ML023030546
| ML023030546 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/16/2002 |
| From: | Entergy Operations |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML023030546 (19) | |
Text
AR Entemgy Waterford 3 Extended Power Uprate NRC/Entergy Meeting October 16, 2002
Af Entergy Agenda
"* Introduction & Objectives
"* Project Scope
- Project Schedule
- Plant Modifications
° Submittals
- Proposed Tech Spec Changes
- Specific Topic Discussion
- Open Discussion 10/14/2002 2
Ak
--Enterogy Introductions/Meeting Objectives
Introductions
Meeting Objectives
"° Inform NRC staff of Entergy's proposed plan, schedule, and approach for implementing an extended power uprate o Discuss submittal approach
"* Gain NRC insights from previous uprates 10/14/2002 3
Project Scope
- 8% increase (from 3441 to 3716 MWt)
- Maintain current Thot temperature
° Westinghouse Electric tasked with NSSS engineering scope
- Enercon Services tasked with BOP engineering scope 10/14/2002 4
-*-- En tergy
n Eteror/
Project Schedule
"° Scoping Study completed November, 2001
"° Submittal scheduled for September, 2003
"° NRC approval requested by January, 2005
"* Implementation during RF13, Spring 2005 10/14/2002 5
--*- En tergroy Plant Modifications
- Replace HP turbine
° Main Generator Rewind
- Replace generator output breakers
° Instrument setpoint changes
- Minor BOP changes as needed 10/14/2002 6
E**
En tergy Submittals
"* Submittal scheduled for September, 2003
"* Use ANO submittal as starting template
- consider RAIs from other submittals
° Utilize guidance of review standard once issued
- Related Submittals 10/14/2002 7
P oThEn teran Proposed Tech Spec Changes 10/14/2002 8
Parameter Current Value Proposed Value Rated Thermal Power 3441 3716 Cold Leg Temperature 541<Tc<558 OF 536<Tc<547 OF Pressurizer Pressure 2025<P<2275 2125<P<2275 Primary to Secondary Leakage 1 gpm / 720 gpd per SG 0.5 qpm / 360 qpd per SG MFIV Closure Times
< 5.0 seconds
< 6.6 seconds ADV N/A 1000 psia
Fuel &Core Design Impact 0 Larger Batch Size
° Reduced Fr Power Peaking Factor
"° Revised Physics Checklists
"* Fuel Performance Confirmation
"* Assessments of Fuel Rod Corrosion and Duty
"* Consistent with Experience Base 10/14/2002 9
E*-*n t ergy
-Entergy Transient Analysis Topics Use of CENTS vs. CESEC:
° CENTS generically approved for all CE plants
Entergy Transient Analysis Topics
- Scoping studies: can support 115% of OLP
° RCS pressurization events:
LOCV with LOOP is limiting AOO:
< 2750 psia maintained 10/1 4/2002 11
En t ergy Main Steam Line Break Post-trip Return-to-Power MS LB Analysis:
- Predicted fuel failure expected; more negative MTC a contributor
° Fuel failure previously predicted at other CE plants for RTP MSLB
- Will meet 10CFR100 limits 10/14/2002 12
SEterg/
"* Probable slight increase over current SAR 9.12% fuel failure
"* Will meet 10CFR100 acceptance criteria
° Will demonstrate <280 cal/gm energy deposition 10/14/2002 13
Entergy ECCS Performance Analysis LBLOCA:
109.5% of OLP e can support beyond
- 1999 EM:
10/14/2002 14 previously 1985 EM
'-----En tergqry ECCS Performance Analysis LOCA Long Term Cooling:
"° Post-LOCA Boric Acid Precipitation analysis will assume mixing volume of core and part of outlet plenum (currently credit core and lower plenum)
"* conservatisms in treatment of BAMT volume
"° analysis remains consistent with CENPD-254 methodology 10/14/2002 15
-- En tergy ECCS Performance Analysis SBLOCA:
e Credit automatic operation SBLOCA ECCS analysis
- ADV's Safety Related
° 1000 psia setpoint of ADV's for 0 No credit for Charging Pumps, ifpossible.
10/14/2002 16
En t ergy Containment Analysis Topics
° SAR 6.2 Containment Pressure-Temperature Analyses remain valid at 3716 MWt RTP
° Use of DDIFF code for subcompartment analysis
° Tributary line breaks selected for subcompartment analyses (credits leak before break, CEN-367) 10/14/2002 17
AE *Entergy Radiological Analyses
- Control room dose analyses:
- non-LOCA events
- increased in-leakage
- Alternative Source Term: separate submittal
"* New X/Q's to be generated for offsite dose and for Main Control Room dose
"* ICRP30 Dose Conversion Factors
"* Analysis to provide fuel failure percentage corresponding to SRP limits 10/14/2002 18
--En te roy Open Discussion NRC feedback:
"* recommendations/suggestions?
"* submittal templates?
"* Power Uprate Standard Review Plan items?
10/14/2002 19