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Category:Inspection Report
MONTHYEARIR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 IR 05000220/20230012023-05-0505 May 2023 Integrated Inspection Report 05000220/2023001 and 05000410/2023001 IR 05000220/20233012023-03-29029 March 2023 Initial Operator Licensing Examination Report 05000220/2023301 IR 05000220/20220062023-03-0101 March 2023 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2022006 and 05000410/2022006) IR 05000220/20220042023-01-23023 January 2023 Integrated Inspection Report 05000220/2022004 and 05000410/2022004 IR 05000220/20220102022-11-22022 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000220/2022010 and 05000410/2022010 IR 05000220/20220032022-11-0404 November 2022 Integrated Inspection Report 05000220/2022003 and 05000410/2022003 IR 05000220/20220052022-08-31031 August 2022 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2022005 and 05000410/2022005) IR 05000220/20224012022-08-30030 August 2022 Security Baseline Inspection Report 05000220/2022401 and 05000410/2022401 IR 05000220/20220022022-08-0808 August 2022 Integrated Inspection Report 05000220/2022002 and 05000410/2022002 and Independent Spent Fuel Storage Installation Report 07201036/2022001 IR 05000220/20210042022-05-19019 May 2022 Reissued Integrated Inspection Report 05000220/2021004 and 05000410/2021004 IR 05000220/20220012022-04-29029 April 2022 Integrated Inspection Report 05000220/2022001 and 05000410/2022001 IR 05000220/20210062022-03-0202 March 2022 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2021006 and 05000410/2021006) ML22026A3502022-01-26026 January 2022 Integrated Inspection Report 05000220/2021004 and 05000410/2021004 IR 05000220/20210122022-01-10010 January 2022 Biennial Problem Identification and Resolution Inspection Report 05000220/2021012 and 05000410/2021012 IR 05000220/20210032021-11-0909 November 2021 Integrated Inspection Report 05000220/2021003 and 05000410/2021003 and Independent Spent Fuel Storage Installation Report 07201036/2021001 IR 05000220/20215012021-10-14014 October 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2021501 and 05000410/2021501 IR 05000220/20214012021-09-0101 September 2021 Material Control and Accounting Program Inspection Report 05000220/2021401 and 05000410/2021401 (Letter Only) IR 05000220/20210052021-09-0101 September 2021 Updated Inspection Plan for the Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2021005 and 05000410/2021005) IR 05000220/20210102021-08-24024 August 2021 Triennial Fire Protection Inspection Report 05000220/2021010 and 05000410/2021010 IR 05000220/20210022021-08-10010 August 2021 Integrated Inspection Report 05000220/2021002 and 05000410/2021002 and Independent Spent Fuel Storage Installation Report 07201036/2021002 IR 05000220/20214022021-06-22022 June 2021 Security Baseline Inspection Report 05000220/2021402 and 05000410/2021402 IR 05000410/20213022021-05-12012 May 2021 Initial Operator Licensing Examination Report 05000410/2021302 IR 05000220/20210012021-05-0505 May 2021 Integrated Inspection Report 05000220/2021001 and 05000410/2021001 IR 05000220/20210112021-05-0404 May 2021 Temporary Instruction 2515/194 Inspection Report 05000220/2021011 and 05000410/2021011 IR 05000220/20200062021-03-0303 March 2021 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2020006 and 05000410/2020006) IR 05000220/20200042021-02-11011 February 2021 Integrated Inspection Report 05000220/2020004 and 05000410/2020004 and Independent Spent Fuel Storage Installation Report 07201036/202004 IR 05000220/20203012021-01-25025 January 2021 Initial Operator Licensing Examination Report 05000220/2020301 IR 05000220/20204202020-12-0909 December 2020 Security Inspection Report 05000220/2020420 and 05000410/2020420 2020 Report ML20343A0112020-12-0909 December 2020 Security Inspection Report Cover Letter 05000220/2020420 and 05000410/2020420 IR 05000220/20200102020-11-24024 November 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000220/2020010 and 05000410/2020010 IR 05000220/20200032020-11-10010 November 2020 Integrated Inspection Report 05000220/2020003 and 05000410/2020003 IR 05000220/20200052020-08-31031 August 2020 Updated Inspection Plan for the Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2020005 and 05000410/2020005) IR 05000220/20204012020-07-29029 July 2020 Security Baseline Inspection Report 05000220/2020401 and 05000410/2020401 ML20149K4122020-05-29029 May 2020 Request for Information for a Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000220/2020010 and 05000410/2020010 IR 05000220/20200012020-05-0404 May 2020 Integrated Inspection Report 05000220/2020001 and 05000410/2020001 and Independent Spent Fuel Storage Installation Inspection Report 07201036/2020001 IR 05000220/20190062020-03-0303 March 2020 Annual Assessment Letter for the Nine Mile Point Nuclear Station, Units 1 and 2 (Reports 05000220/2019006 and 05000410/2019006) IR 05000410/20193012020-02-11011 February 2020 Initial Operator Licensing Examination Report 05000410/2019301 2024-02-01
[Table view] Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] |
Text
May 4, 2021
SUBJECT:
NINE MILE POINT NUCLEAR STATION - TEMPORARY INSTRUCTION 2515/194 INSPECTION REPORT 05000220/2021011 AND 05000410/2021011
Dear Mr. Rhoades:
On April 20, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station and discussed the results of this inspection with Mr. Pete Orphanos, 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, X /RA/
Signed by: Glenn T. Dentel Glenn T. Dentel, Chief Engineering Branch 2 Division of Operating Reactor Safety Docket Nos. 05000220 and 05000410 License Nos. DPR-63 and NPF-69
Enclosure:
As stated
Inspection Report
Docket Numbers: 05000220 and 05000410 License Numbers: DPR-63 and NPF-69 Report Numbers: 05000220/2021011 and 05000410/2021011 Enterprise Identifier: I-2021-011-0015 Licensee: Exelon Nuclear Facility: Nine Mile Point Nuclear Station Location: Oswego, NY Inspection Dates: April 12, 2021 to April 20, 2021 Inspectors: C. Hobbs, Reactor Inspector D. Werkheiser, Senior Reactor Analyst Approved By: Glenn T. Dentel, Chief Engineering Branch 2 Division of Operating Reactor Safety Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Temporary Instruction 2515/194 Inspection at Nine Mile Point Nuclear Station, 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
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 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.
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 on Open Phase Condition, (ADAMS Accession No. ML19163A176)dated June 6, 2019. 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) Exelon selected the Open Phase Condition (OPC) detection system designed and manufactured by Schweitzer Engineering Laboratories (SEL) for use at Nine Mile Point Nuclear Station. The offsite power distribution system at Nine Mile Point Unit 1 and Unit 2 is described below.
Nine Mile Point Unit 1 has two 115 kV independent offsite power sources, Line 1 and Line 4. Line 1 is supplied from the South Oswego substation, while Line 4 is supplied from the Lighthouse Hill substation through the James A. Fitzpatrick Switchyard.
115 kV power is then supplied to circuit breakers R10 and R40, which then supply power to Reserve Transformers T101-North, and T101-South. Power is then supplied to the 4kV emergency buses, PB-102 and PB-103. OPC detection is provided in 4 locations: at the R10 and R40 115 kV circuit breakers, and at the T101-North and T101-South transformers.
Nine Mile Point Unit 2 also has two 115 kV independent offsite power sources, Line 5 and Line 6. Line 5 is supplied power from the 345 kV transformer TB-1 located in the Scriba switchyard. Line 6 is supplied power from the 345 kV transformer TB-2 which is also located in the Scriba switchyard. Line 5 and Line 6 supply 115 kV power to Reserve Station Service Transformers, Reserve Transformer A, and Reserve Transformer B. The Auxiliary Boiler Transformer is a third transformer, that may be supplied from either Line 5 or Line 6. The Auxiliary Boiler Transformer may be used as a backup source of power to the 4kV emergency buses. Power is supplied to the three 4kV emergency buses, 2ENS-SWG101, 2ENS-SWG102, and 2ENS-SWG103 from Reserve Transformer A, and Reserve Transformer B. OPC detection is provided in 5 locations: at the TB-1 and TB-2 transformers in the Scriba switchyard, at Reserve Transformer A, at Reserve Transformer B, and at the Auxiliary Boiler Transformer.
In lieu of automatic OPC protective actions, Nine Mile Point Unit 1 and Unit 2 implemented an alarm only strategy, which relies on proper operator actions to diagnose and respond to an Open Phase Condition. At the end of this inspection, the SEL relays for OPC were monitoring the associated power sources and would provide main control room annunciation if a loss of one or two phases of power was detected, or if an OPC relay was non-functional. In addition, actuation of an OPC relay will also be indicated on alarms in the plant process computer.
INSPECTION RESULTS
Observation: Temporary Instruction 2515/194 - Section 03.01(a) and
- (c) Results 2515/194 Based on discussions with Exelon staff, review of design and testing documentation, and walkdowns of installed equipment, the inspectors had reasonable assurance that Nine Mile Point Nuclear Station is implementing the guidance specified in the NEI Voluntary Industry Initiative on Open Phase Condition, with a noted exception discussed below. The inspectors verified the following criteria:
Detection, Alarms and General Criteria 1. [03.01(a)(1)] OPCs are detected and alarmed in the control room.
2. [03.01(a)(2)] In scenarios where automatic detection may not be possible due to very low or no load conditions, or when transformers are in a standby mode, detection will occur as soon as loads are transferred to the standby source. Additionally, where detection is not reliable, Exelon has established monitoring requirements on a per shift basis, to look for evidence of an OPC.
3. [03.01(a)(3)] The OPC design and protective schemes minimize misoperation or spurious action in the range of voltage unbalance normally expected in the transmission system that could cause separation from an operable off-site power source. Additionally, Exelon has demonstrated that the actuation circuit design does not result in lower overall plant operation reliability.
4. [03.01(a)(4)] No Class-1E circuits were replaced with non-Class-1E circuits in this design.
5. [03.01(a)(5)] The Updated Final Safety Analysis Report was updated to discuss the design features and analyses related to the effects of any OPC design vulnerability.
Use of Risk-Informed Evaluation Method 1. [03.01(c)(1)] The plant configuration matched the Probabilistic Risk Assessment (PRA) model to address an OPC, and the logic of the PRA model is sound.
2. [03.01(c)(2)] The procedures which validate that an OPC alarm would identify the proper indication to validate the OPC at all possible locations.
3. [03.01(c)(3)] Observations associated with procedures and operator actions required to respond to an OPC alarm and potential equipment trip match the Human Reliability Analysis (HRA).
4. [03.01(c)(4)] Sensitivity analyses used in the Nine Mile Point Unit 1 and Unit 2 PRA analysis for using Operator Manual Actions (OMAs) in leu of OPC automatic protective relay actuation, did not exceed the thresholds defined in the NEI 19-02 guidance document for delta Core Damage Frequency (CDF) or delta Large Early Release Frequency (LERF).
5. [03.01(c)(5)] Assumptions, procedures, and operator actions specified in the Nine Mile
Point Unit 1 and Unit 2 NEI 19-02 analysis are consistent with the plant-specific design and licensing basis, including:
- (a) Initiating events considered in the analysis.
- (b) Boundary conditions specified in Attachment 1 of the NEI Voluntary Industry Initiative, Revision 3.
- (c) Operating procedures for steps taken to recover equipment assumed tripped, locked out, or damaged due to an OPC.
- (d) Where recovery was assumed in the PRA analysis for tripped electric equipment, restoration of the equipment was based on analyses that demonstrate that automatic isolation trips did not result in equipment damage.
Observation: Temporary Instruction 2515/194 - Detection, Alarms, and General 2515/194 Criteria - Exception
[03.01(a)(6)] - Identify if Open Phase Isolation System (OPIS) detection and alarm components are maintained in accordance with station procedures or maintenance program, and that periodic tests, calibrations, setpoint verifications, or inspections (as applicable) have been established.
Exception - Nine Mile Point Unit 2 had not developed any maintenance PMs for the OPC relays on Unit 2 at the beginning of the inspection. Nine Mile Point Unit 1 had developed maintenance PMs for Unit 1 OPC relays at the beginning of the inspection. This deviation was identified in a pre-inspection self-assessment performed by Exelon and captured in the corrective action program as Issue Report 04405714. At the end of the inspection, Issue Report 02540320-06 was created to develop maintenance PMs for Nine Mile Point Unit 2 OPC relays.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 20, 2021, the inspectors presented the Temporary Instruction 2515/194 inspection results to Mr. Pete Orphanos, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
2515/194 Corrective Action 2540320,
Documents 4217412,
292365,
296560,
296567,
298487,
298493,
4369561,
4405714
Corrective Action 4416368
Documents
Resulting from
Inspection
Drawings C-19420-C Nine Mile Point Unit 1 Elementary Wiring Diagram 115 kV Revision 1
Line #1, South Oswego, Control Circuits, Sheet 01A
C-19421-C Nine Mile Point Unit 1 Elementary Wiring Diagram 115 kV Revision 8
Line #4, NMP-FITZ., Control Circuits, Sheet 1A
C-19422-C Nine Mile Point Unit 1 Elementary Wiring Diagram 115 kV Revision 0
Reserve Transforms 101N & 101S Open Phase Protection,
Sheet 01A
C-19422-C Nine Mile Point Unit 1 Elementary Wiring Diagram 115 kV Revision 0
Reserve Transforms 101N & 101S Open Phase Protection,
Sheet 01B
C-34857-C Nine Mile Point Unit 1 Elementary Wiring Diagram, Auxiliary Revision 9
Control Cabinet 1S79, Alarm Relay 74A, Sheet 2
ESK 08SPR005 Nine Mile Point Unit 2 D.C. Elementary Diagram XFMR Revision 0
2RTX-XSR1A, Primary Protection, Sheet 2
Engineering ECP-14-000340 Nine Mile Point Unit 1 Open Phase Relaying for Revision 1
Changes Transformers XF-101S and XF-101N
ECP-14-000922 Nine Mile Point Unit 2 Open Phase Detection System Revision 2
Implementation
ECP-16-000021 Nine Mile Point Unit 1 Open Phase Detection Implementation Revision 0
Inspection Type Designation Description or Title Revision or
Procedure Date
Engineering N1-MISC-010 Nine Mile Point Station Unit 1 Open Phase Condition Revision 0
Evaluations Evaluation
N2-MISC-015 Nine Mile Point Station Unit 2 Open Phase Condition Revision 1
Evaluation
Miscellaneous LS-AA-107-1001 Nine Mile Point Unit 1 UFSAR change number 1-19-UFS-003 dated
2/19/19
LS-AA-107-1001 Nine Mile Point Unit 2 UFSAR change number 2-19-UFS-006 dated
2/19/19
ML19344C980 Nine Mile Point Nuclear Station, Units 1 and 2 - Temporary dated
Instruction Report 05000220/2019014 and 12/9/19
05000410/2019014
Presentation TI-2515/194 Open Phase NRC Inspection dated
4/12/21
Procedures N1-ARP-A8 Nine Mile Point Unit 1 Panel A8 Alarm Response Procedures 01900
N1-PM-S1 Nine Mile Point Unit 1 Operator's Rounds Guide 03800
N2-ARP-852600 Nine Mile Point Unit 2 2CEC*PNL852 Series 600 Alarm 01400
Response Procedures
N2-OP-70 Nine Mile Point Unit 2 Station Electrical Feed and 115 kV 02600
Switchyard
Self-Assessments PI-AA-126-1001 NRC Open Phase Inspection TI 2515/194 Self-Assessment dated 3/5/21
7