ML25041A282
| ML25041A282 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/11/2025 |
| From: | Jason Schussler Division of Operating Reactors |
| To: | Rhoades D Constellation Energy Generation |
| References | |
| IR 2024004 | |
| Download: ML25041A282 (1) | |
Text
February 11, 2025 David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer (CNO)
Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - INTEGRATED INSPECTION REPORT 05000333/2024004
Dear David Rhoades:
On December 31, 2024, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at James A. FitzPatrick Nuclear Power Plant. On February 6, 2025, the NRC inspectors discussed the results of this inspection with Alex Sterio, 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 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Jason E. Schussler, Chief Projects Branch 1 Division of Operating Reactor Safety Docket No. 05000333 License No. DPR-59
Enclosure:
As stated cc w/ encl: Distribution via LISTSERV JASON SCHUSSLER Digitally signed by JASON SCHUSSLER Date: 2025.02.11 13:53:31 -05'00'
SUNSI Review x
Non-Sensitive Sensitive x
Publicly Available Non-Publicly Available OFFICE RI/DORS RI/DORS RI/DORS NAME EMiller DBeacon JShussler DATE 2/7/2025 2/10/2025 2/10/2025
Enclosure U.S. NUCLEAR REGULATORY COMMISSION Inspection Report Docket Number:
05000333 License Number:
DPR-59 Report Number:
05000333/2024004 Enterprise Identifier: I-2024-004-0032 Licensee:
Constellation Energy Generation, LLC Facility:
James A. FitzPatrick Nuclear Power Plant Location:
Oswego, NY Inspection Dates:
October 1, 2024 to December 31, 2024 Inspectors:
E. Miller, Senior Resident Inspector V. Fisher, Resident Inspector H. Anagnostopoulos, Senior Health Physicist D. Beacon, Senior Project Engineer P. Cataldo, Senior Reactor Inspector B. Edwards, Health Physicist M. Hardgrove, Senior Project Engineer D. McHugh, Reactor Inspector N. Mentzer, Senior Project Engineer A. Turilin, Reactor Inspector Approved By:
Jason E. Schussler, Chief Projects Branch 1 Division of Operating Reactor Safety
2
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at James A. FitzPatrick Nuclear Power 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 No findings or violations of more than minor significance were identified.
Additional Tracking Items Type Issue Number Title Report Section Status LER 05000333/2023-004-00 Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG A Subsystem 71153 Closed LER 05000333/2024-002-00 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 71153 Closed LER 05000333/2024-002-01 Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation 71153 Closed
3 PLANT STATUS FitzPatrick began the inspection period at rated thermal power. On December 6, 2024, operators reduced reactor power to 73 percent to perform a control rod pattern adjustment and turbine valve testing. The unit was returned to rated thermal power the next day and operated 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 (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY 71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)
Control room emergency ventilation air system on October 7, 2024 (2)
Standby gas treatment system on November 4, 2024 (3)
'A' low pressure coolant injection motor operated valve independent power supply system on November 4, 2024 71111.05 - Fire Protection Fire Area Walkdown and Inspection Sample (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)
Motor generator set room 300', fire area/zone IA/MG-1 on October 7, 2024 (2)
Emergency diesel generator spaces north 272', fire area/zones VI/EG-3, EG-4, and EG-6 on October 7, 2024 (3)
Crescent area west 227' and 242', fire area/zone XVIII/RB-1W on October 8, 2024 (4)
Standby gas filter room 272', fire area/zone XX/SG-1 on October 8, 2024
4 Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
(1)
The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill on December 17, 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 operations personnel during the 'B' and 'D' emergency diesel generator 8-hour full load surveillance test on November 4, 2024, and during a control rod pattern adjustment and power reduction on December 6 and 7, 2024.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed a simulator scenario evaluation that included a reactor water cleanup leak, loss of 10500 bus, main condenser air leak, and torus leak on October 29, 2024.
71111.12 - Maintenance Effectiveness Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended functions:
(1)
Reactor protection system motor generator sets on November 20, 2024 (2)
Reactor building exhaust effluent radiation monitor, 17RM-452A, on November 26, 2024 71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)
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)
Elevated risk during 'A' emergency service water (ESW) pipe replacement following a through-wall leak on December 12, 2024 71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
5 (1) 13MOV-16, reactor core isolation cooling steam supply isolation valve following refuel outage stem coefficient of friction and motor voltage evaluation on November 6, 2024 (2) 13MOV-16, following a steam leak after a seal weld repair on November 13, 2024 (3)
ESW supply pipe through-wall leak on 66UC-22C, west crescent area unit cooler on November 19, 2024 (4) 71DSC-10011, 115 kilovolt (KV) manual disconnect switch following broken gear on November 22, 2024 (5)
Rod block monitor on December 9, 2024 71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
(2 Samples)
The inspectors evaluated the following temporary or permanent modifications:
(1)
Permanent Modification: Compressed Air System Hardening: Installation of Air Dryer Bypass Line and 39BAS-2 Internals Removal on October 25, 2024 (2)
Temporary Modification: 13MOV-16(OP) Reactor Core Isolation Cooling Steam Supply Outboard Containment Isolation Valve Weld Temporary Repair on November 6, 2024 71111.24 - Testing and Maintenance of Equipment Important to Risk The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (7 Samples)
(1)
Main steam safety relief valves 'C,' 'E,' 'K,' and 'L' following replacement on October 2, 2024 (2)
Bypass instrument air dryer following excessive blowdown on October 22, 2024 (3)
Service air isolation valve 39FCV-110 following failure to close on October 22, 2024 (4) 29AOV-86B and 29AOV-86C main steam isolation valve following actuator replacement on October 28, 2024 (5)
Reactor pressure vessel hydrostatic test following planned refuel and maintenance outage on November 4, 2024 (6) 13MOV-16 reactor core isolation cooling steam supply isolation valve following seal weld temporary leak repair on November 7, 2024 (7)
ESW following 'A' pipe replacement due to a leak on December 17, 2024 Surveillance Testing (IP Section 03.01) (4 Samples)
(1)
ST-2F, Low Pressure Coolant Injection Simulated Auto Actuation Test, on October 7, 2024 (2)
ST-6M, Standby Liquid Control Recirculation Injection Test, on October 7, 2024 (3)
ST-2HB, Low Pressure Coolant Injection Logic System 'B' Functional Test, on October 15, 2024 (4)
ST-9CB, 'B' Division Loss of Offsite Power Test and Loss of Coolant Accident Test, on November 6, 2024
6 Inservice Testing (IST) (IP Section 03.01) (1 Sample)
(1)
ST-24J, Reactor Core Isolation Cooling Flow Rate and Inservice Test (IST), on December 18, 2024 Containment Isolation Valve (CIV) Testing (IP Section 03.01) (1 Sample)
(1)
ST-39B, Main Steam Isolation Valve Local Leak Rate Test, on October 2, 2024 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)
Main stack exhaust radiation monitor 17RM-50A (2)
Reactor building perimeter drain sump and sampling system (west outfall)
(3)
Turbine building ventilation exhaust radiation monitor 17RM-432 (4)
Liquid radwaste radiation monitor 17RM-350 Sampling and Analysis (IP Section 03.02) (4 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
(1)
Collection and analysis of the weekly particulate sample for the refuel floor exhaust pathway (2)
Collection and analysis of the weekly iodine sample for the refuel floor exhaust pathway (3)
Collection and analysis of the weekly liquid sample from the reactor building curtain drains (4)
Collection of the weekly particulate and iodine sample from the main stack exhaust Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
(1)
Permit number G-20240402-13542-C, stack particulate/iodine, continuous release (2)
Permit number L-20240630-525-B, SW cable tunnel sump, batch release OTHER ACTIVITIES - BASELINE 71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
(1)
For the period of October 1, 2023 through September 30, 2024
7 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)
For the period of October 1, 2023 through September 30, 2024 71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
(1)
Issue Report (IR) 04803804 - Automatic Voltage Regulator (AVR) Response Following Reactor Scram (2)
IRs 04669409 and 04550060 - 4160-Volt Circuit Breaker Corrective Actions 71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02) (1 Sample)
(1)
The inspectors reviewed the FitzPatrick corrective action program to identify potential trends that might be indicative of a more significant safety issue.
71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02) (2 Samples)
The inspectors evaluated the following licensees event reporting determinations to ensure it complied with reporting requirements.
(1)
Licensee Event Reports (LERs) 05000333/2024-002-00 and LER 05000333/2024-002-01, Reactor Protection System Electric Power Monitoring System Trip Caused Primary Containment Isolation (ADAMS Accession Nos.
ML24327A097 and ML24327A097, respectively). The inspectors determined that the cause of the conditions described in these LERs were not reasonably within the licensee's ability to foresee and correct, and therefore were not reasonably preventable. No performance deficiency nor violation of NRC requirements was identified. These LERs are Closed.
(2)
LER 05000333/2023-004-00, Misaligned Spacer Prevented Tie Breaker Closing Coil Armature Operation on a Magne-Blast for EDG A Subsystem (ML23335A068). The inspectors reviewed the updated LER submittals. The inspection conclusions associated with this LER are documented in the Inspection Results of Inspection Report 05000333/2023002 (ML23219A114). This LER is Closed.
8 Personnel Performance (IP Section 03.03) (2 Samples)
(1)
The inspectors evaluated the degrading instrument air header pressure following excessive purge flow on the bypass dryer system, and the licensee's performance, on October 22, 2024.
(2)
The inspectors evaluated the 'A' reactor water recirculation pump speed decrease, and the licensee's performance, on November 27, 2024.
Reporting (IP Section 03.05) (2 Samples)
(1)
Condensate storage tank valve pit monitoring well water sample results on October 29, 2024 (IR 04813216). The event was reviewed to determine if reporting requirements were met and should have been reported by the licensee.
(2)
Thermal Overload Relay Interim Part 21 (EN 57437) on November 22, 2024. The event was reviewed to determine if reporting requirements were met and should have been reported by the licensee.
INSPECTION RESULTS Minor Performance Deficiency 71152A IRs 04669409 and 04550060 - 4160 Volt Circuit Breaker Corrective Actions The inspectors performed a review of corrective actions associated with 4 KV breaker failures that were documented in NRC Inspection Report 05000333/2023002 (ML23219A114).
FitzPatrick staff completed a level 2 cause evaluation, a corrective action program evaluation (CAPE), in IR 04550060. The inspectors reviewed the results of the CAPE, which determined the station was not implementing preventive maintenance consistent with the Constellation fleet preventive maintenance template, and that maintenance procedures did not contain adequate instructions to perform the maintenance for a 4 KV breaker cubicle. The stations review of internal operating experience also determined there were several missed opportunities to identify the inadequacies with breaker cubicle alignment procedures dating back to cause evaluations performed in 2012 (CR-JAF-2012-06868) and 2013 (CR-JAF-2013-02237).
The inspectors identified that three action items (ACIT) to conduct procedure revisions for maintenance procedures MP-054.01, 4.16 KV Magne-Blast Breaker, and MP-054.02, 4.16 KV Bus and Metal-Clad Switchgear Maintenance, were not completed after the action items were closed in the system. The inspectors found the following ACITs were not completed after they were closed: 0455060-22, 0455060-28 and 0455060-32. The station captured the failure to complete the ACITs in IRs 04824708, 04828294 and 04830431.
The inspectors also identified the breaker cubicle for 71-10650, 4KV breaker feed to 10P-3C(M) residual heat removal pump C motor did not receive the corrective maintenance that was performed on the other safety-related 4 KV circuit breakers. This issue was entered into the corrective action program as IR 04830101.
The inspectors determined that the stations failure to properly update and implement effective breaker cubicle maintenance procedures was a performance deficiency. Specifically, by closing the ACITs without issuing properly updated procedures the station remained vulnerable to additional 4 KV breaker failures. The inspectors determined this was also a
9 violation of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings. Title 10 CFR Part 50, Appendix B, Criterion V requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings. Instructions, procedures, or drawings shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
Contrary to this requirement, procedures used at FitzPatrick to service and inspect safety-related 4 KV breaker cubicles did not include appropriate quantitative or qualitative acceptance criteria to ensure that the breakers and breaker cubicles were properly aligned to prevent interference during breaker operation. As discussed earlier, the station generated IRs 04824708, 04828294, and 04830431 to ensure the breaker maintenance procedures are updated and properly issued. This failure to comply with 10 CFR Part 50, Appendix B, Criterion V constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Screening: The inspectors determined the performance deficiency was minor. Specifically, Constellation has not experienced an additional failure since performing the corrective actions in the CAPE. Also, many of the breakers are cycled periodically during surveillance testing and no new failures have been identified. In addition, Constellation has performed corrective maintenance on all safety-related 4 KV breaker cubicles in response to the CAPE. The prior failures were evaluated by inspectors and dispositioned in NRC Inspection Report 05000333/2023002.
Observation: Automatic Voltage Regulator Response Following Reactor Scram on September 23, 2024 71152A In October of 2020 a fleet modification was implemented at FitzPatrick to install a new AVR for the main generator. The modification was developed by the fleet for all Constellation stations. The testing for the AVR consisted of a factory acceptance test (FAT) and a site acceptance test once installed. The FAT was performed with the setting for the minimum field current limiter enabled. During post-modification installation testing, the station performed testing to ensure settings were correct that would protect the main generator. Following satisfactory testing and incorporation of fleet operating experience, the minimum field current limiter was disabled.
The inspectors conducted a review of available information and found that although some information was captured in accordance with IP-ENG-001, Standard Design Process, FitzPatrick staff did not include specific detail to understand the disabling of the minimum field current limiter. The inspectors found through interview that it was understood through post-modification testing, additional data and fleet operating experience that additional under-excitation limiters would provide redundant protection.
The inspectors concluded that although a scram may have occurred due to the minimum field current limiter being disabled, this was not reasonable to foresee and prevent because the grid conditions were beyond any previous analysis performed. Constellation is continuing to study the grid conditions experienced and plans to make any necessary changes to their main generator protection system.
10 Minor Performance Deficiency 71152S Semi-Annual Trend The inspectors evaluated a sample of issues and events that occurred over the third and fourth quarters of 2024. The evaluation did not reveal any new trends that could indicate a more significant safety issue. The inspectors determined that, in most cases, the issues were appropriately evaluated by Constellation staff for potential trends at a low threshold and resolved within the scope of the corrective action program.
The inspectors identified a trend associated with leaks from the ESW system pipes and heat exchangers. Since September of 2024, three through-wall ESW pipe leaks and two-unit cooler tube leaks occurred. Three of the five leaks were identified by the NRC inspectors. The station documented the trend in IR 04823124.
The NRC inspectors also identified a trend associated with ineffective corrective actions that have resulted in repeat failures of equipment. Equipment issues included the A reactor building exhaust radiation monitor sample pump failure, an instrument air alternate dryer failure, A reactor water recirculation motor generator set unexpected minor changes in speed, and failures of the B reactor protection system motor generator set power supply.
Constellation generated IRs to document the trends in IRs 04823091, 04819213, and 04813835.
Screening: The inspectors determined the performance deficiency was minor. The inspectors determined that Constellations failure to address the leak trend with a trend IR was minor because each issue was entered individually into the corrective action program and addressed. In addition, the inspector reviewed each equipment issue to determine if the issue was more than minor. The inspectors determined that each issue did not impact safe plant operation or affect the safety function of the associated system. Based on the overall results of the semi-annual trend review, the inspectors determined that Constellation had generally identified adverse trends before they could become more significant safety problems. The inspectors independently evaluated the deficiencies noted above for significance in accordance with the guidance in IMC 0612, Appendix B, Issue Screening, and Appendix E, Examples of Minor Issues, and determined them to be minor.
EXIT MEETINGS AND DEBRIEFS The inspectors verified no proprietary information was retained or documented in this report.
On February 6, 2025, the inspectors presented the integrated inspection results to Alex Sterio, Site Vice President, and other members of the licensee staff.
On October 10, 2024, the inspectors presented the radiation protection inspection results to Alex Sterio, Site Vice President, and other members of the licensee staff.
11 DOCUMENTS REVIEWED Inspection Procedure Type Designation Description or Title Revision or Date 71111.04 Drawings FB-45A Flow Diagram Control and Relay Rooms Heating and Ventilation System 70 42 FM-1Y 600V One Line Diag-SH. 14 71mcc-332, 342, 155 and 165 43 FM-48A Flow Diagram Standby Gas Treatment System 01-125 32 Procedures MA-JF-731-001 SGTS, CREVAS, and TSCVASS Testing 2
MST-071.10A LPCI 71BAT-3A Battery Monthly Surveillance Test 001 OP-20 Standby Gas Treatment System 45 OP-43C LPCI Independent Power Supply System 27 OP-55 Control Room Ventilation and Cooling 39 OP-56 Relay Room Ventilation and Cooling 21 71111.05 Fire Plans PFP-PWR15 Crescent Area-West Elev. 227', 242' Fire Area/Zone XVIII/RB-1W 6
PFP-PWR22 Standby Gas Filter Room Elev. 272' Fire Area/Zone XX/SG-1 7
PFP-PWR23 Motor Generator Set Room Elev. 300' Fire Area/Zone IA/MG-1 6
PFP-PWR32 Emergency Diesel Generator Spaces-North Elev. 272' Fire Area/Zone VI/EG-3, EG-4, EG-6 7
Procedures OP-AA-201-003 Fire Drill Performance 22 71111.11Q Procedures ST-9QB EDG B and D Full Load Test 71111.12 Corrective Action Documents 04670001 04680732 04721539 04774208 04785661 04788292 Corrective Action Documents Resulting from Inspection 04819203 04819213 Procedures ER-AA-200 Preventive Maintenance Program 7
12 Inspection Procedure Type Designation Description or Title Revision or Date ER-AA-200-1001 Equipment Classification 8
SP-03.08RX Reactor Building Gaseous Effluent Monitors 3
71111.13 Corrective Action Documents 04822877 04823124 71111.15 Corrective Action Documents 04801389 04803911 04804112 04818300 04819086 Engineering Changes 642449 Evaluation of Voltage Needed to Close 13MOV-16 in DBA LOCA 1
Work Orders 05581552 71111.18 Corrective Action Documents 04803500 Engineering Changes 635997 Compressed Air System Hardening: Installation of Air Dryer Bypass Line and 39BAS-2 Internals Removal 0
642527 13MOV-16 Seal Weld Temporary Repair 0
71111.24 Corrective Action Documents 04801976 04803001 04811081 04811081 04811082 04814994 04814997 Drawings FM-22A Flow Diagram Reactor Core Isolation Cooling System 13 58 Miscellaneous C684-0289 Crane Operation and Maintenance Manual 2
Procedures ER-AA-302-1006 Motor Operated Valve Maintenance and Testing Guidelines 22 ER-AA-410-1000 Air Operated Valve Categorization 4
ER-AA-410-1002 Air Operated Valve Testing Requirements 4
IMP-71.25 Test Equipment Set Up for 10500 and 10600 Emergency Bus Sequencing Test ST-9C*
11 MA-AA-617-012 Post Maintenance Testing 29 MST-011.11 Standby Liquid Control Explosive Valves (IST) 15
13 Inspection Procedure Type Designation Description or Title Revision or Date SEP-IST-007 Inservice Testing (IST) Program Program Plan 16 ST-1B MSIV Fast Closure Test (IST) 029 ST-22K Manual Safety Relief Valve Operation System Test (IST) 8 ST-24J RCIC Flow Rate and Inservice Test (IST) 58 ST-2F LPCI and LPCI MOV Power Supply Simulated Automatic Actuation Test 39 ST-2HB LPCI Initiation Logic System B Functional Test 25 ST-39B Type B and C LLRT of Containment Penetrations (IST) 43 ST-39B-X7A Type C Leak Test Main Steam Line A MSIVS (IST) 19 ST-39B-X7B Type C Leak Test Main Steam Line B MSIVS (IST) 18 ST-39B-X7C Type C Leak Test Main Steam Line C MSIVS (IST) 19 ST-39B-X7D Type C Leak Test Main Steam Line D MSIVS (IST) 18 ST-39H RPV System Leakage Test 42 ST-6M Standby Liquid Control Recirculation, Injection Test (IST, ISI) 15 ST-9CB EDG B and D Load Sequencing Test and 4KV Emergency Power System Voltage Relays Instrument Functional Test 8
Work Orders 05310039 05311049-01 05311051-01 05311053-01 05311056-01 05311158 05311434 05312802 05312969 05322361 05325243 05325246 05338573 05372539 05372540 05377513 05580109
14 Inspection Procedure Type Designation Description or Title Revision or Date 05590970 05591036 05600848 05605976 71152A Corrective Action Documents 04686903 04708932 04731298 04803804 Procedures PI-AA-120 Issue Identification and Screening Process 13 PI-AA-125 Corrective Action Program (CAP) Procedure 9
PI-AA-125-1003 Corrective Action Program Evaluation Manual 7
71153 Corrective Action Documents 04811081 04811082 04813216 04820129 Miscellaneous EN 57437 Procedures AOP-32 Unplanned Power Change 15 AOP-8 Unexpected Change in Core Flow 41