ML24215A072

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LLC, Response to Sdaa Audit Question Number A-3.11-2
ML24215A072
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Issue date: 08/02/2024
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Response to SDAA Audit Question Question Number: A-3.11-2 Receipt Date: 07/03/2023 Question:

Tables 3C-6 through 3C-8 include the environmental conditions for different control building zones (CRB-1, CRB-2, CRB-3, and CRB-4) and Table 3C-3 discusses control building Room 003 exceeding the 1E3 rad threshold for a harsh environment for electronics. However, the application does not provide any information regarding what the different environmental zones for the control building represent. For all other areas, Table 3C-1 describes which rooms or areas are included in each environmental zone. Please update Table 3C-1 to describe which rooms or areas are included in CRB-1, CRB-2, CRB-3, and CRB-4.

Also, for areas containing electronics that exceed the 1E3 rad threshold for a radiologically harsh environment for electronics (e.g. RXBG-5 and RXBG-7)., t The staff suggests revising Table 3C-1 to indicate that these areas are radiologically harsh for electronics. While other information in the SDA indicates that the areas are radiologically harsh for electronics, Table 3C-1 specifying that the areas are environmentally mild could create confusion.

NRC staffs follow-up to Clarification Call on 1/11/24 involving NuScale SDAA Audit Issue A-3.11-2:

Regarding the response to Audit Question A-3.11-2, the staff thinks NuScale should update the response to provide just a little more information based on what was discussed on 1/11/24 for when they submit the response on the docket, as follows (additional changes to the FSAR are not needed unless NuScale feels that they are warranted):

1. For Zone CRB-3E, a brief discussion mentioning that it is the MCR filter and the reason for the high dose rate in the room (i.e. that the dose rate inside the filter is conservatively assumed to apply to the entire room).

NuScale Nonproprietary NuScale Nonproprietary

2. The response should mention that Tables 3C-6 through 3C-8 are changing beyond just what is asked in Question A-3.11-2 and provide a very brief explanation for why it is happening, even if the explanation is just a sentence or two saying based on revised calculations or to make corrections and add details. Otherwise it could imply that all the changes are being made due to Question A-3.11-2, which most of the changes to those tables are not due to the question.

There shouldnt be a need to go into details or specifics since the changes are not very significant.

Response

Original Response:

NuScale revises SDA Table 3C-1 to expand the scope of the table to include the Control building environmental qualification zones. Room numbers and the environment for the environmental qualification zones in the Control Building are included in the revised table. The rooms associated with the environmental qualification zones in the Control Building are:

CRB-1: Rooms 012 through 021 on 100 foot elevation CRB-2: Rooms 120 through 137 on 125 foot elevation CRB-3: Rooms 001 through 011 on 100 foot elevation CRB-4: Rooms 101 through 119 on 125 foot elevation NuScale revises SDA Appendix 3C to differentiate areas of environmental qualification zones RXBG-05, RXBG-07, and CRB-3 that are harsh environment areas for electronic equipment.

The revision to Appendix 3C includes new unique environmental qualification zones that more clearly identify these areas as harsh environment areas for electronic equipment. Reactor Building rooms 306, 319, 408, and 421 and Control Building room 003 are located in the new environmental qualification zones.

Response to NRC Follow-up from 1/11/24 Clarification Call:

Item 1:

NuScale Nonproprietary NuScale Nonproprietary

The control room ventilation system (CRVS) filter unit that is used to filter outside air during an accident condition is located in the mechanical equipment room (ROOM-003) of the control room building (CRB) which is located within Environmental Qualification (EQ) Zone CRB-3E.

The high prescribed beta radiation dose for EQ Zone CRB-3E is due to the modeled dose inside the CRVS filter unit volume being prescribed as the limiting dose for the entire EQ Zone CRB-3E. This conservative characterization is elected in the interest of modeling simplicity and conservatism.

Item 2:

Changes to parameters in Tables 3C-6 through 3C-8 outside the resolution of audit question A-3.11-2 were driven by a NuScale corrective action that identified some parameters had not yet been aligned to the most current issued design information and that there was an inconsistent application of margin to values throughout the document. Significant figures throughout the document were also updated to provide consistency.

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

NuScale Nonproprietary NuScale Nonproprietary

NuScale Final Safety Analysis Report Methodology for Environmental Qualification of Electrical and Mechanical Equipment NuScale US460 SDAA 3C-16 Draft Revision 2 Audit Question A-3.11-2 Table 3C-1: Environmental Qualification Zones - Reactor Building Zone Description Environment Reactor Building Pool Area Zones RXBP-1 NP06-2-A-Room-042, Module pool bay vapor space - outside containment and under the bioshield (top of module) (Figure 1.2-8 Reactor Building 25 foot Elevation)

Harsh RXBP-2 NP06-2-A-Room-040, 041, and 042, pool level to ceiling (RXB pool room vapor space external to top of module) (Figure 1.2-8 Reactor Building 25 foot elevation) and NP06-2-A-Room-435 (RXB pool room vapor space) (Figure 1.2-12 Reactor Building 85 foot elevation) and NP06-2-A-Room-516 (RXB pool room vapor space) (Figure 1.2-13 Reactor Building 100 foot elevation) and NP06-2-A-Room-607, 609, and 612 (RXB pool room vapor space)

(Figure 1.2-16 Reactor Building 126 foot elevation)

Harsh RXBP-3 NP06-2-A-Room-042 from top of liner plate up to top of pool level (surrounding each module under the bioshields) (Figure 1.2-8 Reactor Building 25 foot elevation)

Harsh RXBP-4 NP06-2-A-Room-040, 041, and 042 from top of liner plate up to top of pool level (RXB pool room liquid space) (Figure 1.2-8 Reactor Building 25 foot elevation)

Harsh Reactor Building Gallery Area Zones RXBG-1 NP06-2-A-Room-001 through 039 (Figure 1.2-8 Reactor Building 25 foot elevation) and NP06-2-A-Room-104, 105, and 131 (Figure 1.2-9 Reactor Building 40 foot elevation)

Harsh RXBG-2 NP06-2-A-Room-101, 102, 103, 106 through 130, 132 and 133 (Figure 1.2-9 Reactor Building 40 foot elevation)

Harsh RXBG-3 NP06-2-A-Room-201 through 223 (Figure 1.2-10 Reactor Building 55 foot elevation)

Harsh RXBG-4 NP06-2-A-Room-301 through 305, 316, 317, 318, and 329 through 333 (Figure 1.2-11 Reactor Building 70 foot elevation)

Harsh RXBG-5 NP06-2-A-Room-306 through 315 and 319 through 328 (Figure 1.2-11 Reactor Building 70 foot elevation)

Mild RXBG-5E Electronic equipment in NP06-2-A-Room-306 and 319 (Figure 1.2-11 Reactor Building 70 foot elevation)

Harsh1 RXBG-6 NP06-2-A-Room-401 through 407, 418, 419, 420, 431 through 434, and 436 (Figure 1.2-12 Reactor Building 85 foot Elevation)

Harsh RXBG-7 NP06-2-A-Room-408 through 417 and 421 through 430 (Figure 1.2-12 Reactor Building 85 foot elevation)

Mild RXBG-7E Electronic equipment in NP06-2-A-Room-408 and 421 (Figure 1.2-12 Reactor Building 85 foot elevation)

Harsh1 RXBG-8 NP06-2-A-Room-501 through 515 (Figure 1.2-13 Reactor Building 100 foot elevation)

Harsh RXBG-9 NP06-2-A-Room-601 through 606, 608, 610, 611, 613, 614, and 615 (Figure 1.2-14 Reactor Building 126 foot elevation)

Harsh RXBG-10 NP06-2-A-Room-701, 702, 703 and 704 (Figure 1.2-15 Reactor Building 146 foot 6 inch elevation)

Harsh

NuScale Final Safety Analysis Report Methodology for Environmental Qualification of Electrical and Mechanical Equipment NuScale US460 SDAA 3C-17 Draft Revision 2 Containment Vessel Zones CNV-1 NP06-2-A-Room 042, Containment Vessel - bottom of containment to bottom of upper core plate Harsh CNV-2 NP06-2-A-Room 042, Containment Vessel - bottom of upper core plate to lower riser top Harsh CNV-3 NP06-2-A-Room 042, Containment Vessel - lower riser top to upper riser top Harsh CNV-4 NP06-2-A-Room 042, Containment Vessel - upper riser top to top of RPV head Harsh CNV-5 NP06-2-A-Room 042, Containment Vessel - top of RPV head to bottom of torispherical head Harsh CNV-6 NP06-2-A-Room 042, Containment Vessel - bottom of torispherical head to top of containment Harsh Control Building Area Zones CRB-1 NP06-2-B-Room-012 through 021 (Figure 1.2-18 Control building 100 foot elevation)

Mild CRB-2 NP06-2-B-Room-120 through 137 (Figure 1.2-19 Control building 125 foot elevation)

Mild CRB-3 NP06-2-B-Room-001 through 011 (Figure 1.2-18 Control building 100 foot elevation)

Mild CRB-3E NP06-2-B Room-003 (Figure 1.2-18 Control building 100 foot elevation)

Harsh1 CRB-4 NP06-2-B-Room-101 through 119 (Figure 1.2-19 Control building 125 foot elevation)

Mild 1 Electronic equipment only Table 3C-1: Environmental Qualification Zones - Reactor Building (Continued)

Zone Description Environment

NuScale Final Safety Analysis Report Methodology for Environmental Qualification of Electrical and Mechanical Equipment NuScale US460 SDAA 3C-18 Draft Revision 2 Audit Question A-3.11-2 Table 3C-2: Designated Harsh Environment Areas Area Basis Comment/Remarks RXBP-1 Steam Exposure Harsh environment as a result of primary and secondary HELBs that occur in this area 120°F and > 18°F increase above normal operating conditions with RH 85%

Total integrated dose (60 yrs. + accident)

> 1.0E4 rad None RXBP-2 Steam Exposure Harsh environment as a result of primary and secondary HELBs that occur in the top of module 120°F and > 18°F increase above normal operating conditions with RH 85%

Total integrated dose (60 yrs. + accident)

> 1.0E4 rad None RXBP-3 Harsh environment as a result of primary and secondary HELBs that occur at the top of module 120°F and > 18°F increase above normal operating conditions due to DBA inside the CNV Total integrated dose (60 yrs. + accident)

> 1.0E4 rad None RXBP-4 Harsh environment as a result of primary and secondary HELBs that occur at the top of module 120°F and > 18°F increase above normal operating conditions due to DBA inside the CNV None RXBG-5E RXBG-7E CRB-3E These sub-regions are classified harsh for electronic equipment only due to Total integrated dose (60 yrs. +

accident) > 1.0E3 Rad.

CRB-3E sub-region dose rate exceeds harsh limits due only to filter loading during accident conditions.

None RXBG-1 through RXBG-4, RXBG-6, and RXBG-8 through RXBG-10 These areas contain high and moderate energy piping.

The note in Table 3C-3 clarifies classification of zones RXBG-5 and RXBG-7.

Note: The Radioactive Waste Building and Turbine Generator Building are considered Harsh Non-Environmental Qualification Zones.

NuScale Final Safety Analysis Report Methodology for Environmental Qualification of Electrical and Mechanical Equipment NuScale US460 SDAA 3C-19 Draft Revision 2 Audit Question A-3.11-2 Table 3C-3: Designated Mild Environment Areas Area Basis Comment/Remarks CRB-1 through CRB-4 Non-electronic equipment in CRB-3E No harsh environment DBA or IE are postulated to occur in this building.

Total integrated dose (60 years + accident) 1.0E43 rad Control Building (CRB) does not contain high energy piping systems (>200°F or > 275 psig) and flooding analysis demonstrates that no equipment required to perform a credited function is submerged Maximum temperature is 120°F with humidity < 85%

Satisfies mild environment criteria with the exception of exceeding the 1.0 E+03 rad threshold for electronics located in sub-region CRB-3E (Room 003)the elevation 100 mechanical equipment room (Room 003).

RXBG-5 and RXBG-7 Non-electronic equipment in RXBG-5E and RXBG-7E No harsh environment DBA or IE are postulated to occur in these rooms.

Total integrated dose (60 years + accident 1.0E4 rad) for electrical or mechanical equipment.

Maximum temperature is 120°F with humidity < 85%

Satisfies mild environment criteria with the exception of exceeding 1.0 E+03 rad threshold for electronics located in sub-regions RXBG-5E and RXBG-7E (Rooms 306, 319, 408, or 421)the corridors (Rooms 306, 319, 408, and 421).

NuScale Final Safety Analysis Report Methodology for Environmental Qualification of Electrical and Mechanical Equipment NuScale US460 SDAA 3C-22 Draft Revision 2 Audit Question A-3.11-2 Table 3C-6: Normal Operating Environmental Conditions Zone Temperature

(°F)

Pressure (psig)

(Nominal)

Maximum Relative Humidity (%)

60 Years Integrated N Dose (Rads) 60 Years Integrated Dose (Rads)

(Includes fission, N-, coolant)

Water Level (feet above RXB pool floor)

CNV-1 Figure 3C-2 (1)

-1314.684 0

8.2E+119.00E+11 1.6E+111.75E+11 Note 3 CNV-2 Figure 3C-2 (1)

-1314.684 0

2.9E+113.25E+11 4.5E+105.50E+10 Note 3 CNV-3 Figure 3C-4 (2)

-1314.684 0

4.3E+094.75E+09 1.7E+082.00E+08 Note 3 CNV-4 Figure 3C-4 (2)

-1314.684 0

1.2E+081.50E+08 1.4E+071.75E+07 Note 3 CNV-5 Figure 3C-4 (2)

-1314.684 0

5.9E+076.50E+07 7.7E+068.50E+06 Note 3 CNV-6 Figure 3C-4 (2)

-1314.684 0

3.5E+073.90E+07 1.6E+061.75E+06 Note 3 RXBP-1 140 0

< 85 1.8E+072.00E+07 3.1E+063.50+E06 0

RXBP-2 120 0

< 85 2.3E+042.50E+04 3.5E+044.00E+04 0

RXBP-3 120 0 + submergence head 5.8E+106.50E+10 2.2E+102.50E+10 53 +/- 1 RXBP-4 120 0 + submergence head 9.3E+051.50E+06 1.4E+081.75E+08 53 +/- 1 RXBG-1 105 0

< 85 8.5E+071.00E+08 RXBG-2 105 0

< 85 4.6E+045.10E+04 RXBG-3 105 0

< 85 2.3E+052.50E+05 RXBG-4 105 0

< 85 5.5E+026.10E+02 RXBG-5 85 0

< 85 5.3E+022.00E+03 RXBG-5E 85 0

< 85 1.8E+03 RXBG-6 105 0

< 85 1.6E+021.75E+02 RXBG-7 85 0

< 85 2.8E+023.00E+03 RXBG-7E 85 0

< 85 1.9E+03 RXBG-8 105 0

< 85 2.6E+043.00E+04 RXBG-9 105 0

< 85 2.2E+022.50E+02 RXBG-10 105 0

< 85 0.00E+00 CRB-1 68 Note 44.51E-03 (4)

< 85 CRB-2 68 Note 44.51E-03 (4)

< 85 CRB-3 68 Note 44.51E-03 (4)

< 85 CRB-3E 68 Note 4

< 85

NuScale Final Safety Analysis Report Methodology for Environmental Qualification of Electrical and Mechanical Equipment NuScale US460 SDAA 3C-23 Draft Revision 2 CRB-4 68 Note 44.51E-03 (4)

< 85 Notes: 1. Reactor pressure vessel (RPV) wall temperatures are shown as pressurizer (PZR) wall temperatures on Figure 3C-2 as the PZR wall temperature bounds the RPV temperatures at saturation conditions. CNV wall temperatures are shown Figure 3C-2.

2. Reactor pressure vessel wall temperatures are shown as PZR wall temperatures on Figure 3C-3 as the PZR wall temperature bounds the RPV temperatures at saturation conditions. CNV wall temperatures are shown Figure 3C-4.
3. Containment water level is 0 feet for normal power operation and is a maximum of 55 feet for all other conditions. For anticipated operational occurrence conditions the water level is 19 feet.
4. The CRB is maintained at a slightly positive air pressure to control ingress of airborne reactivity from the RXB or atmosphere outside of the CRB.

Table 3C-6: Normal Operating Environmental Conditions (Continued)

Zone Temperature

(°F)

Pressure (psig)

(Nominal)

Maximum Relative Humidity (%)

60 Years Integrated N Dose (Rads) 60 Years Integrated Dose (Rads)

(Includes fission, N-, coolant)

Water Level (feet above RXB pool floor)

NuScale Final Safety Analysis Report Methodology for Environmental Qualification of Electrical and Mechanical Equipment NuScale US460 SDAA 3C-24 Draft Revision 2 Audit Question A-3.11-2 Table 3C-7: Design Basis Event Environmental Conditions Zone DBE Temperature

(°F)(1)(2)(3)

DBE Pressure (psig)

DBE Relative Humidity (%)

Water Level(4)Water Level (feet above RXB pool floor)(4)

Pipe Rupture (water spray)

CNV-1 All Events Figure 3C-1 and Figure 3C-2 All Events 10051015 +

submergence head All Events 100 55 CNV-2 All Events Figure 3C-1 and Figure 3C-2 All Events 10051015 +

submergence head All Events 100 55 CNV-3 All Events Figure 3C-3 and Figure 3C-4 All Events 10051015 All Events 100 55 Yes CNV-4 All Events Figure 3C-3 and Figure 3C-4 All Events 10051015 All Events 100 55 Yes CNV-5 All Events Figure 3C-3 and Figure 3C-4 All Events 10051015 All Events 100 55 Yes CNV-6 All Events Figure 3C-3 and Figure 3C-4 All Events 10051015 All Events 100 55 Yes RXBP-1 HELB Figure 3C-5 HELB 6

All Events 100 55 Yes RXBP-2 HELB Figure 3C-6 HELB 6

All Events 100 55 RXBP-3 HELB 212 HELB 6 + submergence head All Events 55 RXBP-4 HELB 212 HELB 6 + submergence head All Events 55 RXBG-1 HELB 199 HELB 6

All Events 100 15 Yes RXBG-2 HELB 180 HELB 6

All Events 100 12.75 Yes RXBG-3 HELB 217223 HELB 6

All Events 100 12.75 Yes RXBG-4 HELB 163 HELB 6

All Events 100 7.8 Yes RXBG-5 HELB 120 HELBAll Events No appreciable change from normal All Events

< 85 12.750 RXBG-5E HELB 120 All Events No appreciable change from normal All Events

< 85 12.5 RXBG-6 HELB 181170 HELB 6

All Events 100 12.8 Yes RXBG-7 HELB 120 HELBAll Events No appreciable change from normal All Events

< 85 12.80 RXBG-7E HELB 120 All Events No appreciable change from normal All Events

< 85 12.8 RXBG-8 HELB 388393 HELB 6

All Events 100 5.9 Yes

NuScale Final Safety Analysis Report Methodology for Environmental Qualification of Electrical and Mechanical Equipment NuScale US460 SDAA 3C-25 Draft Revision 2 RXBG-9 HELB 175 HELB 6

All Events 100 4.2 RXBG-10 HELB 134 HELB 6

All Events 100 5.4 CRB-1 Passive Cooling 120 All Events No appreciable change from normal All Events

< 85 0.5 CRB-2 Passive Cooling 120 All Events No appreciable change from normal All Events

< 85 0.6 CRB-3 Passive Cooling 120 All Events No appreciable change from normal All Events

< 85 1

CRB-3E Passive Cooling 120 All Events No appreciable change from normal All Events

< 85 1

CRB-4 Passive Cooling 120 All Events No appreciable change from normal All Events

< 85 1.9 Notes: 1. The temperature listed represents the highest temperature of any room (outside of containment) in a given zone.

2. Reactor pressure vessel wall temperatures are shown as PZR wall temperatures on Figure 3C-2 as the PZR wall temperature bounds the RPV temperatures at saturation conditions. CNV wall temperatures are shown Figure 3C-2.
3. Reactor pressure vessel wall temperatures are shown as PZR wall temperatures on Figure 3C-3 as the PZR wall temperature bounds the RPV temperatures at saturation conditions. CNV wall temperatures are shown Figure 3C-4.
4. The water level listed represents the highest water level of any room (outside of containment) in the zone.
5. The CNV post-accident pH for any postulated accident that results in core damage is 6.9 at 1000 ppm boron concentration and 7.3 at 200 ppm boron concentration. These values remain essentially unchanged between 25 degree C and 200 degree C.

Table 3C-7: Design Basis Event Environmental Conditions (Continued)

Zone DBE Temperature

(°F)(1)(2)(3)

DBE Pressure (psig)

DBE Relative Humidity (%)

Water Level(4)Water Level (feet above RXB pool floor)(4)

Pipe Rupture (water spray)

NuScale Final Safety Analysis Report Methodology for Environmental Qualification of Electrical and Mechanical Equipment NuScale US460 SDAA 3C-26 Draft Revision 2 Audit Question A-3.11-2 Table 3C-8: Limiting Design Basis Accident EQ Radiation Dose Zone Dose Accident Integrated Dose (rads) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 36 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 720 hours CNV-1 Integrated 1.6E+021.75E+02 1.9E+032.00E+03 2.6E+032.75E+03 5.0E+035.00E+03 Integrated 5.8E+026.00E+02 4.7E+034.75E+03 5.9E+036.00E+03 1.1E+041.25E+04 CNV-2 Integrated 6.6E+046.75E+04 8.5E+058.50E+05 1.2E+061.25E+06 3.4E+063.50E+06 Integrated 2.2E+052.25E+05 1.8E+062.00E+06 2.3E+062.50E+06 4.2E+064.25E+06 CNV-3 Integrated 6.6E+046.75E+04 8.5E+058.50E+05 1.2E+061.25E+06 3.4E+063.50E+06 Integrated 2.2E+052.25E+05 1.8E+062.00E+06 2.3E+062.50E+06 4.2E+064.25E+06 CNV-4 Integrated 6.6E+046.75E+04 8.5E+058.50E+05 1.2E+061.25E+06 3.4E+063.50E+06 Integrated 2.2E+052.25E+05 1.8E+062.00E+06 2.3E+062.50E+06 4.2E+064.25E+06 CNV-5 Integrated 6.6E+046.75E+04 8.5E+058.50E+05 1.2E+061.25E+06 3.4E+063.50E+06 Integrated 2.2E+052.25E+05 1.8E+062.00E+06 2.3E+062.50E+06 4.2E+064.25E+06 CNV-6 Integrated 6.6E+046.75E+04 8.5E+058.50E+05 1.2E+061.25E+06 3.4E+063.50E+06 Integrated 2.2E+052.25E+05 1.8E+062.00E+06 2.3E+062.50E+06 4.2E+064.25E+06 RXBP-1 Integrated 8.1E+008.25E+00 3.0E+023.00E+02 5.8E+026.00E+02 8.0E+038.25E+03 Integrated 2.6E+032.75E+03 2.2E+042.25E+04 2.8E+043.00E+04 5.6E+045.75E+04 RXBP-2 Integrated 1.0E-011.25E-01 3.8E+004.00E+00 7.5E+007.75E+00 1.0E+021.25E+02 Integrated 2.6E+032.75E+03 2.2E+042.25E+04 2.7E+042.75E+04 4.9E+045.00E+04 RXBP-3 Integrated 1.0E-011.25E-01 3.8E+004.00E+00 7.5E+007.75E+00 1.0E+021.25E+02 Integrated 2.6E+032.75E+03 2.2E+042.25E+04 2.7E+042.75E+04 4.9E+045.00E+04 RXBP-4 Integrated 1.0E-011.25E-01 3.8E+004.00E+00 7.5E+008.00E+00 1.0E+021.25E+02 Integrated 2.6E+032.75E+03 2.2E+042.25E+04 2.7E+042.75E+04 4.9E+045.00E+04 RXBG-1 Integrated 3.0E+033.00E+03 1.2E+051.25E+05 1.5E+051.50E+05 3.1E+053.25E+05 Integrated 8.5E-018.75E-01 2.3E+012.50E+01 3.0E+013.00E+01 5.9E+016.00E+01 RXBG-2 Integrated 3.0E+033.00E+03 1.2E+051.25E+05 1.5E+051.50E+05 3.1E+053.25E+05 Integrated 8.5E-018.75E-01 2.3E+012.50E+01 3.0E+013.00E+01 5.9E+016.00E+01 RXBG-3 Integrated 3.0E+033.00E+03 1.2E+051.25E+05 1.5E+051.50E+05 3.1E+053.25E+05 Integrated 9.8E+011.00E+02 2.6E+032.75E+03 3.2E+033.25E+03 6.0E+036.25E+03 RXBG-4 Integrated 4.4E+024.50E+02 1.8E+042.00E+04 2.2E+042.25E+04 4.6E+044.75E+04 Integrated 8.6E-018.75E-01 2.3E+012.50E+01 3.0E+013.25E+01 6.0E+016.25E+01 RXBG-5 Integrated Integrated 1.00E+04 1.00E+04 1.00E+04 1.00E+04 RXBG-5E Integrated Integrated 1.0E+04 1.0E+04 1.0E+04 1.0E+04 RXBG-6 Integrated 3.4E+023.50E+02 1.3E+041.50E+04 1.7E+041.75E+04 3.5E+043.75E+04 Integrated 1.1E+001.25E+00 2.9E+013.00E+01 3.8E+014.00E+01 7.6E+017.75E+01 RXBG-7 Integrated Integrated 1.00E+04 1.00E+04 1.00E+04 1.00E+04 RXBG-7E Integrated Integrated 1.0E+04 1.0E+04 1.0E+04 1.0E+04 RXBG-8 Integrated 8.9E+029.00E+02 3.6E+043.75E+04 4.5E+044.50E+04 9.3E+049.50E+04 Integrated 8.5E+018.75E+01 2.2E+032.25E+03 2.8E+033.00E+03 5.4E+035.50E+03 RXBG-9 Integrated 8.9E+029.00E+02 3.6E+043.75E+04 4.5E+044.50E+04 9.3E+049.50E+04 Integrated 2.9E+003.00E+00 7.6E+017.75E+01 9.9E+011.00E+02 2.0E+022.00E+02 RXBG-10 Integrated 8.9E+029.00E+02 3.6E+043.75E+04 4.5E+044.50E+04 9.3E+049.50E+04 Integrated 2.9E+003.00E+00 7.6E+017.75E+01 9.9E+011.00E+02 2.0E+022.00E+02

NuScale Final Safety Analysis Report Methodology for Environmental Qualification of Electrical and Mechanical Equipment NuScale US460 SDAA 3C-27 Draft Revision 2 CRB-1 Integrated

< 1.0E+035.81E+

00

< 1.0E+035.81E+

00

< 1.0E+035.81E+

00

< 1.0E+035.81E+

00 Integrated

< 1.0E+035.42E+

00

< 1.0E+038.53E+

00

< 1.0E+031.05E+

01

< 1.0E+032.23E+

01 CRB-2 Integrated

< 1.0E+035.81E+

00

< 1.0E+035.81E+

00

< 1.0E+035.81E+

00

< 1.0E+035.81E+

00 Integrated

< 1.0E+035.42E+

00

< 1.0E+038.53E+

00

< 1.0E+031.05E+

01

< 1.0E+032.23E+

01 CRB-3 Integrated

< 1.0E+032.07E+

01

< 1.0E+037.20E+

02

< 1.0E+031.17E+

03

< 1.0E+033.79E+

03 Integrated

< 1.0E+035.42E+

00

< 1.0E+038.53E+

00

< 1.0E+031.05E+

01

< 1.0E+032.23E+

01 CRB-3E Integrated

< 1.0E+03

< 1.0E+03 1.3E+03 4.2E+03 Integrated 1.0E+03 1.0E+03 1.0E+03 1.0E+03 CRB-4 Integrated

< 1.0E+035.81E+

00

< 1.0E+035.81E+

00

< 1.0E+035.81E+

00

< 1.0E+035.81E+

00 Integrated

< 1.0E+035.42E+

00

< 1.0E+038.53E+

00

< 1.0E+031.05E+

01

< 1.0E+032.23E+

01 Table 3C-8: Limiting Design Basis Accident EQ Radiation Dose (Continued)

Zone Dose Accident Integrated Dose (rads) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 36 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 720 hours

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