Similar Documents at Hatch |
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Category:Letter type:NL
MONTHYEARNL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0422, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R27 NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0179, National Pollutant Discharge Elimination System (NPDES) Permit Renewal2023-03-13013 March 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023 Cycle 28 Core Operating Limits Report Version 1 NL-23-0003, Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 12023-01-20020 January 2023 Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1 NL-23-0069, Correction of Technical Specification Omission and Typographical Error2023-01-20020 January 2023 Correction of Technical Specification Omission and Typographical Error NL-22-0316, Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-11-30030 November 2022 Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable NL-22-0850, Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-11-18018 November 2022 Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0832, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF .2022-10-27027 October 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF . NL-22-0800, Supplement to Authorized Relief Request HNP-ISI-RR-05-022022-10-27027 October 2022 Supplement to Authorized Relief Request HNP-ISI-RR-05-02 NL-22-0801, Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of .2022-10-14014 October 2022 Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of . NL-22-0757, Units 1 & 2, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-09-30030 September 2022 Units 1 & 2, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NL-22-0687, Notice of Intent to Pursue Subsequent License Renewal for Hatch Units 1 & 22022-08-31031 August 2022 Notice of Intent to Pursue Subsequent License Renewal for Hatch Units 1 & 2 NL-22-0406, Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes2022-08-19019 August 2022 Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes NL-22-0650, Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-08-19019 August 2022 Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0590, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten2022-08-18018 August 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten NL-22-0672, Registration of Spent Fuel Cask Use2022-08-17017 August 2022 Registration of Spent Fuel Cask Use NL-22-0564, and Vogtle Electric Generating Plant, Registration of Spent Fuel Cask Use2022-07-21021 July 2022 and Vogtle Electric Generating Plant, Registration of Spent Fuel Cask Use NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 NL-22-0499, Registration of Spent Fuel Cask Use2022-06-27027 June 2022 Registration of Spent Fuel Cask Use NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0365, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R302022-05-31031 May 2022 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R30 NL-22-0335, Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And.2022-05-17017 May 2022 Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And. NL-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0315, Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report for Drywell Temperature Indicator Inoperable for Greater than 30 Days2022-05-0404 May 2022 Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report for Drywell Temperature Indicator Inoperable for Greater than 30 Days NL-22-0325, Withdrawal of Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-05-0303 May 2022 Withdrawal of Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable NL-22-0283, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-04-29029 April 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. NL-22-0271, Changes to the Physical Security Plan2022-04-19019 April 2022 Changes to the Physical Security Plan NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations NL-21-0918, License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 52022-03-31031 March 2022 License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 5 NL-22-0220, Units 1 and 2 - Nuclear Property Insurance Coverage as of April 1, 20222022-03-28028 March 2022 Units 1 and 2 - Nuclear Property Insurance Coverage as of April 1, 2022 NL-22-0221, Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2022-03-28028 March 2022 Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) 2024-01-30
[Table view] Category:Written Event Report (30 or 60 day)
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~ Southern Nuclear E, D. Dean Ill Sile Vice President 11028 Hatch Parkway , orth Bllxlay, OA 31513 Plant Hatch 912.453.5859 tef 912.453.2077 fax May 4, 2022 U.S. Nucleir R.~gul~tory Commls~lon ATTN: Doeum~nt Control Desk Wishlngton, D. C. 20555e0001 Edwin I. H1teh Nuel@~r Pl~f'lt m Unlt 1 T~chnicil Speelfie~tion ~.6.6 ~oit Accident M@nitorifl{;l lflitn.!m@ntition R~p@rt f@r Drvw~ll T~mp~ratura lndlc~tm Inoperable for Gr~at~r than 30 D~ws Ladiis ~nd G~ntl@m@n:
In ~ceordime~ with Edwin I. H~teh Nucl~~r Plint Unit 1 T~ehnic~l Sp~clfications Llml"t!ng e
Cgnditlon for Operii!tlon 3.3.3.1, Reguird Action B.1, Southfglm Nucl~~r Operatln{;l Compiny (SNC) I~ ~ubmittlng thl~ report r~liited to po~t ~eeldent monitoring lnstrum@ntg1tion, This l~tter eont~ins no r~9,.!l~tory eommitm~n~. If you h~ve any qu@stion~, pl~1s@ ~nt1et Jimmy Collins g1-t 912.4@3.2342.
Resp~et-fully submltt~d,
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E. D. D~~fl Site Vi~~ President. Pl~nt H~teh EDD/jmh Ce: R.~9long1! Adminlitr~tor, R.~sion ll NRR Prnjeet Mimg1g~r = H~teh Senior Re§ident lnsp~ctor = Hatch RTVPE: CHA02.004
NL-22-0315 Edwin I. Hatch Nuclear Plant - Unit 1 Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report for Drywell Temperature Indicator Inoperable for Greater than 30 Days Enclosure Post Accident Monitoring Instrumentation Report
Enclosure to NL-22-0315 Post Accident Monitoring Instrumentation Report In accordance with Edwin I. Hatch Nuclear Plant (HNP) Unit 1 Technical Specification (TS) 5.6.6 a report is required to be submitted within 14 days upon entering LCO 3.3.3.1 Condition B. TS 5.6.6 states that the report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the channel to operable status.
Description of Condition On March 30, 2022, while conducting operator rounds, it was noticed a local Drywell Temperature Element (TE), 1T47N003, was reading outside the acceptance criteria.
Subsequently, the related channel was declared inoperable and Condition A of LCO 3.3.3.1, "Post Accident Monitoring Instrumentation" was entered. The Completion Time (CT) of Condition A is 30 days and expired on April 29, 2022. HNP has been unable to return the channel to operable status prior to the Condition A CT and is thus now in LCO Condition B which requires submittal of this report in accordance with TS 5.6.6 within 14 days.
Preplanned Alternate Method of Monitoring There are thirteen TE's in the drywall used to monitor individual temperatures at various levels along with the drywall bulk average temperature. With TE 1T47N003 inoperable, there remain twelve operable TE's that will continue to be monitored, including one, 1T47N009, on the same elevation as 1T47N003. These other TE's are indicating normal, historical temperatures. These TE's are monitored on operator rounds and automatically by recorders in the control room.
Drywall temperatures can be reliably monitored by the other twelve drywell TE's even with 1T47N003 inoperable. Appropriate actions are procedurally captured and will be taken if an increase is noted on any TE.
Cause of lnoperability During operator rounds, TE 1T47N003 was found to be trending up approximately 1-1.5°F per day and eventually failed upscale. All other drywall temperature indications remained stable, including TE 1T47N009 which is on the same elevation as TE 1T47N003. Engineering and l&C performed troubleshooting activities to investigate the cause and to ensure there was not an actual drywall temperature rise. Historical temperature trend data shows that TE 1T47N003 and 1T47N009 have historically tracked each other within an 8-10 degree difference in temperature until TE 1T47N003 recently began to deviate from TE 1T47N009. Additionally, drywall wide range radiation monitor recorder data was reviewed to identify if there were any increases in radiation correlated with the perceived increase in temperature which would be indicative of a steam leak. These trends were found to be within normal bands. Considering the above information, it has been determined that the temperature trend seen on TE 1T47N003 only, and not on any other drywall TEs, would not be indicative of a genuine rise in drywell temperature but rather a failed individual TE. Based on this, TE 1T47N003 has failed and is inaccurate.
Plans and Schedule for Restoring the Instrument to Operable TE 1T47N003 is located in the drywell which cannot be accessed while at power. Therefore, TE 1T47N003 cannot be repaired until entry into the drywall can be made. Repair activities will be completed during the H1R31 refueling outage (February 2024). If, however, Unit 1 were to be shut down due to a forced outage prior to H1 R31, this work is in the required work scope. This work will replace or repair TE 1T47N003 and will restore normal drywall temperature monitoring to operable status.
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