IR 05000387/2024004
| ML25036A052 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/05/2025 |
| From: | Sarah Elkhiamy Division of Operating Reactors |
| To: | Berryman B Susquehanna |
| References | |
| NPF-014, NPF-022 IR 2024004 | |
| Download: ML25036A052 (1) | |
Text
February 5, 2025
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 -
INTEGRATED INSPECTION REPORT 05000387/2024004 AND 05000388/2024004
Dear Brad Berryman:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station, Units 1 and 2. On January 30, 2025, the NRC inspectors discussed the results of this inspection with Edward Casulli, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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 (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Sarah H. Elkhiamy, Chief Projects Branch 4 Division of Operating Reactor Safety
Docket Nos. 05000387 and 05000388 License Nos. NPF-14 and NPF-22
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000387 and 05000388
License Numbers:
Report Numbers:
05000387/2024004 and 05000388/2024004
Enterprise Identifier: I-2024-004-0042
Licensee:
Susquehanna Nuclear, LLC
Facility:
Susquehanna Steam Electric Station, Units 1 and 2
Location:
769 Salem Blvd., Berwick PA
Inspection Dates:
October 1, 2024 to December 31, 2024
Inspectors:
J. England, Senior Resident Inspector
E. Brady, Resident Inspector
S. Flanagan, Resident Inspector
H. Anagnostopoulos, Senior Health Physicist
B. Dyke, Operations Engineer
S. Haney, Senior Project Engineer
S. McClay, Reactor Inspector
E. Miller, Senior Reactor Inspector
A. Turilin, Reactor Inspector
Approved By:
Sarah H. Elkhiamy, Chief
Projects Branch 4
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Susquehanna Steam Electric Station,
Units 1 and 2, 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
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period at rated thermal power. On December 13, 2024, the unit was down powered to 73 percent for a rod sequence exchange and returned to rated thermal power on December 14, 2024. The unit remained at or near rated thermal power for the remainder of the inspection period.
Unit 2 began the inspection period at rated thermal power. On November 22, 2024, the unit was down powered to 62 percent for a rod sequence exchange and returned to rated thermal power on November 23, 2024. On November 26, 2024, the unit was down powered to 74 percent for a high condensate conductivity and returned to rated thermal power on November 29, 2024. On December 18, 2024, the unit was down powered to 73 percent for a rod pattern adjustment and returned to rated thermal power on December 20, 2024. The unit remained at or near rated thermal power for 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 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in Inspection Manual Chapter 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, 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
Seasonal Extreme Weather (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures on December 20, 2024.
Impending Severe Weather (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 for a winter storm on December 20, 2024.
71111.04 - Equipment Alignment
Partial Walkdown (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 2 containment instrument gas system on November 13, 2024
- (2) Unit 1 reactor building component cooling water on December 10, 2024
71111.05 - Fire Protection
Fire Area Walkdown and Inspection (IP Section 03.01) (4 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) Unit Common 'E' diesel building, fire area 0-41E, on October 2, 2024
- (2) Units 1 and 2 reactor building refueling bay, fire area 0-8A, on October 4, 2024
- (3) Unit 2 turbine building, fire area 2-33B, on October 31, 2024
- (4) Unit Common low level radiation waste building, fire areas 0-65A, 0-65B, 0-65C, 0-65D, and 0-65E, on November 4, 2024
Fire Brigade Drill Performance (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the on-site fire brigade training and performance during an announced fire drill on November 23, 2024.
71111.06 - Flood Protection Measures
Flooding (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated internal flooding mitigation protections in the Unit Common engineered safeguard service water pumphouse on December 12, 2024.
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam completed on November 1, 2024, and the biennial written examinations completed on October 10, 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 Unit 2 control room during down power for a rod pattern adjustment on December 19, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed a Unit 1 simulator evaluation for licensed operator requalification that included an anticipated transient without scram on October 8, 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 remain capable of performing their intended function:
- (1) Units 1 and 2 residual heat removal service water pumps exceeded alert range on November 7, 2024
- (2) Unit 1 scram discharge volume 'A' drain valve (XV147F011) did not reposition during surveillance test on November 13, 2024
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management (IP Section 03.01) (5 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Unit 2 elevated risk during planned maintenance of high-pressure coolant injection steam line drain valve on October 2, 2024
- (2) Unit 2 elevated risk during planned maintenance on 'B' control rod drive pump on October 7, 2024
- (3) Unit Common planned maintenance extension on T20 transformer system during the week of October 15, 2024
- (4) Unit 1 elevated risk during planned maintenance on emergency service water (ESW)system during the week of October 25, 2024
- (5) Unit 2 elevated risk during planned maintenance on division 1 residual heat removal system during the week of November 4, 2024
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (8 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1 reactor water cleanup room fire alarm due to a steam leak on October 9, 2024
- (2) Unit 1 fast acting solenoid for main turbine trip valve failed during SO-193-001 on October 28, 2024
- (3) Unit Common 'A' emergency diesel generator (EDG) jacket water sight glass leak on November 14, 2024
- (4) Review of Units 1 and 2 standby liquid control system hoses preventive maintenance (PM) and material condition on November 19, 2024
- (5) Unit Common 'A' EDG failed during surveillance on November 25, 2024
- (7) Unit 1 Title 10 of the Code of Federal Regulations (10 CFR) Part 21 report due to CR 99 control blade depletion on December 18, 2024
- (8) Unit 1 standby liquid control tank level slowly rising on December 22, 2024
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
- (1) The inspectors evaluated a permanent modification for Unit 2 residual heat removal piping shielding TSR 03-2090.
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 (IP Section 03.01) (4 Samples)
- (1) Unit Common SO-024-014, Monthly Diesel Generator 'E' Operability Test, following Agastat relay replacement on October 9, 2024
- (2) Unit 2 hydraulic control unit scram valve limit switch replacement on November 7, 2024
- (3) Unit 1 SO-116-A03, Quarterly Residual Heat Removal Service Water (RHRSW)
System Flow Verification Division I, following pump lift on November 15, 2024
- (4) Unit Common 'D' EDG following linear reactor replacements on December 17, 2024
Surveillance Testing (IP Section 03.01) (4 Samples)
- (1) Unit Common OP-032-003, Exercising Security Diesel Generator Start on Simulated Loss of Offsite Power, on October 29, 2024
- (2) Unit 2 SO-252-006, High-Pressure Coolant Injection Comprehensive Flow Verification, on December 11, 2024
- (3) Unit Common SO-030-A01, Monthly Control Room Emergency Outside Air Supply System 'A' Operability Test, on December 26, 2024
- (4) Unit 2 SO-260-001, Quarterly LOCA Test of Drywell Area Unit Coolers/Fans, on December 30, 2024
Inservice Testing (IST) (IP Section 03.01) (1 Sample)
- (1) Unit 2 SO-151-A05, Core Spray Comprehensive Flow Verification Division 1, on October 3, 2024
71114.06 - Drill Evaluation
Additional Drill and/or Training Evolution (1 Sample)
- (1) The inspectors evaluated a simulator scenario that included a declaration of an alert due to a manual scram when subsequent actions were not successful in shutting down the reactor at Unit 1 on October 8,
RADIATION SAFETY
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (IP Section 03.01) (4 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
- (1) Liquid radwaste effluent radiation monitor
- (2) Liquid radwaste effluent automatic isolation valve HV-06432A1
- (3) Unit 1 reactor building high, medium, and low range radiation monitors
- (4) Auxiliary boiler system and associated release point
Sampling and Analysis (IP Section 03.02) (4 Samples)
The inspectors evaluated the following effluent samples, sampling processes, and compensatory samples:
- (1) Routine monthly grab sampling and analysis of tritium and noble gas from the Unit 2 turbine building vented effluence radiation monitoring system (VERMS)
- (2) Routine weekly particulate and iodine sampling and analysis from the Unit 1 turbine building VERMS
- (3) Routine weekly sampling from the standby gas treatment system VERMS
- (4) Routine process sampling of the 'E' and 'F' liquid radwaste collection tank
Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
- (1) Calculation for abnormal release from the 'B' auxiliary boiler on April 19, 2023 (tritium, see condition report (CR)-2023-07376)
- (2) Calculation for surveillance SC-069-001(2024001) liquid radwaste release from a condensate storage tank on January 4, 2024
Abnormal Discharges (IP Section 03.04) (2 Samples)
The inspectors evaluated the following abnormal discharges:
- (1) Abnormal release from the 'B' auxiliary boiler on April 19, 2023 (tritium, see CR-2023-07376)
- (2) Abnormal release from the 'B' auxiliary boiler on September 8, 2023 (tritium)
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, 2023, through June 30, 2024
- (2) Unit 2 July 1, 2023, through June 30, 2024
MS07: High-Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 July 1, 2023, through June 30, 2024
- (2) Unit 2 July 1, 2023, through June 30, 2024
MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)
- (1) Unit 1 July 1, 2023, through June 30, 2024
- (2) Unit 2 July 1, 2023, through June 30, 2024
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 October 1, 2023, through September 30, 2024
- (2) Unit 2 October 1, 2023, through September 30, 2024
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 October 1, 2023, through September 30, 2024
- (2) Unit 2 October 1, 2023, through September 30, 2024
OR01: Occupational Exposure Control Effectiveness (IP Section 02.15) (1 Sample)
- (1) September 15, 2023, through September 15, 2024 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual
Radiological Effluent Occurrences (IP Section 02.16) (1 Sample)
- (1) September 15, 2023, through September 15, 2024
===71152A - Annual Follow-up of 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) Unit Common ESW piping degradation
- (2) Unit 1 4 kilovolt (kV) 'D' core spray pump breaker charging motor failure
- (3) Unit Common motor operated valve (MOV) Long Life grease C/N927200 did not meet dedication requirements (CR-2024-02372)
- (4) Failure to adequately control transient combustibles in Units 1 and 2 turbine buildings
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees corrective action program that might be indicative of a more significant safety issue and identified a potential trend in NRC-identified issues related to PM task detail and completion.
INSPECTION RESULTS
Minor Violation 71152A Failure to Perform Engineering Change Evaluation
Minor Violation: In 2013, AREVA recommended and performed changes to the Cutler Hammer Type DHP-VR 4.16kV breakers that they provided to the licensee. However, the inspectors identified the licensee did not take subsequent actions required by their procedures. Specifically, the licensee failed to perform an engineering change evaluation in accordance with MFP-QA-1220, Engineering Change Process Handbook, to ensure that the design changes were acceptable for Susquehanna design requirements.
The licensee documented the issue in CR-2024-14984 and initiated actions to perform an evaluation to validate that the changes to the DHP-VR 4.16kV breakers met the design requirements.
Screening: The inspectors determined the performance deficiency was minor because it did not adversely affect the Mitigating Systems cornerstone objective. Specifically, the failure to evaluate changes to the design of Cutler Hammer Type DHP-VR 4.16kV circuit breakers had little or no safety impact, as the subsequently completed engineering change evaluation determined that the changes would meet design requirements.
Enforcement:
10 CFR Part 50, Appendix B, Criterion III, requires that measures shall be established to assure that design changes, including field changes, shall be subject to design control measures commensurate with those applied to the original design and be approved by the organization that performed the original design unless the applicant designates another responsible organization.
Contrary to this requirement, the licensee did not subject vendor design changes to design control measures commensurate with those applied to the original design. Specifically, the licensee failed to perform an engineering change evaluation in accordance with MFP-QA-1220, Engineering Change Process Handbook, to ensure that the design changes were acceptable for Susquehanna design requirements.
The licensee has taken actions to restore compliance by performing the missed engineering change evaluation. This failure to comply with 10 CFR Part 50, Appendix B, Criterion III, Design Control, constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Observation: Emergency Service Water Piping Degradation 71152A The inspectors reviewed the licensee's evaluations and corrective actions associated with the ESW piping wall thinning and/or pinhole leaks to standards in their corrective action program procedures and American Society of Mechanical Engineers Code Case N-513 which was approved for use. On a sampling basis, the inspectors verified that the licensee measured piping wall thickness to ensure structural integrity of the pipe and performed additional exams at other susceptible locations as required by the code case. The inspectors verified corrective actions were completed to replace the pipe or continue monitoring. The inspectors did not identify any findings or violations of more than minor significance.
Observation: Motor Operated Valve Long Life Grease Did Not Meet Acceptance Criteria 71152A The inspectors reviewed the licensees evaluation and corrective actions to address MOV Long Life grease that did not meet acceptance criteria during commercial grade dedication as documented in CR-2024-20372. The grease was found at the minimum specification for weld point. The inspectors found the licensee credited their MOV monitoring program to identify impacts. The program included grease sampling and analysis every 2 years on active safety-related MOVs. The inspectors found that the licensee also contacted the grease manufacturer to affirm product composition and revised their dedication process to include the acceptance criteria range. The inspectors further independently reviewed a sample of MOV test results and did not identify performance issues since grease application. The inspectors did not identify any findings or violations of more than minor significance.
Observation: Corrective Actions for Failure to Adequately Control Transient Combustibles in Units 1 and 2 Turbine Building 71152A The inspectors reviewed CRs that documented two separate occurrences in which combustible loading permit limits were exceeded. The permits allowed for a specific number of lube oil barrels to be stored in the Units 1 and 2 lube oil conditioner rooms. For each of these instances, the licensee immediately took action to reduce the amount of combustibles located within the rooms in order to comply with their long standing combustible loading permits. The inspectors noted that the licensee has developed an action request to add additional signage in each room to help make work groups aware of the limitations for storing transient combustibles in the area. The inspectors did not identify any findings or violations of more than minor significance.
Observation: Corrective Actions for 4 Kilovolt Breaker Charging Motor Failure 71152A The inspectors reviewed CR-2024-00769 which documented a 4kV breaker removed from 1A20405 that failed as found testing. On January 9, 2024, the licensee identified an issue with the charging motor associated with the Unit 1 D core spray pump breaker during a system outage window where the charging motor would function, but it was unable to properly charge the closing springs. Further investigation identified that a gear, noted as the ratchet wheel, was not making sufficient contact with its counterpart which resulted in the charging motor being unable to perform its intended function. The licensee replaced the breaker with a spare breaker and then shipped the defective breaker to the vendor (Framatome/AREVA) for overhaul and refurbishment.
The inspectors reviewed the CR, actions created in response to the CR, the failure analysis, work orders associated with the failure analysis, and conducted interviews with site Engineering staff. The inspectors noted that the licensee has a replacement strategy in place to replace all the Cutler Hammer Type DHP-VR 4.16kV circuit breakers which will include newer style ratchet wheels that will have improved engagement. The inspectors also noted that the licensee enhanced their maintenance procedures to inspect the ratchet wheels periodically. The inspectors did not identify any findings or violations of more than minor significance.
Observation: Semiannual Trend 71152S The inspectors' semiannual trend review performed in accordance with IP 71152, Problem Identification and Resolution, noted a trend in NRC-identified issues related to PM task detail and completion. The inspectors identified the following examples which illustrate vulnerabilities.
The inspectors identified that the Unit 1 containment instrument gas system nitrogen cylinders exceeded their hydrostatic testing requirement. The containment instrument gas nitrogen serves as the motive force to operate the automatic depressurization valves system in the event of a station blackout. Hydrostatic testing is required every 10 years. The PM task to replace the cylinders was scheduled for completion in August 2023. CR-2023-12374 was generated when the first set of replacement cylinders did not meet the purchasing specification. The purchasing specification requires that new cylinders must complete a hydrostatic test within 6 months of delivery. The bottles received in 2023 had been tested more than 6 months earlier. This CR was closed without replacement nitrogen cylinders being installed. A second replacement was attempted in March 2024, and the second set of replacement cylinders had dimensional differences from the installed cylinders requiring an engineering change to be implemented for installation. The station identified that the same condition was present in Unit 2. The station reduced the PM frequency to 9 years ensuring that the cylinders would be replaced prior to exceeding hydrostatic testing frequency. The inspectors noted the installed gas cylinders did not exhibit a degrading trend in gas pressure.
This issue was captured in CR-2024-16145.
The inspectors identified that there were no PM tasks to verify the condition of staged hoses for the standby liquid control system. These hoses are used to inject a boron solution into the core using the steam driven reactor core isolation cooling pump during a station blackout to add negative reactivity to the core. PM Task S4003-51 requires a quarterly verification that the hose reel is available for deployment and the exposed hose is acceptable. These hoses are approximately 300 feet long and are wound around their holders multiple times. The visible, exposed hose is a fraction of the full hose. The hoses had last been unrolled in the early 2000s. The hoses for both units were subsequently unrolled, pressure tested, and found to be acceptable. The station is determining the appropriate long-term testing or replacement frequency and captured the issue in CR-2024-12099.
The inspectors identified permanent lead shielding blankets were inadequately secured to piping to the radiation waste system piping. The inspectors identified six blankets without adequate banding in November 2024. The suppression pool filter pump, suppression pool filter pump inboard, and outboard isolation valves were below three of the inadequately secured shielding blankets. These components could have been damaged if the shielding became dislodged during a seismic event. These blankets are verified annually per PM task L0000-21. This task requires compliance to be verified against NDAP-QA-0404, Shielding Installation and Removal. NDAP-QA-0404, Attachment E, Approved Banding Mechanisms for Direct Shielding, contains the required approved banding. This PM task was completed in September 2024. This issue was captured in CR-2024-15905 and the banding was corrected.
The PM task was updated to include banding verification.
These examples share the common theme of PM task implementation. The examples cover a wide variety of PM issues including scheduling, implementation, and scope. The inspectors did not identify any findings or violations of more than minor significance.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 29, 2024, the inspectors presented the 4kV breaker charging motors inspection results to Chris Johnson, Design Engineering Manager, and other members of the licensee staff.
- On October 31, 2024, the inspectors presented the radioactive gaseous and liquid effluent treatment inspection results to Derek Jones, Plant Manager, and other members of the licensee staff.
- On November 7, 2024, the inspectors presented the MOV Long Life grease inspection results to Katie Brown, Nuclear Regulatory Affairs Supervisor, and other members of the licensee staff.
- On November 12, 2024, the inspectors presented the ESW pinhole leaks inspection results to Katie Brown, Nuclear Regulatory Affairs Supervisor, and other members of the licensee staff.
- On November 21, 2024, the inspectors presented the turbine building transient combustible loading inspection results to Lonnie Crawford, Assistant Operations Manager, and other members of the licensee staff.
- On January 30, 2025, the inspectors presented the integrated inspection results to Edward Casulli, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Plant
Status
Corrective Action
Documents
Resulting from
Inspection
CR-2024-15748
CR-2024-17622
Corrective Action
Documents
CR-2054-13002
Procedures
NDAP-00-1913
Seasonal Preparedness
Revision 18
Work Orders
Calculations
EC-025-0010
Capacity of Instrument Gas Bottles
Revision 2
Corrective Action
Documents
Resulting from
Inspection
CR-2024-16145
CR-2024-16230
CR-2024-17200
Drawings
M-113
Susquehanna S.E.S. Unit 1 P&ID Reactor Building Closed
Cooling Water
Revision 53
M-2126
Sheet 1 Susquehanna S.E.S. Unit 2 P&ID Containment
Instrument Gas
Revision 35
M-2126
Sheet 2 Susquehanna S.E.S. Unit 2 P&ID Containment
Instrument Gas
Revision 23
Miscellaneous
CL-114-0012
Unit 1 RBCCW
Revision 17
CL-225-0012
Unit 2 Containment Instrument Gas
Revision 17
M8477-51
Replace Unit 2 CIG Header Bottles 2T212A
M8477-52
Replace Unit 2 CIG Header Bottles 2T213A
Work Orders
RTPM 1763796
RTPM 2603620
Corrective Action
Documents
Resulting from
Inspection
AR-2024-15005
CR-2024-15751
CR-2024-16104
Fire Plans
FP-1-E-DG-656
Prefire Plan Unit 1 E. Diesel EL. 656-6
Revision 0
FP-1-E-DG-675
Prefire Plan Unit 1 E. Diesel EL. 675-6
Revision 0
FP-1-E-DG-708
Prefire Plan Unit 1 E. Diesel EL. 708-0
Revision 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
FP-1-RB-818
Susquehanna Prefire Plan
Revision 0
FP-2-RB-818
Susquehanna Prefire Plan
Revision 0
FP-2-TB-699
Prefire Plan Unit 2 699 EL. 699'-0" Isophase Area
Revision 0
Procedures
Susquehanna Fire Brigade Training Program
Revision 5
Low Level Radwaste Building Control and Electrical
Equipment Room, Open East Area Truck Bay, Fire Zones
0-65A, 0-65B, 0-65C Elevation 726'8"
Revision 4
Low Level Radwaste Building East Vault, West Vault, Fire
Zones 0-65D, 0-65E Elevation 726'8"
Revision 4
Calculations
EC-054-0535
ESW Flow through a Moderate Energy Leakage Crack
Revision 1
Engineering
Evaluations
DBD010
Design Basis Document for HELB/MELC/Internal Flooding
Revision 3
Procedures
NDAP-QA-0409
Door, Floor Plug, and Hatch Control
Revision 24
Work Orders
RTPM 1992666
71111.11Q Procedures
OP-AD-338
Reactivity Manipulations Standards and Communication
Requirements
Revision 38
Corrective Action
Documents
CR-2022-16158
CR-2024-10465
CR-2024-14267
CR-2024-14304
CR-2024-15898
Work Orders
PCWO 2441376-1
PCWO 276395-0
Corrective Action
Documents
Resulting from
Inspection
CR 2024-14271
CR-2024-15240
CR-2024-15256
CR-2024-15281
CR-2024-15766
CR-2024-15767
CR-2024-15768
Miscellaneous
03-001-0A105
Tie Bus
10/14/2024
2-001-2
10/02/2024
55-001-2A
CRD Pump
10/07/2024
Procedures
NDAP-QA-0340
Protected Equipment Program
Revision 46
Calculations
EC-023-0005
Diesel Fuel Oil Storage Tanks
Revision 0
EC-024-0503
Diesel Generator Load Calculation
Revision 36
EC-024-1033
Establish a Maximum Allowable Jacket Leakage Rate for
Diesel Generators A-D
Revision 0
Corrective Action
Documents
AR-2024-07790
AR-2024-11045
CR-2024-07335
CR-2024-07395
CR-2024-13026
CR-2024-13709
CR-2024-14601
CR-2024-14610
CR-2024-14840
CR-2024-14983
CR-2024-15400
CR-2024-16564
CR-2024-16582
CR-2024-17173
CR-2024-17658
RTSV 2724861
RTSV 2763683
Corrective Action
Documents
Resulting from
Inspection
CR-2024-14660
CR-2024-14675
Drawings
FF10600
Sheet 1001 Turbine Control Diagram
Revision 16
M-148 SBLC
Storage Tank
Revision 7
M30-124
Sheet 13C DG Control Schematic Staring Sequence Control
Panel 0C521D
Revision 6
Miscellaneous
PM task S4003-51
EC-Fuel-1971 Unit 1 Cycle 24 Cycle Step Out
Revision 0
UFSAR Section 9.5.5/9.5.4
Revision 71
Fuel Oil Systems for Standby Diesel Generators
Revision 1
Procedures
DBD 009
Design Basis Document for ESW, RHRSW, and Ultimate
Heat Sink
Revision 4
DBD013
Design Basis Document for Diesel Generators & Auxiliaries
Revision 5
EAL Classification Basis
Revision 22
M-144 Unit 1
P&ID Reactor Water Clean-Up, Sheet 2
Revision 20
SO-100-007
Daily Surveillance Operating Log
Revision 92
Work Orders
WO 2761835-0
Corrective Action
Documents
Resulting from
Inspection
AR-2024-15762
CR-2024-11838
CR-2024-11889
CR-2024-11891
CR-2024-15905
Engineering
Changes
EC-SHLD-1001
Seismic Qualification of Shadow Shielding for Use Inside
Containment During Conditions 4 to 5
Revision 0
Procedures
NDAP-QA-0404
Shielding Installation and Removal
Revision 3
TSR 03-2090
Shadow Shielding of U2 Common RHR Shutdown Cooling
Line
Revision 1
Corrective Action
Documents
CR-2024-15541
CR-2024-17391
CR-2024-17393
CR-2024-17417
CR-2024-17524
Procedures
OP-032-003
Security 480 VAC System
Revision 30
SO-024-001D
Monthly Diesel Generator 'D' Operability Test
Revision 29
SO-024-014
Monthly Diesel Generator 'E' Operability Test
Revision 54
SO-030-A01
Monthly Control Room Emergency Outside Air Supply
System 'A' Operability Test
Revision 6
SO-116-A03
Quarterly Residual Heat Removal Service Water (RHRSW)
System Flow Verification Division I
Revision 20
SO-151-A05
Core Spray Comprehensive Flow Verification Division 1
Revision 15
SO-252-006
High-Pressure Coolant Injection Comprehensive Flow
Verification
Revision 28
SO-260-001
Quarterly LOCA Test of Drywell Area Unit Coolers/Fans
Revision 20
Work Orders
PCWO 2441376-1
PCWO 2614999-0
REWL 2745575
RTSV 2587915
RTSV 2737393
RTSV 2755917
RTSV 2760446
RTSV 2771991
71151
Miscellaneous
DI-2022-16669
DI-2022-16670
DI-2022-16671
DI-2022-16672
DI-2022-16673
DI-2023-17653
DI-2023-17656
DI-2023-17657
DI-2023-17659
DI-2023-17660
Procedures
PL-NF-06-002
SSES Mitigating System Performance Index Basis
Document
Revision 11
Corrective Action
Documents
AR-2024-02696
AR-2024-14775
CR-2014-34342
CR-2023-05773
CR-2023-10546
CR-2023-16982
CR-2024-00769
CR-2024-02372
CR-2024-03136
CR-2024-03552
CR-2024-07832
CR-2024-09068
CR-2024-09544
CR-2024-10224
CR-2024-10231
CR-2024-10500
CR-2024-11436
CR-2024-12630
CR-2024-14115
Corrective Action
Documents
Resulting from
Inspection
CR-2024-14984
Engineering
Evaluations
ACT-06-CR-2020-
00954
Evaluation for CR-2020-00954 - Oil drum storage exceeds
the fire hazard analysis and three-hour fire barrier in U1/U2
TB 656' El
Revision 1
Miscellaneous
Operations Directive 20-02
07/01/2020
51-9193861-001
Medium Voltage Breaker Evaluation for Bruce, DC Cook,
and Susquehanna
NC-2019
ASME Code Case N-513-5 Evaluation Criteria for
Temporary Acceptance of Flaws in Moderate Energy Class 2
or 3 Piping and Gate ValvesSection XI, Division 1
Revision 5
ASTM Standard
D2596
Standard Test Method for Measurement of Extreme-
Pressure Properties of Lubricating Grease (Four-Ball
Method)
20
LT-0199
Combustible Material Permit for fire zone I-31E
Revision 22
LT-0200
Combustible Material Permit for Fire Zone 2-31E
Revision 16
Procedures
LS-120
Issue Identification and Screening Process
Revision 15
MPF-QA-1220
Engineering Change Process Handbook
Revision 18
NDAP-QA-0440
Control of Transient Combustible/Hazardous Materials
Revision 29
PM M1338-81
Perform MOV Inspections, Grease Sampling, Stem Lube -
Required By 89-10 Program
Work Orders
WO 2082046
WO 2217515
WO 2471653
WO 2632833-1
WO 2682230
WO 2740459