ML021910610
| ML021910610 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/10/2002 |
| From: | Jabbour K NRC/NRR/DLPM/LPD2 |
| To: | |
| References | |
| Download: ML021910610 (13) | |
Text
NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9-1999)
TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed) by the person who announced the meeting (i.e., the person who issued the meeting notice). The completed form, and the attached copy of meeting handout materials, will be sent to the Document Control Desk on the same day of the meeting; under no circumstances will this be done later than the working day after the meeting.
Do not include proprietary materials.
DATE OF MEETING The attached document(s), which was/were handed out in this meeting, is/are to be placed 07/10/2002 in the public domain as soon as possible. The minutes of the meeting will be issued in the near future. Following are administrative details regarding this meeting:
Docket Number(s) 50-259, 50-260, and 50-296 Plant/Facility Name Browns Ferry Nuclear Plant, Units 1, 2, and 3 TAC Number(s) (if available)
Reference Meeting Notice 06/20/2002 Purpose of Meeting (copy from meeting notice)
To discuss the content and results of the alternative source term analysis for Browns Ferry Units 1, 2, and 3 NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE Kahtan N. Jabbour Senior Project Manager OFFICE Office of Nuclear Reactor Regulation DIVISION Division of Licensing Project Management BRANCH Project Directorate II, Section 2 Distribution of this form and attachments:
Docket File/Central File PUBLIC NRC FORM 658 (9-1999)
PRINTED ON RECYCLED PAPER This form was designed using InForms
I I
I
[
[
I
(
I I
I
(
I Tennessee Valley Authority Browns Ferry Nucdear Piant Alternative Source Term Implementation V
-
<4 ;
x
i9
TVAINRC Meeting Nuclear Reactor Regulation - Rockville MD July 10,2002 4,.
4 II
- Aug,
I I
I I
I
[
I I
Agenda
" Introduction/Meeting Objectives
" Background
" Analysis Overview
" Analysis Results
" Submittal Content
" Unit 1 Synergy
" Summary and Conclusion Tim Abney 1
Introduction/Meeting Objectives 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
i i
Background
" Initial Meeting with NRC Staff January 16, 2002
- Discussed AST Approach, Submittal Content and Schedule
" Contracted Polestar Applied Technology, Inc. to Perform Analysis
" Submittal in Final Approval
- Incorporates Applicable RAIs from Previous AST Amendments
" Plan to Submit by July 31, 2002
" Approval Needed by April 2003, to Support Extended Power Uprate Tim Abney
-5
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
I I
APnaysis Overview( (ont.)
- Analysis Scope
- Loss of Coolant Accident (LOCA)
Main Steam Line Break (MSLB)
- Refueling Accident (RA)
- Control Rod Drop Accident (CRDA)
Henry Jones 5
ffA
I I
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 z5
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
I I
[
I Unit 1 Synergy LW
- TVA Plans to Restart Unit 1 by 2007
- AST 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 IV
I I
I I
Summary and Conclusion Tim Abney 11 I
I I
i