ML022070508
| ML022070508 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/10/2002 |
| From: | NRC/NRR/DLPM/LPD2 |
| To: | NRC/NRR/DLPM |
| References | |
| Download: ML022070508 (12) | |
Text
Tennessee Valley Authority Browns Ferry Nuclear Plant Alternative Source Term Implementation
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TVA/NRC Meeting Nuclear Reactor Regulation - Rockville MD July 10, 2002
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Tim Abney I
Agenda
" Introduction/Meeting Objectives
"* Background
"* Analysis Overview
" Analysis Results
"* Submittal Content
"* Unit 1 Synergy
"* Summary and Conclusion
Introduction/Meeting Objectives LU
- Introduction
- Meeting Objectives Preview AST Analysis Results
- Discuss Submittal Content Describe Approach for Unit 1 Notify Staff of Schedule for Submittal and Need Date for Review Tim Abney 2
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Background===
LL71
- Initial Meeting with NRC Staff January 16, 2002
- Discussed AST Approach, Submittal Content and Schedule
- Contracted Polestar Applied Technology, Inc. to Perform Analysis
- Plan to Submit by July 31, 2002
- Approval Needed by April 2003, to Support Extended Power Uprate Tim Abney 3
Analysis Overview
- BFN Design Features All 3 Units Essentially Identical
- Pressurized Control Room
- Two Intakes for Control Room Emergency Ventilation (CREV) System 600 Feet Stack
- Common Secondary Containment for all 3 Units Main Steam Lines Seismically Rugged Henry Jones 4
Analysis Overview (Cont.)
- Analysis Scope
- Loss of Coolant Accident (LOCA)
Main Steam Line Break (MSLB)
- Refueling Accident (RA)
- Control Rod Drop Accident (CRDA)
Henry Jones 5
Analysis Overview (Cont.)
Analysis Assumptions Bounding Core Fission Product Inventory No Credit for Standby Gas Treatment Charcoal Adsorption No Credit for CREV Charcoal Adsorption No Credit for Drywell Spray Standby Liquid Control (SLC) System Operation for Suppression Pool pH Control ECCS Leakage Steamline and Condenser Model for Particulate Deposition New X/Q Instantaneous Ground Level Puff Release for Main Steam Line Break Henry Jones 6
Analysis Results Design Basis Accident LOCA MSLB RA CRDA Control Room Dose 1.25 rem (5 rem limit) 0.41 rem (5 rem limit) 0.38 rem (5 rem limit) 0.25 rem (5 rem limit)
Low Population Zone Dose 1.25 rem (25 rem limit) 0.65 rem (25 rem limit) 0.33 rem (6.3 rem limit) 0.68 rem (6.3 rem limit)
Exclusion Area Boundary Dose 1.02 rem (25 rem limit) 1.3 rem (25 rem limit) 0.67 rem (6.3 rem limit) 1.19 rem (6.3 rem limit)
Henry Jones 7
Submittal Content
" Consistent with RG 1.183 without Exception
" Extensive Effort to Incorporate Applicable RAIs from Previous AST Amendments
" Technical Specification Changes Eliminate Requirement for Charcoal in Standby Gas Treatment and CREV Systems Eliminate Requirement for Secondary Containment, Standby Gas Treatment, and CREV during Movement of Irradiated Fuel and Core Alterations Increase the Volume and Concentration of Sodium Pentaborate Solution in SLC Tank Henry Jones 8
Submittal Content (Cont.)
- Other License Changes
-Add New SLC System Function to Control Post-Accident Suppression Pool pH
-Delete License Condition That Was Previously Met Regarding Analysis of Design Basis Accident
- Affected FSAR Chapter 14 Sections for NRC Information Henry Jones 9
Unit 1 Synergy LLW STVA Plans to Restart Unit 1 by 2007 SAST is Being Requested for All 3 Units
-Only Refueling Accident Analysis Complete for Unit 1
-Due to Essentially Identical Units, Analysis is Expected to Give Similar Results
-Existing Unit 1 License Condition C. (4) States:
The licensee shall review the Technical Specification (TS) changes made by License Amendment No. 234 and any subsequent TS changes, verify that the required analyses and modifications needed to support the changes are complete, and submit them for NRC review and approval prior to entering the mode for which the TS applies. This amendment is effective immediately and shall be implemented prior to entering the mode for which the TS applies.
-License Condition Provides Basis to Approve AST for Unit 1 Tim Abney 10
Summary and Conclusion Tim Abney I1I