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EPID:L-2019-LLA-0197, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation (Approved, Closed) |
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Category:E-Mail
MONTHYEARML24024A1372024-01-24024 January 2024 NRR E-mail Capture - Final Snsb RAI Regarding FitzPatrick Amendment to Modify Safety Relief Valves Setpoint Lower Tolerance ML24017A1112024-01-17017 January 2024 NRR E-mail Capture - Acceptance of Requested Licensing Action Amendment Request to Adopt TSTF-529, Clarifyuse and Applicaion Rules, Revision 4 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23261C3982023-09-0808 September 2023 Acceptance Review of Amendment to Update the Fuel Handling Accident Analysis ML23244A2662023-09-0101 September 2023 Acceptance of Requested Licensing Action Amendment Request to Modify Surveillance Requirement 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML23237B3972023-08-24024 August 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Alternative Request to Use Updated BWRVIP Guidelines ML23194A1822023-08-0303 August 2023 Acceptance Review for LAR Re SRM 3.3.1.2 ML23163A2292023-06-12012 June 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-580, Revision 1 ML22354A2622022-12-20020 December 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22124A2672022-05-0404 May 2022 Request for Additional Information for James A. FitzPatrick Nuclear Power Plant TSTF-505 ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML22063A4742021-11-29029 November 2021 Acceptance of Requested Licensing Action License Amendment Request to Eliminate Selected Response Time Testing ML21301A0672021-10-28028 October 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-541 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21252A0482021-09-0707 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Alternative Request for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21246A2112021-09-0303 September 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-505 ML21246A2072021-09-0303 September 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt 10 CFR 50.69 ML21215A3502021-08-0303 August 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Amendment Request to Adopt TSTF-554 ML21187A0522021-07-0606 July 2021 Fitz RAI Regarding FitzPatrick Amendment Request to Modify SR 3.5.1.6 ML21246A2142021-06-23023 June 2021 Acceptance of Requested Licensing Action Regarding License Amendment Request to Adopt TSTF-264 ML21154A0112021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0142021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21154A0132021-05-28028 May 2021 NRR E-mail Capture - Extension of Comment Period for the Exelon Generation Company, LLC License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A1072021-05-17017 May 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-582 ML21117A0442021-04-26026 April 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21084A2532021-03-24024 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21033A8552021-02-0202 February 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Alternative Request to Expand the Use ASME Codes Cases N-878 and N-880 ML21014A5112021-01-12012 January 2021 Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-545 Revision 3 ML20352A2752020-12-17017 December 2020 Request for Additional Information Regarding FitzPatrick Primary Containment Isolation Valve Amendment Request ML20350B5582020-12-14014 December 2020 NRR E-mail Capture - Exelon Generation Company, LLC -Alternative Request for Documentation of Replacement of Pressure Retaining Bolting ML20294A0372020-10-19019 October 2020 Request for Additional Information Primary Containment Isolation Valve License Amendment Request ML20266G3032020-09-22022 September 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Request to Use Paragraph IWA-5120 of the 2017 Edition of the ASME B&PV Code, Section XI ML20217L3882020-08-0404 August 2020 Acceptance of Requested Licensing Action License Amendment Request to Modify Primary Containment Isolation Valve TS (EPID L-2020-LLA-0145) (E-Mail) ML20204A9692020-07-22022 July 2020 Acceptance of Requested Licensing Action License Amendment Request to Adopt-TSTF-478 Revision 2 ML20122A2302020-05-0101 May 2020 NRR E-mail Capture - Exelon Generation Company, LLC - Acceptance of Fleet License Amendment Request to Adopt TSTF-566 ML20066L3682020-03-0505 March 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment ML20056E7992020-02-25025 February 2020 Request for Additional Information for LAR on Primary Containment Hydrodynamic Loads ML20035D5762020-02-0303 February 2020 Request for Additional Information: License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequence ML20027A0672020-01-24024 January 2020 Accepted for Review - Fitzpatrick License Amendment Request to Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20027A0112020-01-23023 January 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation ML19353A9452019-12-19019 December 2019 Request for Additional Information: License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML19319C3582019-11-15015 November 2019 NRR E-mail Capture - Accepted for Review - FitzPatrick License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation ML19322A0062019-11-15015 November 2019 NRR E-mail Capture - Fermi 2: Request for Additional Information- Relief Request VRR-006, Proposed Alternative for Preservice Testing of Butterfly Valves ML19316A0162019-11-0404 November 2019 NRR E-mail Capture - Revised Staff Hours Estimate - FitzPatrick License Amendment Request on Proposed Changes to the Technical Specifications Related to Primary Containment Hydrodynamic Loads 2024-01-24
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24024A1372024-01-24024 January 2024 NRR E-mail Capture - Final Snsb RAI Regarding FitzPatrick Amendment to Modify Safety Relief Valves Setpoint Lower Tolerance ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23164A0322023-06-13013 June 2023 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000333/2023010 ML22321A0102022-11-17017 November 2022 Notification of Conduct of a Fire Protection Team Inspection ML22124A2672022-05-0404 May 2022 Request for Additional Information for James A. FitzPatrick Nuclear Power Plant TSTF-505 ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22020A0642022-01-13013 January 2022 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21187A0522021-07-0606 July 2021 Fitz RAI Regarding FitzPatrick Amendment Request to Modify SR 3.5.1.6 ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21041A1932021-02-10010 February 2021 Request for Information for a Triennial Baseline Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements Inspection; Inspection Report (05000333/2021011) ML20066L3682020-03-0505 March 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment ML20056E7992020-02-25025 February 2020 Request for Additional Information for LAR on Primary Containment Hydrodynamic Loads ML20035D5762020-02-0303 February 2020 Request for Additional Information: License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequence ML20027A0112020-01-23023 January 2020 Request for Additional Information: License Amendment Request for Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation ML19353A9452019-12-19019 December 2019 Request for Additional Information: License Amendment Request for Application of the Alternative Source Term for Calculating Loss-of-Coolant Accident Dose Consequences ML19322A0062019-11-15015 November 2019 NRR E-mail Capture - Fermi 2: Request for Additional Information- Relief Request VRR-006, Proposed Alternative for Preservice Testing of Butterfly Valves ML19280A0372019-10-0505 October 2019 NRR E-mail Capture - FitzPatrick Revised Request for Additional Information: Emergency Amendment to Extend Completion Time of Transformer to 21 Days ML19280A0392019-10-0505 October 2019 NRR E-mail Capture - FitzPatrick Additional Request for Additional Information: Emergency Amendment to Extend Completion Time of Transformer to 21 Days ML19280A0362019-10-0404 October 2019 NRR E-mail Capture - FitzPatrick Request for Additional Information: Emergency Amendment to Extend Completion Time of Transformer to 21 Days ML19099A2672019-04-16016 April 2019 Use of Encryption Software for Electronic Transmission of Safeguards Information ML19099A2852019-03-12012 March 2019 Draft RAI: FitzPatrick Request to Update Electronic Transmission of Safeguards Information ML19025A1202019-01-24024 January 2019 NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing ML18353B5112018-12-20020 December 2018 Request for Additional Information Relief Request No. 14R-22, for Fourth 10-Year Inservice Inspection Interval ML18164A3652018-06-13013 June 2018 NRR E-mail Capture - FitzPatrick RAIs - LAR to Adopt EAL Schemes Pursuant to NEI 99-01, Revision 6 ML18094B0922018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59) ML18085A6922018-03-26026 March 2018 NRR E-mail Capture - James A. FitzPatrick Nuclear Power Plant, Unit 1 - Request for Information to Adopt Traveler TSTF-542, RPV Water Inventory Control ML18085A6912018-03-23023 March 2018 NRR E-mail Capture - Draft Request for Information (RAI) for JAFNPP Traveler TSTF-542, RPV Water Inventory Control ML18029A8422018-01-29029 January 2018 NRR E-mail Capture - Request for Additional Information: FitzPatrick License Amendment Request to Revise Technical Specifications to Address Secondary Containment Personnel Access Door Openings ML17335A1002017-11-29029 November 2017 NRR E-mail Capture - FitzPatrick - Request for Additional Information - Relief Request 15R-02 Regarding the Use of BWRVIP Guidelines Instead of ASME Code (CAC: MG0116; EPID: L-2017-LLR-0083) ML17285B1962017-10-27027 October 2017 Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. ML17228A0052017-08-15015 August 2017 NRR E-mail Capture - Request for Additional Information - St. Lucie Relief Request #3 - Icw 30 Pipe Defect Removal (MF9288) ML16299A0192016-11-0202 November 2016 Request for Additional Information Regarding Direct License Transfer from Entergy to Exelon ML16287A6502016-10-21021 October 2016 Request for Additional Information Regarding: License Amendment Request to Revise Technical Specifications Section 5.5.6 for Extension of Type a and Type C Leak Rate Test Frequencies ML16280A5732016-10-18018 October 2016 Request for Additional Information Relief Request for Proposed Alternative for the Implementation of BWRVIP-05 ML16117A1862016-04-26026 April 2016 Entergy Fleet Relief Request EN-ISI-15-1 Request for Additional Information - 04/26/16 Email from R. Guzman to G. Davant (CAC Nos. MF7133-MF7136) ML16013A0642016-01-13013 January 2016 NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097) ML15341A1662015-12-0707 December 2015 NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349) ML14240A6122014-09-24024 September 2014 Request for Additional Information Regarding Proposed Changes to the Technical Specification Low Pressure Safety Limit ML14184A6152014-07-25025 July 2014 Request for Additional Information Regarding Proposed Safety Limit Minimum Critical Power Ratio License Amendment ML14195A0972014-07-16016 July 2014 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report ML14164A5382014-07-0202 July 2014 Request for Additional Information Regarding 10 CFR 50.55A Alternate Request PRR-05 (Tac No. MF3680) ML14093A6772014-05-0101 May 2014 SONGS - Request for Additional Information Concerning Pre-Emption Authority ML13338A6452013-12-12012 December 2013 Interim Staff Evaluation and Request for Additional Information, Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13226A5342013-08-29029 August 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) ML13179A4622013-07-0505 July 2013 Entergy Nuclear Operations, Inc., Decommissioning Funding Status Report Request for Additional Information Regarding the Decommissioning Funding Status Report 2024-01-24
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Text
From: Lee, Samson To: Villar, Enrique:(Exelon Nuclear)
Subject:
FitzPatrick request for additional information for LAR on primary containment hydrodynamic loads (EPID: L-2019-LLA-0197)
Date: Tuesday, February 25, 2020 10:01:00 AM By letter dated September 12, 2019, Agencywide Documents Access and Management System (ADAMS) Accession No. ML19255D988, Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request (LAR) for changes to the James A. FitzPatrick Nuclear Power Plant (FitzPatrick) Technical Specifications (TSs). The proposed changes would delete TS Limiting Condition for Operation (LCO) 3.6.2.4, Drywell-to-Suppression Chamber Differential Pressure, associated Actions and Surveillance Requirements; revise the upper level in LCO 3.6.2.2, Suppression Pool Water Level from 14 feet (ft) to 14.25 ft; and revise the Allowable Value for Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation Function 3.e. Suppression Pool Water Level - High from 14.5 ft to 14.75 ft. The NRC staff has reviewed the LAR and determined that additional information is required to complete the review. The NRC staffs requests for additional information (RAIs) are listed below. These RAIs are in the nuclear systems performance area. A clarification call was held on February 19, 2020. The Exelon staff indicated that there was no proprietary or sensitive information. The Exelon staff requested, and NRC agreed, to a RAI response by April 10, 2020.
The NRC staff considers that timely responses to RAIs help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. Please note that if you do not respond to this request by the agreed-upon date or provide an acceptable alternate date, we may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If circumstances result in the need to revise the agreed upon response date, please contact me at (301) 415-3168 or via e-mail Samson.Lee@nrc.gov.
Containment Pressure and Temperature Response Regulatory Basis:
GDC-16 as it relates to the containment and associated systems be provided to establish an essentially leak-tight barrier against the uncontrolled release of radioactivity to the environment and to assure that the containment design conditions important to safety are not exceeded for as long as postulated accident conditions require.
GDC-50 as it relates to the reactor containment structure, including access openings, penetrations, and the containment heat removal system shall be designed so that the containment structure and its internal compartments can accommodate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from any loss-of-coolant accident.
SNSB RAI-1:
Define the most limiting design basis loss-of-coolant accident (DBLOCA) on which the proposed short-term containment response is based. Provide all initial conditions and key inputs, and assumptions used in the DBLOCA short-term containment pressure and temperature response. Justify if the conservatism in any of the inputs and assumption is
reduced from those used in the NRC accepted current analysis of record (AOR) documented in NEDC-33087P, Revision 1.
SNSB RAI-2:
For the suppression pool swell response to a DBLOCA, the postulated break is the reactor recirculation suction line break (RSLB) that draws water from the annulus area of the reactor in which the break effluent is subcooled. The LOCA mass and energy (M&E) analysis would be non-conservative if the break fluid is assumed saturated because of its lower density as compared to subcooled. For the subcooled break fluid, the higher mass released should result in a higher drywell peak pressure, and therefore higher suppression pool swell loads acting upon structures and components located in the wetwell within the suppression pool swell zone. Provide the reactor water pressure and temperature input for the M&E release analysis and confirm that the break fluid is subcooled. Provide justification if the break fluid is not assumed to be subcooled.
SNSB RAI-3:
The AOR documented in NEDC-33087P, Revision 1, Section 9.0 provides evaluation and results of the following short-term analysis cases of DBLOCA containment pressure and temperature response for normal feedwater temperature (NFWT) and final feedwater temperature reduction (FFWTR). The results of these analyses were used for evaluating the containment hydrodynamic loads.
Case 1 which corresponds to 102% of current licensed thermal power (CLTP) and 100% of rated core flow (RCF).
Case 2 which corresponds to 102% of CLTP, with 105% of RCF (i.e., increased core flow (ICF)).
Case 3 which corresponds to 102% of CLTP, with 79.8% of RCF (i.e., on the maximum extended load line limit analysis (MELLLA) line).
Case 4 which corresponds to 62% of CLTP, with 36.8% of RCF (Minimum Pump Speed (MPS) on the MELLLA line).
Provide containment pressure and temperature response evaluation and results, both graphs and peak values, for the above cases based on the proposed change in the suppression pool TS maximum level. In case all of the above 4 cases are not re-analyzed, provide the results of the most limiting case with quantitative justification showing that it bounds the remaining 3 cases.
LOCA Containment Hydrodynamic Loads Regulatory Basis:
GDC-4 as it relates to structures, systems, and components shall be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and
discharging fluids, that may result from equipment failures and from events and conditions outside the nuclear power unit.
SNSB RAI-4:
The AOR documented in NEDC-33087P, Revision 1, Section 9.0 provides assessment of the following containment LOCA hydrodynamic loads based on the short-term containment pressure and temperature response analysis:
Pool Swell Vent Thrust Condensation Oscillation Chugging
- a. Provide assessment of these loads based on the revised containment pressure and temperature response for the bounding case.
- b. The pool swell loads depend on the drywell pressurization rate. NEDC-33087P, Revision 1, the third paragraph in Section 9.3.2 states:
The test condition pressurization rate and scale factor for the JAF quarter scale tests (Reference 19 [NEDE-21944-P, "Mark I Containment Program 1/4 Scale Pressure Suppression Pool Swell Test Program: Plant Unique Tests," Volume 1, March 1979.]) are 31 psi/sec and 0.2627, respectively.
From Reference 19, the composite scaling factor then becomes 0.2627 so that the pressurization rate in full scale is 31.0 / 0.2627 = 60.48 psi/sec. The pool swell loads evaluation reviews the drywell pressurization rate obtained from Case 5 and compares it to the Reference 19 pool swell test condition scaled up to full-scale.
An initial drywell pressurization rate of 58.9 psi/sec was calculated for Case 5.
As stated above, in the current analysis, the initial pressurization rate of 58.9 psi/sec is bounded by the derived full-scale test value of 60.48 psi/sec. Provide the most limiting drywell pressurization rate based on the proposed TS changes to confirm that it remains bounded by the full-scale drywell pressurization rate of 60.48 psi/sec.
- c. Based on the proposed TS changes, provide bounding values of the vent thrust loads based on which the structural analysis given in Attachment 6 of the LAR is performed.
Main Steam Line Break Response Regulatory Basis:
GDC-16 as it relates to the containment and associated systems be provided to establish an essentially leak-tight barrier against the uncontrolled release of radioactivity to the environment and to assure that the containment design conditions important to safety are
not exceeded for as long as postulated accident conditions require.
GDC-50 as it relates to the reactor containment structure, including access openings, penetrations, and the containment heat removal system shall be designed so that the containment structure and its internal compartments can accommodate, without exceeding the design leakage rate and with sufficient margin, the calculated pressure and temperature conditions resulting from any loss-of-coolant accident.
SNSB RAI-5:
Confirm that based on the proposed TS changes, the containment pressure and temperature response and the drywell pressurization rate for the most limiting main steam line break is bounded by the RSLB DBLOCA.