ML062630481
| ML062630481 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 12/31/2005 |
| From: | Global Nuclear Fuel |
| To: | Office of Nuclear Reactor Regulation |
| Byrdsong A T | |
| References | |
| 50-271-OLA, Entergy-Licensee-8, RAS 12258 0000-0035-6443-SRLR, Rev 0 | |
| Download: ML062630481 (5) | |
Text
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1, DOCKET NUMBER PROD. & UTIL FAC. 5,-*7I-OL GNFý Global Nuclear Fuel A JoIrt Ventur d GE. Tostba, & HIta8Ch 0000-0035-6443-SRLR Revision 0 Class I December 2005 Supplemental Reload Licensing Report for Vermont Yankee Nuclear Power Station Reload 24 Cycle 25 (with Extended Power Uprate)
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- 8.
Operating Flexibility Options 4 The following information presents the operational domains and flexibility options which are supported by the reload licensing analysis. Inclusion of these results in this report is not meant to imply that these domains and options have been fully licensed and approved for operation.
Extended Operating Domain (EOD):
Yes EOD type: Maximum Extended Load Line Limit (MELLLA)
Minimum core flow at rated power:
99.0%
Increased Core Flow:
Yes Flow point analyzed throughout cycle:
Feedwater Temperature Reduction:
107.0%
ARTS Program:
Single Loop Operation:
No Yes Yes Yes Equipment Out of Service:
Safety/relief valves Out of Service:
(credit taken for 3 of 4 relief valves (I RV OOS))
- 9.
Core-wide AOO Analysis Results$
Methods used: GEMINI, GEXL-PLUS Operating domain: ICF(HBB)
Exposure range
Uncorrected ACPR Event Flux Q/A GE14C Fig.
Event_____________(%rated)
(%rated)
GE_4__Fig.
FW Controller Failure 354 121 0.26 2
Load Rejection w/o Bypass 382 119 0.28 3
Turbine Trip w/o Bypass 372 118 0.27 4
Inadvertent HPCI /L8 347 123 0.27 5
4 Refer to GESTAR for those operating flexibility options that are referenced and supported within GESTAR.
' Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 1i.
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Operating domain: ICF (HBB)
Exposure range
Uncorrected ACPR Event Flux Q/A
(%rated) (%rated)
GEI4C Fig.
FW Controller failure 379 123 0.26 6
Load Rejection w/o Bypass 400 120 0.27 7
Turbine Trip w/o Bypass 395 120 0.27 8
Inadvertent HPC] /L8 372 125 0.27 9
Operating domain: MELLLA (HBB)
Exposure range
Uncorrected ACPR Event Flux Q/A
___vent___________(%rated)
(%rated)
GEI4C Fig.
FW Controller Failure 314 119 0.25 10 Load Rejection w/o Bypass 328 116 0.26 1I Turbine Trip w/o Bypass 331 116 0.25 12 Inadvertent HPCI /L8 306 121 0.25 13 Operating domain: MELLLA (HBB)
Exposure range
Uncorrected ACPR Event Flux Q/A
(%rated) (%rated)
GEl4C Fig.
FW Controller Failure 328 120 0.25 14 Load Rejection w/o Bypass 337 117 0.26 15 Turbine Trip w/o Bypass 340 117 0.25 16 Inadvertent HPCI /L8 324 122 0.26 17 Page 9
VERMONT YANKEE Reload 24 0000-0035-6443-SRLR Revision 0 Operating domain: ICF (UB)
Exposure range
Uncorrected ACPR Event Flux QIA ent_________(%rated) (%rated)
GE14C Fig.
FW Controller Failure 250 115 0.25 18 Load Rejection w/o Bypass 301 114 0.27 19 Turbine Trip w/o Bypass 278 114 0.26 20 Inadvertent HPCI /L8 247 118 0.26 21 Operating domain: MELLLA (UB)
Exposure range
Uncorrected ACPR Event Flux Q/A GE14C Fig.
Event_____________(%rated)
(%rated)
GE_4__Fg.
FW Controller Failure 213 113 0.22 22 Load Rejection w/o Bypass 260 111 0.24 23 Turbine Trip w/o Bypass 238 112 0.24 24 Inadvertent HPCI /L8 207 115 0.23 25
- 10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary Rod withdrawal error (RWE) limits with ARTS are reported in Vermont Yankee Nuclear Power Station APRM/RBM/Technical Specifications / Maximum Extended Load Line Limit Analysis (ARTM/MELLLA),
NEDC-33089P, March 2003. A statistically based RWE limit of 1.40 is established in the Statistically Based Rod Withdrawal Error Analysis for Vermont Yankee Nuclear Power Station, GE-NE-0000-00 16 345 1-R0, July 2003.
A cycle specific analysis was performed for Vermont Yankee Cycle 25 to determine the MCPR corresponding to full withdrawal. (RBM was not credited in this analysis.) For the exposure range from BOC25 to EOC25, it is concluded that the statistically based RWE analysis value of 1.40 bounds the Cycle 25 specific analysis value. Therefore, it is the statistically based value that is reported in Section I I of the SRLR.
The RBM operability requirements specified in Section 3.4 of ARTS Report NEDC-33089P have been evaluated and shown to be sufficient to ensure that the Safety Limit MCPR and cladding 1 % plastic strain criteria will not be exceeded in the event of an unblocked RWE event.
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Operating domain: MELLLA (HBB)
Exposure range
Option A Option B GE14C GE14C FW Controller Failure 1.54 1.37 Load Rejection w/o Bypass 1.55 1.38 Turbine Trip w/o Bypass 1.55 1.38 Inadvertent HPCI /L8 1.55 1.38 Operating domain: ICF (UB)
Exposure range MOC to EOC (Application Condition: I )
Option A Option B
-GE14C GE14C FW Controller Failure 1.54 1.37 Load Rejection w/o Bypass 1.57 1.40 Turbine Trip w/o Bypass 1.56 1.39 Inadvertent HPCI /L8 1.55 1.38 Operating domain: MELLLA (UB)
Exposure range
-Option A
Option B GE14C GE14C FW Controller Failure 1.51 1.34 Load Rejection w/o Bypass 1.53 1.36 Turbine Trip w/o Bypass 1.53 1.36 Inadvertent HPCI /L8 1.52 1.35
- 12. Overpressurization Analysis Summary Psi Pdome Pv Plant (psig)
(psig)
(psig)
Response
MSIV Closure (Flux Scram) - ICF (HBB) 1302 1303
.1328 Figure 26 MSIV Closure (Flux Scram) - MELLLA (HBB) 1299 1300 1324 Figure 27 Page 13