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| | issue date = 08/29/2018 | | | issue date = 08/29/2018 |
| | title = Issuance of Amendments to Revise Technical Specification 3.7.7, ECCS - Operating (CAC Nos. MF9997 and MF9998; EPID L-2017-LLA-0263) | | | title = Issuance of Amendments to Revise Technical Specification 3.7.7, ECCS - Operating (CAC Nos. MF9997 and MF9998; EPID L-2017-LLA-0263) |
| | author name = Hall J R | | | author name = Hall J |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Gayheart C A | | | addressee name = Gayheart C |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000321, 05000366 | | | docket = 05000321, 05000366 |
| | license number = DPR-057, NPF-005 | | | license number = DPR-057, NPF-005 |
| | contact person = Hall J R | | | contact person = Hall J |
| | case reference number = CAC MF9997, CAC MF9998, EPID L-2017-LLA-0263 | | | case reference number = CAC MF9997, CAC MF9998, EPID L-2017-LLA-0263 |
| | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation, Technical Specifications | | | document type = Letter, License-Operating (New/Renewal/Amendments) DKT 50, Safety Evaluation, Technical Specifications |
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| -----------------------------------------------------------NOTE------------------------------------------------------------ | | -----------------------------------------------------------NOTE------------------------------------------------------------ |
| Not required to be met when the Main Turbine Bypass System is not required to be OPERABLE SR 3.7.7.1 SR 3.7.7.2 HATCH UNIT2 SURVEILLANCE Verify one complete cycle of each main turbine bypass valve. Perform a system functional test. 3.7-18 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued) | | Not required to be met when the Main Turbine Bypass System is not required to be OPERABLE SR 3.7.7.1 SR 3.7.7.2 HATCH UNIT2 SURVEILLANCE Verify one complete cycle of each main turbine bypass valve. Perform a system functional test. 3.7-18 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued) |
| Amendment No. 2 3 7 1.0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 292 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 237 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY, INC. EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-321 AND 50-366 INTRODUCTION By application dated July 10, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 171918163), Southern Nuclear Operating Company, Inc. (SNC, the licensee) requested changes to the Technical Specifications (TSs) for the Edwin I. Hatch Nuclear Plant (HNP), Unit Nos. 1 and 2. The proposed changes would: (1) add a Note to the Surveillance Requirements (SRs) of TS 3.7.7, "Main Turbine Bypass System" clarifying that the SRs are not required to be met when the Limiting Condition for Operation (LCO) does not require the Main Turbine Bypass System (TBS) to be OPERABLE, (2) clarify that LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," also has limits for an inoperable TBS that are made applicable as specified in the Core Operating Limits Report (COLR), and (3) delete an outdated footnote for LCO 3.2.3. | | Amendment No. 2 3 7 1.0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 292 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 237 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY, INC. EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-321 AND 50-366 INTRODUCTION By application dated July 10, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML171918163), Southern Nuclear Operating Company, Inc. (SNC, the licensee) requested changes to the Technical Specifications (TSs) for the Edwin I. Hatch Nuclear Plant (HNP), Unit Nos. 1 and 2. The proposed changes would: (1) add a Note to the Surveillance Requirements (SRs) of TS 3.7.7, "Main Turbine Bypass System" clarifying that the SRs are not required to be met when the Limiting Condition for Operation (LCO) does not require the Main Turbine Bypass System (TBS) to be OPERABLE, (2) clarify that LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," also has limits for an inoperable TBS that are made applicable as specified in the Core Operating Limits Report (COLR), and (3) delete an outdated footnote for LCO 3.2.3. |
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| ==2.0 REGULATORY EVALUATION== | | ==2.0 REGULATORY EVALUATION== |
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| EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS TO REVISE TECHNICAL SPECIFICATION 3.7.7, "MAIN TURBINE BYPASS SYSTEM" (CAC NOS. MF9997 AND MF9998; EPID L-2017-LLA-0263) | | EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS TO REVISE TECHNICAL SPECIFICATION 3.7.7, "MAIN TURBINE BYPASS SYSTEM" (CAC NOS. MF9997 AND MF9998; EPID L-2017-LLA-0263) |
| DATED AUGUST 29, 2018 DISTRIBUTION: | | DATED AUGUST 29, 2018 DISTRIBUTION: |
| PUBLIC RidsNrrDssSrxb Resource RidsACRS_MailCTR Resource RidsNrrDorlLp12-1 Resource RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrLAKGoldstein Resource RidsNrrPMHatch Resource RidsRgn2Mail Center Resource FForsaty, NRR ADAMS Accession No. ML 18222A296 | | PUBLIC RidsNrrDssSrxb Resource RidsACRS_MailCTR Resource RidsNrrDorlLp12-1 Resource RidsNrrDssStsb Resource RidsNrrLAJBurkhardt Resource RidsNrrLAKGoldstein Resource RidsNrrPMHatch Resource RidsRgn2Mail Center Resource FForsaty, NRR ADAMS Accession No. ML18222A296 |
| *via memorandum | | *via memorandum |
| **via e-mail OFFICE NRR/DORL/LPL2-1 | | **via e-mail OFFICE NRR/DORL/LPL2-1 |
Letter Sequence Approval |
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MONTHYEARML17191B1632017-07-10010 July 2017 Request for Addition of Surveillance Requirements Note for LCO 3.7.7 Project stage: Request ML17230A1042017-08-18018 August 2017 NRR E-mail Capture - Hatch Nuclear Plant, Units 1 and 2 - Acceptance of Amendment Request Regarding TS 3.7.7 Main Turbine Bypass System Project stage: Acceptance Review ML18222A2962018-08-29029 August 2018 Issuance of Amendments to Revise Technical Specification 3.7.7, ECCS - Operating (CAC Nos. MF9997 and MF9998; EPID L-2017-LLA-0263) Project stage: Approval 2017-08-18
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MF9590 and MF9591; EPID L-2017-LLA-0216) ML17271A3072017-11-30030 November 2017 Issuance of Amendments to Revise Actions of TS 5.5.12, Primary Containment Leakage Rate Testing Program ML17208A2312017-08-29029 August 2017 Issuance of Amendments Regarding the Adoption of TSTF 500, DC Electrical Rewrite - Update to TSTF 360 ML17152A2182017-06-30030 June 2017 Southern Nuclear Fleet - Issuance of Amendments Regarding the Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing (CAC Nos. MF8176 - MF8181) ML17137A0412017-06-27027 June 2017 Issuance of Amendments Regarding the Adoption of TSTF-529, Revision 4, Clarify Use and Application Rules (CAC Nos. MF8897, MF8898, MF8900-MF8902, and MF8921) ML17023A2372017-03-16016 March 2017 Issuance of Amendments Regarding the Adoption of NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors(Cac Nos. MF7460-MF7465) ML16141A1472017-03-14014 March 2017 Issuance of Amendments to Incorporate Southern Nuclear Company Fleet Emergency Plan ML16291A0302017-01-13013 January 2017 Issuance of Amendments the Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions (CAC Nos. MF7466, MF7467, MF7468, MF7469, MF7470, & MF7471) 2023-03-03
[Table view] Category:Safety Evaluation
MONTHYEARML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23034A2462023-02-21021 February 2023 Audit Summary for License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML22363A3932023-02-15015 February 2023 Issuance of Amendments Nos. 321 and 266, Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program ML22346A1482023-02-0909 February 2023 Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10 ML22297A1462022-12-22022 December 2022 Issuance of Amendments Nos. 319 and 264, Regarding Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times RITS ML22293A0302022-11-0707 November 2022 Amendments 318 & 263 Issuance, Regarding LAR to Adopt TSTF-227, Revision to EOC-RPT Pump Actions, and TSTF-297, ATWS-RPT (EPID L-2021-LLA- 0227) ML22192A1172022-09-0202 September 2022 Issuance of Amendments Nos. 317 & 262, Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates ML22192A1992022-08-19019 August 2022 Issuance of Amendments Nos. 316 and 261, Regarding Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML22101A0942022-05-20020 May 2022 Issuance of Amendments Nos. 315 and 260, Regarding Request to Eliminate Automatic Main Steam Line Isolation on High Turbine Building Area Temperature ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls ML21264A6442021-09-24024 September 2021 Issuance of Amendment to Revise Technical Specification 3.7.2, Plant Service Water (Psw) System and Ultimate Heat Sink (UHS) (EPID L-2021-LLA-0164) (Emergency Circumstances) ML21217A0912021-09-21021 September 2021 SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21167A3152021-07-30030 July 2021 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position ML21161A2012021-06-22022 June 2021 Associated Independent Spent Fuel Storage Facilities - Reduction in Commitment to the Quality ML21109A3592021-04-22022 April 2021 Issuance of Amendment No. 254, Regarding Revision to Technical Specifications for One-Time Extension of Completion Times Related to Residual Heat Removal System (Emergency Circumstances) ML20294A0762020-12-0707 December 2020 Issuance of Amendments Nos. 308 and 253, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements ML20254A0752020-09-18018 September 2020 Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 307 to Facility Operating License No. DPR-57 and Amendment No. 252 to Facility Operating License No. NPF-5 ML20202A0052020-09-15015 September 2020 Issuance of Amendments Nos. 306 and 251, Regarding the Application to Revise Technical Specifications to Adopt TSTF-568, Revise Appliciability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20077J7042020-06-26026 June 2020 Issuance of Amendment Nos. 305 and 250, Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML20066F5922020-06-11011 June 2020 Issuance of Amendments Nos. 304 and 249, Regarding License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) ML20143A2332020-06-0303 June 2020 Relief Request for Deferral of ASME Boiler and Pressure Vessel Code, Section XI, Required Summary Report Submittal (EPID L-2020-LLR-0074 (COVID-19)) ML20034E8942020-02-11011 February 2020 Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19239A2442019-11-19019 November 2019 Issuance of Amendments Regarding Revision to Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations ML19267A0232019-11-13013 November 2019 Issuance of Amendments the Revision to Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable (Residual Heat Removal) RHR Shutdown Cooling Subsystems, Using Consolidated Line Item Improvement Process ML19212A0542019-09-20020 September 2019 Issuance of Amendments 299 and 244 Regarding Revision to Technical Specifications to Adopt Tstf-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML19198A1042019-09-0404 September 2019 Issuance of Amendments Regarding Revision to Technical Specification 3.6.4.1 - Secondary Containment ML19177A1662019-07-0808 July 2019 Edwin Hatch Unit Nos. 1 and 2, Issuance of Amendments Regarding License Amendment Request to Correct Non-Conservative Technical Specification Allowable Values for the Condensate Storage Tank Low Level Transfer Function ML19091A2912019-04-30030 April 2019 Issuance of Amendments 296 and 241 to Revise Technical Specifications 3.6.2.5, Condition C, Residual Heat Removal Drywell Spray End State ML19064A7742019-04-26026 April 2019 Issuance of Amendments Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum on Shift Staff Tables ML19044A5552019-04-0303 April 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 ML19064A0872019-03-0808 March 2019 Proposed Inservice Inspection Alternative HNP-ISI-ALT-05-08 ML19053A0932019-02-22022 February 2019 Issuance of Amendments to Revise Technical Specification 3.8.1, AC Sources - Operating (EPID L-2019-LLA-0026) (Emergency Circumstances) ML19035A5502019-02-0606 February 2019 Relief Request HNP ISI RR 05-02 Regarding Reactor Pressure Vessel Head Stud Inservice Inspection Requirements ML19010A0092019-01-28028 January 2019 Issuance of Amendments to Revise Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation ML19011A0102019-01-22022 January 2019 Proposed Alternative HNP-ISI-ALT-05-04 for the Implementation of BWRVIP Guidelines ML18320A0572018-11-30030 November 2018 Plant, Units 1 and 2 - Proposed Inservice Inspection Alternative GEN-ISI-ALT-2017-03, Code Case N-513-4 for Moderate Pressure ML18289A6192018-10-18018 October 2018 Proposed Inservice Inspection Alternative HNP-ISI-ALT-05-07 ML18222A2962018-08-29029 August 2018 Issuance of Amendments to Revise Technical Specification 3.7.7, ECCS - Operating (CAC Nos. MF9997 and MF9998; EPID L-2017-LLA-0263) ML18183A0732018-07-26026 July 2018 Unites 1, 2, 3, and 4; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2(CAC Nos. MG0188, MG0189, MG0191, MG0192, MG0193, MG0194, and MG0195; EPID L-2017-LLA-0293) ML18163A1602018-06-15015 June 2018 Proposed Alternative RR-V-11, Extension of Main Steam Safety Relief Valve Test Interval ML18123A3682018-05-31031 May 2018 Issuance of Amendments to Adopt TSTF-542, RPV Water Inventory Control (CAC Nos. MF9662 and MF9663; EPID L-2017-LLA-0215) ML18102B0162018-04-16016 April 2018 Proposed Inservice Inspection Alternative HNP-ISI-ALT-05-05 (CAC Nos. MF9812 and MF9813; EPID L-2017-LLR-0053) ML18022A1072018-01-25025 January 2018 Inservice Inspection Alternative GEN-ISI-ALT-2017-02, Version 1.0, Regarding the Use of ASME Code Case N-789-1 (CAC Nos. MF9942, MF9943, MF9944, and MF9945; EPID L-2017-LLR-0059) ML17355A4402018-01-22022 January 2018 Issuance of Amendments to Revise TS 3.6.4.1, Secondary Containment (CAC Nos. MF9590 and MF9591; EPID L-2017-LLA-0216) ML17271A3072017-11-30030 November 2017 Issuance of Amendments to Revise Actions of TS 5.5.12, Primary Containment Leakage Rate Testing Program ML17279A0452017-10-26026 October 2017 Relief Requests ISI-RR-13, -14, -18, -19, -23, and -24 for Relief from Inservice Inspection Requirements ML17268A0442017-10-20020 October 2017 Relief Requests ISI RR 16, ISI-RR-17, ISI-44-21, and ISI-RR-22 for Relief from Inservice Inspection Requirements ML17208A2312017-08-29029 August 2017 Issuance of Amendments Regarding the Adoption of TSTF 500, DC Electrical Rewrite - Update to TSTF 360 2023-08-02
[Table view] Category:Technical Specifications
MONTHYEARML24069A0012024-03-0909 March 2024 – Correction of Amendment No. 266 Regarding License Amendment Request Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program (TSTF-425, Revision 3) NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024 Correction of Technical Specification Omission ML22346A1482023-02-0909 February 2023 Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10 ML23018A0042023-01-24024 January 2023 Correction of Amendment Nos. 319 and 264 Regarding Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF ML22192A1992022-08-19019 August 2022 Issuance of Amendments Nos. 316 and 261, Regarding Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML22101A0942022-05-20020 May 2022 Issuance of Amendments Nos. 315 and 260, Regarding Request to Eliminate Automatic Main Steam Line Isolation on High Turbine Building Area Temperature 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. ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls NL-21-0385, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-09-29029 September 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML21109A3592021-04-22022 April 2021 Issuance of Amendment No. 254, Regarding Revision to Technical Specifications for One-Time Extension of Completion Times Related to Residual Heat Removal System (Emergency Circumstances) ML20303A1812020-09-29029 September 2020 Rev. 117 to Technical Requirement Manual, Unit 1, Part 2 NL-20-1000, Responses to NRC Requests for Additional Information to License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time2020-08-23023 August 2020 Responses to NRC Requests for Additional Information to License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time NL-20-0793, Correction of Technical Specification Typographical Error2020-07-0202 July 2020 Correction of Technical Specification Typographical Error ML20066F5922020-06-11011 June 2020 Issuance of Amendments Nos. 304 and 249, Regarding License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19212A0542019-09-20020 September 2019 Issuance of Amendments 299 and 244 Regarding Revision to Technical Specifications to Adopt Tstf-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML19198A1042019-09-0404 September 2019 Issuance of Amendments Regarding Revision to Technical Specification 3.6.4.1 - Secondary Containment ML19164A0172019-06-21021 June 2019 Correction of Amendment No. 223 Multiple Technical Specification Changes (CAC Nos. MF5026 and MF5027) ML19091A2912019-04-30030 April 2019 Issuance of Amendments 296 and 241 to Revise Technical Specifications 3.6.2.5, Condition C, Residual Heat Removal Drywell Spray End State ML18222A2962018-08-29029 August 2018 Issuance of Amendments to Revise Technical Specification 3.7.7, ECCS - Operating (CAC Nos. MF9997 and MF9998; EPID L-2017-LLA-0263) NL-16-1617, Request for Addition of Surveillance Requirements Note for LCO 3.7.7 (NL-16-1617)2017-07-10010 July 2017 Request for Addition of Surveillance Requirements Note for LCO 3.7.7 (NL-16-1617) NL-17-0810, Transmittal of Marked-Up and Clean Technical Specifications Pages for Section 5.5.15 for HNP Implementation of TSTF-500, DC Electrical Rewrite.2017-05-11011 May 2017 Transmittal of Marked-Up and Clean Technical Specifications Pages for Section 5.5.15 for HNP Implementation of TSTF-500, DC Electrical Rewrite. NL-17-0841, Correction of Technical Specification Typographical Error2017-05-10010 May 2017 Correction of Technical Specification Typographical Error ML17076A4342017-03-23023 March 2017 TSTF-542 Marked-Up Technical Specifications and Bases for Hatch Nuclear Plant NL-16-2013, Transmittal of Revised Technical Specification Pages2016-10-26026 October 2016 Transmittal of Revised Technical Specification Pages NL-16-1564, Revised Technical Specifications Pages for Technical Specifications Revision Request to Implement TSTF-500, DC Electrical Re-Write.2016-09-20020 September 2016 Revised Technical Specifications Pages for Technical Specifications Revision Request to Implement TSTF-500, DC Electrical Re-Write. NL-16-1571, Supplemental Response Regarding Request to Adopt TSTF-222, Control Rod Scram Times2016-08-26026 August 2016 Supplemental Response Regarding Request to Adopt TSTF-222, Control Rod Scram Times ML16090A1742016-04-14014 April 2016 Issuance of Amendments Regarding Managing Gas Accumulation ML16062A0992016-03-23023 March 2016 Issuance of Amendments Regarding the Relocation of the Pressure Temperature Limit Curves Following TSTF-419 NL-15-1956, Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions2016-03-14014 March 2016 Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions ML16043A1012016-03-0707 March 2016 Edwin I Hatch Nuclear Plant, Unit Nos. 1 and 2, Issuance of Amendments Regarding Typographical Errors in the Facility Operating License and Technical Specifications (CAC Nos. MF6580 and MF6581) ML15342A3982016-01-29029 January 2016 Issuance of Amendment Regarding Minimum Critical Power Ratio NL-14-1075, Technical Specifications. Part 4 of 42015-12-15015 December 2015 Technical Specifications. Part 4 of 4 NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 3 of 42015-12-15015 December 2015 E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 3 of 4 ML15350A4112015-12-15015 December 2015 Technical Specifications. Part 3 of 4 ML15350A4102015-12-15015 December 2015 Technical Specifications. Part 2 of 4 ML15350A4092015-12-15015 December 2015 License Amendment Request for Adoption of TSTF-423-A, Rev. 1, Technical Specification End States, NEDC-32988-A, Using the Consolidated Line Item Improvement Process. Part 1 of 4 NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 42015-12-15015 December 2015 E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 4 NL-15-1881, Revised Technical Specification Page for Primary Containment Isolation Instrumentation2015-10-15015 October 2015 Revised Technical Specification Page for Primary Containment Isolation Instrumentation NL-15-1535, GNF-002N9964-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Hatch 1 Cycle 282015-08-31031 August 2015 GNF-002N9964-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Hatch 1 Cycle 28 NL-15-0407, Request to Revise Typographical Error in Unit 1 Operating License and in Unit 2 Technical Specifications, and to Add Staggered Test Basis to Unit 1 and Unit 2 Technical Specifications2015-08-0404 August 2015 Request to Revise Typographical Error in Unit 1 Operating License and in Unit 2 Technical Specifications, and to Add Staggered Test Basis to Unit 1 and Unit 2 Technical Specifications ML15180A3342015-08-0303 August 2015 Issuance of Amendments ML15054A4002015-02-24024 February 2015 (HNP-2), Correction for Amendments Regarding Reactor Core Safety Limits ML14349A7152014-12-23023 December 2014 Edwin I Hatch Nuclear Plant, Unit Nos. 1 and 2, Issuance of Amendments Regarding a Critical Instrumentation Bus ML14328A3232014-12-16016 December 2014 Edwin I Hatch Nuclear Plant, Unit Nos. 1 and 2, Issuance of Amendments for Degraded Voltage Protection Modification Schedule ML14279A2612014-12-10010 December 2014 Issuance of Amendments Regarding the Control Room Air Conditioning System ML14147A4102014-08-29029 August 2014 Issuance of Amendments Regarding Control Room Habitability NL-13-1751, Application to Revise Tech Specs to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs.2014-03-17017 March 2014 Application to Revise Tech Specs to Adopt TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs. NL-12-1078, Edwin I. Hatch, Units 1 and 2, License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well2012-07-0505 July 2012 Edwin I. Hatch, Units 1 and 2, License Amendment Request to Revise the Minimum Water Level in the Plant Service Water Pump Well 2024-03-09
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION Ms. Cheryl A. Gayheart Regulatory Affairs Director WASHINGTON, D.C. 20555-0001 August 29, 2018 Southern Nuclear Operating Company, Inc. P. 0. Box 1295, Bin 038 Birmingham, AL 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS TO REVISE TECHNICAL SPECIFICATION 3.7.7, "ECCS -OPERATING" (CAC NOS. MF9997 AND MF9998; EPID L-2017-LLA-0263)
Dear Ms. Gayheart:
The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 292 to Renewed Facility Operating License No. DPR-57 and Amendment No. 237 to Renewed Facility Operating License No. NPF-5 for the Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (HNP), respectively.
The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated July 10, 2017. The amendments revise the TSs by: (1) adding a Note to the Surveillance Requirements (SRs) of TS 3. 7. 7 to clarify that the SRs are not required to be met when the Limiting Condition for Operation (LCO) does not require the Main Turbine Bypass System to be operable; (2) clarifying that LCO 3.2.3, "LINEAR HEAT GENERATION RATE," also has limits for an inoperable Main Turbine Bypass System that are made applicable as specified in the Core Operating Limits Report; and (3) deleting an outdated footnote for LCO 3.2.3.
C. A Gayheart A copy of the related Safety Evaluation is also enclosed.
A Notice of Issuance will be included in the Commission's biweekly Federal Register notice. Docket Nos. 50-321 and 50-366
Enclosures:
- 1. Amendment No. 292 to DPR-57 2. Amendment No. 237 to NPF-5 3. Safety Evaluation cc: Listserv Sincerely, a' /) ;r ~c LW-f~. JRM J R. Hall, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC. GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DAL TON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 292 Renewed License No. DPR-57 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit No. 1 (the facility)
Renewed Facility Operating License No. DPR-57 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated July 10, 2017, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1 2. Accordingly, the license is hereby amended by page changes as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-57 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 292, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.
Attachment:
Changes to Renewed Facility Operating License No. DPR-57 and Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION
~-;.~ Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance:
August 29, 2018 ATTACHMENT TO LICENSE AMENDMENT NO. 292 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the license and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove Pages Insert Pages License License 4 4 TSs TSs 3.2-4 3.2-4 3.7-18 3.7-18 for sample analysis or instrumentation calibration, or associated with radioactive apparatus or components; (6) Southern Nuclear, pursuant to the Act and 1 O CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions specified or incorporated below: ( 1) Maximum Power Level Southern Nuclear is authorized to operate the facility at steady state reactor core power levels not in excess of 2804 megawatts thermal. (2) Technical Specifications (3) The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 292, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. The Surveillance Requirement (SR) contained in the Technical Specifications and listed below, is not required to be performed immediately upon implementation of Amendment No. 195. The SR listed below shall be successfully demonstrated before the time and condition specified:
SR 3.8.1.18 shall be successfully demonstrated at its next regularly scheduled performance.
Fire Protection Southern Nuclear shall implement and maintain in effect all provisions of the fire protection program, which is referenced in the Updated Final Safety Analysis Report for the facility, as contained in the updated Fire Hazards Analysis and Fire Protection Program for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, which was originally submitted by letter dated July 22, 1986. Southern Nuclear may make changes to the fire protection program without prior Commission approval only if the changes Renewed License No. DPR-57 Amendment No. 292 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) LHGR 3.2.3 LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR. APPLICABILITY:
THERMAL POWER~ 24% RTP. ACTIONS CONDITION REQUIRED ACTION A. Any LHGR not within limits. A.1 Restore LHGR(s) to within limits. 8. Required Action and 8.1 Reduce THERMAL associated Completion POWER to< 24% ATP. Time not met. SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.2.3.1 HATCH UNIT 1 Verify all LHGRs are less than or equal to the limits specified in the COLA. 3.2-4 COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4 hours FREQUENCY Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after .!: 24% RTP In accordance with the Surveillance Frequency Control Program Amendment No. 2 9 2 Main Turbine Bypass System 3.7.7 3. 7 PLANT SYSTEMS
ACTIONS The Main Turbine Bypass System shall be OPERABLE.
OR LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," and LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR, are made applicable.
THERMAL POWER.:: 24% RTP. CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not met. of the LCO. B. Required Action and 8.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< 24% ATP. Time not met. SURVEILLANCE REQUIREMENTS
NOTE------------------------------------------------------------
Not required to be met when the Main Turbine Bypass System is not required to be OPERABLE SR 3.7.7.1 SR 3.7.7.2 SR 3.7.7.3 HATCH UNIT 1 SURVEILLANCE Verify one complete cycle of each main turbine bypass valve. Perform a system functional test. Verify the TURBINE BYPASS SYSTEM RESPONSE TIME is within limits. 3.7-18 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 2 9 2 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC. GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DAL TON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 237 Renewed License No. NPF-5 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit No. 2 (the facility)
Renewed Facility Operating License No. NPF-5 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated July 10, 2017, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 2 2. Accordingly, the license is hereby amended by page changes as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-5 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 237, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days from its date of issuance.
Attachment:
Changes to Renewed Facility Operating License No. NPF-5 and Technical Specifications Date of Issuance:
August 29, 2018 FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation ATTACHMENT TO LICENSE AMENDMENT NO. 237 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the license and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. Remove Pages Insert Pages License License 4 4 TSs TSs 3.2-4 3.2-4 3.7-18 3.7-18 (6) Southern Nuclear, pursuant to the Act and 1 O CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This renewed license shall be deemed to contain, and is subject to, the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions 2 specified or incorporated below: ( 1) Maximum Power Level Southern Nuclear is authorized to operate the facility at steady state reactor core power levels not in excess of 2,804 megawatts thermal, in accordance with the conditions specified herein. (2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 237, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. (3) Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the renewed license or within the operational restrictions indicated.
The removal of these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission. (a) Fire Protection Southern Nuclear shall implement and maintain in effect all provisions of the fire protection program, which is referenced in the Updated Final Safety Analysis Report for the facility, as contained 2 The original licensee authorized to possess, use, and operate the facility with Georgia Power Company (GPC). Consequently, certain historical references to GPC remain in certain license conditions.
Renewed License No. NPF-5 Amendment No. 237 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) LHGR 3.2.3 LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLA. APPLICABILITY:
THERMAL POWER<!: 24% ATP. ACTIONS CONDITION REQUIRED ACTION A. Any LHGR not within limits. A.1 Restore LHGR(s) to within limits. B. Required Action and B.1 Reduce THERMAL associated Completion POWER to< 24% RTP. Time not met. SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.2.3.1 HATCH UNIT 2 Verify all LHGRs are less than or equal to the limits specified in the COLA. 3.2-4 COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4 hours FREQUENCY Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after .::: 24% RTP In accordance with the Surveillance Frequency Control Program Amendment No. 2 3 7 Main Turbine Bypass System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Main Turbine Bypass System LCO 3.7.7 APPLICABILITY:
ACTIONS The Main Turbine Bypass System shall be OPERABLE.
OR LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," and LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLA, are made applicable.
THERMAL POWER 2: 24% RTP. CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not met. of the LCO. B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion POWER to< 24% ATP. Time not met. SURVEILLANCE REQUIREMENTS
NOTE------------------------------------------------------------
Not required to be met when the Main Turbine Bypass System is not required to be OPERABLE SR 3.7.7.1 SR 3.7.7.2 HATCH UNIT2 SURVEILLANCE Verify one complete cycle of each main turbine bypass valve. Perform a system functional test. 3.7-18 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
Amendment No. 2 3 7 1.0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 292 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 237 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY, INC. EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-321 AND 50-366 INTRODUCTION By application dated July 10, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML171918163), Southern Nuclear Operating Company, Inc. (SNC, the licensee) requested changes to the Technical Specifications (TSs) for the Edwin I. Hatch Nuclear Plant (HNP), Unit Nos. 1 and 2. The proposed changes would: (1) add a Note to the Surveillance Requirements (SRs) of TS 3.7.7, "Main Turbine Bypass System" clarifying that the SRs are not required to be met when the Limiting Condition for Operation (LCO) does not require the Main Turbine Bypass System (TBS) to be OPERABLE, (2) clarify that LCO 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," also has limits for an inoperable TBS that are made applicable as specified in the Core Operating Limits Report (COLR), and (3) delete an outdated footnote for LCO 3.2.3.
2.0 REGULATORY EVALUATION
2.1 Applicable Requirements and Guidance The U.S. Nuclear Regulatory Commission (NRC) staff considered the following regulatory requirements and guidance documents in its review of the proposed amendment:
- Title 10 of the Code of Federal Regulations (10 CFR) 50.36, "Technical Specifications," which details the content and information that must be included in a station's TS. In accordance with 10 CFR 50.36, TSs are required to include ( 1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.
As stated in 10 CFR 50.36(c)(2), limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility.
When a limiting condition for operation of a nuclear reactor is not met, the licensee shall Enclosure 3 shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met. As stated in 10 CFR 50.36(c)(3), surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. 2.2 System Design and Operation Main Turbine Bypass System (TBS) The TBS provides operational flexibility to dissipate a portion of the energy of the main steam exiting the reactor in order to reduce the steam load on the turbine during certain plant evolutions.
These include reactor heatup and cooldown, evolutions where the turbine is brought up to speed and synchronized with the generator, and during power operation when the reactor system steam generation could exceed turbine limitations.
The TBS removes this excess energy by discharging a percentage of rated main steam flow directly to the main condensers, bypassing the turbine. This heat is rejected to the condenser through three bypass (regulating) valves mounted on a valve manifold.
The bypass capacity of the TBS at HNP is around 20 percent of the Nuclear Steam Supply System rated steam flow for both Units 1 and 2. The TBS is not a safety system, because it is not required for safe shutdown.
However, the TBS is assumed to function during events crediting the system (e.g., feedwater controller failure -maximum demand) as discussed in Chapter 15 of the HNP Final Safety Analysis Report (FSAR). Opening the bypass valves during pressurization events mitigates the increase in reactor vessel pressure and affects the minimum critical power ratio (MCPR) and the linear heat generation rate (LHGR). When the TBS is inoperable, more restrictive limits for these values are applied, to maintain the assumptions in the FSAR Chapter 15 analyses.
3.0 TECHNICAL EVALUATION TS 3.7.7 LCO Current HNP TS 3.7.7 provides the requirements for the TBS. LCO 3.7.7 is applicable when THERMAL POWER (defined in the TSs as the total reactor core heat transfer rate to the reactor coolant) is greater than or equal to 24 percent of RATED THERMAL POWER (RTP). The LCO 3.7.7 requirements can be met in two ways; either the Main Turbine Bypass System shall be OPERABLE, or LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR, must be applied. Similar to TS 3.2.2 for MCPR, TS 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)," requires that the limits specified in the COLR for LHGRs also must be met when THERMAL POWER is greater than or equal to 24 percent RTP. The Applicability, Conditions, Required Actions, and associated Completion Times for LCOs 3.2.2, 3.2.3, and 3.7.7 are the same. All three LCOs allow two hours to satisfy the requirements of the LCO if it is not met, and then four hours thereafter to reduce THERMAL POWER to less than 24 percent RTP. The licensee proposes to modify LCO 3.7.7 to add the provision that LCO 3.2.3 limits on LHGR for an inoperable Main Turbine Bypass System, as specified in the COLR, are made applicable, similar to the existing provision regarding MCPR limits. This change clarifies that the requirements of LCO 3.2.3 also apply when considering whether LCO 3.7.7 requirements are met, when the TBS is inoperable and THERMAL POWER is greater than or equal to 24 percent RTP. The NRC staff also notes that this change is consistent with NUREG-1433, Standard Technical Specifications, General Electric BWR/4 Plants, Revision 4.0, April 2012. The NRC staff considers this to be an editorial change that clarifies the existing HNP TS requirements, and finds it acceptable.
TS 3.7.7 SR Note The proposed change to add a Note to TS 3.7.7, would clarify that the SRs are not required to be met when the LCO does not require the TBS to be operable.
The TS 3.7.7 SRs require testing of the main turbine bypass valves and the system itself, and thus are intended to demonstrate that the TBS is operable.
However, as written, the SRs could be considered to be applicable even in cases where the TBS is not required to be operable, or is inoperable, when LCO 3.7.7 is met by applying the more restrictive thermal limits of LCOs 3.2.2 and 3.2.3. The NRC staff agrees that the existing TS 3.7.7 SRs do not apply when LCO 3.7.7 is met by applying the more restrictive thermal limits of LCOs 3.2.2 and 3.2.3 for an inoperable TBS. These more restrictive limits ensure that the assumptions in the FSAR Chapter 15 analyses will be met without reliance on the TBS. The proposed Note would clarify that the SRs do not apply when the TBS is not required to be operable and would thus remove any existing ambiguity regarding their applicability.
Therefore, the NRC staff finds the proposed change acceptable.
TS 3.2.3 Footnote Both HNP Units 1 and 2 have an outdated footnote for TS 3.2.3, "LINEAR HEAT GENERATION RATE (LHGR)." The footnotes cite the respective operating cycles for which the current TS requirements became effective.
Because these dates have passed, the deletions of the respective footnotes have no meaningful impact. Therefore, the NRC staff finds this change acceptable.
Technical Evaluation Conclusion The NRC staff evaluated the license amendment request and determined that the proposed changes are primarily editorial in nature and that the applicable regulatory requirements will continue to be met. Therefore, the NRC staff concludes that the proposed changes are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Georgia State official was notified of the proposed issuance of the amendments on August 15, 2018 and the State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION The amendments change requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements.
The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on November 21, 2017 (82 FR 55412). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. Principal Contributor:
Fred Forsaty, NRR Da~: August 29, 2018 C. A Gayheart
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 -ISSUANCE OF AMENDMENTS TO REVISE TECHNICAL SPECIFICATION 3.7.7, "MAIN TURBINE BYPASS SYSTEM" (CAC NOS. MF9997 AND MF9998; EPID L-2017-LLA-0263)
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