ML050980075
| ML050980075 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/06/2005 |
| From: | Constellation Energy Group |
| To: | Office of Nuclear Reactor Regulation |
| Skay D | |
| References | |
| TAC MC4033 | |
| Download: ML050980075 (24) | |
Text
NRC Meeting April 6, 2005 4/5 12005 1
Ginna Uprate Project Goal is to continue close communication between the Ginna Uprate Project Team and NRC
- Introduction - Mark Finley
- PSA Approach - Rob Cavedo
- Pre-RSOO I Submittal LARs - George Wrobel
- Fuel Assembly - Mark Finley Li Questions 4/5/2005 2
Ginna Uprate Project Engineering Calculations and Reviews are 80%
Complete - No Surprises to Date RS-001 Submittal Planned for June 2005 Three LARs are Planned for April PSA Results Nearing Completion 4/5/2005 3
Ginna Uprate Project m
A Ag*
- 6 6
Key PRA Tasks for the Ginna Power Uprate Robert Cavedo 4/5/2005 4
Ginna Uprate Project Pre-Uprate Uprate (Prelim.)
CDF:
6.4E-5/yr 7.0E-5/yr LERF:
7.6E-6/yr TBD This includes internal events, fires, floods and shutdown events.
4/6/2005 4
Ginna Uprate Project Modification and Megawatt Changes can Impact:
Internal Events, External Events, Shutdown
- Human Action Timing n Component/System Reliability
- System Level Success Criteria 4/5/2005 6
Ginna Uprate Project System and Design Review Packages Contain a PSA Screening Form m Identifies margin reductions that could cause risk increases
- Provides a basis that there is no significant reduction in margin
- Significant changes will be incorporated into the PSA model 4/5/2005 7
Ginna Uprate Project S
j AID S.
S Human Action Timing and System Success Criteria will be Evaluated using PCTran and/or Design Calculations 4/5/2005 8
Ginna Uprate Project p
Ag 5
p PCTran has been used by the NRC as Early as 1986 and used as recently as Feb 2003 The Ginna version of PCTran has been benchmarked against MAAP runs and the UFSAR. PCTran Bleed-and-Feed cases have recently been reviewed by Westinghouse.
4/5/2005 9
Ginna Uprate Project Key Human Action Failure Rates will be Adjusted using the EPRI Human Action Methodology and the Revised Success Criteria The remaining Human Actions will be Conservatively Adjusted using the Time-Reliability Correlation (e.g. Hall 82 NUREG/CR-3010 or Swain 85 NUREG/CR-1278) 4/5/2005 10
Ginna Uprate Project We will Evaluate the Post-Uprate Risk Profile and Consider Cost Beneficial Modifications to Reduce Risk 4/5/2005 11
Ginna Uprate Project 4/5/2005 12
Ginna Uprate Project mReplace 80 second valve with 30 second valve
- Redundant to Feed Regulating Valve; safety-related; fail-safe mSI signal meets single failure criteria
- Not required to operate in harsh EQ environment inAction completion times changed from 24 to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> per ITS 4/5/2005 13
Ginna Uprate Project
- BELOCA method change in TS 5.6.5.b m ASTRUM method change in TS 5.6.5.b m SBLOCA (NOTRUMP addendum) method change in TS 5.6.5.b
- Accumulator water volume and BAC - SR 3.5.1.2 and 3.5.1.4
- RWST BAC - SR 3.5.4.2 4/6/2005 13
Ginna Uprate Project
- Heat flux hot channel factor m Axial Flux Difference m Quadrant Power Tilt Ratio (QPTR)
E RAOC method change in TS 5.6.5.b E Limits in COLR s Consistent with NUREG-1431, Rev. 3 4/5/2005 1 5
Ginna Uprate Project 4/5/2005 16
Ginna Uprate Project Ginna will implement the Westinghouse 14x14 422VW fuel assembly design for power uprate.
The first region will be inserted in the fall 2006 outage.
Assembly design is essentially the same as Point Beach and Kewaunee.
4/5/2005 17
Ginna Uprate Project The Ginna uprate fuel assembly is essentially the same as the Point Beach and Kewaunee assembly with the following exceptions:
Features/Design Types 14X14 422V+ GINNA 14X14 OFA GINNA 14X14 422V+ POINT F
(Uprate fuel assembly)
(Existing)
BEACH Overall Assembly Ref. + 0.2" Ref. + 0.16" Ref.
Height Type of Guide Thimble Tube-In-Tube Double Dashpot Single Dashpot Total Number of Grids 9
9 7
Mid Grid Design Balanced Vane Original Vane Original Vane Dimple Configuration 3T 2T 2T Fuel Rod Length Ref. + 0.2" Ref. - 3.4" Ref.
4/5/2005 18
Ginna Uprate Project I
i The tube-in-tube RCCA thimble design, dimple configuration and balanced vane mixing grids represent improvements in the generic Westinghouse design that have already been implemented for the 1 7x1 7 RFA-2 fuel assembly (i.e., these changes build in more margin for fuel rod fretting wear and IRI).
Ginna will retain the current grid separation (9-grid design) in order to match the reinsert OFA fuel.
The overall assembly height and fuel rod length differences represent minor adjustments to the generic design to accommodate fission gas release.
4/5/2005 19
Ginna Uprate Project 6
p 3
0 Westinghouse has completed a successful evaluation under the approved Fuel Criterion Evaluation Process (WCAP-1 2488-A) for the generic fuel design.
As part of the application of the generic 14x14 422 V+
design for Ginna, minor enhancements are made and a supplemental FCEP notification is forth coming.
Ginna intends to implement the 14x14 422V+ assembly design under the 10CFR50.59 process.
4/5/2005 20
Ginna Uprate Project 5
B
S.
S U
S Full scale VIPER and FACTS flow loop testing have been completed for the generic design to verify expected pressure drop, vibration and wear. Additional testing for the Ginna 9-grid design is now in progress.
Small scale VISTA flow loop testing has been completed to demonstrate acceptable FIV and high frequency vibration.
Mid-grid impact strength and stiffness have been verified through dynamic testing.
4/5/2005 21
Ginna Uprate Project Thermal-hydraulic stability characteristics are unchanged.
Parameters remain within the WRB-1 database.
LOCA, Non-LOCA and all other safety analysis parameters are unaffected.
4/5/2005 22
Ginna Uprate Project Transition core effects for reload 33 will be addressed through the cycle-specific reload process.
The methodology for the transition core analysis is based on NRC approved methodology:
DNB: WCAP-1 1837-P-A LOCA: WCAP-1 6009-P-A Seismic/LOCA/Grid Crush: WCAP-9 500-A 4/5/2005 23
Ginna Uprate Project 4/5/2005 24