ML23304A447
| ML23304A447 | |
| Person / Time | |
|---|---|
| Site: | 05200050 |
| Issue date: | 10/31/2023 |
| From: | NuScale |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML23306A049 | List:
|
| References | |
| LO-152560 | |
| Download: ML23304A447 (1) | |
Text
NuScale Nonproprietary Response to SDAA Audit Question Question Number:A-4.3-8 Receipt Date:05/30/2023 Question:
Revise Table 4.3-2: Nuclear Design Parameters (for Equilibrium Cycle) to correct the Doppler temperature coefficient. The value presented in Table 4.3-2 shows a positive value of the Doppler temperature coefficient. NRC staff believes this is a typo. Please provide a markup correction to the FSAR.
Response
Table 4.3-2 of the Standard Design Approval Application Final Safety Analysis Report is updated as shown in the attached markups.
Markups of the affected changes, as described in the response, are provided below:
NuScale Nonproprietary
NuScale Final Safety Analysis Report Nuclear Design NuScale US460 SDAA 4.3-24 Draft Revision 1 Audit Question A-4.3-8 1 Figure 4.3-15 provides the moderator temperature coefficient as a function of power.
2 No xenon is assumed for the design-basis refueling boron concentration calculation.
Table 4.3-2: Nuclear Design Parameters (for Equilibrium Cycle)
Core Average Linear Power (kw/ft) 3.9 Heat Flux Hot Channel Factor 2.196 Maximum Enthalpy Rise Hot Channel Factor 1.4 Reactivity Coefficients Doppler temperature coefficient ($/F, least negative)
-2.1E-03 Doppler temperature coefficient ($/F, most negative)
-4.6E-03 MTC (HZP-hot full power (HFP), least negative) ($/F)1 0.010 to -0.010 MTC (HZP-HFP, most negative) ($/F)1
-0.060 to -0.140 Boron coefficient (pcm/ppm)
-10 Effective Delayed Neutron Fraction and Prompt Neutron Lifetime eff BOC 0.0064 eff EOC 0.0048 Prompt lifetime BOC (10-5seconds) 3.0 Prompt lifetime EOC (10-5seconds) 1.0 Control Rods CRA requirement Table 4.3-3 Maximum ejected rod Section 15.4.8 Bank Worth Figure 4.3-22 through Figure 4.3-25 Boron Concentration Limits (ppm)
Mode 1 1900 Mode 1 (equilibrium xenon) 1400 Reduction with fuel burnup Figure 4.3-19 Mode 2 600 Mode 3 650 Design-basis refueling2 1900