IR 05000266/2022003
| ML22311A203 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/07/2022 |
| From: | Billy Dickson NRC/RGN-III/DORS/RPB2 |
| To: | Strope M Point Beach |
| References | |
| IR 2022003 | |
| Download: ML22311A203 (1) | |
Text
SUBJECT:
POINT BEACH NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000266/2022003 AND 05000301/2022003
Dear Mr. Strope:
On September 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear Plant. On October 17, 2022, the NRC inspectors discussed the results of this inspection with Mr. J. Bryant, Maintenance Site Director, 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.
November 7, 2022 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 Dickson, 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:
05000266/2022003 and 05000301/2022003
Enterprise Identifier:
I-2022-003-0052
Licensee:
NextEra Energy Point Beach, LLC
Facility:
Point Beach Nuclear Plant
Location:
Two Rivers, WI
Inspection Dates:
July 01, 2022 to September 30, 2022
Inspectors:
J. Cassidy, Senior Health Physicist
T. Hartman, Senior Resident Inspector
V. Petrella, Resident Inspector
Approved By:
Billy Dickson, 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 Implement the Alpha Monitoring Program Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000266,05000301/2022003-01 Open/Closed
[H.13] -
Consistent Process 71124.01 The inspectors identified a finding of very low safety significance with an associated non-cited violation of 10 CFR 20.1501(a) for the failure to perform surveys to ensure compliance with 10 CFR 20.1902(d), posting of airborne radioactivity areas during the Unit 1 R40 refueling outage. Specifically, the licensee failed to assess loose contamination and/or airborne radioactivity for alpha emitting radionuclides even in systems and areas that the licensee determined the contamination contained significant contributions of alpha emitting radionuclides. Analysis performed to address the inspectors' issue of concern identified areas that should have been posted as airborne radioactivity areas but were not.
Additional Tracking Items
Type Issue Number Title Report Section Status URI 05000266/2022002-03 Alpha Monitoring Program 71124.01 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. On September 7, 2022, the unit was reduced to approximately 61 percent rated thermal power to support main turbine stop valve testing. The unit returned to full power on September 8, 2022, 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
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on September 8, 2022.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1 safety injection train A on July 6, 2022
- (2) G-03 emergency diesel generator fuel oil system, starting air system, and the glycol cooling system on July 15, 2022
- (3) Unit 1 turbine-driven auxiliary feedwater system on July 25, 2022
- (4) Unit 2 motor driven auxiliary feedwater system on August 31, 2022
- (5) Unit 1 motor driven auxiliary feedwater system on September 1, 2022
- (6) Unit 1 service water system on September 9, 2022
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 safety injection system on July 29, 2022.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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 304S and 304N on July 26, 2022 (2)fire zones 305, 306, 307, 308, and 309 on July 26, 2022 (3)fire zones 318, 326, 333, 334, 335, 336, and 337 on July 26, 2022
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) vital switchgear room and the G-01/G-02 emergency diesel generator rooms
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 service water pump testing and Unit 2 power ascension following turbine stop valve testing on September 8, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated simulator training on September 7, 2022.
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)reduced margin for standby emergency power due to G-01 emergency diesel generator maintenance on August 23, 2022 (2)increased risk due to the working area having dose rates greater than 1000 mrem/hr on September 15, 2022
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)through-wall leak on the service water strainer blowdown line (2)both starting air compressors for G-04 emergency diesel generator broken
- (3) Unit 2 containment cooler liquid monitor sample flow indicator grass fouled
- (4) Unit 1 pressurizer level indication has oscillations
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
(1)testing for work order 40792841-01 after the calibration of the 2Y-02 blue 120V vital instrument panel voltmeter on July 7, 2022 (2)2RMP 9329-1, 2P-15A Safety Injection Pump Motor Relay Testing and Calibration, after calibration and testing of the safety injection pump motor relays on July 14, 2022
- (3) IT 08A, Cold Start of Turbine-Driven Auxiliary Feed Pump and Valve Test (Quarterly)
Unit 1, after the replacement of 1SAF-04000 open contactor on July 21,2022
- (4) TS 82, Emergency Diesel Generator G-02 Monthly, after replacement of the G-02 exhaust piping on July 21, 2022 (5)0-PT-FP-002, Diesel Engine-Driven Fire Pump Functional Test, after replacement of the diesel fire pump expansion joint on July 28, 2022 (6)testing for work order 40833860-03 after the replacement and calibration of the T-31A diesel generator day tank high/low level switch on July 28, 2022 (7)testing for work order 40748474-04 after the video probe inspection of HX-13A spent fuel pool heat exchanger, on August 16, 2022
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (2 Samples)
(1)1ICP 02.002WH, Reactor Protection and Engineered Safety Features White Channel Analog Surveillance Test on July 19, 2022
- (2) IT 07A, P-32A Service Water Pump (Quarterly), IT 07B, P-32B Service Water Pump (Quarterly), and IT 07C, P-32C Service Water Pump (Quarterly), on September 8, 2022
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) IT 02 Train A, High Head Safety Injection Pumps and Valves Train A Unit 2, on July 13,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (IP Section 03.01) (3 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
(1)drumming area ventilation system (2)gas stripper building exhaust ventilation
- (3) Unit 1 service water discharge header
Sampling and Analysis (IP Section 03.02) (5 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
(1)gas stripper building ventilation - particulate and iodine sample
- (2) Unit 1 service water discharge
- (3) Unit 2 service water discharge (4)drumming area vent - particulate, iodine, tritium and SPING samples
- (5) Unit 1 steam generator blowdown grab sample
Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
- (1) Unit 1 containment forced vent - gaseous permit number 22-00089B
- (2) Unit 1 hotwell discharge - August 2, 2021
Abnormal Discharges (IP Section 03.04) (1 Sample)
The inspectors evaluated the following abnormal discharges:
- (1) Unit 1 hotwell discharge - August 2,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) Unit 1 (July 1, 2021 through June 30, 2022)
- (2) Unit 2 (July 1, 2021 through June 30, 2022)
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 (July 1, 2021 through June 30, 2022)
- (2) Unit 2 (July 1, 2021 through June 30, 2022)
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 (July 1, 2021 through June 30, 2022)
- (2) Unit 2 (July 1, 2021 through June 30, 2022)
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (2 Samples)
- (1) Unit 1 (July 1, 2021 through June 30, 2022)
- (2) Unit 1 (July 1, 2021 through June 30, 2022)
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) July 1, 2021 through March 31, 2022 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) July 1, 2021 through June 30,
INSPECTION RESULTS
Failure to Implement the Alpha Monitoring Program Cornerstone Significance Cross-Cutting Aspect Report Section Occupational Radiation Safety Green NCV 05000266,05000301/2022003-01 Open/Closed
[H.13] -
Consistent Process 71124.01 The inspectors identified a finding of very low safety significance with an associated non-cited violation of 10 CFR 20.1501(a) for the failure to perform surveys to ensure compliance with 10 CFR 20.1902(d) posting of airborne radioactivity areas during the Unit 1 R40 refueling outage. Specifically, the licensee failed to assess loose contamination and/or airborne radioactivity for alpha emitting radionuclides even in systems and areas that the licensee determined the contamination contained significant contributions of alpha emitting radionuclides. Analysis performed to address the inspectors' issue of concern identified areas that should have been posted as airborne radioactivity areas but were not.
Description:
Alpha emitting radionuclides have a significantly lower annual limit on intake than beta-gamma emitting radionuclides that might be present at a nuclear power plant. While the processes used to identify, monitor, and control alpha contamination are similar to those used for beta-gamma emitting contamination, the instrumentation used for alpha contamination is often different and the time needed to measure alpha contamination is often much longer than the count times normally used for beta-gamma contamination. Consequently, nuclear power plants typically perform detailed evaluations of plant systems and areas and determine the ratio of beta-gamma contamination to alpha contamination. The results of this assessment identify circumstances where the controls normally used for beta-gamma contamination may no longer be effective for the contamination hazards in zones or systems with relatively low ratios of beta-gamma to alpha contamination. Some additional actions and controls typically used in areas with relatively low ratios of beta-gamma to alpha contamination include the use of breathing zone or lapel air samplers as dosimeters to estimate the intake of radioactive material taken into the body and additional calculations of whole body counter results as this equipment does not detect alpha emitting radionuclides.
The inspectors reviewed licensee Technical Evaluation titled Site Alpha Characterization Update completed by the licensee's Health Physics staff on April 4, 2022 (HP-100-032922). The evaluation identified that the reactor coolant system, residual heat removal system, and chemical & volume control system for both units were characterized as alpha level 2 (Significant) for both units. The safety injection system for both units and the shared systems of spent fuel and radwaste processing were characterized as alpha level 3 (Elevated). However, another section of the same evaluation report appeared to have contradictory information, summarizing the activity ratios for each unit, and concluding that the most recent classification was alpha level 1 (Minimal).
While observing work activities that were in progress during the refueling outage, the inspectors identified that the licensees work controls and exposure monitoring seemed to be more consistent with the summarized (Alpha Level 1) information rather than the characterization for the systems that were being worked. Specifically, the inspectors observed:
- (1) work activities in the Unit 1 keyway (under vessel),
- (2) replacement of the resistance temperature detector (RTD) manifold from the reactor coolant system,
- (3) opening the steam generator manways with diaphragm removal, and
- (4) spent fuel pool work. Based on the inspectors observations and discussions with the licensee, the licensee was unable to demonstrate whether the radiological controls implemented to protect workers and monitor possible internal exposure were effective for the alpha contamination hazards present in these work areas.
The licensee subsequently provided detailed assessments of radiological surveys, including air samples data, for the work activities observed. The surveys requested by the inspectors were not evaluated for alpha emitting nuclides until after the NRC request, despite work involving Alpha Level 2 systems being performed 10 days earlier. After the evaluation was completed, airborne radioactive material existed in concentrations in excess of the derived air concentrations (DACs) specified in Appendix B, to §§ 20.1001-20.2401. As a result, there were areas with airborne radioactivity hazards that were not properly posted to alert personnel to the presence of radiological hazards and to aid them in minimizing exposures.
Corrective Actions: The licensee evaluated the inspectors observations and determined several actions were needed to correct the issues. Specifically, the licensee changed the as low as
- (is) reasonably achievable (ALARA) pre-job planning process to determine the alpha level based on the system to be worked and initiated a training work request to review alpha knowledge gaps and develop training to close the gaps. Additionally, the licensee is performing benchmarking for best practices in alpha characterization, revising the alpha characterization report to include these best practices, and revising processes for air sample documentation.
Corrective Action References: AR 02432779
Performance Assessment:
Performance Deficiency: The inspectors identified a finding of very low safety significance with an associated Non-Cited Violation of 10 CFR 20.1501(a) for the failure to perform surveys to ensure compliance with 10 CFR 20.1902(d) posting of airborne radioactivity areas during the Unit 1 R40 refueling outage.
Screening: The inspectors reviewed the guidance in IMC 0612, Appendix E, Examples of Minor Issues, and did not find any similar examples. The performance deficiency was determined to be of more than minor safety significance in accordance with IMC 0612, Appendix B, Issue Screening, because it was associated with the program and process attribute of the Occupational Radiation Safety cornerstone and adversely affected the cornerstone objective of ensuring adequate protection of worker health and safety from exposure to radiation, in that inaccurate radiation monitoring affects the licensees ability to control and limit radiation exposures.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix C, Occupational Radiation Safety SDP. Specifically, the inspectors determined that this finding is of very low safety significance (Green) because the performance deficiency was not related to ALARA, did not result in an overexposure nor a substantial potential for an overexposure, and the ability to assess dose was not compromised.
Cross-Cutting Aspect: H.13 - Consistent Process: Individuals use a consistent, systematic approach to make decisions. Risk insights are incorporated as appropriate. Specifically, the license did not have a consistent process to incorporate the anticipated contribution of alpha emitting nuclides in the ALARA pre-job planning activities to ensure radiation work permits and instructions to radiation protection technicians include risk insights to these hazards.
Enforcement:
Violation: Title 10 of the Code of Federal Regulations Part 20.1501 requires that each licensee make, or cause to be made, surveys that may be necessary for the licensee to comply with the regulations in Part 20 and that are reasonable under the circumstances to evaluate the extent of radiation levels, concentrations or quantities of radioactive materials, and the potential radiological hazards that could be present. Pursuant to 10 CFR 20.1003, survey means an evaluation of the radiological conditions and potential hazards incident to the production, use, transfer, release, disposal, or presence of radioactive material or other sources of radiation.
Title 10 of the Code of Federal Regulations Part 20.1902(d) requires the licensee to post each airborne radioactivity area with a conspicuous sign or signs bearing the radiation symbol and the words "CAUTION, AIRBORNE RADIOACTIVITY AREA" or "DANGER, AIRBORNE RADIOACTIVITY AREA".
Contrary to the above, as of April 7, 2022, the licensee did not make surveys to assure compliance with 10 CFR 20.1902, which requires the licensee to post each airborne radioactivity area with a conspicuous sign or signs bearing the radiation symbol and the words "CAUTION, AIRBORNE RADIOACTIVITY AREA" or "DANGER, AIRBORNE RADIOACTIVITY AREA". Although samples were collected, they were not evaluated for alpha emitting radionuclides. Consequently, areas in which airborne radioactive materials, composed wholly or partly of licensed material, existed in concentrations in excess of the derived air concentrations (DACs) specified in Appendix B, to §§ 20.1001-20.2401 and not posted with the words "CAUTION, AIRBORNE RADIOACTIVITY AREA" or "DANGER, AIRBORNE RADIOACTIVITY AREA".
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: 05000266/2022002-03.
URI Alpha Monitoring Program URI 05000266/2022002-03 71124.01
Description:
A finding/violation was identified as described above.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On October 17, 2022, the inspectors presented the integrated inspection results to Mr. J. Bryant, Maintenance Site Director, and other members of the licensee staff.
On July 14, 2022, the inspectors presented the radiation protection inspection results to Mr. M. Strope, Site Vice President, and other members of the licensee staff.
On September 6, 2022, the inspectors presented the radiation protection inspection results to Mr. D. Peterson, Radiation Protection and Chemistry Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
PBF-2124A
Mean Converted Lake Level Calculation
08/27/2022
NP 8.4.17
PBNP Flooding Program
Procedures
RMP 9422
Circulating Water Pumphouse and Turbine Hall Barrier
Placement
Guarded Equipment Postings Related to G-02 Outage
07/11/2022
Anchor SI-1501R-2-2H3 Not Labeled on Isometric Drawing
P-220
08/19/2022
M-207 - Service Water Sys.
09/09/2022
Corrective Action
Documents
Resulting from
Inspection
Drawing Error Identified
09/19/2022
110E017 Sheet 1
P&ID Safety Injection System Point Beach N.P. Unit 1
110E017 Sheet 2
P&ID Safety Injection System Point Beach N.P. Unit 1
110E035 Sheet 1
P&ID Safety Injection System Point Beach N.P. Unit 2
110E035 Sheet 2
P&ID Safety Injection System Point Beach N.P. Unit 2
M-201 Sheet 1
P&ID Main & Reheat Steam System Point Beach N.P. Unit 1
M-202 Sheet 2
Feedwater System Point Beach N.P. Unit 1
M-207 Sheet 1
P&ID Service Water Point Beach N.P. Unit 1
M-207 Sheet 1A
P&ID Service Water Point Beach N.P. Unit 1
M-207 Sheet 3
P&ID Service Water Point Beach N.P. Unit 1
M-207 Sheet 4
P&ID Service Water System Point Beach N.P. Unit 1
M-209 Sheet 14
P&ID Starting & Service Air System Diesel Generator
Building Point Beach N.P. Unit 1 & 2
M-217 Sheet 1
P&ID Auxiliary Feedwater System Point Beach N.P.
Unit 1 & 2
107
M-217 Sheet 3
P&ID Auxiliary Feedwater 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-2202 Sheet 2
P&ID Feedwater System Point Beach N.P. Unit 2
M-2217
P&ID Auxiliary Feedwater System Point Beach N.P. Unit 2
M-227 Sheet 1
P&ID Glycol Cooling System Diesel Generator Building Point
Beach N.P. Unit 1 & 2
Drawings
P-202
Suction From RWST to SI, CS, RHR Pumps Point Beach
N.P. Unit 2
P-219
Safety Injection Pump Discharge to Injection SI-1501R-1
and SI-1501R-3 Point Beach N.P. Unit 2
P-220
Safety Injection Pump Discharge to Injection Line
SI-1501R-1 and SI-1501R-2 Point Beach N.P. Unit 2
PFP-0-CB - Pre-Fire Plan Control Building Elev 8 ft, 26 ft
08/02/2022
Corrective Action
Documents
Resulting from
Inspection
NRC Question: PFP-0-CB
08/02/2022
Fire Plans
Pre-Fire Plan Control Building Elev 8 ft, 26 ft, 44 ft and 66 ft
Calculations
2014-0007
Allowable Flood Levels
Corrective Action
Documents
Resulting from
Inspection
Assumption for Consideration to be Added to Calc
2014-0007
09/29/2022
Procedures
OM 4.3.8
Control of Time Critical and Time Sensitive Operator Actions
Miscellaneous
PBN LOC 22E
003S
Loss of Heat Sink
OP 2D Unit 2
Power Operation Maneuvering - Unit 2
Procedures
Conduct of Operations
Work Activity Risk Management Plan for the G-01
Emergency Diesel Generator 2YR PMs and Governor
Replacement
08/23/2022
Miscellaneous
PDC for the Work Activity of Obtain Samples of Unit 1
Containment Filter and Two Unit 2 Containment Filters
09/15/2022
Through Wall Leak Found on Service Water Zurn Blowdown
Line
06/30/2022
15/K-4D Speed Switch Seized
07/06/2022
Flow Indicator Grass Fouled
08/28/2022
Corrective Action
Documents
1L426 - Level Oscillations
09/26/2022
Corrective Action
Documents
Resulting from
Inspection
Assumption for Consideration to be Added to CALC
2014-007
09/29/2022
M-207 Sheet 1
P&ID Service Water Point Beach N.P. Unit 1
Drawings
M-2206, Sh. 2
P&ID Service Water System
Station Log - Swing Shift
07/06/2022
Miscellaneous
Station Log - Day Shift
07/07/2022
Corrective Action
Documents
Data Lost for Procedure in DWP
07/14/2022
Recorded Data Discrepancy
08/22/2022
Corrective Action
Documents
Resulting from
Inspection
Work Orders Tasks Stuck in Closeout Review
09/01/2022
TS-82, G-02 EDG Operability Test (PMT)
08/03/2022
HX-13A GL 89-13 Video-Probe Inspection Shell Side
09/06/2022
2A52-74 - Calibrate and Test 2P-15A Breaker Relays
07/14/2022
2Y-02-VM; Panel Voltmeter Calibration
07/07/2022
P-035B-E Maintain, Clean and Lubricate Engine
07/29/2022
XJ-03772: Replace Expansion Joint
07/28/2022
Spurious T-31A EDG Day Tank Level Alarms
07/28/2022
Work Orders
1AF-4000; 1P-29 AFP Disch SG B Inlet MOV Fails to Open
07/21/2022
Calculation Accuracies and Associated Issues
07/19/2022
Step Change in P-32A SWP Vibration Readings During
IT-07A
09/08/2022
P-32C SWP Flow was 63 GPM Above the Alert Range
09/08/2022
Corrective Action
Documents
PCR 2432336
1ICP 02.001WH - Reactor Protection and Engineered Safety
Fea
07/19/2022
IT 07A - P-32A Service Water Pump (Quarterly)
09/08/2022
IT 07B - P-32B Service Water Pump (Quarterly)
09/08/2022
IT 07C - P-32C Service Water Pump (Quarterly)
09/08/2022
IT 07D - P-32D Service Water Pump (Quarterly)
09/08/2022
IT 07E - P-32E Service Water Pump (Quarterly)
09/08/2022
Corrective Action
Documents
Resulting from
Inspection
IT 07F - P-32F Service Water Pump (Quarterly)
09/08/2022
Procedures
1ICP 02.001WH
Reactor Protection and Engineered Safety Features White
Channel Analog Surveillance Test
IT 02 Train A
07/14/2022
IT-07A, P-32A Service Water Pump Test
09/09/2022
IT-07B, P-32B Service Water Pump Test
09/09/2022
Work Orders
IT-07C, P-32C Service Water Pump Test
09/09/2022
Miscellaneous
U1R40 Alpha Monitoring Review
06/16/2022
DXW06GY
Personnel Contamination Event Package
03/27/2022
HP-100-02118
R0
Prospective Evaluation for Dose Monitoring
2/01/2018
JXF0CU9
Personnel Contamination Event Package
03/27/2022
HPIP 3.52
Airborne Radioactivity Surveys
HPIP 3.53
Counting of Air Sampling for Low Level, Long-Lived
Radioactive Alpha Particulate Contamination
Procedures
Alpha Monitoring
Air Sample 30-
050
Airborne Radioactivity Survey - Keyway Access Back-up
03/27/2022
Radiation
Surveys
Air Sample 30-
051
Airborne Radioactivity Survey - Keyway Bottom of Ladder
03/27/2022
Several AP Effluent Samples with Low Level Isotopes
07/11/2022
2016 AMR Liquid Dose Update
05/12/2022
Unit 1 Hotwell Dump with Tritium
10/25/2021
Air Sample Calibration Data Sticker Inaccuracy
2/17/2022
Low Volume Air Sampler #330746 had a Switch in Cord
Failure
07/12/2022
Corrective Action
Documents
Digital Display on DAVS Isokinetic Sampler Missing Digits
07/12/2022
DAVS Isokinetic Rotometer Challenging to Read
07/14/2022
Sampling Observations
07/14/2022
Isokinetic Flow Guidance
07/14/2022
Corrective Action
Documents
Resulting from
Inspection
Establish Basis for Administrative Limits
07/14/2025
Engineering
Changes
SJAE Exhaust Flow Curve
08/10/2020
Offsite Dose Calculation Manual
Gaseous Permit
Airborne Waste Discharge Permit
07/11/2022
CFR 72.44
2019 Annual Monitoring Report
04/27/2020
CFR 72.44
20 Annual Monitoring Report
04/29/2021
Miscellaneous
CFR 72.44
21 Annual Monitoring Report
04/04/2022
CAMP 032
Preparation of Batch Liquid and Gaseous Effluent Permits
Using RADEAS Software
HPIP 3.52.1
Radiological Sampling for Release Accountability
Procedures
Containment Venting and Purging
Self-Assessments
LICA 02394762-03
22 IP 71124.06 Radioactive Gaseous and Liquid Effluent
Treatment Pre-Inspection Assessment
06/14/2022
MSPI Margin Reports; Units 1 and 2
07/01/2021 -
06/30/2022
MSPI Derivation Reports; High Pressure Injection, Emergency
AC, Cooling Water; Unavailability Index;
Units 1 and 2
07/01/2021 -
06/30/2022
MSPI Derivation Reports; High Pressure Injection, Emergency
AC, Cooling Water; Unreliability Index;
Units 1 and 2
07/01/2021 -
06/30/2022
NP 5.2.16 -
Occupational
Exposure
Effectiveness
B; PI Data Calculation, Review and Approval
07/01/2021 -
03/31/2022
NP 5.2.16 - ODCM
Radioactive
Effluents
Effectiveness
B; PI Data Calculation, Review and Approval
07/01/2021 -
06/30/2022
NP 5.2.16 - RCS
Activity Fuel
Performance
NP 5.2.16 - RCS Activity Fuel Performance
07/01/2021 -
06/30/2022
71151
Miscellaneous
PBN-BFJR-18-054
MSPI Basis Document for PBNP
27