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Category:Inspection Report
MONTHYEARIR 05000443/20234032023-11-0707 November 2023 Security Baseline Inspection Report 05000443/2023403 and Independent Spent Fuel Storage Installation 07200063/2023401 IR 05000443/20230032023-11-0606 November 2023 Integrated Inspection Report 05000443/2023003 IR 05000443/20230102023-10-19019 October 2023 Triennial Fire Protection Inspection Report 05000443/2023010 IR 05000443/20234012023-09-0808 September 2023 Cybersecurity Inspection Report 05000443/2023401 (Cover Letter Only) IR 05000443/20234202023-09-0505 September 2023 Security Baseline Inspection Report 05000443/2023420 IR 05000443/20230052023-08-31031 August 2023 Updated Inspection Plan for Seabrook Station (Report 05000443/2023005) IR 05000443/20233022023-08-16016 August 2023 Operator Licensing Retake Examination Report 05000443/2023302 IR 05000443/20230022023-08-0808 August 2023 Integrated Inspection Report 05000443/2023002 IR 05000443/20233012023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000443/2023301 IR 05000443/20230012023-05-11011 May 2023 Integrated Inspection Report 05000443/2023001 IR 05000443/20220062023-03-0101 March 2023 Annual Assessment Letter for Seabrook Station (Report 05000443/2022006) IR 05000443/20234022023-02-21021 February 2023 Security Baseline Inspection Report 05000443/2023402 (Cover Letter Only) IR 05000443/20220042023-01-30030 January 2023 Integrated Inspection Report 05000443/2022004 and Independent Spent Fuel Storage Installation Inspection Report 07200063/2022001 ML22339A2312022-12-19019 December 2022 Review of the Fall 2021 Steam Generator Tube Inspections IR 05000443/20220102022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000443/2022010 IR 05000443/20220032022-11-22022 November 2022 Reissued Integrated Inspection Report 05000443/2022003 ML22304A1002022-11-0101 November 2022 Integrated Inspection Report 05000443/2022003 IR 05000443/20225022022-09-28028 September 2022 Emergency Preparedness Inspection Report 05000443/2022502 IR 05000443/20220052022-08-31031 August 2022 Updated Inspection Plan for Seabrook Station (Report 05000443/2022005) IR 05000443/20220022022-08-11011 August 2022 Integrated Inspection Report 05000443/2022002 IR 05000443/20224012022-07-0707 July 2022 Security Baseline Inspection Report 05000443/2022401 (Cover Letter Only) IR 05000443/20225012022-05-13013 May 2022 Emergency Preparedness Biennial Exercise Inspection Report 05000443/2022501 IR 05000443/20220012022-05-0202 May 2022 Integrated Inspection Report 05000443/2022001 IR 05000443/20220112022-03-22022 March 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000443/2022011 IR 05000443/20210062022-03-0202 March 2022 Annual Assessment Letter for Seabrook Station, Unit 1 (Report 05000443/2021006) IR 05000443/20210042022-02-10010 February 2022 Integrated Inspection Report 05000443/2021004 IR 05000443/20210032021-11-10010 November 2021 Integrated Inspection Report 05000443/2021003 IR 05000443/20210052021-09-0101 September 2021 Updated Inspection Plan for the Seabrook Station (Report 05000443/2021005) IR 05000443/20215012021-08-24024 August 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000443/2021501 IR 05000443/20214022021-08-23023 August 2021 Material Control and Accounting Program Inspection Report 05000443/2021402 (Letter Only) IR 05000443/20210022021-08-11011 August 2021 Integrated Inspection Report 05000443/2021002 IR 05000443/20210012021-05-0404 May 2021 Integrated Inspection Report 05000443/2021001 IR 05000443/20210102021-04-20020 April 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000443/2021010 IR 05000443/20214012021-04-0606 April 2021 Security Baseline Inspection Report 05000443/2021401 (Letter Only) IR 05000443/20200062021-03-0303 March 2021 Annual Assessment Letter for Seabrook Station, Unit No. 1 (Report 05000443/2020006) IR 05000443/20200042021-02-0202 February 2021 Integrated Inspection Report 05000443/2020004 IR 05000443/20210132021-01-20020 January 2021 Information Request to Support Triennial Baseline Design-Basis Capabilities of Power-Operated Valves Inspection; Inspection Reportt 05000443/2021013 IR 05000443/20200102020-12-0101 December 2020 Biennial Problem Identification and Resolution Inspection Report 05000443/2020010 IR 05000443/20204202020-11-10010 November 2020 Security Inspection Report 05000443/2020420 FOF Report IR 05000443/20200032020-11-0505 November 2020 Integrated International Report 05000443/2020003 SBK-L-20127, Generator Tube Inspection Report2020-10-20020 October 2020 Generator Tube Inspection Report IR 05000443/20203012020-09-17017 September 2020 Initial Operator Licensing Examination Report 05000443/2020301 IR 05000443/20200052020-08-31031 August 2020 Updated Inspection Plan (Inspection Report 05000443/2020005) IR 05000443/20200012020-04-29029 April 2020 Integrated Inspection Report 05000443/2020001 and Independent Spent Fuel Storage Installation (ISFSI) Report No. 07200063/2020001 IR 05000443/20204012020-03-10010 March 2020 Security Baseline Inspection Report 05000443/2020401 and Independent Spent Fuel Storage Installation Security Inspection Report 07200063/2020401(Letter Only) IR 05000443/20190062020-03-0303 March 2020 Annual Assessment Letter for Seabrook Station, Unit No. 1 (Report 05000443/2019006) IR 05000443/20190042020-02-0505 February 2020 Integrated Inspection Report 05000443/2019004 IR 05000443/20194032019-11-25025 November 2019 Cyber Security Inspection Report 05000443/2019403 (Cover Letter Only) IR 05000443/20190032019-11-0505 November 2019 Integrated Inspection Report 05000443/2019003 IR 05000443/20190052019-08-28028 August 2019 Updated Inspection Plan (Inspection Report 05000443/2019005) 2023-09-08
[Table view] Category:Letter
MONTHYEARML24009A1152024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L 2023 LLE-0043 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24022A0652024-01-22022 January 2024 Senior Reactor and Reactor Operator Initial License Examinations L-2024-003, NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2024-01-11011 January 2024 NextEra Energy Seabrook, LLC - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report ML23312A1822023-12-22022 December 2023 Issuance of Amendment No. 172 Revision to Cooling Tower Service Water Loop or Cell Requirements L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-180, Submittal of Changes to the Technical Specification Bases2023-12-13013 December 2023 Submittal of Changes to the Technical Specification Bases L-2023-177, Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Seabrook Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-160, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Final Rule ML23318A0772023-11-14014 November 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000443/2024011 IR 05000443/20234032023-11-0707 November 2023 Security Baseline Inspection Report 05000443/2023403 and Independent Spent Fuel Storage Installation 07200063/2023401 IR 05000443/20230032023-11-0606 November 2023 Integrated Inspection Report 05000443/2023003 IR 05000443/20230102023-10-19019 October 2023 Triennial Fire Protection Inspection Report 05000443/2023010 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23275A0522023-10-0202 October 2023 Requalification Program Inspection IR 05000443/20234012023-09-0808 September 2023 Cybersecurity Inspection Report 05000443/2023401 (Cover Letter Only) IR 05000443/20234202023-09-0505 September 2023 Security Baseline Inspection Report 05000443/2023420 IR 05000443/20230052023-08-31031 August 2023 Updated Inspection Plan for Seabrook Station (Report 05000443/2023005) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update IR 05000443/20233022023-08-16016 August 2023 Operator Licensing Retake Examination Report 05000443/2023302 IR 05000443/20230022023-08-0808 August 2023 Integrated Inspection Report 05000443/2023002 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-104, Preparation and Scheduling of Operator Licensing Examinations2023-08-0303 August 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-103, Inservice Inspection Examination Report2023-08-0303 August 2023 Inservice Inspection Examination Report ML23192A0782023-07-11011 July 2023 Operator Licensing Retake Examination Approval L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) SBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 ML23157A0722023-06-0606 June 2023 Notification of Conduct of a Fire Protection Team Inspection L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal IR 05000443/20233012023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000443/2023301 L-2023-064, License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-05-11011 May 2023 License Amendment Request 23-01, Revision 1, Update the Period of Applicability (Poa) for the Pressure-Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves IR 05000443/20230012023-05-11011 May 2023 Integrated Inspection Report 05000443/2023001 ML23129A0312023-05-0909 May 2023 Reactor Operator Retake License Examination ML23117A3652023-05-0404 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Remove Period of Applicability from PTL and Low Temperature Over Pressure Protection Curves SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report L-2023-053, Core Operating Limits Report for Cycle 232023-04-0505 April 2023 Core Operating Limits Report for Cycle 23 ML23088A1522023-03-29029 March 2023 Summary of Meeting Between Nrc/Region I and C-10 - Questions Regarding Seabrook 4Q2022 Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications ML23073A1562023-03-23023 March 2023 Relief Request 4RA-22-01, Relief from the Requirements of the ASME Code L-2023-012, License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves2023-03-15015 March 2023 License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves L-2023-025, Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-12023-03-15015 March 2023 Fleet Relief Request (Frr) 23-01, Proposed Alternative to ASME Section XI Authorizing Implementation of ASME Code Case N-752-1 L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2023-023, Revised Steam Generator Tube Inspection Report2023-03-0303 March 2023 Revised Steam Generator Tube Inspection Report ML23020A1002023-03-0303 March 2023 OEDO-22-00419 - 2.206 Petition for Seabrook Station Structure Concrete Concerns (EPID L-2022-CRS-0000)- Closure Letter 2024-01-29
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ber 12, 2018
SUBJECT:
SEABROOK STATION, UNIT NO. 1 - NRC BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000443/2018010
Dear Mr. Nazar:
On August 9, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Seabrook Station, Unit No. 1. The NRC inspectors discussed the results of this inspection with Mr. Eric McCartney, Vice President - Northern Region and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations corrective action program (CAP) and the stations implementation of the program to evaluate Seabrook stations effectiveness in identifying, prioritizing, evaluating and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for CAPs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed Seabrook station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment.
Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
The NRC inspectors did not identify any finding or violation of more than minor significance. 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 the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Fred L. Bower, III, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket Number: 50-443 License Number: NPF-86
Enclosure:
Inspection Report 05000443/2018010
Inspection Report
Docket Number: 50-443 License Number: NPF-86 Report Number: 05000443/2018010 Enterprise Identifier: I-2018-010-0062 Licensee: NextEra Energy Seabrook, LLC (NextEra)
Facility: Seabrook Station, Unit No. 1 (Seabrook)
Location: Seabrook, NH Inspection Dates: July 23, 2018 to August 9, 2018 Inspectors: C. Lally, Project Engineer, Team Lead P. Meier, Seabrook Resident Inspector C. Highley, Millstone Resident Inspector E. Allen, Project Engineer Observer: S. Ghrayeb, Project Engineer Approved By: F. Bower, III, Chief Reactor Projects Branch 3 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring NextEras performance at Seabrook by conducting the biennial problem identification and resolution inspection 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.
Based on the samples selected for review, the inspection team concluded that NextEra was effective in identifying, evaluating, and resolving problems and that NextEra effectively used operating experience and self-assessments. The inspectors found no evidence of significant challenges to NextEras safety conscious work environment at Seabrook and concluded that NextEra staff are willing to raise nuclear safety concerns through at least one of the several means available.
No findings or more-than-minor violations were identified.
INSPECTION SCOPES
This inspection was 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 reviewed selected procedures and records, observed activities, and interviewed personnel to assess NextEras performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
OTHER ACTIVITIES - BASELINE
71152 - Problem Identification and Resolution Biennial Team Inspection
The inspectors performed a biennial assessment of NextEras corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment. The assessment is documented below.
- (1) Corrective Action Program Effectiveness - The inspection team evaluated NextEras effectiveness in identification, prioritization and evaluation, and correcting problems, and verified the station was complied with NRC regulations and NextEras standards for corrective action programs.
- (2) Operating Experience - The team evaluated the stations effectiveness in its use of industry and NRC operating experience information and verified the station complied with NextEras standards for the use of operating experience.
- (3) Self-Assessments and Audits - The team evaluated the effectiveness of the stations audits and self-assessments and verified the station complied with NextEras standards for the use of self-assessments and audits.
- (4) Safety Conscious Work Environment - The team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs.
INSPECTION RESULTS
Evaluation of the Seabrook PI&R Program 71152B The NRC inspection team reviewed Seabrook stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined NextEra staffs performance in each of these areas adequately supported nuclear safety. No findings or more-than-minor violations were identified.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessment.
Based on the samples reviewed, the team determined that NextEras performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed Seabrook station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of those interviews, the team found no evidence of challenges to NextEras safety-conscious work environment. Site employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
Observation and Minor Performance Deficiency 71152B Corrective Action Program: The inspectors noted that out of service analytical chemistry equipment was not being documented in the corrective action program through the initiation of condition reports (CRs). The chemistry equipment deficiencies were being tracked in the chemistry department logs, but were not entered into the corrective action program.
Minor Performance Deficiency: The initiation of CRs for out of service chemistry equipment is required by NextEra procedure CS 0904.04, Laboratory Instrument Control Charts, and occurred multiple times during the period of January 2017 to July 2018. The station has documented this in the corrective action program under CR 2275048.
Screening: The failure to implement a procedural requirement had no safety impact under the given situation. Specifically, no out of service laboratory equipment was used to perform analysis to support technical specification requirements, redundant analytical equipment remained available, and no technical specification required samples were missed. Therefore, this performance deficiency is minor.
EXIT MEETINGS AND DEBRIEFS
On August 9, 2018, the inspectors presented the biennial problem identification and resolution inspection results to Mr. Eric McCartney, Vice President - Northern Region, and other members of the NextEra staff. Inspectors verified no proprietary information was retained or documented in this report.
DOCUMENTS REVIEWED
71152B
Procedures
AD-AA-103, Nuclear Safety Culture Program, Revision 12
CD0913.06, Grab Sample Technique, Revision 10
CS0924.06, Total Particulate Contamination in Emergency Diesel Fuel Oil, Revision 8
CS0904.04, Laboratory Instrument Control Charts, Revision 15
EN-AA-203-1001, Operability Determinations and Functionality Assessment, Revision 30
ER-AA-100-2002, Maintenance Rule Program Administration, Revision 6
ER-AA-101, Equipment Reliability, Revision 8
EX1806.001, RPS and ESF AS Response Time Summation Procedure, Revision 11
LX0563.02, Reactor Coolant Pump Undervoltage Channel Calibration and Relay PM,
Revision 17
MS0535.11, Equipment Hatch Missile Shield Removal and Installation, Revision 5
NA-AA-200-1000, Employee Concerns Program, Revision 1
OS1426.12, Diesel Generator A and B Weekly and Monthly Surveillances,
Revisions 11, 12, and 25
Steam Generator Reference Leg Fill and Transmitter Venting IN1640.920 Revision 0
OX0443.01, Diesel Fire Pump Weekly Test, Revision 16
OX1406.12 18 Month Containment and Containment Spray Recirculation Sump Surveillance,
Revision 9
OX1406.12 18 Month Containment and Containment Spray Recirculation Sump Surveillance,
Revision 14
OX1426.27, DG 1B Semiannual Operability Surveillance, Revision 28
PI-AA-101-1000, Level 2 Independent Assessment, Revision 20
PI-AA-102, Operating Experience Program, Revision 14
PI-AA-104-1000, Condition Reporting, Revision 17
Seabrook Station Administrative Procedure, Classification of Emergencies ER 1.1 Revision 59
Seabrook Station Administrative Procedure, Classification of Emergencies ER 1.1 Revision 56
Seabrook Quality Assurance Topical Report, Revision 21
Seabrook Station Quality Assurance Manual, Revision 54
Condition Reports (*initiated in response to inspection)
1668314 1934562 1942006 1962214 2022462 2026407
2030152 2040165 2044627 2044707 2049737 2063732
2065314 2069062 2069607 2069801 2075739 2076893
2083685 2092608 2097375 2098733 2100147 2100186
2100199 2100232 2100565 2100572 2100742 2100795
2100846 2101155 2102315 2102565 2103817 2105712
2108355 2108372 2109563 2112715 2113205 2115492
2115531 2124899 2124957 2127066 2127145 2129116
29382 2132014 2132503 2133415 2135666 2135775
2135836 2136567 2137152 2138579 2142754 2147795
2147873 2148431 2149225 2150494 2153195 2158282
2158283 2158290 2158291 2168202 2169614 2170509
2172204 2182279 2187577 2191791 2196114 2197408
2199166 2199196 2199340 2199855 2200100 2200254
200705 2201450 2202358 2202648 2207372 2207905
213342 2213584 2215058 2216373 2221606 2222634
27559 2232291 2236176 2239906 2242073 2242592
243460 2245862 2260177 2261891 2266072 2267214
268628 2269068 2272373 2272500 2272682 2273163*
273177* 2273276* 2273387* 2273426* 2273474* 2273521*
273570* 2273594* 2273613* 2273628* 2273656* 2273659*
273670* 2273685* 2273974* 2274830* 2275048* 2275282*
Work Orders/Work Requests
40132620 40228569 40264381 40265516 40287160 40308888
40316168 40322466 40346955 40422993 40427609 40432772
40441339 40451124 40465916 40505649 40533840 40561380
40563191 40563236 40563259 40563265 40563271 40563283
40563350 40586631 40593072 94139510 94143377 94162598
Calculations
ES-4.003, 125 Volt DC Short Circuit and System Voltage Drop Calculation, Revision 10
Evaluations
2019628 2076893 2092608 2097062 2102315 2103429
2105636 2106893 2114495 2115215 2115331 2116669
2119394 2120131 2124898 2124957 2125151 2129382
2137168 2140612 2156562 2158284 2169614 2172204
2197408 2199855 2200623 2200705 2202923 2207011
210450 2239906 2223905 2236037 2242520 2248447
Drawings
211630-B-9532 Sheet 1, No. 1 Unit No. 1A, 1B and 1C Vital Buses Safeguard Equipment
Control System Schematic Controls, Revision 8
Operating Experience
70077135, NRC Information Notice 2007-36 EDG Volt Regulator, dated May 16, 2008
24905 2026947 2065778 2083865 2112715 2132520
2136567 2199219 2222634 2265706
Self-Assessment and Audits
277135, Operability Evaluation Focused Area Self-Assessment, dated May 16, 2010
Operating Experience Summary, Manual Reactor Trip in Response to a Feedwater Isolation
Due to High Level in Steam Generator B Seabrook Station - April 29, 2017 (CR 2202358)
OR16 Steam Generator Tube Inspection Report SBK-L-14190, dated October 14, 2014
OR17 Steam Generator Tube Inspection Report SBK-L-16058, dated April 22, 2016
OR18 Steam Generator Tube Inspection Report SBK-L-17166, dated October 17, 2017
SBK-16-003 SBK-16-005 SBK-17-005 SBK-17-008
Miscellaneous
Chemistry logs from January 2017 to July 2018
Structural Integrity Associates, Inc. Report 1600052.401.R0