|
---|
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
ber 9, 2019
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - TEMPORARY INSTRUCTION REPORT 05000220/2019014 AND 05000410/2019014
Dear Mr. Hanson:
On November 20, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station, Units 1 and 2 and discussed the results of this inspection with Mr. Todd Tierney, Plant 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. 05000220 and 05000410 License Nos. DPR-63 and NPF-69 Enclosure:
As stated cc w/ encl: Distribution via LISTSERV
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Temporary Instruction at Nine Mile Point Nuclear Station, Units 1 and 2, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors.
Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations No findings or violations of more than minor significance were identified.
Additional Tracking Items None.
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, (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) Exelon selected the open phase detection system designed and manufactured by Schweitzer Engineering Laboratories (SEL) as the design vendor for the open phase condition system at Nine Mile Point Nuclear Station. The open phase protection system is designed to protect the offsite power sources from a loss of phase condition.
Nine Mile Point Nuclear Station Unit 1 has two 115kV independent offsite power sources (Lines 1 and 4), which provide power to the station through breakers R10 and R40, and through Reserve Transformer 101N and Reserve Transformer 101S. Unit 2 has two 115kV independent offsite power sources (Lines 5 and 6),which provide power to the station through Reserve Transformer A, Reserve Transformer B, and the Auxiliary Boiler Transformer. SEL relays were installed to monitor, alarm, and provide a trip function on each of the 5 offsite power transformers, and for breakers R10 and R40. The relays are wired to provide annunciation and are configured to trip the associated power sources if a loss of phase condition is detected. The loss of phase detection relays include main control room annunciation and plant process computer alarms for relay trips, relay malfunction, and, in some cases, minimum loading conditions.
At the end of the inspection, the SEL system was in the alarm only mode of operation. The relay trip signals were isolated from the lockout relays by leaving test switches open. Exelon plans to pursue an alternate implementation method (i.e. risk based with manual actions) for Unit 1 and Unit 2 to comply with the open phase detection initiative.
INSPECTION RESULTS
Temporary Instruction 2515/194-03.01 - Voluntary Industry Initiative 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 the Exelon is appropriately implementing, with noted exceptions discussed below, the voluntary industry initiative at Nine Mile Point Nuclear Station. The inspectors determined that:
Detection, Alarms and General Criteria 1. The open phase condition 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. 03.01(a)(3)2. No Class 1E circuits were being replaced with non-Class 1E circuits in this design.
03.01(a)(4)
Protective Actions Criteria 1. The identified offsite power sources are susceptible to an open phase condition and the licensee was implementing design changes to mitigate the effects. 03.01(b)(1)2. With an open phase condition present and no accident condition signal, Technical Specification Limiting Conditions for Operation would be maintained, important-to-safety equipment would not be damaged by the open phase condition, and shutdown safety would not be compromised. Exelon's open phase condition design solution added a set of additional tripping inputs in parallel with existing power isolation devices. These additional devices added a new tripping condition (open phase) to the previously analyzed electrical faults which result in isolation of the transformers. The credited plant response was unaffected and would be the same regardless of the conditions that generated the isolation of the transformers. 03.01(b)(2)
No findings were identified.
Detection, Alarms and General Criteria Exceptions 2515/194 03.01(a)(1) In general, open phase condition detection and alarming was adequately implemented at Nine Mile Point Nuclear Station. Inspectors noted one exception to this criteria.
During a system walkdown on November 18, 2019, inspectors identified that a test switch associated with the SEL relay for the 101N transformer was tagged in the open position. The test switch was opened on May 20, 2019, in response to nuisance alarms in the main control room associated with a minimum loading condition on the 101N transformer. Operators opened the test switch, believing that the plant process computer would still produce an alarm in the main control room. However, inspectors determined that with the test switch opened, no alarms would be received for any detected open phase condition for transformer 101N and that additional compensatory measures to monitor for these conditions should be in place. Inspectors did not identify any additional compensatory measures in place while the open phase condition alarm was bypassed for the 101N transformer. However, operators monitor transformer bus voltages every four hours and would have likely recognized an open phase condition. At the end of the inspection, additional compensatory measures were established, including taking additional transformer voltage and current readings at least once per shift. This issue was documented in their corrective action program as issue report 04298487.
03.01(a)(2) For cases in which automatic detection was not possible in very low or no loading conditions when the offsite power transformers are in a standby mode, inspectors determined that automatic detection would occur as soon as loads were transferred to the standby source. However, Exelon determined that additional shiftly surveillances were needed to adequately monitor and detect an open phase condition while in a very low or no loading condition. This was identified during an Exelon self-assessment performed prior to the inspection and documented in issue report 04296560.
03.01(a)(5) Exelon had neither updated the Nine Mile Point Unit 1 Updated Final Safety Analysis Report (UFSAR) nor the Unit 2 Updated Safety Analysis Report (USAR) to discuss the design features and analyses related to the effects of, and protection for, any open phase condition design vulnerability. The Unit 2 USAR did include a listing of the added open phase condition relays, without further system or analysis description. This was identified during an Exelon self-assessment performed prior to the inspection and documented in issue report 04296560.
Protective Actions Exceptions 2515/194 03.01(b)(3) Inspectors determined that with an open phase condition and an accident condition signal present, the open phase detection system would not adversely affect the function of the load shedding and sequencing system to provide a means of disconnecting and sequencing of loads on the safety-related buses. Automatic detection of an open phase condition has been installed, but the automatic actuation of the system has been bypassed. Exelons operating procedures, once detection has occurred, would allow operators to diagnose the condition and transfer the required loads to the non-affected offsite source, or the onsite emergency power source. A loss of voltage caused by isolation of offsite sources due to an open phase condition does not have an adverse effect on the availability of the non-affected offsite sources, or to the onsite emergency power sources. The bypass of the automatic isolation was identified during an Exelon self-assessment performed prior to the inspection and documented in issue report 04296567.
03.01(b)(4) Relay setpoints associated with the open phase detection scheme were verified and validated as part of acceptance factory testing, and as part of the system monitoring period. Preventative maintenance testing and periodic calibrations were developed for some aspects of the open phase detection system for Unit 1 systems, but none had been developed for Unit 2 systems. This was identified during an Exelon self-assessment performed prior to the inspection and documented in issue report
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 20, 2019, the inspectors presented the Temporary Instruction results to Mr. Todd Tierney, Plant Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
2515/194 Calculations 115kV- NMP1 Open Phase EMTP Analysis Revision
OPENPHASE- 0000
STUDY
115kV- NMP1 Open Phase LOCA Analysis Revision
OPENPHASELOCA- 0000
STUDY
115KV- Unit 1 XF-101N and XF-101S Relay Settings for Open Revision
OPENPHASEXFMR- Phase 0000
SP
EC-204 NMP2 Open Phase EMTP Analysis Revision
0000
EC-205 NMP2 Open Phase LOCA Analysis Revision
0000
EC-208 Unit 2 SEL-487E Relay Settings Revision
0000
EC-209 NMP2 Open Phase Alternate Offsite Source Analysis Revision
0000
Corrective Action 04015088
Documents 04296556
250274
296554
250274
296560
292365
Corrective Action 04298477 Door C288-1 Failed to Latch on First Closure
Documents 04298484 Discrepancies Noted with Unit 1 and Unit 2 Open Phase
Resulting from Relay (clocks)
Inspection 04298487 N1-OP-033A Procedure Discrepancy Identified
298493 Scriba Yard Relay Data Historian UPS in Alarm
Engineering ECP-14-000340 Unit 1 Open Phase Relaying for Transformers XF-101S Revision
Changes and XF-101N 0001
ECP-14-000922 NMP2 Open Phase Detection System Implementation Revision
Inspection Type Designation Description or Title Revision or
Procedure Date
(Scriba Transformers) 0002
ECP-15-000297 Open Phase Detection System Implementation (NMP2 Revision
Transformers) 0002
ECP-16-000021 Unit 1 Open Phase Detection Implementation (115 kV Line Revision
- 1 (BKR-R10) and 115 kV Line #4 (BKR-R40)) 0001
ECP-17-000507 NMP Unit 1 & 2 - Open Phase Algorithm and OPD Relay Revision
Setting Change Modification 0000
ECP-17-000507 NMP Unit 1 & 2 - Open Phase Algorithm and OPD Relay Revision
Setting Change Modification 0001
Miscellaneous AR 04289767 NRC Open Phase Inspection TI 2515/194 Self- 10/22/2019
Assessment
N1-PM-S1 NMP1 Control Room Parameter Monitoring 11/19/2019
(Compensatory Measures) for OPC 101N
NMP1 LER 05-004 Operation Prohibited by Technical Specification due to 02/17/2006
Unrevealed Inoperability of One Off-site Power Source
PCRS-18-01100 Update to N1-OP-033A 05/28/2018
Tag ACPS NMP-U1 ACPS to Maintain Configuration of Open Phase Mod Knife 11/18/2019
19-055 Switch (P&ID C34857C, Sht 2)
Procedures N1-ARP-A8 Control Room Panel A8 Revision
01500
N1-OP-033A 115kV System Revision
03300
N2-ARP-852600 2CEC*PNL852 Series 600 Alarm Response Procedures Revision
01100
7