-02 emergency diesel generator on March 5, 2024
Surveillance Testing (IP Section 03.01) (5 Samples)
- (1) Unit 1 train B engineered safety features logic testing, on January 18, 2024
- (2) Unit 1 train B reactor protection system logic testing on January 18, 2024
- (3) IT 05B, Containment Spray Pumps and Valves (Cold Shutdown) Unit 1, on January 22, 2024 (4)1ICP 02.032, 1P-29 Auxiliary Feedwater Suction Header Pressure Trip Channel Operability Test, on January 25, 2024
- (5) Calculation of sodium hydroxide in the spray additive tank on February 1, 2024
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Cold start of turbine-driven auxiliary feed pump, on February 8, 2024
71114.06 - Drill Evaluation
Required Emergency Preparedness Drill (1 Sample)
- (1) Point Beach first quarter emergency preparedness and information technology cyber drill on January 16, 2024.
Additional Drill and/or Training Evolution (1 Sample)
The inspectors evaluated:
- (1) Drill and exercise performance (DEP) opportunity during licensed operator requalification training on January 22,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 1 (January 1, 2023 through December 31, 2023)
- (2) Unit 2 (January 1, 2023 through December 31, 2023)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (2 Samples)
- (1) Unit 1 (January 1, 2023 through December 31, 2023)
- (2) Unit 2 (January 1, 2023 through December 31, 2023)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (2 Samples)
- (1) Unit 1 (January 1, 2023 through December 31, 2023)
- (2) Unit 2 (January 1, 2023 through December 31, 2023)
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in pre-fire plan accuracy that might be indicative of a more significant safety issue. A minor violation identified as a part of this review is documented in the Results Section of this report.
INSPECTION RESULTS
Failure to Account for Instrument Uncertainty Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000266,05000301/2024001-01 Open/Closed
[P.3] -
Resolution 71111.24 The inspectors identified a Green finding and an associated non-cited violation (NCV) of Title 10 CFR, Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, when the licensee failed to prescribe an instruction or procedure with the appropriate qualitative or quantitative acceptance criteria for determining that important activities have been satisfactorily accomplished. Specifically, the licensee failed to account for instrument uncertainty when calculating the technical specification value of sodium hydroxide in the spray additive tank.
Description:
In the Point Beach 4th Quarter Integrated Inspection Report, 2023004 (ML24032A056), the NRC documented Unresolved Item 2023004-03 concerning a potential failure to correct a NRC identified violation. Specifically, the inspectors reviewed the corrective actions for NCV 2022002-01, issued in July 2022 (ML22208A123). The inspectors found that the licensee had failed to implement corrective actions to address this violation. Working with regional staff, the inspectors have determined that this represents a repeat violation of 10 CFR, Part 50, Appendix B, Criterion V. The following is a synopsis of this violation.
The spray additive system, supported by the containment spray system, assists in reducing the iodine fission product inventory in the containment atmosphere resulting from a design basis accident (DBA).
Radioiodine in its various forms is the fission product of primary concern in the evaluation of a DBA. It is absorbed by the spray from the containment atmosphere. To enhance the iodine absorption capacity of the spray, the spray solution is adjusted to an alkaline pH that promotes iodine hydrolysis. This process converts iodine to a nonvolatile form. Because of its stability when exposed to radiation and elevated temperatures, sodium hydroxide (NaOH) is the preferred spray additive. The NaOH added to the spray also ensures a pH value in the acceptable range of 7.0 to 10.5. The minimum pH in the containment sump needed to keep iodine in the iodate form is 7.0. A pH greater than 7 assures the continued iodine removal effectiveness. The maximum pH is based on equipment qualification considerations to minimize the occurrence of chloride and caustic stress corrosion on mechanical systems and components and is set to 10.5.
Technical Specification Surveillance Requirement (SR) 3.6.7.3 requires the licensee to determine the concentration of NaOH in the spray additive tank and perform this surveillance test every six
- (6) months. The requirement is to verify that the spray additive tank NaOH solution concentration is greater than or equal to 30 percent and less than or equal to 33 percent by weight.
The licensee uses procedure CAMP 226, Sodium Hydroxide: H2SO4 Titration Method, to determine the concentration of sodium hydroxide in the sample. In the procedure, the licensee titrates the sample from the sodium hydroxide tank using sulfuric acid. After the titration, the licensee then calculates the percentage of NaOH. The procedure states, in part, that the 2-sigma precision and single measurement accuracy is approximately +/- 0.3
[percent] NaOH. This means that the instrument uncertainty of the titration is +/- 0.3 percent NaOH.
The work orders that direct the licensee to perform CAMP 226 contain the acceptance criteria from the technical specification surveillance requirement SR 3.6.7.3 of greater than or equal to 30 percent and less than or equal to 33 percent by weight. This acceptance criteria does not consider the instrument uncertainty discussed in CAMP 226.
The NRC inspectors and licensee did not find any evidence that the calculation 2000-0036, pH of Post LOCA Sump and Containment Spray, took instrument uncertainty into account.
Corrective Actions: Once the licensee became aware of the problem, they updated the asset change table and made assignments to progress the change through their system. The PM model work order has been updated and the procedure has been performed correctly for each unit.
Corrective Action References: Action Request (AR) 02430785 - SAT Analysis Work Order Documentation (NRC Identified), AR 02472083 - PMC in Screening for Extended Amount of Time and AR 02473217 - CA Untimely due to Inappropriate Closure to PMCR
Performance Assessment:
Performance Deficiency: The inspectors determined that the failure to prescribe an instruction or procedure with the appropriate qualitative or quantitative acceptance criteria for determining that important activities have been satisfactorily accomplished was a violation of 10 CFR Part 50, Appendix B, Criterion V, and was a performance deficiency. Specifically, the licensee did not consider the instrument uncertainty when determining the concentration of sodium hydroxide.
Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, the failure to not take into account the instrument uncertainty on the spray additive tank solution could result in the NaOH concentration being outside of the allowed band and therefore the system would not meet its design basis.
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 the questions in Exhibit 3.C.
Cross-Cutting Aspect: P.3 - Resolution: The organization takes effective corrective actions to address issues in a timely manner commensurate with their safety significance. Specifically, the licensee closed their corrective action document to a work order change but failed to update the work order. The failure went unnoticed until the NRC questioned the status of the work order change.
Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires in part, that instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
Contrary to the above, prior to October 25, 2023, the licensee failed to prescribe an appropriate instruction or procedure with the appropriate qualitative or quantitative acceptance criteria for determining that important activities have been satisfactorily accomplished. Specifically, in the work orders calculating sodium hydroxide concentration in the spray additive tank, the licensee did not consider the instrument uncertainty for determining this concentration, as specified in CAMP 226, Sodium Hydroxide: H2SO4 Titration Method.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
The disposition of this finding and associated violation closes URI:
05000266,05000301/2023004-03.
Unresolved Item (Closed)
Potential Failure to Correct an NRC Identified Violation URI 05000266,05000301/2023004-03 71152A
Description:
A finding/violation was identified as described above.
Corrective Action Reference(s): AR 02472083 - PMC in Screening for Extended Amount of Time and AR 02473217 - CA Untimely due to Inappropriate Closure to PMCR Minor Violation 71152S Failure to Perform Independent Assessment in Accordance with Written Checklist Minor Violation: The licensee's independent assessment, "PBN 21-006, Fire Protection,"
reviewed the Point Beach Fire Protection Program and its compliance with 10 CFR 50.48, "Fire protection." The assessment contained checklist items that direct the auditor to review elements that are related to the requirements of the fire protection program. Checklist item 6 contained an element that directed the auditor to perform the following:
Verify current and detailed pre-fire plans are available to the industrial fire brigade for all areas in which a fire could jeopardize the ability to meet NFPA 805, Section 1.5, performance criteria, including the following:
- The plans detail the fire area configuration and fire hazards to be encountered in the fire area, along with any nuclear safety components and fire protection systems and features that are present.
- The plans are available in the control room and made available to the plant industrial fire brigade.
The plans address coordination with other plant groups during fire emergencies.
Ref. NFPA 805, 3.4.2 The completed assessment results state:
Fire Plans are in the Control Room and the Fire Brigade Ready Area in a hard copy format. A physical walkdown by the auditor found both binders contained current revisions as required. Auditor validated no outstanding revisions to these pre-fire plans existed. The review and validation did not identify any gaps and is considered satisfactory.
The inspector noted that the assessment results do not specifically state how the auditor verified the plans detail the fire area configuration and fire hazards to be encountered in the fire area, along with any nuclear safety components and fire protection systems and features that are present.
The NRC inspectors have identified several cases where pre-fire plans (PFPs) contained discrepancies in their respective fire area configurations. Upon discovery of these discrepancies, the inspectors notified the licensee, and the licensee revised the PFPs accordingly. Below is a summary of some condition reports initiated due to the inspectors' questions:
- AR 2410039, (P) PFP-2-CONT-FAC - PRE-FIRE PLAN UNIT 2 (DOCDIST)o 11/2/2021 - The Unit 2 containment PFP was updated because two oil collection tanks and two hose reels were in the wrong location, a ventilation duct was drawn as a walking path, and there was no opening drawn on 66' containment elevation that leads to the reactor head laydown area.
- AR 2422170, PFP-0-PAB 8 UPDATES NEEDED, NRC QUESTION o
3/21/2022 - The auxiliary building PFP was updated to show the correct orientation of sprinklers and to add a flammable liquid cabinet.
- AR 2422453, (S) PFP-0-PAB 8 PRE-FIRE PLAN PRIMARY AUXILIARY BUILDING o
3/23/2022 - The auxiliary building PFP was updated to add pump oil to the Fire category and note that transient combustibles may be present for maintenance.
- AR 2424251, (S) PFP-1-CONT-FAC - PRE-FIRE PLAN UNIT 1 o
4/8/2022 - The Unit 1 containment PFP was updated to add the reactor coolant pump oil collection tank on the 10' platform, and draw obstacles that personnel must walk around.
- AR 2433350, (P) PFP-0-CB - PRE-FIRE PLAN CONTROL BLDG (DOCDIST) - REV 6 o
8/2/2022 - The control building PFP was updated to draw a missing fire door on the map, and revise coloring to represent high risk fire areas.
- AR 2447769, PFP-0-PAB 8 - PRE-FIRE PLAN PRIMARY AUXILIARY (DOCDIST) - R6 o
2/7/2023 - The auxiliary building PFP was updated to add room names, add a subsoil drain, and make fire zone labels more clearly identify their respective zones.
- AR 2463684, (S) PFP-1-TB-26 - PRE-FIRE PLAN UNIT 1 TURBINE o
8/2/2023 - The turbine building PFP was updated to include a missing dry chemical fire extinguisher, halon storage tanks, a flammable locker, and a flammable cabinet.
These condition reports and the lack of specific documentation in the independent assessment checklist element referenced led the inspectors to conclude that the auditor did not perform the assessment according to the written checklist.
The inspectors determined that failure to perform the independent assessment in accordance with the written checklist was a performance deficiency. Specifically, the auditor did not verify that the plans detail the fire area configuration and fire hazards to be encountered in the fire area, along with any nuclear safety components and fire protection systems and features that are present.
Point Beach Renewed Facility Operating License condition 4.F requires, in part, NextEra Energy Point Beach Units 1 and 2 shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c).
Point Beach's Fire Protection Plan: NP 1.9.14, Section 1.1 states, in part, that the Fire Protection Plan has been established to describe the overall Fire Protection Program (FPP)for the Point Beach Nuclear Plant (PBNP). NP 1.9.14, Section 4.12 states, in part, that the NextEra Quality Assurance Topical Report (QATR) (FPL-1) provides the quality assurance requirements for the PBNP. The following elements of the QATR apply to those items within the scope of the Fire Protection Program: Audits.
The NextEra QATR, Section C.3, Independent Assessment, states, in part, planning for independent assessments identifies the characteristics and activities to be assessed and the relevant performance and/or acceptance criteria. Independent assessments are then conducted using these predetermined criteria.
Contrary to the above, on August 27, 2021, the licensee did not conduct an independent assessment using the predetermined criteria. Specifically, independent assessment PBN 21-006, Fire Protection, checklist item #6 contained a predetermined criterion for the auditor to verify detailed pre-fire plans detail the fire area configuration and fire hazards to be encountered in the fire area, along with any nuclear safety components and fire protection systems and features that are present. However, the NRC inspectors found no evidence of verification of this predetermined criterion. The NRC inspectors also identified multiple errors which the audit could have caught. The licensee documented these errors under action requests: 2410039, 2422170, 2422453, 2424251, 2433350, 2447769, and 2463684.
Screening: The inspectors determined the performance deficiency was minor. The NRC inspectors screened the performance deficiency as minor because the NRC inspectors answered no to all the more than minor questions found in Inspection Manual Chapter (IMC)0612 Appendix B, "Issue Screening Directions." The NRC inspectors consulted example 4.i of IMC 0612 Appendix E, "Examples of Minor Issues," and concluded that the performance deficiency would be minor because the performance deficiency would not impact the ability of the licensee to manually fight a fire.
Enforcement:
The licensee has taken actions to restore compliance. This failure to comply with Point Beach Renewed Facility Operating License condition 4.F constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 4, 2024, the inspectors presented the integrated inspection results to Michael Durbin and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Severe Weather Conditions
MI 32.20
FPL/Point Beach Nuclear Plant Snow Removal Plan
NP 7.2.29
External Events Program
Procedures
OM 3.30
Operations Snow Emergency Staffing
Corrective Action
Documents
Resulting from
Inspection
2480169
G-01 Drawing Inconsistencies with Field Conditions
2/28/2024
110E018 Sheet 1
P&ID Auxiliary Coolant System
110E018 Sheet 2
P&ID Auxiliary Coolant System
110E018 Sheet 3
P&ID Auxiliary Coolant System
E-6, Sheet 1
25V DC Dist. System
E-6, Sheet 2
25 Volt D.C. System
E-6, Sheet 3
25V DC Dist. System
M-209 Sheet 12
P&ID EM. Diesel Air Starting Sys. Point Beach N.P. Unit 1&2
M-209 Sheet 15
P&ID Starting Air System Diesel Generator Building M-209
SH. 15 Point Beach N.P. Unit 1 & 2
M-217 Sheet 1
P&ID Auxiliary Feedwater System
107
M-219 Sheet 1
P&ID Fuel Oil System Point Beach N.P. Unit 1
M-219 Sheet 3
P&ID Fuel Oil System Diesel Generator Building Point
Beach N.P. Unit 1&2
M-2217
P&ID Auxiliary Feedwater System
Drawings
M-227 Sheet 2
P&ID Glycol Cooling System Diesel Generator Building Point
Beach N.P. Unit 1&2
Miscellaneous
25 VDC System Design Basis Document
CL 13E Part 2
Auxiliary Feedwater Valve Lineup Motor Driven
Procedures
RMP 9046-1
Station Battery 92 Day, 12 Month Surveillance Tests
Corrective Action
Documents
Resulting from
Inspection
2477311
PFP-0-PAN - Pre-Fire Plan Protected Area North
01/23/2024
Drawings
M2005-6-44,
Yellow Instrument Bus Fire Barrier Equip. Room "B" (226)
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Sheet B
26' El. Ceiling
PBM-250
P&ID Battery & EE Room Rms. Vac.
PFP-0-PAB 26
Pre-Fire Plan Unit 1 & Unit 2 Auxiliary Building 26 ft
Fire Plans
Pre-Fire Plan Protected Area North (Inside the Fence)
Miscellaneous
FPEE 1999-009
Undampered Ventilation Ducts in Significant Fire Barriers in
the Control, Primary Auxiliary and Turbine Buildings
NP 1.9.14
Fire Protection Plan
Procedures
NP 8.4.11
Penetrating Barriers
Calculations
2014-0007
Allowable Flood Levels
ARP 1C20 A 1-4
Auxiliary Building -19ft Sump/Area Level High
NP 8.4.17
PBNP Flooding Program
Procedures
PC 37
Plant Sump Alarm Tests (Semiannual)
Calculations
2016-0009
PBNP SFP Heat Exchanger Performance Calculation
Procedures
Program
Document
GL 89-13 Program Document
Work Orders
40875661-01
Eddy Current Task 1 Work Standard
03/21/2024
Miscellaneous
PBN LOC 24A
001E
Licensed Operator Continuing Training
PPCS Malfunction
Procedures
Normal Power Operation Unit 2
Corrective Action
Documents
2476908
Defective Fire Penetration Foam Kits
01/18/2024
DG-F02
Fire Barrier Penetration Seal Typical Detail Designs
Procedures
RMP 9393
Mixing and Installation of Two Component Silicones for Fire
Barriers
Work Orders
40810325-23
Foam Seal Penetration M-2005-6-20-E27
01/22/2024
Work Activity Risk Management Plan for the Unit 1(2)
Turbine Trip Block Testing
01/24/2024
Miscellaneous
Work Activity Risk Management Plan for the 1(2) ICP 02.013
4.16KV Undervoltage Matrix Relays 31-Day Surveillance
Test (TADOT)
01/02/2024
Calculations
2010-0010
Acceptance Criteria for GAMP Sentinel Points
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2424405
High Motor Temperatures on 1P-11A
04/10/2022
2438454
1P-11A Motor Temp High
10/02/2022
2475191
~34 DPM Inboard Seal Leakage on 1P-11B, CCW Pump
2/22/2023
2475646
Boric Acid Found In 2W-1B1/1B2 Fan Cubicle
01/02/2024
2477201
Void Greater than NRI Found during UT Checks
01/22/2024
2477218
Void Greater than NRI Found during UT Checks
01/22/2024
Corrective Action
Documents
2480468
1P-11A-M CCW Pump Motor Temperature Elevated
03/04/2024
Corrective Action
Documents
Resulting from
Inspection
2477288
NRC Identified: 2W-1B1 ACC Fan Discharge Temperature
Trend
01/23/2024
110E018 Sheet 1
P&ID Auxiliary Coolant System
M-2215 Sheet 1
P&ID Heating & Ventilation Point Beach N.P. Unit 2
Drawings
PBA-1137
Piping Isometric 1-P10A & B RHR Pump Bypass
Boric Acid Leak Screening for 2W-1B1
EQCK-WEST-
008
Checklist for Environmental Qualification Assessment of
Electrical Equipment
EQMR-CCW
Equipment Qualification Maintenance Requirement
TLB-9
Component Cooling Water Surge
Miscellaneous
NP-V1
Testing and Evaluation of Gas Transport to the Suction of
ECCS Pumps
Work Orders
40875121-01
1-TS-ECCS-002 Train B
01/22/2024
2002-0039
Fire Loading Calculation
Calculations
22-04502
Point Beach Auxiliary Building Battery & Inverter Rooms
Supplemental Cooling Calculation
Engineering
Changes
PAB Battery and Inverter Room Cooler Installation
Miscellaneous
SL-017901
Fire Risk Evaluation of EC 296454 PAB Battery and Inverter
Room Cooler Installation
2000-0036
pH of Post LOCA Sump and Containment Spray
Calculations
97-0231
Auxiliary Feedwater Pump Low Suction Pressure Trip
Instrument Loop Uncertainty/Setpoint Calculation
Corrective Action
2430785
SAT Analysis Work Order Documentation (NRC Identified)
06/27/2022
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2472083
PMC in Screening for Extended Amount of Time
11/10/2023
2473217
CA Untimely due to Inappropriate Closure to PMCR
11/28/2023
2477533
Main Zurn Strainer Alarm
01/26/2024
2478619
Sections Reperformed during IT 09A
2/08/2024
Documents
2479695
Fuel Leak on Elbow Near F-180B G-02
2/21/2024
2471915
IST Program Inadequate Testing of MOVS
11/08/2023
2477742
Use of Fluke 289 in Calibrations - NRC Identified
01/29/2024
Corrective Action
Documents
Resulting from
Inspection
2479620
NRC Identified Completed Work Order Not in NAMS
2/21/2024
883D195 Sheet 7
Logic Diagrams Safeguards Actuation Signals
Drawings
M-207
Miscellaneous
Internal Correspondence: M&TE Equivalency and Related
Items
2/12/2024
0-SOP-G02-001
Maintenance Operation For EDG G-02
1ICP 2.3B
Reactor Protection System Logic Train B Surveillance Test
1ICP 2.5B
Engineered Safety Features System Logic Train B Actuation
Logic Test
CAMP 226
Sodium Hydroxide: H2SO4 titration Method
CAMP 226
Sodium Hydroxide: H2SO4 titration Method
IT 09A
Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve
Test (Quarterly) Unit 2
MA-AA-204-
1000-10001
Preventative Maintenance Change Request (PMCR)
OI 70
Service Water System Operation
Condition Reporting
RMP 9043-23
Emergency Diesel Generator G-02 Mechanical Inspection
Procedures
TS 82
Emergency Diesel Generator G-02 Monthly
100
40769618-01
SAT NaOH SR 3.06.07.3
01/14/2022
40769627-01
SAT NaOH SR 3.06.07.3
01/14/2022
40792544-01
SAT NaOH SR 3.06.07.3
07/13/2022
40792548-01
SAT NaOH SR 3.06.07.3
07/13/2022
40819818-01
SAT NaOH SR 3.06.07.3
01/11/2023
Work Orders
40819820-01
SAT NaOH SR 3.06.07.3
01/11/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
40830496-01
IT-05B, Cont Spray Pump/Vlv Testing (CSD), "Task
Required to
10/25/2023
40844646-01
G-02, 12Y Group A PMs
2/20/2024
40844646-02
G-02, OPS PMT/RTS
2/21/2024
40847898-01
SAT NaOH SR 3.06.07.3
07/13/2023
40847905-01
SAT NaOH SR 3.06.07.3
07/13/2023
40873341-01
SAT NaOH SR 3.06.07.3
01/24/2024
40873344-01
SAT NaOH SR 3.06.07.3
01/24/2024
40873347-01
1ICP 2.3B -- Reactor Protection Logic Test - Train B
01/11/2024
40873352-01
1ICP 2.5B -- Safeguards Logic Test - Train B
01/11/2024
40875095-01
1ICP-2.32 -- 1P-29 Auxiliary Feedwater Suction Pressure
Trip
2/21/2024
40875191-02
SW-02912-BS Inspect Zurn Strainer
01/24/2024
40877343-01
IT-09A, 2P-29 AFP Cold Start Test/Valves
2/08/2024
40963338-01
SW-02912-BS; Replace Limit Switch
2/13/2024
40963338-02
SW-02912-BS; OPs PMT/RTS
01/31/2024
2476726
Unexpected Simulator Behavior During EP Drill
01/16/2024
2476761
Simulator Unexpectedly Set to Inactive During EP Drill
01/17/2024
2478166
Develop JPM for SRO Staff on Emergency Live Operator
Service
2/02/2024
2478169
Non DEP ERO Notification Would Have Been Late
2/02/2024
2478195
1Q24 EP Drill: SM Stumbled Announcement for Alert
2/02/2024
2478446
EP Drill - SM Stumbled Announcement for Alert
2/06/2024
Corrective Action
Documents
2479344
EPIP 2.1 - Notifications - ERO, State and Counties, and
NRC
2/16/2024
1Q24 EP and
Drill Combined
Facility Critique
Powerpoint
2/12/2024
Cyber Drill
Drill Spreadsheet
01/09/2024
Miscellaneous
PBN LOC 24A
001E
As Found Training Scenario
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
EP 5.0
Organizational Control of Emergencies
EP Appendix A
Emergency Response Organization Personnel Function and
Responsibility
EP Appendix B
Emergency Classification
Nuclear Division Drill and Exercise Procedure
EPG 1.1
Performance Indicators (PI's) Guideline
EPIP 1.1
Course of Actions
EPIP 1.2
Emergency Classification
Procedures
EPIP 2.1
Notifications - ERO, State and Counties, and NRC
2391043
(P) PFP-0-PAB 8 - Pre-Fire Plan Primary (DOCDIST)
04/23/2021
2410039
(P) PFP-2-CONT-FAC - Pre-Fire Plan Unit 2 (DOCDIST)
11/02/2021
22170
PFP-0-PAB 8 Updates Needed, NRC Question
03/21/2022
22453
(S) PFP-0-PAB 8 Pre-Fire Plan Primary Auxiliary Building
03/23/2022
24251
(S) PFP-1-CONT-FAC - Pre-Fire Plan Unit 1
04/08/2022
2433350
(P) PFP-0-CB - Pre-Fire Plan Control BLDG (DOCDIST) -
REV 6
08/02/2022
2447769
PFP-0-PAB 8 - Pre-Fire Plan Primary Auxiliary (DOCDIST) -
R6
2/07/2023
Corrective Action
Documents
2463684
(S) PFP-1-TB-26 - Pre-Fire Plan Unit 1 Turbine
08/02/2023
Corrective Action
Documents
Resulting from
Inspection
2482046
NRC Potential Minor Violation-PBN 2021 FP Audit Not per
03/22/2024
Performance of Nuclear Assurance Audits
NP 1.9.14
Fire Protection Plan
Procedures
Pre-Fire Plan Standard Operating Guidelines
Self-Assessments PBN 21-006
Nuclear Assurance Audit, Fire Protection
08/27/2021