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Category:Letter
MONTHYEARIR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 ML23090A2302023-03-31031 March 2023 NRC Decommissioning Funding Status Report PLA-8049 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) ML23095A0572023-03-29029 March 2023 NRC Decommissioning Funding Status Report December 31, 2022 PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 2024-02-07
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23334A1502023-11-30030 November 2023 NRC Request for Additional Information Re. Susquehanna Relief Request RR-02 ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information ML23013A2082023-01-13013 January 2023 Request for Additional Information ML22146A1022022-05-26026 May 2022 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000387/2022404 and 05000388/2022404 ML22146A0742022-05-25025 May 2022 NRR E-mail Capture - NRC Request for Additional Information - Susquehanna License Amendment Request ML22111A3132022-04-21021 April 2022 NRR E-mail Capture - NRC Request for Additional Information - Susquehanna License Amendment Request ML22041A1562022-02-10010 February 2022 Information Request for a Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000387/2022013 and 05000388/2022013 ML21316A1242021-11-18018 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Emergency Core Cooling Technical Specifications ML20056E4392020-02-21021 February 2020 Ti 2515/194 Inspection Documentation Request ML20010D2012020-01-0909 January 2020 Request for Additional Information Related to Request to Allow Application of Framatome Analysis Methodologies Necessary to Support a Planned Transition to Atrium 11 Fuel Under Maximum ML19319B1922019-11-14014 November 2019 NRR E-mail Capture - RAI for Susquehanna, 1 and 2 License Amendment Request - Replace the Emergency Service Water System and Residual Heat Removal Service Water System ML19319A0092019-11-14014 November 2019 NRR E-mail Capture - Draft RAI for SSES Units 1 and 2 LAR to Replace ESW Piping ML19128A0232019-05-0707 May 2019 Request for Additional Information: Susquehanna Steam Electric Station, Units 1 and 2 License Amendment Request for ESW Piping Replacement ML18352B1832018-12-13013 December 2018 Enclosurequest for Additional Information (Letter to K. Cimorelli Request for Additional Information Regarding Susquehanna Nuclear, Llc'S Decommissioning Funding Plan Update for Susquehanna Steam Electric Station Independent Spent Fuel Stor ML17180A2002017-07-0707 July 2017 Request for Additional Information Regarding License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage and Frequency Limits ML17059D2142017-03-0606 March 2017 Susquehanna Steam Electric Station - Supplemental Information Needed for Acceptance of Requested Licensing Action Re: License Amendment Request to Revise Diesel Generator Surveillance Requirements with New Steady State Voltage Frequency Limits ML16251A0652016-09-0909 September 2016 Susquehanna Steam Electric Station, Unit 2 - RAI Regarding Temporary Change of Unit 2, Technical Specifications 3.7.1 & 3.8.7 to Allow Replacement of Unit 1, 480 Volt Engineered Safeguard System Load Center Transformers(CAC No. MF7298) ML16245A2052016-09-0101 September 2016 Draft Request for Additional Information Replacement of Load Center Transformers ML16243A0952016-08-30030 August 2016 Draft Request for Additional Information Application for Approval of Indirect Transfer of Control of Licenses ML16060A2302016-03-24024 March 2016 Acceptance of Requested Licensing Action License Amendment Request for Temporary Change of Unit 2 Technical Specifications 3.71 and 3.87 to Allow Replacement of Unit 1 480V Ess Load Center Transformers ML15316A5632015-11-13013 November 2015 Request for Additional Information Regarding Proposed Relief Requests for the Third 10-Year Inservice Inspection Interval(Cac Nos. MF6302 Through MF6307) ML15292A1782015-10-15015 October 2015 TSTF-425 LAR Draft 3rd RAIs ML15230A0802015-08-26026 August 2015 Request for Additional Information Regarding License Amendment Request to Adopt NEI 99-01, Revision 6, EAL Scheme Change ML15209A9742015-08-24024 August 2015 Request for Additional Information License Amendment Request to Adopt Technical Specifications Task Force Traveler (TSTF)-425 ML15229A2002015-08-17017 August 2015 E-mail from J. Whited to J. Jennings SSES Draft TSTF-425 RAIs ML15229A2092015-08-17017 August 2015 SSES Draft Request for Additional Information Licensee Request to Adopt TSTF-425 ML15230A0462015-08-17017 August 2015 Draft RAIs SSES EAL Scheme Change LAR in Accordance with NEI 99-01 Rev 6 ML15183A3502015-07-0202 July 2015 SSES Relief Requests 3RR-19, 3RR-20, and 3RR-21 Draft Identified Information Insufficiencies (TAC Nos. MF6302 Through MF6307) ML15103A3962015-05-22022 May 2015 Request for Additional Information License Amendment Request to Adopt Technical Specifications Task Force Traveler (TSTF)-425 (TAC Nos. MF5151 and MF5152) ML15128A5162015-05-0808 May 2015 SSES Draft Request for Additional Information LAR for Implementation of TSTF-425 ML15128A5092015-05-0808 May 2015 E-mail from J. Whited to D. Filchner SSES Draft Request for Additional Information LAR for Implementation of TSTF-425 ML15008A4702015-01-30030 January 2015 Request for Additional Information Request to Revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits. ML15016A2742015-01-16016 January 2015 Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980) ML15016A2722015-01-16016 January 2015 E-mail from J. Whited to D. Filchner Draft RAIs License Amendment Request for Change to TS 3.4.10 P/T Limits (TAC Nos. MF4597 and MF45980) ML14343A9842015-01-0808 January 2015 Request for Additional Information Relief Request 4RR-01 ML14345A2412014-12-16016 December 2014 Request for Additional Information Request for Order Approving Indirect Transfer of Control and Conforming License Amendments ML14346A1022014-12-12012 December 2014 Draft License Transfer Revised 2nd RAIs ML14346A4022014-12-12012 December 2014 Draft RAIs Relief Request 4RR-01 ML14346A4012014-12-12012 December 2014 E-mail from J. Whited to D. Filchner Susquehanna Steam Electric Station Draft RAIs Relief Request 4RR-01 ML14346A1002014-12-12012 December 2014 E-mail from J. Whited to R. Sgarro Susquehanna Steam Electric Station Draft License Transfer Revised 2nd RAIs ML14342A8082014-12-0808 December 2014 E-mail from J. Whited to R. Sgarro (PPL) SSES Units 1 and 2 Draft RAIs Application for Approval of Indirect Transfer of Control of Licenses ML14342A8132014-12-0808 December 2014 SSES Units 1 and 2 Draft RAIs Application for Approval of Indirect Transfer of Control of Licenses ML14233A2772014-08-27027 August 2014 Request for Additional Information License Amendment Request to Change the Low Pressure Safety Limit ML14233A3392014-08-21021 August 2014 Draft RAIs for Susquehanna Steam Electric Station Units 1 and 2 License Amendment Request for Changes to the Low Pressure Safety Limits ML13298A7582014-03-0707 March 2014 Request for Additional Information Regarding Request for Changes to Technical Specification Surveillance Requirements to Increase Diesel Generator Minimum Steady State Voltage (TAC ME9607 and ME960) ML13298A7812014-03-0707 March 2014 Request for Additional Information Regarding Request for Changes to Technical Specification Surveillance Requirement 3.8.1.19 to Increase Diesel Generator Minimum Steady State Frequency (TACs ME9609. ML14013A1502014-01-31031 January 2014 Request for Additional Information Regarding Relief Requests for the Fourth 10-Year Inservice Testing Interval ML14024A4752014-01-24024 January 2014 Draft 4th IST RRs 1RR05 RAIs ML13338A4422013-12-19019 December 2013 Request for Additional Information Regarding Relief Requests for the Fourth Ten-Year Inservice Inspection Interval ML13312A9142013-12-18018 December 2013 Request for Additional Information Regarding Request for Changes to Technical Specification Surveillance Requirements 3.5.1.12 2023-11-30
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PROPRIETARY INFORMATION
- -;el\'\-L b ML
Dear Mr. Jurek,
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r *. 11 By letter dated July 15, 2019, Talen Energy submitted a license amendment request (LAR} for . ,
Susquehanna Steam Electric Station, Units 1 and 2 (Susquehanna) to allow application of the ~,t.LO-{q_AJ Framatome analysis methodologies necessary to support a planned transition to ATRIUM 11 0I fuel under the currently licensed Maximum Extended Load Line Limit Analysis (MELLLA) llta.. Bo'}l operating domain (Agencywide Documents Access and Management System (ADAMS) ...-< n Accession No. ML19196A270). Dr'\ ..JO~,
The Nuclear Regulatory Commission's (NRC) staff has reviewed your LAR and has detennined that additional information is needed to complete its review. The specific questions are in the attachment to this letter.
Your response to these questions is due by February 6, except for question 2, which is due to the NRC by March 6, 2020.
Sujata Goetz Project Manager, Susquehanna Steam Electric Station Nuclear Regulatory Commission 11555 Rockville Pike Office of the Nuclear Reactor Regulation NRC/NRR/D0RL/LPL3 Office 08F2 Mailroom 08-BlA Rockville, MD 20852-2738 Washington, DC 20555-0001 (o) 301.415.8004 (f) 301.415.3313
PROPRIETARY INFORMATION REQUESTS FOR ADDITIONAL INFORMATION FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 TO SUPPORT REVIEW OF THE LICENSE AMENDMENT REQUEST REGARDING APPLICATION OF FRAMATOME METHODOLOGIES TO SUPPORT TRANSITION TO ATRIUM 11 FUEL Facility Docket EPID Susquehanna Steam Electric Station, Unit 1 50-387 L-2019-LLA-0153 Susquehanna Steam Electric Station, Unit 2 50-388 By letter dated July 15, 2019, Talen Energy submitted a license amendment request (LAR) for Susquehanna Steam Electric Station, Units 1 and 2 (Susquehanna) to allow application of the Framatome analysis methodologies necessary to support a planned transition to ATRIUM 11 fuel under the currently licensed Maximum Extended Load Line Limit Analysis (MELLLA) operating domain (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML19196A270). The staff has reviewed the LAR and has the following requests for additional information.
The proprietary information in this document is marked with double brackets and bold font such as ((Example)).
1.0 CONTAINMENT Regulatory Basis - Title 10, "Energy" of the Code of Federal Regulations ( 10 CFR),
Section 50, General Design Criteria (GDCs) 16, 38, and 50 In Section 8.3 of ANP-3753P of the LAR, the licensee states that fuel design differences may impact the power and pressure excursion experienced during an anticipated transient without scram (ATWS) event. The licensee further stated that ATRIUM-10 analysis bounds the ATRIUM 11 fuel because ((
))
- a. Describe the analysis done to justify that ((
)).
- b. Provide quantitative results for the containment pressure and suppression pool temperature response changes due to the change in fuel type. Describe the PROPRIETARY INFORMATION
PROPRIETARY INFORMATION analyses performed to confirm the ATRIUM-10 analysis bounds the ATRIUM 11 fuel transition.
2.0 ANTICIPATED OPERATIONAL OCCURENCES (AOOS) AND ATWS Regulatory Basis -10 CFR 50, GDCs 10, 13, 15, 20, 25, 26, and ATWS acceptance criteria 2.1 ANP-3753P and ANP-3783P provide a subset of the events analyzed in the Susquehanna Chapter 15 Updated Final Safety Analysis Report (UFSAR) and covered by the AURORA-B AOO/ATWS methodology. To ensure the methodology is implemented appropriately for the events not covered in ANP-3753P and ANP-3783P, provide the following:
- a. Describe how each Chapter 15 UFSAR event (that is covered by the AURORA-B AOO/ATWS methodology) will be analyzed in the AURORA-B AOO methodology framework (e.g., a table identifying UFSAR Section/Event Name/Disposition)
- b. Describe how the methodology is implemented (including steps prior to the execution of the uncertainty analysis) to ensure nuclear power plant - specific options are covered in the analyses.
- c. Void quality correlation uncertainties are discussed in Section 6.1 of ANP-3753P.
Provide information about which parameters are sampled and which parameters are biased. How is a conservative approach ensured regarding the sampled and biased parameters?
2.2 To ensure there is appropriate coverage of the parameters used in the uncertainty analysis and to ensure there is no significant trends with respect to the uncertainty parameters in the results such that the Susquehanna implementation of the AURORA-B methodology is sufficient, provide the following for the load rejection no bypass/turbine trip without bypass event at 100% power/ 108% flow, main steam isolation valve closure A TWS event at 100% power and 99% flow, and high pressure coolant injection event at 100% power / 108% flow:
- a. The sampled values of the uncertainty parameters for all cases executed in the set
- b. The figure of merit results for all cases executed in the set 2.3 Please provide the schedule for Reload Safety Analysis Report (RSAR) submittal.
Discuss how the information in the RSAR is used to confirm the AURORA-B limitations and conditions in ANP-2637P, "Boiling Water Reactor Licensing Methodology Compendium, Rev. 8", are appropriately applied.
2.4 Section 5.4 of ANP-3753P describes the safety limit minimum critical power ratio methodology at SUSQUEHANN. This methodology is used to determine that 99.9% of the fuel rods are expected to avoid boiling transition during normal reactor operation and anticipated operation occurrences. The analysis provided by the licensee shows that ((
PROPRIETARY INFORMATION
PROPRIETARY INFORMATION
)) Please provide the approach used to confirm the bounds will be checked in the appropriate assemblies of the core for future reloads. What process is applied if (( ))?
2.5 In the AOO event analysis in ANP-3753P, the load rejection no bypass event is combined with the turbine trip without bypass event even though plant systems may respond differently for each event. Justify that one event bounds the other without doing explicit analysis for both events. Confirm that the bounding analysis can be determined by combining these two events.
3.0 FUEL: INTRODUCTION OF ATRIUM 11 FUEL TO SUSQUEHANN REGULATORY BASIS-10 CFR 50, GDCS 10, 13, 15, 20, 25, 26, AND ATWS ACCEPTANCE CRITERIA GDC 10 requires that specified acceptable fuel design limits are not exceeded during normal operation including the effects of AOOs. Oxidation and hydriding are two specified acceptable fuel design limits that ensure components maintain strength and ductility. Section 3.5.1 of ANP-3762P mentions that water chemistry is controlled to reduce oxidation in the fuel channel. Please describe what process is used to control the water chemistry and what are the key figures-of-merit monitored to ensure satisfactory performance of ATRIUM 11 fuel and the 248 water channel.
4.0 LOSS OF COOLANT ACCIDENT (LOCA)
REGULATORY BASIS-10 CFR 50, GDCS 10, 13, 15, 20, 25, 26, AND ATWS ACCEPTANCE CRITERIA The regulatory bases for the following LOCA related requests for additional information are the requirements contained in 10 CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," insofar as they establish the requirements and acceptance criteria for emergency core cooling system (ECCS) design, and for the evaluation models used to evaluate ECCS performance during a hypothetical LOCA. Specific considerations include:
- 10 CFR 50.46(a)(1 )(i) requires the use of an acceptable evaluation models to evaluate ECCS performance under the conditions of a hypothetical LOCA, and 10 CFR 50.46(a)(1 )(ii) allows for the development of an evaluation models that conforms to the required and acceptable features specified in Appendix K to 10 CFR 50.
- 10 CFR 50.46(a}(1 )(i) also requires ECCS cooling performance to be calculated for a number of postulated LOCAs of different sizes, locations, and other properties sufficient to provide assurance that the most severe hypothetical LOCAs are calculated.
- Acceptance criteria set forth in paragraph (b) of 10 CFR 50.46, and the results of the ECCS evaluation must show that the acceptance criteria are met. Among others, these include requirements related to peak cladding temperature (PCT), maximum cladding oxidation, and maximum hydrogen generation.
PROPRIETARY INFORMATION
PROPRIETARY INFORMATION 4.1 For licensed operating domain and equipment-out-of-service, please provide justification to assure that the LOCA analysis has been performed conservatively to cover Susquehanna licensed operating domain and equipment out-of-service conditions.:.
4.2 For, limiting PCT: Explain why the limiting PCT of ((
)) of exposure-dependent LOCA analysis.
4.3 For local Cladding Oxidation (Table 9.1 of ANP-3784P): Explain why the change of local cladding oxidation from the assembly average planar exposure of ((
)]
4.4 Linear heat generation rate (LHGR) and maximum average planar LGHR (MAPLHGR)
Data Used in Exposure-Dependent Analysis
- a. What is the process for determining the LHGR used, for both U02 and Gd203-U02 pellets during exposure-dependent analysis, in the AURORA-B LOCA analysis?
Specifically, are the LHGR limit curves presented in Figures 2.2 and 2.3 shown in ANP-3784P, "Susquehanna ATRIUM 11 Introduction - Exposure-Dependent LOCA Analysis," ((
)]
- b. Please demonstrate the analysis margin for the MAPLHGR limit in Figure 2.1 of ANP-3784P, (( )).
5.0 Please address how the implementation of Atrium 11 fuel affects the aging degradation on the reactor vessel pressure and reactor pressure internal components.
REGULATORY BASIS-10 CFR 50, GDCS 10, 13, 15, 20, 25, 26, AND ATWS ACCEPTANCE CRITERIA If the neutron fluence values associated with Atrium 11 are higher than the Atrium 10 fuel, the licensee should provide a technical explanation how it intends to manage the aging degradation related to irradiation embrittlement, irradiation-assisted stress corrosion cracking, and, irradiation stress relaxation at Susquehanna units in the current licensing period:.
PROPRIETARY INFORMATION}}