ML24215A192

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LLC, Response to SDAA Audit Question Number A-16.3.3.1-2
ML24215A192
Person / Time
Site: 05200050
Issue date: 08/02/2024
From:
NuScale
To:
Office of Nuclear Reactor Regulation
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LO-169995
Download: ML24215A192 (1)
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Response to SDAA Audit Question Question Number: A-16.3.3.1-2 Receipt Date: 09/18/2023 Question:

Should generic TS Table 3.3.1-1, page 4 of 8, include footnote (f) in the list of footnotes below the table, since the MODE 3 Applicability of Functions 17.b and 17.c includes footnote (f). This comment is based on the formatting convention of table footnotes described in Section 2.1.9 of TSTF-GG-05-01 ITS Writers Guide, Rev. 1.

Response

NuScale revises SDAA Technical Specification Table 3.3.1-1 (page 4 of 8) to include the following footnote:

(f) When not PASSIVELY COOLED.

This change was previously identified by NuScale, and is included in SDAA Revision 1.

Markups of the affected changes, as described in the response, are provided below:

NuScale Nonproprietary NuScale Nonproprietary

MPS Instrumentation 3.3.1 NuScale US460 3.3.1-10 Draft Revision 1 Table 3.3.1-1 (page 4 of 8)

Module Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS

14. High RCS Average Temperature a.

RTS 1

4 D

b.

DWSI 1

4 H

15. Low RCS Flow a.

DWSI 1, 2, 3 4

H

16. Low Low RCS Flow a.

RTS 1, 2(a), 3(a) 4 D

b.

DWSI 1, 2, 3 4

H

17. High Main Steam Pressure a.

RTS 1, 2(a) 4 per SG D

b.

DHRS 1, 2, 3(f) 4 per SG I

c.

SSI 1, 2, 3(f) 4 per SG I

d.

DWSI 1, 2(b) 4 per SG H

e.

PHT 1, 2(g), 3(g) 4 per SG G

18. Low Main Steam Pressure a.

RTS 1(h) 4 per SG N

b.

SSI 1(h) 4 per SG N

c.

DWSI 1(h) 4 per SG N

(a)

When capable of withdrawal of more than one CRA.

(b)

When capable of withdrawal of more than one CRA and the RCS temperature above the T-3 interlock.

(f)

When not PASSIVELY COOLED.

(g)

With pressurizer heater breakers closed.

(h)

With narrow range RCS hot temperature above the T-4 interlock.

Manual Actuation Functions 3.3.4 NuScale US460 3.3.4-3 Draft Revision 1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. As required by Required Action A.1 or B.1 and referenced in Table 3.3.4-1.

H.1 Open twoone or more reactor vent valves.

Immediately I.

As required by Required Action A.1 or B.1 and Referenced in Table 3.3.4 1.

I.1 Be in MODE 3 with containment isolated.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform actuation device operational test.

In accordance with the Surveillance Frequency Control Program

Reporting Requirements 5.6 NuScale US460 5.6-3 Draft Revision 1 5.6 Reporting Requirements 5.6.3 Core Operating Limits Report (COLR) (continued) 1.

[NuScale Standard Design Approval (SDA), NuScale Final Safety Analysis Report (FSAR), Section 4.3, Nuclear Design, Revision 0, December 2022; TR-0516-49416-P, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 4, December 2020 (NuScale Proprietary); TR-0516-49422-P, "Loss-of-Coolant Accident Evaluation Methodology," Revision 3, December 2022 (NuScale Proprietary); TR-0716-50350-P, "NuScale Rod Ejection Accident Methodology," Revision 2, December 2022 (NuScale Proprietary); and TR-0616-48793-P-A, Nuclear Analysis Codes and Methods Qualification, Revision 1, November 2018, (NuScale Proprietary).

(Methodology for Specifications 3.1.1 - SHUTDOWN MARGIN (SDM), 3.1.3 - Moderator Temperature Coefficient, 3.1.4 - Rod Group Alignment Limits, 3.1.5 - Shutdown Bank Insertion Limits, 3.1.6 - Regulating Bank Insertion Limits, and 3.1.8 - PHYSICS TESTS Exceptions.)]

2.

[NuScale SDA, NuScale FSAR, Section 9.3.4, Chemical and Volume Control System, Revision 0, December 2022; TR-0516-49416-P, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 4, December 2022 (NuScale Proprietary);

and TR-0616-48793-P-A, Nuclear Analysis Codes and Methods Qualification, Revision 1, November 2018, (NuScale Proprietary).

(Methodology for Specification 3.1.9 - Boron Dilution Control.)]

3.

[NuScale SDA, NuScale FSAR, Sections 4.3, Nuclear Design, and 4.4, Thermal and Hydraulic Design, Revision 0, December 2020; TR-0516-49416-P, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 4, December 2022 (NuScale Proprietary);

TR-0915-17564-P-A, Subchannel Analysis Methodology, Revision 2, February 2019 (NuScale Proprietary); TR-108601-P, Statistical Subchannel Analysis Methodology, Supplement 1 to TR-0915-17564-P-A, Revision 2, Revision 1, December 2022; TR-0516-49422-P, "Loss-of-Coolant Accident Evaluation Methodology," Revision 3, December 2022 (NuScale Proprietary);

TR-0716-50350-P, "NuScale Rod Ejection Accident Methodology,"

Revision 2, December 2022 (NuScale Proprietary); and TR-0616-48793-P-A, Nuclear Analysis Codes and Methods Qualification, Revision 1, November 2018, (NuScale Proprietary).

(Methodology for Specifications 3.2.1 - Enthalpy Rise Hot Channel Factor (FH), and 3.2.2 - AXIAL OFFSET (AO).)]

Reporting Requirements 5.6 NuScale US460 5.6-4 Draft Revision 1 5.6 Reporting Requirements 5.6.3 Core Operating Limits Report (COLR) (continued)

4.

[NuScale SDA, NuScale FSAR, Section 4.4, Thermal and Hydraulic Design, Revision 0, December 2022; TR-0516-49416-P, Non-Loss-of-Coolant Accident Analysis Methodology, Revision 4, December 2022 (NuScale Proprietary);

TR-0516-49422-P, "Loss-of-Coolant Accident Evaluation Methodology," Revision 3, December 2022 (NuScale Proprietary);

TR-0915-17564-P-A, Subchannel Analysis Methodology, Revision 2, February 2019 (NuScale Proprietary); TR-108601-P, Statistical Subchannel Analysis Methodology, Supplement 1 to TR-0915-17564-P-A, Revision 2, Revision 2, December 2022; and TR-0716-50350-P, "Rod Ejection Accident Methodology,"

Revision 2, December 2022 (NuScale Proprietary).

(Methodology for Specification 3.4.1 - RCS Pressure, Temperature, and Flow Resistance CHF Limits.)]

5.

[NuScale SDA, NuScale FSAR, Section 4.3, Nuclear Design, Revision 0, December 2022; TR-0616-48793-P-A, Nuclear Analysis Codes and Methods Qualification, Revision 1, November 2018 (NuScale Proprietary); and TR-124587, Extended Passive Cooling and Reactivity Control Methodology Topical Report, Revision 0, December 2022, (NuScale Proprietary).

(Methodology for Specifications 3.5.3 - Ultimate Heat Sink, 3.5.4 - Emergency Core Cooling System Supplemental Boron (ESB), and 3.8.1 - Nuclear Instrumentation.)]

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Passive Core Cooling Systems limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reloadfuel cycle to the NRC.

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