ML22123A333

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Pre-Submittal Meeting 2: TSTF-51, TSTF-471, TSTF-490, and Alternative Source Term License Amendment Request - May 10, 2022 (EPID L-2022-LRM-0033)(slides)
ML22123A333
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 05/10/2022
From:
Southern Nuclear Company
To:
Office of Nuclear Reactor Regulation
Lamb, J.
References
EPID L-2022-LRM-0033
Download: ML22123A333 (41)
v • d • e


Text

Vogtle Units 1 & 2 PreSubmittal Meeting 2: TSTF51, TSTF471, TSTF490, and Alternative Source Term License Amendment Request Tuesday May 10th, 2022

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Overview

  • Purpose
  • Recap of 1st PreSubmittal Meeting
  • License Amendment Request (LAR) Overview
  • Table of Contents
  • Preliminary Dose Analyses Summary
  • Submittal and Requested Review Schedule
  • Comments and Discussion 2

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Purpose Discuss the following:

-An overview of the LAR contents

-SNC schedule for LAR submittal

-Requested LAR review duration 3

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Recap of 1st PreSubmittal Meeting

  • Requested use of AST to allow for peak burnup 62 GWD/MTU (covered by RG 1.183 Rev. 0)
  • Requested exception to allow up to 40% of rods in an assembly exceed RG1.183 Rev. 0 LHGR limit of 6.3 kW/ft

- Requested LHGR of 7.5 kW/ft for 40% of rods

  • Requested to include TSTF490 in the submittal
  • Meeting materials and notes can be found in

- ML21238A384; ML21172A131 4

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Recap of 1st PreSubmittal Meeting

  • Precedents for RG1.183 Rev. 0 Footnote 11 exception Plant  % of Rods Exceed ADAMS #

Kewaunee 50 ML070430020 Point Beach 100 ML110240054 Indian Point 2 100 ML042960007 Indian Point 3 100 ML050750431 Wolf Creek 10 ML19100A122 Vogtle 1 & 2 (Requested) 40 TBD 5

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License Amendment Request OverviewTSTFs

  • TSTF490 Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec (ML052630462)
  • TSTF51A, Rev. 2, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (ML040400343)
  • TSTF471A, Rev. 1, Eliminate Use of Term Core Alterations in Actions and Notes (ML19101A215) 6

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License Amendment Request OverviewAST Technical Evaluations

  • Technical Evaluations for AST:

- Atmospheric Dispersion Factors

>> Meteorological data used is same as in the approved analyses of record (AOR)

>> New Onsite X/Q dosereceptor pairs used for nonLOCA events (Fuel Building, ARV discharge to atmosphere)

- Core and RCS Source Terms

- Loss of Coolant Accident (LOCA)

- Fuel Handling Accident (FHA)

- Locked Rotor Accident (LRA)

- Control Rod Ejection Accident (CRE)

- Main Steam Line Break Accident (MSLB)

- Steam Generator Tube Rupture Accident (SGTR) 7

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License Amendment Request Overview (contd)

  • Key analysis specific descriptions and inputs included in the enclosures:

- Control Room Emergency Filtration System (CREFS) modeling specifics

- Analysis specific X/Qs

- Analysis specific gap fractions

- Generic Inputs

>> RCS mass and volumes

>> SG mass and volumes

>> Break flows (where applicable)

>> Primary to secondary flows (where applicable)

>> Atmospheric flows, leak rates, etc.

8

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License Amendment Request Overview (contd)

  • AST Accident Analysis Input Values Comparison Tables
  • Environmental Qualification

- Impacts evaluated using legacy approved approach (TID14844)

- EQ is unaffected by the adoption of AST methods 9

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LAR Table of Contents Enclosure 1.0 Summary of Description 2.0 Detailed Description 3.0 Technical Evaluation 4.0 Regulatory Evaluation 5.0 Environmental Evaluation 6.0 References 10

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LAR Table of Contents Attachments

1. Operating License and TS Markups
2. TS Bases Markups
3. RG 1.183 Conformance Tables
4. LOCA Analysis
5. FHA Analysis
6. MSLB Analysis
7. SGTR Accident Analysis
8. CRE Accident Analysis
9. LR Accident Analysis
10. AST Accident Analysis Input Values Comparison Tables 11

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Preliminary Dose Analyses Summary REM (TEDE)

Accident EAB LPZ CR Acceptance Criteria (EAB/LPZ/CR)

LOCA 8.4 9.6 4.4 25/25/5 FHA 1.0 0.4 3.9 6.3/6.3/5 LRA <0.1 <0.1 0.3 2.5/2.5/5 CRE* 1.5 1.8 1.1 6.3/6.3/5 MSLB** 0.2 0.2 0.2 2.5/2.5/5 SGTR*** 1.6 0.9 0.6 25/25/5

  • Containment release limiting for offsite. Secondary release limiting for onsite.
    • Concurrent Spike case is limiting and reported above (both analyzed)
      • Preaccident Spike case is limiting and reported above (both analyzed)

All doses demonstrate margin to regulatory limits 12

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Preliminary Dose Analyses Summary Accident Discussion LOCA Limiting analysis for dose (EAB/LPZ/CR)

1. Utilizes increased gap fractions for RG1.183 Footnote 11 exception (LHGR)
2. Unfiltered 2hour release from Fuel Building is limiting by inspection (X/Qs)

FHA

3. No credit for filtration or containment hatch closures
4. All doses demonstrate margin to regulatory limits LRA Not a significant contributor to dose CRE Containment release limiting offsite. Secondary release limiting for onsite MSLB Not a significant contributor to dose SGTR Not a significant contributor to dose 13

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Preliminary Dose Analyses Summary

  • Highlights

- LOCA

>> Most limiting accident for total dose

- FHA

>> Models 100% of rods as exceeding LHGR limit, even though only 40% could exceed

  • Uses increased release fractions for all damaged rods (314)
  • Decay time is 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> after shutdown 14

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Impact of TSTFs on AST Dose Analyses

  • TSTF490

- RCS equilibrium initial dose concentrations for noble gases based on dose equivalent Xenon - 133 at (280 µCi/g)

  • TSTF471 and TSTF51

- Applicable in shutdown modes where fuel movement or core alterations occur

- FHA analysis takes no credit for filtered ventilation or closure of containment hatches 15

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Proposed TS Changes

  • TS 3.3.6 Containment Ventilation Isolation Instrumentation
  • T 3.3.7 CREFS Actuation Instrumentation
  • T 3.8.2 AC Sources - Shutdown
  • T 3.8.5 DC Sources - Shutdown
  • TS 3.9.2 Unborated Water Source Isolation Valves
  • TS 3.9.7 Refueling Cavity Water Level 16

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TS 1.1 Definitions 17

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TS 1.1 Definitions 18

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TS 3.3.6 Containment Ventilation Isolation Instrumentation 19

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TS 3.3.6 Containment Ventilation Isolation Instrumentation 20

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T 3.3.7 CREFS Actuation Instrumentation 21

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TS 3.4.16 RCS Specific Activity 22

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TS 3.4.16 RCS Specific Activity 23

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TS 3.4.16 RCS Specific Activity 24

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TS 3.4.16 RCS Specific Activity 25

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TS 3.7.12 CREFS Both Units Shutdown 26

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TS 3.7.12 CREFS Both Units Shutdown 27

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T 3.8.2 AC Sources Shutdown 28

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T 3.8.2 AC Sources Shutdown 29

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T 3.8.5 DC Sources Shutdown 30

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TS 3.8.8 Inverters Shutdown 31

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TS 3.8.10 Distribution Systems Shutdown 32

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TS 3.8.10 Distribution Systems Shutdown 33

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TS 3.9.1 Boron Concentration 34

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TS 3.9.2 Unborated Water Source Isolation Valves 35

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TS 3.9.3 Nuclear Instrumentation 36

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TS 3.9.4 Containment Penetrations 37

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TS 3.9.7 Refueling Cavity Water Level 38

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Submittal and Requested Review Schedule NRC Review SNC Submit (Requested)

LAR Approval LAR June and approve July 2023 2022 LAR July 2022

- July 2023 39

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Comments and Discussion 40

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