RAIO-0218-58544, LLC Response to NRC Request for Additional Information No. 301 (Erai No. 9236) on the NuScale Design Certification Application

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LLC Response to NRC Request for Additional Information No. 301 (Erai No. 9236) on the NuScale Design Certification Application
ML18037A732
Person / Time
Site: NuScale
Issue date: 02/06/2018
From: Rad Z
NuScale
To:
Document Control Desk, Office of New Reactors
References
RAIO-0218-58544
Download: ML18037A732 (11)
v • d • e


Text

RAIO-0218-58544 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com February 06, 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 Response to NRC Request for Additional Information No.

301 (eRAI No. 9236) on the NuScale Design Certification Application

REFERENCE:

U.S. Nuclear Regulatory Commission, "Request for Additional Information No.

301 (eRAI No. 9236)," dated December 15, 2017 The purpose of this letter is to provide the NuScale Power, LLC (NuScale) response to the referenced NRC Request for Additional Information (RAI).

The Enclosure to this letter contains NuScale's response to the following RAI Question from NRC eRAI No. 9236:

11.05-1 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 Steven Mirsky at 240-833-3001 or at smirsky@nuscalepower.com.

Sincerely, Zackary W. Rad Director, Regulatory Affairs NuScale Power, LLC Distribution:

Gregory Cranston, NRC, OWFN-8G9A Samuel Lee, NRC, OWFN-8G9A Anthony Markley, NRC, OWFN-8G9A : NuScale Response to NRC Request for Additional Information eRAI No. 9236 Za Zackary W.

W Rad Director Regulatory Affairs

RAIO-0218-58544 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928 www.nuscalepower.com :

NuScale Response to NRC Request for Additional Information eRAI No. 9236

NuScale Nonproprietary Response to Request for Additional Information Docket No.52-048 eRAI No.: 9236 Date of RAI Issue: 12/15/2017 NRC Question No.: 11.05-1 11.5 RAI - Determination of RCS coolant leakage of 1.0 gpm within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Regulatory Basis: GDC 13, 30, and 64 In review of DCD sections 11.5.2.1.2, 11.5.2.2.7, and 11.5.2.2.8, the staff determined that there is not enough information presented in the DCD to verify the low end nominal ranges provided in DCD Table 11.5-1. 10 CFR Part 50, Appendix A, GDC 13 requires instrumentation to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety.

GDC 30 requires an applicant to identify sources of leakages. GDC 64, requires monitoring for the reactor containment atmosphere, spaces containing components for recirculation of loss-of-coolant accident fluids, effluent discharge paths, and the plant environs for radioactivity that may be released from normal operations, including anticipated operational occurrences, and from postulated accidents. Regulatory Guide 1.45 describes that all monitoring to detect leakages should be able to respond to a leakage increase of 1.0 gpm in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Key Issue:

The staff is unable to confirm the applicants ability to detect RCS coolant leakage based on the assumed RCS activities presented in DCD section 11.1.

As discussed in the audit, the staff requests the applicant provide the equations and data used to determine the RCS coolant leakage rates for the Condenser Air Removal System monitors (11.5.2.1.2), the Containment Evacuation System monitors (11.5.2.2.7) and the Main Steam System monitors (11.5.2.2.8). Information such as volumes, leakage rates, and assumed RCS activity concentrations should be clearly stated in the response. The staff also requests the applicant provide a discussion on the applicability of a plate out factor given the containment vessel design.

In addition the staff notes discussions in DCD sections 11.1.1.2 and 11.5.2 that mentions the injection of natural argon gas to maintain a constant level in the RCS coolant for leakage detection purposes. It is not clear to staff what the assumed level of Ar-41 will be in the RCS coolant. Is this value based on the primary coolant realistic source terms presented in DCD Table 11.1-6? Or is some higher level of Argon anticipated? If some level of Argon needs to be

NuScale Nonproprietary maintained where is the requirement specified?

The staff requests that the necessary methodology and parameters to perform this calculation be contained in DCD section 11.5. The necessary pointers, parameters, and applicable guidance needs to be clearly stated for the staff to make a determination of compliance with 10 CFR Part 50, Appendix A, GDCs 13, 30,and 64.

NuScale Response:

As described in FSAR Section 5.2.5 and Section 9.3.6.3, the primary means to detect and quantify reactor coolant system (RCS) pressure boundary leakage are changes in containment vessel (CNV) pressure and containment evacuation (CES) sample tank level. Radiation monitors in the CES gaseous discharge line and the CES sample tank provide indication of an RCS leak and the source of the leak, but are not primarily used to quantify the leak rate.

Primary to secondary tube leaks are monitored and quantified using main steam system (MSS) line monitors, condenser air removal system (CARS) monitors and secondary water sampling.

The MSS line monitors are designed to detect Ar-41, and the CARS monitors are capable of detecting various isotopes, including Ar-41, Cs-137, I-131 and other noble gases.

For the purposes of establishing radiation monitor ranges low end, the primary coolant activity concentration of Ar-41 is provided in FSAR Table 11.1-6, and is reported as 1.3314E-01 Ci/gram. The corresponding secondary coolant activity concentration of Ar-41 is provided in FSAR Table 11.1-7, and is reported as 7.1917E-07 Ci/gram. The activity concentrations in the secondary coolant was developed using the applicable parameters listed in FSAR Table 11.1-2 (Primary-to-secondary leak rate = 3.53 lb/day/unit; Argon injection concentration = 0.10 Ci/cc; Secondary coolant mass = 7.158E+04 lb; Secondary steam leak rate = 80 lb/hr/unit).

For the CARS Ar-41 radiation monitors, the nominal range for the Ar-41 detector has been revised to range from 1.0E-07 Ci/cc to 1.0E-01 Ci/cc. This revised low end of the range is more appropriate for detecting the realistic concentration of Ar-41 in the secondary coolant (FSAR Table 11.1-7), and conforms to ANSI N42.18-2004. Similarly, for the MSS line monitors, the nominal range has been revised to range from 1.0E-07 Ci/cc to 1.0E-01 Ci/cc. The range for the CES Ar-41 radiation monitors are also revised to range from 1.0E-07 Ci/cc to 1.0E-01 Ci/cc, however these monitors are not relied upon for quantifying primary coolant leakage into containment.

The injection of argon is an operational option in the event the primary coolant does not contain sufficient radionuclides to detect primary to secondary tube leaks. As discussed in FSAR Section 11.5.2, natural argon can be injected into the reactor coolant system using the guidance of EPRI 1022832, Steam Generator Management Program: PWR Primary to Secondary Leak Guidelines, Rev. 4. This guideline contains the methodology and equations for argon injection, and recommends an Ar-41 target concentration of 0.10 Ci/cc, with a high limit of 0.15 Ci/cc. If

NuScale Nonproprietary there are sufficient radionuclides in the primary coolant (e.g., due to failed fuel or activated corrosion products), injection of argon may not be required. The operating procedure to implement this methodology will be developed as part of COL item 5.4-1.

Because argon is a noble gas, there is no plate out effect within the containment vessel.

Impact on DCA:

Table 11.5-1 and Table 11.5-4 have been revised as described in the response above and as shown in the markup provided in this response.

NuScale Final Safety Analysis Report Process and Effluent Radiation Monitoring Instrumentation and Sampling System Tier 2 11.5-27 Draft Revision 1 RAI 11.05-1, RAI 15.00.03-8 Table 11.5-1: Process and Effluent Radiation Monitoring Instrumentation Characteristics System Quantity Type Service Isotopes Nominal Range Location/Function PAM Safety-related Media Instrument type ABS 2

ABS return flow from MHS Cs-137 1.0E-7 to 1.0E-2 Ci/ml ABS return flow from MHS heat exchangers 6A and 6B No No Liquid Adjacent-to-line ABS 2

ABS return flow from MHS Ar-41 3E-3 to 1E-11.0E-7 to 1.0E-1 Ci/cc ABS return flow from MHS heat exchangers 6A and 6B No No Gas Adjacent-to-line ABS 1

ABS high pressure condensate tank vent Ar-41 3E-3 to 1E-11.0E-7 to 1.0E-1 Ci/cc ABS 1100 psi condensate tank vent No No Gas Adjacent-to-line ABS 1

ABS high pressure boiler to low pressure boiler cross feed Ar-41 3E-3 to 1E-11.0E-7 to 1.0E-1 Ci/cc High pressure boiler to low pressure boiler cross feed No No Gas Adjacent-to-line ABVS 1

Radioactive waste building ventilation system (particulate)

Cs-137 3.0E-10 to 1.0E-6 Ci/cc Hot machine shop RWBVS exhaust air No No Gas Off-line BPDS 4

BOP drains Cs-137 1.0E-7 to 1.0E-2 Ci/ml Monitors condensate regeneration skid effluent and TGB drains.

No No Liquid In-Line BPDS 1

BOP drains Cs-137 1.0E-7 to1.0E-2 Ci/ml Inlet to 6A-BPD-TNK-0001 from ABS blowdown No No Liquid Adjacent-to-line CARS 12

Condenser air removal Sys Ar-41 3.E-3 to 1E+11.0E-7 to 1.0E-1 Ci/cc Condenser air removal skid - Ar-41 Yes No Gas Adjacent-to-line CARS 12

Condenser air removal sys (particulate)

Cs-137 3E-10 to 1E-6 Ci / cc Condenser air removal skid air particulate Yes No Gas Off-line (PING)

CARS 12

Condenser air removal sys (iodine)

I-131 3E-10 to 5E-8 Ci / cc Condenser air removal skid supply air iodine Yes No Gas Off-line (PING)

CARS 12

Condenser air removal sys (noble gas)

Kr-85 Xe-133 3E-7 to 1.0E+5 Ci/cc Condenser air removal skid (NG)

Yes No Gas Off-line (PING)

CVCS 12

CVCS suction from RCS sample line Cs-137 1E-7 to 1E-2 Ci / ml RCS discharge sample line No No Liquid Adjacent-to-line CES 12

Containment evacuation atmosphere gas Ar-41 3.E-3 to 1E+11.0E-7 to 1.0E-1 Ci/cc CES vacuum pump discharge line No No Gas Adjacent-to-line CES 12

Containment evacuation atmosphere gas (particulate)

Cs-137 3.E-10 to 1E-6 Ci/cc CES vacuum pump discharge line particulate No No Gas Off-line (PING)

NuScale Final Safety Analysis Report Process and Effluent Radiation Monitoring Instrumentation and Sampling System Tier 2 11.5-29 Draft Revision 1 GRW 2

GRW decay beds discharge lines Kr-85 Xe-133 3E-7 to 1E-2 Ci/cc Downstream of decay beds discharge line to HVAC exhaust No No Gas Off-line LRW 2

LRW discharge to environment Cs-137 1E-7 to 1E-2 Ci/ml LRW effluent discharge line to environment No No Liquid Adjacent-to-line MSS 24

MSS main steam line A Ar-41 3.E-3 to 1E+11.0E-7 to 1.0E-1 Ci/cc Main steam line A No No Gas Adjacent to-line MSS 24

MSS main steam line B Ar-41 3.E-3 to 1E+11.0E-7 to 1.0E-1 Ci/cc Main steam line B No No Gas Adjacent to-line PSCS 1

Pool surge control system Kr-85 Xe-133 3E-7 to 1E-2 Ci / cc Pool surge control storage tank vent line No No Gas Off-line RBVS 3

Spent fuel pool ventilation exhaust (particulate)

Cs-137 3E-10 to 1E-6 Ci / cc RBVS spent fuel pool and refuel dock exhaust air No No Gas Off-line (PING)

RBVS 3

Spent fuel pool ventilation exhaust (iodine)

I-131 3E-10 to 5E-8 Ci / cc RBVS spent fuel pool and refuel dock exhaust air No No Gas Off-line (PING)

RBVS 3

Spent fuel pool ventilation exhaust (noble gas)

Kr-85 Xe-133 3E-7 to 1.0E-2 Ci/cc RBVS spent fuel pool and refuel dock exhaust air No No Gas Off-line (PING)

RBVS 1

Reactor Building ventilation system (particulate)

Cs-137 3E-10 to 1E-6 Ci/cc RBVS general area exhaust air No No Gas Off-line RBVS 1

Reactor Building ventilation system (iodine)

I-131 3E-10 to 5E-8 Ci / cc RBVS general area exhaust air No No Gas Off-line RBVS 1

Plant vent particulate Cs-137 1E-7 to 1E-2 Ci/cc Plant exhaust stack Yes No Gas Off-line (PING)

RBVS 1

Plant vent iodine I-131 3E-10 to 1E-6 Ci/cc Plant exhaust stack Yes No Gas Off-line (PING)

RBVS 1

Plant vent noble gas (normal range)

Kr-85 Xe-133 3E-7 to 1E-2 Ci/cc Plant exhaust stack Yes No Gas Off-line (PING)

RBVS 1

/

Plant vent extended range gas (accident mid-range)

Kr-85 Xe-133 3E-7 to 1E+4 Ci/cc Plant exhaust stack Yes No Gas Off-line (PING)

RBVS 1

/

Plant vent extended range gas (accident high range)

Kr-85 Xe-133 3E-7 to 1E+4 Ci/cc Plant exhaust stack Yes No Gas Off-line (PING)

Table 11.5-1: Process and Effluent Radiation Monitoring Instrumentation Characteristics (Continued)

System Quantity Type Service Isotopes Nominal Range Location/Function PAM Safety-related Media Instrument type

NuScale Final Safety Analysis Report Process and Effluent Radiation Monitoring Instrumentation and Sampling System Tier 2 11.5-30 Draft Revision 1 RWBVS 1

Radioactive Waste Building ventilation system (particulate)

Cs-137 3E-10 to 1E-6 Ci/cc RWBVS exhaust air particulate No No Gas Off-line RWBVS 1

Radioactive Waste Building ventilation system (iodine)

I-131 3E-10 to 5E-8 Ci / cc RWBVS exhaust air iodine No No Gas Off-line RCCW 12

RCCW return lines from CES condensers Cs-137 1E-7 to 1E-2 Ci/ml RCCW return lines from CES condensers No No Liquid Adjacent-to-line RCCW 24

RCCW return lines from CVC NRHX and PSS coolers Cs-137 1E-7 to 1E-2 Ci/ml RCCW return lines from CVC NRHX and PSS coolers No No Liquid Adjacent-to-line RWDS 1

RCCWS water drained from the CVCS non-regenerative and RCCW HX Cs-137 1E-7 to 1E-2 Ci/ml RWDS tank-0020 No No Liquid Adjacent-to-line SCWS 1

Site cooling water Cs-137 1E-7 to 1E-2 Ci/ml From cooling tower to UWS discharge basin blowdown line No No Liquid Off-line with sampling capability SCWS 1

Site cooling water Cs-137 1E-7 to 1E-2 Ci/ml From cooling tower to UWS discharge basin overflow line No No Liquid Adjacent-to-line SCWS 3

SCW reactor pool cooling HXs return lines Cs-137 1E-7 to 1E-2 Ci/ml SCW reactor pool cooling HXs return lines prior to entering the main header No No Liquid Off-line SCWS 2

SCW spent fuel pool cooling HX return lines Cs-137 1E-7 to 1E-2 Ci/ml SCW spent fuel pool cooling HX return lines No No Liquid Off-line SCWS 4

SCW RCCW return lines Cs-137 1E-7 to 1E-2 Ci/ml SCW RCCW return lines No No Liquid Off-line TGSS 2

Turbine gland sealing system skid exhaust common vent, Turbine Building Ar-41 3.E-3 to 1E-11.0E-7 to 1.0E-1 Ci/cc Turbine generator skid common exhaust vent point Ar-41 No No Gas Adjacent-to-line TGSS 2

Turbine gland sealing system skid exhaust common vent, Turbine Building I-131 3E-10 to 5E-8 Ci / cc Turbine generator skid common exhaust vent point Iodine No No Gas Off-line (PING)

Table 11.5-1: Process and Effluent Radiation Monitoring Instrumentation Characteristics (Continued)

System Quantity Type Service Isotopes Nominal Range Location/Function PAM Safety-related Media Instrument type

NuScale Final Safety Analysis Report Process and Effluent Radiation Monitoring Instrumentation and Sampling System Tier 2 11.5-34 Draft Revision 1 RAI 11.05-1, RAI 15.00.03-8 Table 11.5-4: Effluent and Process Radiation Monitoring System Dynamic Ranges Radiation Monitor Dynamic Detection Range Principal Radionuclides Measured Basis for Dynamic Range A. Effluent Radiation Monitors RBVS 3E-7 to 1E+4 Ci /cc 1E-9 to 1E+2 Ci /cc 1E-9 to 1E+2 Ci /cc Noble gas (Kr-85, Xe-133):

Particulate (Cs-137):

Iodine (I-131):

  • Realistic Primary Coolant and Secondary Coolant Activity
  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 CARS 3E-3 to 1E+11.0E-7 to 1.0E-1 Ci /cc Ar-41:
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 CARS 3E-7 to 1E+5 Ci / cc 1E-9 to 1E+2 Ci / cc 1E-9 to 1E+2 Ci / cc Noble gas (Kr-85, Xe-133):

Particulate (Cs-137):

Iodine (I-131):

  • Realistic Primary Coolant and Secondary Coolant Activity
  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 TGSS 3E-3 to 1E+11.0E-7 to 1.0E-1 Ci /cc Ar-41:
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004

Particulate (Cs-137):

Iodine (I-131):

  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 PSCS 3E-7 to 1E-2 Ci / cc Noble gas (Kr-85, Xe-133):
  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 LRWS 1E-7 to 1E-2 Ci / ml Cs-137:
  • Realistic Primary Coolant and Secondary Coolant Activity
  • Best Estimate Fuel Isotopic Inventory Calculation

NuScale Final Safety Analysis Report Process and Effluent Radiation Monitoring Instrumentation and Sampling System Tier 2 11.5-36 Draft Revision 1 ABVS 3E-10 to 1E-6 Ci / cc Particulate (Cs-137):

  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 GRWS Common Discharge to HVAC 3E-7 to 1E-2 Ci / cc Noble gas (Kr-85, Xe-133)
  • Normal Effluent Release Source Term Calculation GRWS Decay Bed Discharge Lines 3E-7 to 1E-2 Ci / cc Noble gas (Kr-85, Xe-133)

Particulate (Cs-137)

Iodine (I-131)

  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004.

CES Vacuum Pump Discharge 3E-3 to 1E+11.0E-7 to 1.0E-1 Ci /

cc Ar-41:

  • Realistic Primary Coolant and Secondary Coolant Activity
  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 MSS 3E-3 to 1E+11.0E-7 to 1.0E-1 Ci /

cc Ar-41:

  • Realistic Primary Coolant and Secondary Coolant Activity
  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 CVCS*
  • Also area radiation monitors described in Section 12.3.4 1E-7 to 1E-2 Ci / ml Cs-137:
  • Realistic Primary Coolant and Secondary Coolant Activity
  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 Table 11.5-4: Effluent and Process Radiation Monitoring System Dynamic Ranges (Continued)

Radiation Monitor Dynamic Detection Range Principal Radionuclides Measured Basis for Dynamic Range

NuScale Final Safety Analysis Report Process and Effluent Radiation Monitoring Instrumentation and Sampling System Tier 2 11.5-37 Draft Revision 1 RCCWS 1E-7 to 1E-2 Ci / ml Cs-137:

  • Realistic Primary Coolant and Secondary Coolant Activity
  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 SCWS Heat Exchanger Outlets 1E-7 to 1E-2 Ci / ml Cs-137:
  • Realistic Primary Coolant and Secondary Coolant Activity
  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 SCWS Cooling Tower Basin Blowdown 1E-7 to 1E-2 Ci / ml Cs-137:
  • Realistic Primary Coolant and Secondary Coolant Activity
  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 SCWS Cooling Tower Basin Overflow 1E-7 to 1E-2 Ci / ml Cs-137:
  • Realistic Primary Coolant and Secondary Coolant Activity
  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 ABS Flash Tank Vent 3E-3 to 1E+11.0E-7 to 1.0E-1 Ci /cc Ar-41
  • Realistic Primary Coolant and Secondary Coolant Activity
  • Release of Radioactive Materials in Gaseous and Liquid Effluent
  • Best Estimate Fuel Isotopic Inventory Calculation
  • Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N42.18-2004 ABS MHS Return 3E-3 to 1E+11.0E-7 to 1.0E-1 Ci /cc Ar-41
  • NEI 97-06, Steam Generator Program Guidelines, Revision 3 Table 11.5-4: Effluent and Process Radiation Monitoring System Dynamic Ranges (Continued)

Radiation Monitor Dynamic Detection Range Principal Radionuclides Measured Basis for Dynamic Range

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