ML021920064
| ML021920064 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/10/2002 |
| From: | Jabbour K NRC/NRR/DLPM/LPD2 |
| To: | |
| References | |
| Download: ML021920064 (16) | |
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) 50-260 and 50-296 Plant/Facility Name Browns Ferry Nuclear Plant, Units 2 and 3 TAG 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 extended power uprate submittal for Browns Ferry Units 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 NR FRM68 9-99)PRNEDONREYLE PPR hi or wsdesge01igInom NRC FORM 658 (9-1999)
PRINTED ON RECYCLED PAPER This form was designed using InForms
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Tennessee Valley Authority Browns Ferry Nuclear Plant Units 2 and 3 Extended Power Uprate
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Agenda
" Introduction/Meeting Objectives
"* Background
" Project Overview
" Submittal Content
" Applicability of Methodology to BFN
" Summary and Conclusion Tim Abney 1
Introduction/Meeting Objectives
"* Introduction
" Meeting Objectives
- Describe Submittal Content
- Discuss Other Required Changes to Licensing Basis
- Provide Basis for Applicability of Constant Pressure Power Uprate Methodology to BFN Tim Abney 2
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Background===
- TVA Board of Directors Approved Extended Power Uprate Project for Browns Ferry Units 2 and 3 in March of 2001
- TVA Met with NRC Staff December 5,2001, to Describe the Extended Power Uprate Project and Schedule
- Submittal in Final Approval
- Uses GE Constant Pressure Power Uprate (CLTR)
Methodology Incorporates Applicable RAI Questions from Previous Extended Power Uprates Tim Abney 3
Background (Cont.)
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- TVA Considered Environmental Impacts of Operation of all 3 BFN Units at 120% of Original Licensed Power for License Renewal Term and Issued Supplemental Environmental Impact Statement (SEIS)
- Public Meetings Held March 6, 2001 and January 17, 2002 Draft SEIS Published in Federal Register December 14, 2001 TVA Board Record of Decision Published in Federal Register June 18, 2002 Tim Abney 4
Project Overview 2001 2002 July 02 TVA Submittal To NRC For AST July 02 TVA Submittal To NRC For EPU Mar 03 K0 TVA Submittal To NRC for MELLLA+
Mar 03 TVA Submittal To NRC for Revised PT Curves Dec03 NRC SER For MELLLA+
Mar 04 NRC SER For PT Curves SprinC1 U2g3 Outage EPU EFll Imletation Unit-3 Spring U3C10 Outage Ed Hartwig Sp~ring U3C11 Outage EPU Full Imblementation 5
NRC SER For AST NRC SER For EPU Unit-2 Spring U2C1 1 Outage Spring U2C12 Outage
Submittal Content
- Consistent with Content and Level of Detail of GE Licensing Topical Report for Constant Pressure Power Uprate Will Justify Exclusion of Large Transient Testing Will Request Credit for Containment Overpressure for ECCS Suction NPSH
- Other Changes to Licensing Basis
- Revised P/T Curves (Separate Submittal)
- Alternative Source Term (Separate Submittal)
Jackie Wright 6
Applicability f Methodology to BFN
- BFN Analysis Supports Uprate to 3952 MWt
, Industry Experience in 1970s Little Large Plant Experience
- Rapid Plant Growth "o BWR2 - 640 MWe (1969)
"o BWR3 - 850 MWe (1971)
- BWR4 - 1100 MWe (1974)
. BWR5 - 1150 MWe (planned)
. BWR6 - 1500 MWe (planned)
- Planned Plants Exceeded Rotating Equipment Experience Base Ron Engel
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Applicability Of Methodology to BFN (Cont SNRC Reg Guide 1.49 Revision 0- May 1973
- Construction Permit Applications Limited to 3800 MWt Ultimate Power Level Limited to 4100 MWt Limitation Applies Until Sufficient Experience Gained with Design, Construction, and Operation of Larger Plants Ron Engel 8
Applicability Of Methodology to BFN (Cont
- NRC Reg Guide 1.49 Revision 1 - December 1973.
- Construction Permit Applications Limited to 3800 MWt Until January 1, 1979, at Earliest
- 2% Allowance in Power Level Adequate for Instrument Errors (Maximum of 3876 MWt)
Radiological Analyses Limited to 4100 MWt
- Acceptability to Increase Maximum Licensed Power Level to be Carefully Reviewed Ron Engel 9
Applicability Of Methodology to BFN (Cont)m
"* Operating Experience Supports Power Uprates up to 20%
"* Power Uprate Methodology Approved ELTR (February 1996)
CLTR (June 2002)
"* After Power Uprates, Large Plants Will Exceed 3800 MWt
"* Operating Experience Base Numerous Plants Licensed Power > 3200 MWt
". About 30 Years of Operation at the Oldest Facilities
"* No Safety or Operational Problems Attributed to Plant Size
"* Plants are Currently Licensed and Operating at a Higher Power Density than Browns Ferry After EPU Ron Engel 10
Applicability Of Methodology to BFN (Contim
" Browns Ferry Uprate Power Density = 60.3 kw/I Currently Licensed Power Density (GE14 Fuel)
BWR3 = 42.2 kwhI BWR4 = 60.9 kw/l BWR6 = 64.9 kw/I
"* Maximum Operating = 65.6 kw/Il (Foreign Plant)
- GE Analysis Methodology Methods Used Documented in PUSAR Code Limitations and Restrictions Observed Appropriate Use Confirmed Power Uprate Audits Performed by NRC
Applicability Of Methodology to BFN (Cont)
- GE Analysis Methodology
- Safety Analyses Consistent with 102% Power Requirement Increase in Power Does Not Significantly Change Plant
Response
- Increase in Decay Heat Well Defined
- Thermal-Hydraulic Conditions (Pressures, Temperatures, Flows, Void Fractions) Remain Within Experience Base
- Thermal-Hydraulic Conditions Controlled by GEXL Correlation
"* NRC Approved
"* Not Changed for Changes in Core Power Level Limitations on Bundle Power (MAPLHGR, LHGR and MCPR)
Constrain Plant Operation Ron Engel 12
Applicability Of Methodology to BFN (Cont)
"* Reg Guide 1.49 Constrains Construction Permit Applications
"* Substantial Body of Safe and Reliable Operation of Large Plants
"* Analysis Methodology Applicable Above 3800 MWt
" Fuel Operating Limitations Appropriate
"* No Technical Limitations Identified
"* License Submittal Provides Comprehensive Evaluations Ron Engel 13
Summary and Conclusion Tim Abney 14 RA.