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Category:Letter
MONTHYEARML23180A1512023-06-29029 June 2023 LLC, Request for Exemption to the Reporting Requirements of 10 CFR 50.46(a)(3) ML21102A3072021-04-15015 April 2021 OEDO-21-00155 - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC, Small Modular Reactor ML21050A4312021-02-19019 February 2021 LLC - Lessons-Learned from the Design Certification Review of the NuScale Power, LLC Small Modular Reactor ML20247J5642020-09-11011 September 2020 Standard Design Approval for the NuScale Power Plant Based on the NuScale 600 Standard Plant Design Certification Application ML20231A8042020-08-28028 August 2020 Final Safety Evaluation Report for the NuScale Standard Plant Design ML20224A4602020-08-25025 August 2020 OEDO-20-00292-Response to the Advisory Committee on Reactor Safeguards Letter on NuScale Power, LLC, Report on the Safety Aspects of the NuScale Small Modular Reactor ML20231A5982020-08-25025 August 2020 OEDO-20-00285_NuScale Area of Focus - Boron Redistribution ML20210M8902020-07-29029 July 2020 Area of Focus - Boron Redistribution ML20195A5872020-07-13013 July 2020 LLC - Submittal of Draft Operator Licensing and Examination Standard for NuScale Small Modular Reactors ML20195C7662020-07-13013 July 2020 LLC Request for Standard Design Approval Based on the NuScale Standard Plant Design Certification Application ML20192A3262020-07-10010 July 2020 LLC, Submittal of Environmental Report: Revision Status ML20198M3932020-07-0202 July 2020 LLC Submittal of Revised Packing Slip for Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1, Dated June 19, 2020 ML20174A3472020-07-0101 July 2020 OEDO-20-00220 - Area of Focus - Probabilistic Risk Assessment and Emergency Core Cooling System Valve Performance ML20184A2872020-07-0101 July 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and General Design Criterion 33, PM-0720-70785, Revision 0 ML20181A4322020-06-22022 June 2020 Final SER for NuScale TR-0516-49416 NON-Loss-of-Coolant Analysis Model, Rev 3 (Letter) ML20181A2702020-06-22022 June 2020 Final SER for NuScale TR-0516-49422 Loss-of-Coolant Analysis Model, Rev 2 (Letter) ML20198M3922020-06-19019 June 2020 LLC - Submittal of the NuScale Standard Plant Design Certification Application, Revision 4.1 ML20171A7312020-06-19019 June 2020 LLC, Submittal of Riser Flow Hole Methodology and Associated Changes to Final Safety Analysis Report Incorporating Its Use ML20157A2232020-06-0303 June 2020 Letter to NuScale Requesting -A for TR-0716-50350 ML20150C5172020-05-29029 May 2020 LLC Submittal of Presentation Materials Entitled NRC Public Meeting Presentation: Boron Redistribution and Associated Design and DCA Changes, PM-0620-70336, Revision 0 ML20150E1772020-05-29029 May 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Extended Dhrs Operation and RCS Boron Redistribution (Closed Session), PM-0620-70243, Revision 0 ML20150C8812020-05-29029 May 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and Associated Design and DCA Changes, PM-0620-70244, Revision 0 ML20149M1192020-05-28028 May 2020 LLC Summary of Impacts to Erai 8930 Response and Discussion on the Exemption from General Design Criterion 33 ML20141L8082020-05-20020 May 2020 LLC Submittal of Containment Response Analysis Methodology Technical Report, TR-0516-49084, Revision 3 ML20141N0122020-05-20020 May 2020 LLC Submittal of Changes to Final Safety Analysis Report, Section 6.2, Containment Systems, Section 6.3, Emergency Core Cooling System, and Technical Report TR-0516-49084, Containment Response Analysis Methodology Technical Report ML20141M7642020-05-20020 May 2020 LLC Submittal of Nuclear Steam Supply System Advanced Sensor Technical Report, TR-0316-22048, Revision 3 ML20141L7872020-05-20020 May 2020 LLC, Submittal of Second Updates to Standard Plant Design Certification Application, Revision 4 ML20141L8162020-05-20020 May 2020 LLC, Submittal of Long-Term Cooling Methodology, TR-0916-51299, Revision 3 ML20141M1142020-05-20020 May 2020 LLC Submittal of NuScale Instrument Setpoint Methodology Technical Report, TR-0616-49121, Revision 3 ML20141L8042020-05-20020 May 2020 LLC Submittal of Technical Specifications Regulatory Conformance and Development, TR-1116-52011, Revision 4 ML20128J3162020-05-18018 May 2020 OEDO-20-00167 - Response to the ACRS Letter on Combustible Gas Monitoring ML20133K0882020-05-12012 May 2020 LLC, Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution (Closed Session), PM-0420-69512, Revision 0 ML20133J9142020-05-11011 May 2020 LLC Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0420-69511, Revision 0 ML20112F4552020-05-0101 May 2020 LLC, Design Certification Application Phases 5 and 6 Review Status ML20107F8492020-05-0101 May 2020 OEDO-2000140 - NuScale Area of Focus - Helical Tube Steam Generator Design ML20104A0792020-04-27027 April 2020 OEDO-20-00115 - Safety Evaluation Report for Topical Report TR-0516-49416, Revision 2, Non-Loss-of-Coolant Accident Analysis Methodology ML20099H0802020-04-0808 April 2020 LLC - Submittal of Presentation Materials Entitled NRC Public Meeting: Revisions to Nuscale'S EPZ Sizing Methodology Topical Report, PM-0420-69598, Revision 0 ML20098G2372020-04-0707 April 2020 Nuscale Power, LLC Submittal of Remaining Closure Items for the Emergency Core Cooling System Valve Failure Mode Effects Analysis Audit Items ML20097F1922020-04-0606 April 2020 Nuscale Power, LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: Nuscale Topic - Hydrogen/Oxygen Monitoring, PM-0420-69518, Revision 0 ML20094H6742020-04-0303 April 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation NuScale Topic-Probabilistic Risk Assessment with a Focus on Emergency Core Cooling System Analysis PM-0420-69559, Revision 0 ML20092L8992020-04-0101 April 2020 LLC - Submittal of Updates to Standard Plant Design Certification Application, Revision 4 ML20072M6682020-03-30030 March 2020 Response to NuScale Letter Dated February 24, 2020, on Planned SDA Application Content ML20072H3332020-03-0909 March 2020 LLC - Submittal of Presentation Materials Entitled Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron Distribution, PM-0320-69218, Revision 0 ML20057D9002020-03-0606 March 2020 Submittal of Errata to Final SE for NuScale Power, LLC TR-1010-859-NP-A, Quality Assurance Program Description for the NuScale Power Plant ML20062F7262020-03-0505 March 2020 Request for Withholding Information from Public Disclosure for Nuscale Power, LLC Letter Public ML20069A1572020-03-0404 March 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident Methodology, PM-0320-69146, Revision 0 ML20069A1772020-03-0404 March 2020 LLC - Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report-Non-Loss-of-Coolant Accident, PM-0320-69141, Revision 0 ML20069A9632020-03-0404 March 2020 LLC Submittal of Presentation Materials Entitled ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accident Evaluation Model, PM-0320-69138, Revision 0 ML20066G2802020-03-0303 March 2020 LLC, Submittal of Presentation Materials Entitled ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring, PM-0220-69071, Revision 0 ML20066G2882020-02-28028 February 2020 LLC Submittal of Presentation Materials Titled ACRS Full Committee Presentation: NuScale - Steam Generator Design (Closed Session), PM-0220-69053, Revision 0 2023-06-29
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRAIO-0420-69855, LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification2020-04-30030 April 2020 LLC, Submittal of Corrected Response to NRC Request for Additional Information No. 284 (Erai No. 9225) on the NuScale Design Certification ML19332A1202019-11-27027 November 2019 LLC Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19304B4712019-10-31031 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 466 (Erai No. 9482) on the NuScale Design Certification Application ML19296D8052019-10-23023 October 2019 LLC Response to NRC Request for Additional Information No. 526 (Erai No. 9719) on the NuScale Design Certification Application ML19283E5302019-10-10010 October 2019 LLC Supplemental Response to NRC Request for Additional Information No. 522 (Erai No. 9681) on the NuScale Design Certification Application ML19260G7352019-10-0707 October 2019 Summary of Public Meeting with NuScale to Discuss Response to RAI 9681 ML19266A5872019-09-23023 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 518 (Erai No. 9659) on the NuScale Design Certification Application ML19262G9742019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Tier 1, Section 3.11, Reactor Building and Section 3.13, Control Building, and Tier 2, Section 3.8.4, Design of Category I Structure and Section 14.3, Certified ... ML19262G5762019-09-19019 September 2019 LLC - Submittal of Changes to Final Safety Analysis Report, Section 14.2, Initial Plant Test Program, Table 14.2-2, Pool Cleanup Systems Test #2, and Table 14.2-50, Module Assembly Equipment Test #50 ML19259B8102019-09-16016 September 2019 LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application ML19259A0922019-09-16016 September 2019 LLC Response to NRC Request for Additional Information No. 525 (Erai No. 9705) on the NuScale Design Certification Application ML19238A3722019-08-26026 August 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19238A3662019-08-23023 August 2019 LLC - Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19215A0032019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19215A0062019-08-0202 August 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 441 (Erai No. 9485) on the NuScale Design Certification Application ML19212A7622019-07-31031 July 2019 LLC Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19212A3752019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 483 (Erai No. 9516) on the NuScale Design Certification Application ML19212A7992019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19212A6892019-07-31031 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 205 (Erai No. 9044) on the NuScale Design Certification Application ML19210D1592019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 401 (Erai No. 9447) on the NuScale Design Certification Application ML19210D7342019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 520 (Erai No. 9642) on the NuScale Design Certification Application ML19210E1462019-07-29029 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19207B3812019-07-26026 July 2019 LLC - Response to NRC Request for Additional Information No. 427 (Erai No. 9408) on the NuScale Design Certification Application ML19207A5342019-07-26026 July 2019 LLC - Response to NRC Request for Additional Information No. 523 (Erai No. 9682) on the NuScale Design Certification Application ML19207B8522019-07-25025 July 2019 LLC Response to NRC Request for Additional Information No. 194 (Erai No. 8884) on the NuScale Design Certification Application ML19203A3152019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 325 (Erai No. 9268) on the NuScale Design Certification Application ML19203A3212019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 333 (Erai No. 9282) on the NuScale Design Certification Application ML19203A3092019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 54 (Erai No. 8837) on the NuScale Design Certification Application ML19203A3422019-07-22022 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 154 (Erai No. 8938) on the NuScale Design Certification Application ML19200A2482019-07-19019 July 2019 LLC Response to NRC Request for Additional Information No. 522 (Erai No. 9681) on the NuScale Design Certification Application ML19200A2082019-07-19019 July 2019 LLC - Response to NRC Request for Additional Information No. 524 (Erai No. 9691) on the NuScale Design Certification Application ML19199A1172019-07-18018 July 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 484 (Erai No. 8930) on the NuScale Design Certification Application ML19198A3252019-07-17017 July 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 249 (Erai No. 9135) on the NuScale Design Certification Application ML19196A3682019-07-15015 July 2019 LLC Response to NRC Request for Additional Information No. 516 (Erai No. 9647) on the NuScale Design Certification Application ML19191A2202019-07-10010 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application ML19184A6152019-07-0303 July 2019 LLC Supplemental Response to NRC Request for Additional Information No. 386 (Erai No. 9316) on the NuScale Design Certification Application ML19176A5802019-06-25025 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19170A3702019-06-19019 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19168A2442019-06-17017 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 325 (Erai No. 9268) on the NuScale Design Certification Application ML19164A1452019-06-13013 June 2019 LLC - Submittal of Containment Response Analysis Methodology Technical Report, TR-0516 -49 08 4, Revision 1 ML19157A3262019-06-0606 June 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 232 (Erai No. 9113) on the NuScale Design Certification Application ML19154A6222019-06-0303 June 2019 LLC Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on the NuScale Design Certification Application ML19154A6052019-06-0303 June 2019 LLC Response to NRC Request for Additional Information No. 514 (Erai No. 9645) on the NuScale Design Certification Application ML19151A8372019-05-31031 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 377 (Erai No. 9380) on the NuScale Design Certification Application ML19140A4592019-05-20020 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 401 (Erai No. 9447) on the NuScale Design Certification Application ML19137A2902019-05-17017 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application ML19137A2872019-05-15015 May 2019 LLC Response to NRC Request for Additional Information No. 519 (Erai No. 9656) on the NuScale Design Certification Application ML19126A2942019-05-0606 May 2019 LLC Supplemental Response to NRC Request for Additional Information No. 26 (Erai No. 8840) on the NuScale Design Certification Application ML19122A5092019-05-0202 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 494 (Erai No. 9548)on the Design Certification Application ML19121A6002019-05-0101 May 2019 LLC - Supplemental Response to NRC Request for Additional Information No. 202 (Erai No. 8911) on Design Certification Application 2020-04-30
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Text
RAIO-0418-59545 April 13, 2018 Docket No.52-048 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738
SUBJECT:
NuScale Power, LLC Supplemental Response to NRC Request for Additional Information No. 64 (eRAI No. 8863) on the NuScale Design Certification Application
REFERENCES:
- 1. U.S. Nuclear Regulatory Commission, "Request for Additional Information No. 64 (eRAI No. 8863)," dated June 20, 2017
- 2. NuScale Power, LLC Response to NRC "Request for Additional Information No. 64 (eRAI No.8863)," dated August 21, 2017 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) supplemental
response to the referenced NRC Request for Additional Information (RAI).
The Enclosure to this letter contains NuScale's supplemental response to the following RAI
Question from NRC eRAI No. 8863:
06.02.04-4 This letter and the enclosed response make no new regulatory commitments and no revisions to
any existing regulatory commitments.
If you have any questions on this response, please contact Marty Bryan at 541-452-7172 or at
mbryan@nuscalepower.com.
Sincerely, Zackary W. Rad Di t Regulatory Director, R l t Aff i Affairs NuScale Power, LLC Distribution: Omid Tabatabai, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A Prosanta Chowdhury NRC, OWFN-8G9A : NuScale Supplemental Response to NRC Request for Additional Information eRAI No. 8863 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
RAIO-0418-59545 :
NuScale Supplemental Response to NRC Request for Additional Information eRAI No. 8863 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com
Response to Request for Additional Information Docket No.52-048 eRAI No.: 8863 Date of RAI Issue: 06/20/2017 NRC Question No.: 06.02.04-4 10 CFR 50.34(f)(2)(xiv) part (D) requires that an applicant provide containment isolation
systems that utilize a containment set point pressure for initiating containment isolation as low
as is compatible with normal operation (additional background information can be found in
DSRS 6.2.4 and NUREG-0737). NuScales pressure set point is determined by taking the
analytical limit and subtracting total loop uncertainty (see NuScales setpoint methodology
Technical Report: TR-0616-49121-P Rev. 0). Applying NuScales setpoint methodology results
in a set point that is based off the analytical limit and does not consider normal operation as
required by the TMI regulation cited above. Therefore, based on the regulation and staff
guidance, the NRC staff requests that the NuScale design certification applicant provide
information that addresses the TMI regulation related to containment pressure set point given
that NuScales set point methodology does not explicitly require or account for the TMI
requirement. As part of the response, provide a mark-up of the FSAR, as appropriate.
In addition, NuScale utilizes a temperature set point (under the bioshield) to initiate containment
isolation. In a similar manner as discussed above for the pressure set point, NuScales
temperature set point is determined by taking the analytical limit and subtracting total loop
uncertainty (see NuScales setpoint methodology Technical Report: TR-0616-49121-P Rev. 0).
For the temperature setpoint, the NRC staff request that the NuScale design certification
applicant provide information on how NuScale arrives at a minimum containment isolation
temperature set point that is in keeping with the approach used to determine the containment
isolation pressure set point (as low as is compatible with normal operation). As part of the
response, provide a mark-up of the FSAR, as appropriate.
NuScale Response:
The response to eRAI 8863, Question 06.02.04-4, transmited by NuScale letter RAIO-0817-55516, dated August 17, 2017 addressed the high containment pressure containment isolation signal setpoint and the high under the bioshield temperature containment isolation signal setpoint. This supplemental response replaces the high containment pressure containment isolation setpoint discussion in RAIO-0817-55516. The response to Question NuScale Nonproprietary
06.02.04-4 in RAIO-0817-55516 continues to address the high under the bioshield temeprature containment isolation setpoint.
NUREG-0737 - Item II.E.4.2 provides additional guidance to 10CFR50.34(f)(2)(xiv)(D). In the section marked "Clarification,", item (6) states:
The containment pressure history during normal operation should be used as a basis for arriving at an appropriate minimum pressure setpoint for initiating containment isolation.
The pressure setpoint selected should be far enough above the maximum observed (or expected) pressure inside containment during normal operation so that inadvertent containment isolation does not occur during normal operation from instrument drift or fluctuations due to the accuracy of the pressure sensor. A margin of 1 psi above the maximum expected containment pressure should be adequate to account for instrument error. Any proposed values greater than 1 psi will require detailed justification. Applicants for an operating license and operating plant licensees that have operated less than one year should use pressure history data from similar plants that have operated more than one year, if possible, to arrive at a minimum containment setpoint pressure.
The NuScale design has no relevant operating history to base a lower containment setpoint below the high containment pressure analytical limit upon. Therefore, it is impossible to select a setpoint far enough above the observed (or expected) pressure inside containment during normal operation, that accounts for instrument drift or fluctuations, due to the pressure sensor accuracy. Additionally, the NuScale containment operates under vacuum conditions, and the high containment pressure analytical limit is also subatmospheric, therefore, there is no need to develop an isolation setpoint 1 psi above the normal operating pressure, to prevent a release to the environs. Therefore, 10 CFR 50.34(f)(2)(xiv)(D) is not technically relevant to the NuScale design. FSAR Table 1.9-2 is revised accordingly.
Impact on DCA:
Table 1.9-5 has been revised as described in the response above and as shown in the markup provided in this response.
NuScale Nonproprietary
Tier 2 NuScale Final Safety Analysis Report RAI 06.02.04-4S1, RAI 06.02.04-7S1, RAI 06.02.04-9, RAI 06.02.04-9S1, RAI 08.01-1, RAI 08.02-4, RAI 08.02-6, RAI 08.03.02-1, RAI 09.02.06-1 Table 1.9-5: Conformance with TMI Requirements (10 CFR 50.34(f)) and Generic Issues (NUREG-0933)
Item Regulation Description / Title Conformance Comments Section Status 50.34(f)(1)(i) Perform a plant/site-specific probabilistic Partially Design certification will address reliability of core 19.0 risk assessment, the aim of which is to seek Conforms and containment heat removal systems, with an 19.1 such improvements in the reliability of core update required by COL applicant to reflect site- 19.2 and containment heat removal systems as specific conditions.
are significant and practical and do not impact excessively on the plant (II.B.8) 50.34(f)(1)(ii) Perform an evaluation of the proposed Not Applicable This rule requires an evaluation of proposed Not Applicable auxiliary feedwater system (II.E.1.1) PWR auxiliary feedwater (AFW) systems. The NuScale plant design does have an AFW system like a typical LWR. Neither the literal language nor the intent of this rule applies to the NuScale design.
50.34(f)(1)(iii) Perform an evaluation of the potential for Not Applicable The NuScale reactor design differs from large Not Applicable and impact of reactor coolant pump seal PWRs because the NuScale design does not 1.9-234 damage following small-break LOCA require or include reactor coolant pumps.
(II.K.2.16 and II.K.3.25) Rather, the NuScale design uses passive natural circulation of the primary coolant, eliminating the need for reactor coolant pumps.
50.34(f)(1)(iv) Perform an analysis of the probability of a Not Applicable This guidance is applicable only to PWRs that are Not Applicable small-break LOCA caused by a stuck-open designed with power-operated pressurizer relief power-operated relief valve (PORV) (II.K.3.2) valves. The NuScale design does not use power-operated relief valves.
50.34(f)(1)(v) Perform an evaluation of the safety Not Applicable This requirement applies only to BWRs. Not Applicable effectiveness of providing for separation of Conformance with Regulatory Criteria high pressure coolant injection and reactor core isolation cooling system initiation levels (II.K.3.13) 50.34(f)(1)(vi) Perform a study to identify practicable Not Applicable This requirement applies only to BWRs. Not Applicable system modifications that would reduce Regardless, the issue contemplated by this challenges and failures of relief valves requirement was related to power-operated (II.K.3.16) relief valves. The NuScale design does not use Draft Revision 2 power-operated relief valves.
Table 1.9-5: Conformance with TMI Requirements (10 CFR 50.34(f)) and Generic Issues (NUREG-0933) (Continued)
Tier 2 NuScale Final Safety Analysis Report Item Regulation Description / Title Conformance Comments Section Status 50.34(f)(2)(xiv) Provide containment isolation systems that Departure The containment evacuation system has the 5.2.5 50.34(f)(2)(xiv)(A) (A) ensure all non-essential systems are potential for an open path from containment to 6.2.4 50.34(f)(2)(xiv)(B) isolated automatically; (B) ensure each non- the environs but is isolated upon a high 7.1.5 50.34(f)(2)(xiv)(C) essential penetration (except instrument containment vessel pressure signal, a low-low 7.2.13 50.34(f)(2)(xiv)(D) lines) have two isolation barriers in series; pressurizer level signal, a low alternating current 9.3.6 50.34(f)(2)(xiv)(E) (C) do not result in reopening of the voltage signal, or high under-the-bioshield 19.2 containment isolation valves on resetting of temperature. Additionally, the CES discharge is the isolation signal; (D) use a containment re-directed into the gaseous radioactive waste set point pressure for initiating system upon a high radiation signal.The NuScale containment isolation as low as is design conforms to 50.34(f)(2)(xiv)(A), (B), and compatible with normal operation; and (E) (C). The requirements of 50.34(f)(2)(xiv)(D) and include automatic closing on a high (E) are not technically relevant to the NuScale radiation signal for all systems that provide design. For 50.34(f)(2)(xiv)(D), NUREG 0737 - Item a path to the environs (II.E.4.2) II.E.4.2 provides additional guidance to 10 CFR 50.34(f)(2)(xiv)(D). Specifically, the clarification states the minimum containment pressure history during normal operation should be used 1.9-239 as a basis for an appropriate minimum pressure setpoint for initiating containment isolation. The NuScale design has no relevant operating history to base an isolation setpoint upon.
Furthermore, the containment high pressure analytical limit is subatmospheric, therefore, any pressure setpoint up to and including the analytical limit will prevent a release to the environs. For 50.34(f)(2)(xiv)(E), The NuScale Conformance with Regulatory Criteria design differs from that of a traditional large water reactor design of a TMI-era vintage because reactor core uncovery, and resulting core damage, cannot occur without reaching the low low pressurizer level containment isolation setpoint. The pressurizer is an integral part of the reactor vessel, located well above the reactor Draft Revision 2 core, and not connected to the reactor core by piping. Design basis events meet their thermal
Table 1.9-5: Conformance with TMI Requirements (10 CFR 50.34(f)) and Generic Issues (NUREG-0933) (Continued)
Tier 2 NuScale Final Safety Analysis Report Item Regulation Description / Title Conformance Comments Section Status and hydraulic acceptance criteria without reliance on isolating the CES in a high radiation signal. No design basis event results in degraded or damaged core conditions. Section 19.2 analyses demonstrate severe accident conditions, with resultant core damage, also result in generation of reliable containment isolation signals, without reliance on isolation on high containment radiation. An in-containment event resulting in core damage or degradation also results in containment isolation on low low pressurizer level and high containment pressure.
An event that leads to core damage or degradation also results in containment isolation on low low pressurizer level. These features provide a reliable alternative means to prevent radiological release from the CES to the environs.
1.9-240 50.34(f)(2)(xv) Capability for containment purging/venting Not Applicable The NuScale containment vessel is smaller than a Not Applicable designed to minimize the purging time typical containment building, does not contain consistent with as low as reasonably sub-compartments and does not does not achievable (ALARA) (II.E.4.4) require or incorporate a purge or venting system function as contemplated by this requirement.
Personnel access during reactor operation is not needed. In addition, the NuScale ECCS design does not include pumps, and does not involve a typical PWR ECCS recirculation mode where Conformance with Regulatory Criteria ECCS pump performance relies on containment pressure. Thus purge or vent capability as prescribed by 10 CFR 50.34(f)(2)(xv) is neither required nor included in the NuScale design. This requirement is not technically relevant to the NuScale design.
Draft Revision 2