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Category:Inspection Report
MONTHYEARIR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 IR 05000003/20230012023-05-22022 May 2023 Unions 1, 2 and 3 - NRC Inspection Report Nos. 05000003/2023001, 05000247/2023001, 05000286/2023001, and 07200051/2023001 IR 05000003/20234012023-05-10010 May 2023 NRC Security Decommissioning Inspection Report Nos. 05000003/2023401, 05000247/2023401, and 05000286/2023401 IR 05000003/20220042023-03-13013 March 2023 NRC Inspection Report Nos. 05000003/2022004, 05000247/2022004, 05000286/2022004, and 07200051/2022002 IR 05000003/20220022022-11-17017 November 2022 NRC Inspection Report Nos. 05000003/2022002, 05000003/2022003, 05000247/2022002, 05000247/2022003, 05000286/2022002, 05000286/2022003, and 07200051/2022001 IR 05000003/20224022022-10-28028 October 2022 Reissued NRC Security Decommissioning Inspection Report Nos. 05000003/2022402, 05000247/2022402, and 05000286/2022402 (Letter Only) IR 05000003/20224012022-05-25025 May 2022 NRC Security Decommissioning Inspection Report Nos. 05000003/2022401, 05000247/2022401, and 05000286/2022401 IR 05000003/20220012022-05-25025 May 2022 NRC Inspection Report Nos. 05000003/2022001, 05000247/2022001, and 05000286/2022001 IR 05000003/20210042022-03-0404 March 2022 NRC Inspection Report Nos. 05000003/2021004, 05000247/2021004, 05000286/2021004, and 07200051/2021001 IR 05000003/20210032021-11-0909 November 2021 NRC Inspection Report Nos. 05000003/2021003, 05000247/2021003, and 05000286/2021003 IR 05000003/20210022021-08-0404 August 2021 NRC Inspection Report Nos. 05000003/2021002, 05000247/2021002, and 05000286/2021002 IR 05000286/20210022021-06-0707 June 2021 Integrated Inspection Report 05000286/2021002 IR 05000286/20214022021-05-0505 May 2021 Security Baseline Inspection Report 05000286/2021402 IR 05000003/20210012021-04-21021 April 2021 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Units 1 and 2 - NRC Inspection Report No. 05000003/2021001 and 05000247/2020001 IR 05000286/20210012021-04-15015 April 2021 Integrated Inspection Report 05000286/2021001 IR 05000286/20200062021-03-0303 March 2021 Annual Assessment Letter for Indian Point Energy Center, Unit 3 (Report 05000286/2020006) IR 05000247/20200142021-02-0101 February 2021 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 2 NRC Inspection Report No. 05000247/2020014 IR 05000286/20200042021-01-28028 January 2021 Integrated Inspection Report 05000286/2020004 IR 05000003/20200012020-12-0808 December 2020 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Units 1 and 2, NRC Inspection Report No. 05000003/2020001 and 05000247/2020013 IR 05000286/20200032020-10-28028 October 2020 Integrated Inspection Report 05000286/2020003 IR 05000286/20200102020-09-16016 September 2020 Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000286/2020010 IR 05000286/20200052020-08-31031 August 2020 Updated Inspection Plan for Indian Point Energy Center, Unit 3 (Inspection Report 05000286/2020005) IR 05000247/20200022020-08-10010 August 2020 Integrated Inspection Report 05000247/2020002 and 05000286/2020002 IR 05000286/20200122020-07-27027 July 2020 Design Basis Assurance Inspection (Programs) Inspection Report 05000286/2020012 IR 05000247/20020102020-05-12012 May 2020 Final ASP Analysis - Indian Point 2 (IR 050002472002010) IR 05000247/20200012020-04-29029 April 2020 Integrated Inspection Report 05000247/2020001 and 05000286/2020001 IR 05000247/20190062020-03-0303 March 2020 Annual Assessment Letter for Indian Point Energy Center, Units 2 and 3 (Report 05000247/2019006 and 05000286/2019006) IR 05000247/20190042020-02-10010 February 2020 Integrated Inspection Report 05000247/2019004 and 05000286/2019004 IR 05000003/20190012020-01-16016 January 2020 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 1 - NRC Inspection Report No. 05000003/2019001 IR 05000247/20190122020-01-0909 January 2020 Temporary Instruction 2515/194 Inspection Report 05000247/2019012 and 05000286/2019012 IR 05000247/20194112020-01-0909 January 2020 Material Control and Accounting Program Inspection Report 05000247/2019411 and 05000286/2019411 (Cover Letter Only) IR 05000247/20194032019-11-0505 November 2019 Cyber Security Inspection Report 05000247/2019403 and 05000286/2019403 (Cover Letter Only) IR 05000247/20190032019-11-0404 November 2019 Integrated Inspection Report 05000247/2019003 and 05000286/2019003 IR 05000247/20194102019-10-0202 October 2019 Security Inspection Report 05000247/2019410 and 05000286/2019410 (Cover Letter Only) IR 05000247/20190102019-09-26026 September 2019 Biennial Problem Identification and Resolution Inspection Report 05000247/2019010 and 05000286/2019010 IR 05000247/20190052019-08-28028 August 2019 Updated Inspection Plan (Inspection Report 05000247/2019005 and 05000286/2019005) IR 05000247/20190022019-08-13013 August 2019 Integrated Inspection Report 05000247/2019002 and 05000286/2019002 IR 05000247/20190112019-07-0909 July 2019 Design Basis Assurance Inspection (Programs) Inspection Report 05000247/2019011 and 05000286/2019011 IR 05000247/20190012019-05-13013 May 2019 Integrated Inspection Report 05000247/2019001 and 05000286/2019001 ML19130A0422019-05-0808 May 2019 Information Request for the Cyber-Security Inspection, Notification to Perform Inspection 05000247/2019403 and 05000286/2019403 IR 05000247/20193012019-04-18018 April 2019 Initial Operator Licensing Examination Report 05000247/2019301 IR 05000247/20180062019-03-0404 March 2019 Annual Assessment Letter for Indian Point Energy Center, Units 2 and 3 (Reports 05000247/2018006 and 05000286/2018006) IR 05000247/20180042019-02-0707 February 2019 Integrated Inspection Report 05000247/2018004 and 05000286/2018004 IR 05000247/20180102019-01-15015 January 2019 Design Bases Assurance Inspection (Teams) Report 05000247/2018010 and 05000286/2018010 IR 05000247/20180022019-01-0909 January 2019 Errata for Indian Point Nuclear Generating - Integrated Inspection Report 05000247/2018002 and 05000286/2018002 IR 05000247/20184102018-12-0606 December 2018 Security Inspection Report 05000247/2018410 and 05000286/2018410 (Cover Letter Only) IR 05000247/20182012018-11-27027 November 2018 NRC Inspection Report 05000247/2018201 and 05000286/2018201 IR 05000247/20180032018-11-0808 November 2018 Integrated Inspection Report 05000247/2018003 and 05000286/2018003 IR 05000003/20180012018-10-25025 October 2018 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 1 - NRC Inspection Report No. 05000003/2018001 Dated October 25, 2018 2023-08-22
[Table view] Category:Letter
MONTHYEARML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks ML23235A0602023-07-17017 July 2023 LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23194A0442023-07-11011 July 2023 Clarification for Indian Point Energy Center License Amendment Request, Independent Spent Fuel Storage Installation Physical Security Plan ML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23171B0432023-06-23023 June 2023 Letter - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML23118A0972023-06-0606 June 2023 06-06-23 Letter to the Honorable Michael V. Lawler, Et Al., from Chair Hanson Regarding Holtec'S Announcement to Expedite Plans to Release Over 500,000 Gallons of Radioactive Wastewater from Indian Point Energy Center Into the Hudson River ML23144A3512023-05-25025 May 2023 Clementina Bartolotta of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3522023-05-25025 May 2023 Loredana Bidmead of New York E-Mail Against Treated Water Release from Indian Point Site ML23144A3412023-05-25025 May 2023 Dianne Schirripa of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23144A3472023-05-25025 May 2023 David Mart of Blauvelt, New York Email Against Treated Water Release from Indian Point Site ML23144A3402023-05-25025 May 2023 Melvin Israel of New York Email Against Treated Water Release from Indian Point Site ML23144A3542023-05-25025 May 2023 Terri Thal of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3532023-05-25025 May 2023 John Shaw of New York Email Against Treated Water Release from Indian Point Site 2024-01-09
[Table view] |
Text
ary 9, 2020
SUBJECT:
INDIAN POINT NUCLEAR GENERATING, UNITS 2 AND 3 - TEMPORARY INSTRUCTION 2515/194 INSPECTION REPORT 05000247/2019012 AND 05000286/2019012
Dear Mr. Vitale:
On December 19, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Indian Point Nuclear Generating, Units 2 and 3 and discussed the results of this inspection with Mr. Richard Drake, Acting Design and Programs Engineer Manager 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,
/RA/
Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 05000247 and 05000286 License Nos. DPR-26 and DPR-64
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000247 and 05000286 License Numbers: DPR-26 and DPR-64 Report Numbers: 05000247/2019012 and 05000286/2019012 Enterprise Identifier: I-2019-012-0035 Licensee: Entergy Nuclear Operations, Inc.
Facility: Indian Point Nuclear Generating, Units 2 and 3 Location: Buchanan, NY Inspection Dates: December 16, 2019 to December 19, 2019 Inspectors: C. Hobbs, Reactor Inspector A. Patel, Senior Reactor Inspector Approved By: Glenn T. Dentel, Chief Engineering Branch 2 Division of Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Temporary Instruction inspection at Indian Point Nuclear Generating, Units 2 and 3, 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.
INSPECTION SCOPES
The inspection was conducted using Temporary Instruction 2515/194 (ADAMS Accession No. ML17137A416), effective November 1, 2017. The inspectors reviewed Entergys implementation of the Nuclear Energy Institutes voluntary industry initiative in compliance with Commission guidance. The inspectors discussed Entergys open phase condition system design and ongoing implementation plans with plant staff. The inspectors reviewed Entergy and vendor documentation, and performed system walkdowns to verify that the installed equipment was supported by the design documentation. Entergy had recently completed physical installation and the equipment was being operated in a monitoring mode with the trip functions enabled.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 2515/194 - Inspection of the Licensees Implementation of Industry Initiative Associated With the Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012-01)
The inspectors reviewed the licensees implementation of the Nuclear Energy Institute Voluntary Industry Initiative, (ADAMS Accession No. ML15075A454) dated March 16, 2015. This included reviewing how the licensee updated their licensing basis to reflect the need to protect against open phase conditions.
Inspection of the Licensees Implementation of Industry Initiative Associated With the Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012-01)
(1 Sample)
- (1) Entergy Operations Inc. selected the open phase detection system designed and manufactured by PCS2000 Solutions, LLC, as the design vendor for the open phase condition system at Indian Point Nuclear Generating. The onsite and offsite electrical distribution system is functionally the same for both Indian Point Unit 2 and Unit 3.
Two general design criteria (GDC-17) offsite power sources are credited for each unit.
The normal offsite power source is a 138 kV feeder from the Buchanan switchyard that supplies a station auxiliary transformer (SAT) which in turn feeds two 6.9 kV buses in the onsite electrical distribution. If the normal source of offsite power is lost, the two 6.9 kV buses can be manually connected to the alternate offsite power source which is the gas turbine autotransformer (GTA). The GTA is fed by a 13.8 kV feeder from a different section of the Buchanan switchyard. The 6.9 kV buses then feed the four safety-related 480 V engineered safeguards (ESF) buses through station service transformers (SSTs).
During normal operation with the reactor at power, the SAT will feed 6.9 kV buses 5 and 6. These (6.9 kV buses 5 and 6) will then feed 480 V ESF buses 5A and 6A through SSTs 5 and 6. If 138 kV offsite power is lost, or if a lockout of the SAT occurs due to an electrical fault such as an open phase condition, power will be lost to 6.9 kV buses 5 and 6 as well as as 480 V bus 5A and 6A temporarily. Each 480 V ESF is supplied by an emergency diesel generator and the respective emergency diesel generator for 480 V bus 5A and 6A will start and supply power to its respective bus. Operators can then manually shift power from the SAT to the GTA and supply 13.8 kV offsite power to 6.9 kV buses 5 and 6, thus restoring offsite power to the buses. Once offsite power has been restored to 6.9 kV buses 5 and 6, the emergency diesel generator supplying power to the respective 480 V bus may be secured. Throughout the loss of offsite power, 6.9 kV buses 1 through 4 will continue to supply power to 480 V ESF buses 2A and 3A. Power to 6.9 kV buses 1 through 4 are supplied from the main generator through the unit auxiliary transformer while the reactor is at power. These buses also supply power to all four reactor coolant pumps, therefore, a loss of offsite power by itself does not result in a reactor and turbine trip.
In the event of a reactor and turbine trip, 6.9 kV buses 1 through 4 will fast transfer to 6.9 kV buses 5 and 6 so that power will be supplied to all six 6.9 kV buses from offsite power, thus continuity of power is retained. This same configuration is used during a refueling outage when the reactor is offline.
Indian Point has installed redundant open phase detection systems on each offsite power transformer for each unit. For a single offsite power transformer, there are duplicate current sensors installed on each phase on the line side of the transformer bushings, as well as duplicate electronic relay cabinets. Coincidence logic is utilized for the electronic relays to prevent spurious trips of the system. At the end of this inspection, the PCS2000 system was operating with all functions enabled for each SAT and GTA.
INSPECTION RESULTS
Voluntary Industry Initiative (Part 1) 2515/194 Based on discussions with licensee staff; review of design, installation, and testing documentation; and walkdowns of installed equipment; the inspectors had reasonable assurance the licensee is appropriately implementing the voluntary industry initiative. No exceptions were noted. The inspectors verified by design document review, walkdowns, staff discussions, and observation the following criteria:
Detection, Alarms, and General Criteria
- (1) Open phase conditions will be detected and alarmed in the both the Unit 2 and Unit 3 control rooms.
- (2) Detection circuits are sensitive enough to identify an open phase condition for all credited loading conditions.
- (3) The PCS2000 system is designed to minimize misoperation or spurious action in the range of voltage unbalance normally expected in the transmission system that could cause separation from an operable offsite power source. The licensee has demonstrated that the actuation circuit design did not result in lower overall plant operation reliability.
- (4) No Class-1E circuits were replaced with non-Class 1E circuits in the design.
- (5) The licensee had updated the Unit 2 and Unit 3 Final Safety Analysis Reports to discuss the design features and analyses related to the effects of, and protection for, any open phase condition vulnerabilities.
Protective Actions Criteria
- (1) The SATs and the GTAs at both Unit 2 and Unit 3 were identified as susceptible to an open phase condition and the licensee has implemented design changes to mitigate the effects.
- (2) With an open phase condition present, and no accident condition signal present, the PCS2000 system would not adversely affect the function of important-to-safety systems, structures, or components. The PCS2000 open phase condition design solution added a set of additional tripping inputs in parallel with existing transformer isolation controls. This addition added a new tripping condition (open phase) to the previously analyzed electrical faults, which result in isolation of the offsite power transformer. The credited plant response was unaffected and would be the same independent of the conditions that would generate electrical isolation of the offsite power transformer.
- (3) With an open phase condition present, and an accident condition signal present, the PCS2000 system would not adversely affect the transfer of 480 V ESF buses to the onsite emergency diesel generators as required by the current licensing bases. Only a new tripping condition (open phase) was added to the electrical faults which result in isolation of the offsite source of power.
- (4) Periodic tests, calibrations, and setpoint verifications have been established for the open phase detection system for both Unit 2 and Unit 3.
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On December 19, 2019, the inspectors presented the Temporary Instruction results to Mr. Richard Drake, Acting Design and Programs Engineer Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
2515/194 Calculations IP-CALC-15- Open Phase Detection Time Delay Trip Setting for Unit 2 0
00103
IPC-CALC-16- Open Phase Detection Time Delay Trip Setting for Unit 3 0
00023
Corrective Action Condition Reports CR-HQN-2018-02169, CR-IP3-2017-03153, CR-IP2-2018-
Documents 03631, CR-IP3-2018-02862, CR-IP3-2018-02656, CR-IP2-
2019-04438, CR-IP2-2019-04439, CR-IP3-2019-03728, CR-
IP3-2019-04217, CR-IP3-2019-03496, CR-IP3-2019-03727
Drawings 504277 Indian Point Unit 2 Station Aux Transformer OPD Systems 1 0
& 2 Trip and Alarm Schematic Diagram
504288 Indian Point Unit 2 GT1 Autotransformer OPD Systems 1 & 2 0
Trip and Alarm Schematic Diagram
504379 Indian Point Unit 3 Station Aux Transformer OPD Systems 1 0
& 2 Trip and Alarm Schematic Diagram
504391 Indian Point Unit 3 GT1 Autotransformer OPD Systems 1 & 0
Trip and Alarm Schematic Diagram
617F645 Indian Point Unit 3 Main One Line Diagram 24
908 Indian Point & Buchanan System Ties 46
21-LL-3132-15 Schematic Diagram Pilot Wire and Misc. Lockout Relays, 15
Sheet 3
A208377-21 Indian Point Unit 2 Main One Line Diagram 21
Engineering EC-52526 Open Phase Detection on Unit 2 Station Aux Transformer 0
Changes and GT Autotransformer
EC-52527 Open Phase Detection on Unit 3 Station Aux Transformer 0
and GT Autotransformer
Miscellaneous Maintenance Rule IPEC Maintenance Rule Basis Document for 13.8 kVAC 3
Electrical System
Maintenance Rule IPEC Maintenance Rule Basis Document for 138 kVAC 4
Electrical System
UFSAR Indian Point Unit 2 UFSAR 26
UFSAR Indian Point Unit 3 UFSAR 7
Work Orders 00433527, 00433529
Inspection Type Designation Description or Title Revision or
Procedure Date
Procedures 2-ARP-SCF ARP - Condensate and Boiler Feed 54
2-ARP-SHF ARP - CCR Electrical 32
3-ARP-010 ARP - 13.8 KV Substation Trouble 36
3-ARP-011 ARP - Station Aux XFMR Trouble 38
Self-Assessments LO-IP3LO-2019- NRC Inspection of Implementation of Open Phase Detection 10/29/2019
00121 Modifications
7