ML062640413

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Vermont Yankee Hearing - Entergy Exhibit 28, Global Nuclear Fuel, Supplemental Reload Licensing Report for Vermont Yankee, Reload 24 Cycle 25 (with Extended Power Uprate), Report No. 0000-0035-6443-SRLR (Rev. 0)
ML062640413
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 12/31/2005
From:
Global Nuclear Fuel - Americas
To:
Office of Nuclear Reactor Regulation
Byrdsong A T
References
50-271-OLA, Entergy-Licensee-28, RAS 12279 0000-0035-6443-SRLR, Rev 0
Download: ML062640413 (60)
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Text

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GNF. Gloal Nuclear Fuel A .Joint Venture of GE. Toshiba. &Hitachi 0000-0035-6443-SRLR Revision 0 DOCKET NUMBER * .... Class I

-PROD.& UTIL FAG, 5O- 61--4 December 2005 Supplemental Reload Licensing Report for Vermont Yankee Nuclear Power Station Reload 24 Cycle 25 (with Extended Power Uprate)

DOCKETED USNRC September 19, 2006 (3:37pm)

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VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF-A) solely for use by Entergy Nuclear Vermont Yankee ("Recipient") in support of the operating license for Vermont Yankee (the "Nuclear Plant"). The information contained in this report (the "Information") is believed by GNF-A to be an accurate and true representation of the facts known by, obtained by or provided to GNF-A at the time this report was prepared.

The only undertakings of GNF-A respecting the Information are contained in the contract between Recipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") and nothing contained in this document shall be construed as amending or modifying the Fuel Contract. The use of the Information for any purpose other than that for which it was intended under the Fuel Contract, is not authorized by GNF-A. In the event of any such unauthorized use, GNF-A neither (a) makes any representation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness of the Information or that such unauthorized use may not infringe privately owned rights, nor (b) assumes any responsibility for liability or damage of any kind which may result from such use of such information.

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VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Acknowledgement The engineering and rejoad licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by GNF - Fuel Engineering Services and GE Energy - NSA personnel. The Supplemental Reload Licensing Report was prepared by L. A. Leatherwood. This document has been verified by G. N. Marrotte.

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VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 The basis for this report is General Electric StandardApplicationfor Reactor Fuel, NEDE-2401 I-P-A 14, June 2000; and the U.S. Supplement, NEDE-2401 I-P-A-14-US, June 2000.

1. Plant-unique Items Appendix A: Analysis Conditions Appendix B: Decrease in Core Coolant Temperature Events Appendix C: ARTS Power and Flow Operating Limits Adjustments Appendix D: Implementation of Extended Power Uprate (EPU)

Appendix E: Stability Solution Option 1-D Exclusion and Buffer Regions at EPU Condition Appendix F: List of Acronyms

2. Reload Fuel Bundles Fuel Type FuelypeCycle Loaded Number Irradiated:

GE 14-P 10DNAB394-7G5.0/6G4.0- 1OOT- 150-T6-2566 (GE I4C) 23 92 GE 14-P 1ODNAB394-8G5.0/6G4.0- IOOT- I50-T6-2595 (GE I4C) 23 16 GEl 4-P 1ODNAB394-12G5.0-1OOT- 150-T6-2596 (GE14C) 23 20 GEl 4-P 1ODNAB426-16G6.0- IOOT- I50-T6-2682 (GEl 4C) 24 32 GEl 4-P 1ODNAB390-14GZ- IOOT- I50-T6-2683 (GE 14C) 24 44 GE 14-P 1ODNAB3 88-17GZ- IO1T- I50-T6-2684 (GE 14C) 24 40 New:

GE 14-P 1ODNAB383-1 7G6.0- IOOT- 150-T6-2865 (GE14C) 25 16 GE14-P 1ODNAB383- 13G6.0-1OOT- 150-T6-2863 (GE14C) 25 28 GE 14-P 1ODNAB383-14G6.0-100T- 150-T6-2864 (GE 14C) 25 32 GE 14-P 1ODNAB422-16GZ- IOOT- I50-T6-2862 (GE 14C) 25 48 Total: 368 Page 4

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0

3. Reference Core Loading Pattern Core Average Cycle Average Exposure Exposure 27305 MWd/MT 12153 MWd/MT Nominal previous end-of-cycle exposure: (24771 MWd/ST) (11025 MWd/ST)

Minimum previous end-of-cycle exposure (for cold 26976 MWd/MT 11823 MWd/MT shutdown considerations): (24472 MWd/ST) (10726 MWd/ST) 14829 MWd/MT 0 MWd/MT Assumed reload beginning-of-cycle exposure: (13453 MWd/ST) (0 MWd/ST)

Assumed reload end-of-cycle exposure (rated 29093 MWd/MT 14264 MWd/MT conditions): (26393 MWd/ST) (12940 MWd/ST)

Reference core loading pattern: Figure 1

4. Calculated Core Effective Multiplication and Control System Worth - No Voids, 200 C Beginning of Cycle, keffective Uncontrolled 1.118 Fully controlled 0.953 Strongest control rod out 0.988 R, Maximum increase in strongest rod out reactivity during the cycle (Ak) 0.0001 14264 MWd/MT Cycle average exposure at which R occurs (12940 MWd/ST)
5. Standby Liquid Control System Shutdown Capability Boron (ppm) Shutdown Margin (Ak)

(at 20(C) (at 160°C, Xenon Free)

Analytical Requirement Achieved 800 _>0.010 0.037 Page 5

VERMONT YANKEE 0000-0035-6443-SRLR Rplnnii 9! Revkioin 0

6. Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters Operating domain: ICF (HBB)

Exposure range  : BOC to MOC (Application Condition: 1)

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Design___ _(MWt) (1000 lb/hr) MCPR GE14C 1.45 1.43 1.29 1.040 7.244 110.6 1.35 Operating domain: ICF (HBB)

Exposure range  : MOC to EOC (Application Condition: 1)

Peaking Factors Fuel Local Radial Axial R-Factor Bundle Power Bundle Flow Initial Design (MWt) (1000 lb/hr) MCPR GEI4C 1.45 1.42 1.31 1.040 7.159 111.9 1.34 Operating domain: MELLLA (HBB)

Exposure range  : BOC to MOC (Application Condition: 1)

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow (1000 lb/hr) MCPR Design__ __(MWt)

GE14C 1.45 1.41 1.28 1.040 7.125 102.0 1.33 Operating domain: MELLLA (HBB)

Exposure range  : MOC to EOC (Application Condition: 1 )

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Design__ __(MWt) (1000 lb/hr) MCPR GE14C 1.45 1.40 1.30 1.040 7.054 103.0 1.33

' Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.

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VERMONT YANKEE 0000-0035-6443-SRLR Reload 94 Operating domain: ICF (UB)

Exposure range : MOC to EOC (Application Condition: 1 )

Peaking Factors Fuel Bundle Bundle Initial Local Radial Axial R-Factor Power Flow Design (MWt) (1000 lb/hr) MCPR GE14C 1.45 1.49 1.31 1.040 7.556 107.5 1.34 Operating domain: MELLLA (UB)

Exposure range : MOC to EOC (Application Condition: 1)

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Design GE14C 1.45 1.49 1.42 1.040 (MWt) 7.518 lb/hr)

(100098.3 MCPR 1.31

7. Selected Margin Improvement Options 2 Recirculation pump trip: No Rod withdrawal limiter: No Thermal power monitor: No Improved scram time: Yes (ODYN Option B)

Measured scram time: No Exposure dependent limits: Yes Exposure points analyzed: 2 Table 7-1 Cycle Exposure Range Designation Name Exposure Range 3 BOC to MOC BOC25 to EOR25-1213 MWd/MT (I 100 MWd/ST)

MOC to EOC EOR25-1213 MWd!MT (1100 MWd/ST) to EOC25 BOC to EOC BOC25 to EOC25 2 Refer to GESTAR for those margin improvement options that are referenced and supported within GESTAR.

3 End of Rated (EOR) is defined as the cycle average exposure corresponding to all rods out, 100% power/100%

flow, and normal feedwater temperature.

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VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0

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.

ExtendedOperating 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: 107.0 %

Feedwater Temperature Reduction: No ARTS Program: Yes Single Loop Operation: Yes Equipment Out of Service:

Safety/relief valves Out of Service: Yes (credit taken for 3 of 4 relief valves (I RV OOS))

9. Core-wide AOO Analysis Results 5 Methods used: GEMINI, GEXL-PLUS Operating domain: ICF (HBB)

Exposure range : BOC to MOC (Application Condition: I)

Uncorrected ACPR Event Flux Q/A GEI4C Fig.

(%rated) (%rated)

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.

5Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.

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VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Operating domain: ICF (HBB)

Exposure range  : MOC to EOC (Application Condition: I)

Uncorrected ACPR Event Flux Q/A GEI4C Fig.

(%rated) (%rated)

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 HPCI /L8 372 125 0.27 9 Operating domain: MELLLA (HBB)

Exposure range  : BOC to MOC (Application Condition: 1)

Uncorrected ACPR Event Flux Q/A GEI4C Fig.

(%rated) (%rated)

FW Controller Failure 314 119 0.25 10 Load Rejection w/o Bypass 328 116 0.26 11 Turbine Trip w/o Bypass 331 116 0.25 12 Inadvertent HPCI/L8 306 121 0.25 13 Operating domain: MELLLA (HBB)

Exposure range : MOC to EOC (Application Condition: I )

Uncorrected ACPR Event Flux Q/A GE14C Fig.

(%rated) (%rated)

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 0000-0035-6443-SRLR Reload 24 Revision 0 Operating domain: ICF (UB)

Exposure range  : MOC to EOC (Application Condition: I)

Uncorrected ACPR Event Flux Q/A GE14C Fig.

(%rated) (%rated)

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  : MOC to EOC (Application Condition: 1)

Uncorrected ACPR Event Flux Q/A GE14C Fig.

(%rated) (%rated)

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/RBMiTechnical Specifications / Maximum Extended Load Line Limit Analysis (ARTS/MELLLA),

NEDC-33089P, March 2003. A statistically based RWE limit of 1.40 is established in the Statistically Based Rod Withdrawal ErrorAnalysis for Vermont Yankee Nuclear Power Station, GE-NE-0000-00 16 345 1-RO, 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 II 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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VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0

11. Cycle MCPR Values 678 Two ioop operation safety limit: 1.07 Single loop operation safety limit: 1.09 Stability MCPR Design Basis: See Section 15 ECCS MCPR Design Basis: See Section 16 (Initial MCPR)

Non-pressurization events:

Exposure range: BOC to EOC GEI4C Loss of Feedwater Heating (See Appendix B) 1.20 Rod Withdrawal Error (full withdrawal) 1.40 Fuel Loading Error (misoriented) 1.28 Limiting Pressurization Events OLMCPR Summary Table:'

Appl. Exposure Range Option A Option B Cond. I GEI4C GEI4C I Normal Operation (w/ equipment in-service)

BOC to MOC 1.47 1.36

-IMOC to EOC 1.57 1.40 6 The two loop and single loop Safety Limit values include a 0.02 additional bundle uncertainty at the EPU condition as required by NRC and documented in VY Cycle 25 Extended Power Uprate (EPU)Safetiy Limit Minimum CriticalPower Ratio (SLMCPR), Letter, B. Vita (VY) to C. Collins (GNF), NEA-05-067, November 30, 2005. This restriction will remain in place until such time that NRC removes it.

Exposure range designation is defined in Table 7-1.

8 For single loop operation, the MCPR operating limit is 0.02 greater than the two loop value.

9 Each application condition (Appl. Cond.) covers the entire range of licensed flow and feedwater temperature unless specified otherwise. The OLMCPR values presented apply to rated power operation based on the two loop operation safety limit MCPR.

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VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Pressurization events: 10 Operating domain: ICF (HBB)

Exposure range : BOC to MOC (Application Condition: 1)

Option A Option B GE14C GEI4C FW Controller Failure 1.46 1.35 Load Rejection w/o Bypass 1.47 1.36 Turbine Trip w/o Bypass 1.46 1.35 Inadvertent HPCI /L8 1.47 1.36 Operating domain: ICF (HBB)

Exposure range : MOC to EOC (Application Condition: 1)

Option A Option B GE14C GEI4C FW Controller Failure 1.56 1.39 Load Rejection w/o Bypass 1.57 1.40 Turbine Trip w/o Bypass 1.56 1.39 Inadvertent HPCI /L8 1.57 1.40 Operating domain: MELLLA (HBB)

Exposure range : BOC to MOC (Application Condition: 1)

Option A Option B GEI4C GEI4C FW Controller Failure 1.44 1.33 Load Rejection w/o Bypass 1.46 1.35 Turbine Trip w/o Bypass 1.45 1.34 Inadvertent HPCI /L8 1.45 1.34

'0 Application condition numbers shown for each of the following pressurization events represent the application conditions for which this event contributed in the determination of the limiting OLMCPR value.

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VERMONT YANKEE 0000-0035-6443-SRLR 01 *,A 'M

.- w- -- Revision 0 Operating domain: MELLLA (HBB)

Exposure range : MOC to EOC (Application Condition: I)

Option A Option B GEI4C GEI4C 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 GEI4C GEI4C 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  : MOC to EOC (Application Condition: I)

Option A Option B GE14C GEI4C 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 Event Psi Pdome Pv Plant (psig) (psig) (psig) Response MSIV Closure (Flux Scram) - ICF (HBB) 1302 1303 1328 Figure 26 MSIV Closure (Flux Scram) - MELLLA 1299 1300 1324 Figure 27 (HBB) I f Page 13

VERMONT YANKEE 0000-0035-6443-SRLR 01*,1- IA I2fpaC~dn n

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13. Loading Error Results Variable water gap misoriented bundle analysis: Yes" Misoriented Fuel Bundle ACPR GE 14-P 1ODNAB426-16G6.0-1 OOT- I50-T6-2682 (GE I4C) 0.07 GE 14-P 1ODNAB390-14GZ- IOOT- 150-T6-2683 (GE 14C) 0.20 GEl 4-P 1ODNAB422-16GZ-1OOT-150-T6-2862 (GEl4C) 0.07 GE14-PI ODNAB383-14G6.0-1OOT-150-T6-2864 (GE14C) 0.09 GE 14-P 1ODNAB3 88-17GZ- IOOT- 150-T6-2684 (GE I4C) 0.21 GE14-PI ODNAB383-13G6.0-1OOT-150-T6-2863 (GEl 4C) 0.08 GE 14-P 1ODNAB383-17G6.0-1OOT- 150-T6-2865 (GE 14C) 0.08
14. Control Rod Drop Analysis Results This is a banked position withdrawal sequence plant, therefore, the control rod drop accident analysis is not required. NRC approval is documented in NEDE-2401 I-P-A-US.
15. Stability Analysis Results Vermont Yankee has implemented the Option l-D solution documented in Reference 15.1. The NRC approved ODYSY methodology (Reference 15.2) has been applied to this reload. ODYSY applications offer the benefit of more accurate simulations of BWR stability events and conditions. Option I-D has (1)

"prevention" elements (Exclusion and Buffer Regions) and (2) a "detect & suppress" element (MCPR safety limit (MCPRSL) protection provided by the flow-biased APRM flux trip for the dominant core wide mode of coupled thermal-hydraulic/neutronic reactor instability). Core and hot channel decay ratio calculations (Reference 15.3) to determine the Exclusion Region and additional bases demonstrate that core-wide is the predominant reactor instability mode for Vermont Yankee. The detect and suppress calculation (Reference 15.4) consists of (A) calculation of a 95% probability/95% confidence level statistically-based hot channel oscillation magnitude for anticipated core-wide mode reactor instability and (B) calculation of the stability-based Operating Limit MCPR (OLMCPR) which provides 95/95 MCPRSL protection.

The detect and suppress calculation requires the use of the Delta CPR over Initial MCPR Versus the Oscillation Magnitude (DIVOM) curve. Recent TRACG evaluations by GE have shown that the generic core-wide DIVOM curve specified in Reference 15.5 may not be conservative for current plant operating conditions for plants that have implemented Stability Option l-D. Specifically, a non-conservative deficiency has been identified for high power-to-flow ratios in the generic core-wide mode DIVOM 11Includes a 0.02 penalty due to variable water gap R-factor uncertainty.

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VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 curve. The deficiency results in a non-conservative slope of the associated core-wide DIVOM curve so that the APRM flux trip setpoint is too high. GE had made a Part 21 Notification on this issue. For Option I-D plants, the applicability of the core-wide mode DIVOM curve may be determined by comparing the core average power-to-flow ratio following a simulated flow runback on the rated rod line to approximately 30% of rated core flow to a value of 66 (MWt/Mlbm/hr) (Reference 15.6). If the core average power-to-flow ratio exceeds this value, then the generic core-wide mode DIVOM curve is not applicable and appropriate corrective actions should be taken. For Vermont Yankee, the calculated core average power-to-flow ratio is 71.7 (MWt/Mlbm/hr) for Cycle 25 EPU conditions, which confirms that the core-wide mode generic DIVOM slope value of 0.175 is not applicable. Therefore, a conservative DIVOM slope of 0.35 (twice the generic DIVOM slope of 0.175) was selected for Cycle 25 EPU operation.

(1) The Exclusion Region and Buffer Region were calculated for Cycle 25 operation. The regions are based on Reference 15.3 and are provided in Appendix E for EPU conditions.

(2A) The hot channel oscillation magnitudes at natural circulation, 45% rated core flow, and 55% rated core flow were determined for Cycle 25 EPU conditions. Revised values for 45% rated core flow and 55% rated core flow are used in the calculation of the stability-based OLMCPR.

(2B) The stability-based OLMCPR was calculated for Cycle 25 EPU conditions. The calculation demonstrated that reactor stability does not produce the limiting OLMCPR for Cycle 25 EPU operation.

It is shown that the rated OLMCPR, OLMCPR(1 00%P/ I00%F), is greater than the OLMCPR for a two pump trip scenario, OLMCPR(2PT), the OLMCPR at 100% rod line and 45% rated core flow, OLMCPR(100%RL/45%F), is greater than the OLMCPR at steady state, OLMCPR(SS,45%F), and that the OLMCPR at 100% rod line and 55% rated core flow, OLMCPR(100%RL/55%F), is greater than the OLMCPR at steady state, OLMCPR(SS,55%F). For this analysis, the rated OLMCPR, OLMCPR(100%RL/45%F), and OLMCPR(100%RL/55%F) values are used for comparison (Reference 15.4). For all scenarios considered, the criteria are met at EPU conditions.

OLMCPR(I00%P/100%F) > OLMCPR(2PT)

OLMCPR(100%RL/45%F) > OLMCPR(SS,45%F)

OLMCPR(100%RL/55%F) > OLMCPR(SS,55%F)

References:

15.1 Application of the "Regional Exclusion with Flow-Biased APRM Neutron Flux Scram" Stability Solution (Option I-D) to the Vermont Yankee Nuclear Power Plant,Licensing Topical Report, GENE-637-018-0793, July 1993.

15.2 ODYSY Application for Stability Licensing Calculations, Licensing Topical Report, NEDC 32992P-A, July 2001.

15.3 Vermont Yankee Cycle 25 Option I-D Stability Exclusion Region Analysis (EPU),

GE-NE-0000-0043-577 I-RO, December 2005.

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VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 15.4 Vermont Yankee Cycle 25 Option I-D Stability Detect and Suppress Analysis (EPU),

GE-NE-0000-0044-5878-RO, December 2005.

15.5 Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, Licensing Topical Report, NEDO-32465-A, August 1996.

15.6 Determination of Figure of Merit for Stability DIVOM Curve Applicability, OGO1-0228-001, July 16, 2001.

16. Loss-of-Coolant Accident Results 16.1 10CFR50.46 Licensing Results The ECCS-LOCA analysis is based on the SAFER/GESTR-LOCA methodology. The licensing results applicable to all fuel types in the new cycle are summarized in the following table:

Table 16.1-1 Licensing Results Core-Wide Licensing Local Ce-Wide Fuel Type Basis PCT Oxidation Reatio

(°F) (OF) (%)Reaction

(%) (%)

GE14C 1960 < 3.00 < 0.10 The SAFER/GESTR-LOCA analysis results for GE14C fuel type are documented in Section 16.4, Reference I.

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VERMONT YANKEE 0000-0035-6443-SRLR 0I-A 1 A 16.2 10CFR50.46 Error Evaluation The IOCFR50.46 errors applicable to the Licensing Basis PCT are shown in the tables below.

Table 16.2-1 Impact on Licensing Basis Peak Cladding Temperature for GEI4C I 0CFR50.46 Error Notifications PCT Impact (OF) 2003-05 Impact of postulated hydrogen-oxygen recombination 0 on PCT.

STotal PCT Adder (*F) 0 The GE14C Licensing Basis PCT remains below the IOCFR50.46 limit of 2200'F.

16.3 ECCS-LOCA Operating Limits The ECCS MAPLHGR operating limits for the fuel bundles in this cycle are shown in the tables below.

Table 16.3-1 MAPLHGR Limits Bundle Type: GE 14-P 1ODNAB426-16G6.0- 100T- 150-T6-2682 (GEl 4C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 21.08 19.12 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Table 16.3-2 MAPLHGR Limits Bundle Type: GE 14-Pi ODNAB390-14GZ- IOOT- 150-T6-2683 (GE 14C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 21.08 19.12 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Page 17

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Table 16.3-3 MAPLHGR Limits Bundle Type: GE 14-P 1ODNAB422-16GZ- 1OOT- 150-T6-2862 (GE 14C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 21.08 19.12 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Table 16.34 MAPLHGR Limits Bundle Type: GE14-PiODNAB383-14G6.0-IOOT-150-T6-2864 (GEI4C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 21.08 19.12 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Table 16.3-5 MAPLHGR Limits Bundle Type: GE1 4-PI ODNAB388-17GZ-1 OOT-150-T6-2684 (GEl 4C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 21.08 19.12 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Table 16.3-6 MAPLHGR Limits Bundle Type: GE 14-Pi ODNAB383-13 G6.0-1 OOT- 150-T6-2863 (GE 14C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 21.08 19.12 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Page 18

VERMONT YANKEE 0000-0035-6443-SRLR PV1,.A IA 12-vic;nn Q Table 16.3-7 MAPLHGR Limits Bundle Type: GE 14-P 1ODNAB383-17G6.0-1OOT- 150-T6-2865 (GE 14C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 21.08 19.12 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Table 16.3-8 MAPLHGR Limits Bundle Type: GE 14-P 1ODNAB394-7G5.0/6G4.0-1OOT- 150-T6-2566 (GE 14C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 21.08 19.12 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Table 16.3-9 MAPLHGR Limits Bundle Type: GEl 4-P 1ODNAB394-8G5.0/6G4.0-1OOT- 150-T6-2595 (GE 14C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 21.08 19.12 12.82 63.50 57.61 8.00 70.00 63.50 5.00 Page 19

VERMONT YANKEE 0000-0035-6443-SRLR D I A ')A Rpvi~inn Al Revision 0 Table 16.3-10 MAPLHGR Limits Bundle Type: GE14-PIODNAB394-12G5.0-1OOT-150-T6-2596 (GEI4C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 21.08 19.12 12.82 63.50 57.61 8.00 70.00 63.50 5.00 The single-loop operation multiplier on PLHGR and MAPLHGR and ECCS analytical Initial MCPR values applicable to each fuel type in the new cycle core are shown in the table below.

Table 16.3-5 Initial MCPR and Single Loop Operation PLHGR and MAPLHGR Multiplier Single Loop Operation Fuel Type Initial MCPR PLHGR and MAPLHGR Multiplier GEI4C 1.275 0.82 16.4 References The SAFER/GESTR-LOCA analysis report applicable to the new cycle core is listed below for each fuel type. The report is based on a power level of 1912 MWt. ECCS-LOCA results at this power level bound any lower power levels.

References for GEI4C

1. Entergy Nuclear Operations Incorporated Vermont Yankee Nuclear Power Station Extended Power Uprate ECCS-LOCA SAFER/GESTR, GE-NE-0000-0015-5477-01, July 2003.

Page 20

VERMONT YANKEE 0000-0035-6443-SRLR R Innrl 94 Revision 0 44 [H] EH*][EH SHEH [HE 42 40 38 36

[] EHEH))[H] [ AE _l*[C*[E]_DEE [D [A] [H]EJ:]ED [E] L 34 32 3_*U1 CEOI E

[ElIEED ElACEDB F~~J~I

+1;B OH D *D[E

[]E]D,HO 8[E] [g[]

F [CD GE CA*

0i B I

[2]1[E]DI*L*

30

'!*[H] 0D [ID__ I*tE* ][ U_* _* D*I*

28 S 1EI] I9* ] M _W* E-L1 U9L*ILTD &I E[]ID*_LD0 26 24 E[,

IL*Ec D[F]EI[D[1] [_OmlD Ij* ][ ][ *LD[

22 *3_*DU [][ _* jD*LEDl*ID] [Ell*S DID ME]

20 18 ElHM ACE*D 19 [PIR] B] F] M H88HBFD l*_* IDD [M 0 BD0F] DFE A]

16 14 12 10 8

6 4

2 1 3 5 7 9 E] 1 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 Fuel Type A=GE14-PI ODNAB426-16G6.0-100T- 150-T6-2682 (Cycle 24) F=GE] 4-PI ODNAB383-13G6.0- OOT- 150-T6-2863 (Cycle 25)

B=GE]4-PIODNAB390-14GZ-IOOT-150-T6-2683 (Cycle 24) G=GE14-PIODNAB383-17G6.0-1OOT-150-T6-2865 (Cycle 25)

C=GE]4-PIODNAB422-16GZ-IOOT-150-T6-2862 (Cycle 25) H=GE14-PIODNAB394-7G5.0/6G4.0-1OOT-150-T6-2566 (Cycle 23)

D=GE14-PIODNAB383-14G6.0-1 OOT- I50-T6-2864 (Cycle 25) I=GE I4-PI ODNAB394-8G5.0/6G4.0-10OT-1 50-T6-2595 (Cycle 23)

E=GE14-PIODNAB388-17GZ-1OOT-150-T6-2684 (Cycle 24) J=GE 14-PIODNAB394-12G5.0-1OOT-150-T6-2596 (Cycle 23)

Figure 1 Reference Core Loading Pattern Page 21

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Iw U 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Tine (sec) Tam (sec) 150.0 0

U 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Tmfe (sec) Time (sec)

Figure 2 Plant Response to FW Controller Failure (MOC ICF (HBB))

Page 22

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0

-a- Dome Press Rise (psi)

---.-Relief SafetyVave Va FlowRow Bypass Valve FRow 150.0 200.0

.-I l100.0 NU 100.01 0.0 I 0.0 3.0 6.0 0.0 3.0 &0 Time (sec) Thn=e (sec) 8 aC 100.0 20 0n 3.0 6.0 0.0 3.0 6.0 Tim- 5Cc) Tfim (sec)

Figure 3 Plant Response to Load Rejection w/o Bypass (MOC ICF (HBB))

Page 23

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 0

0000-0035-6443-SRLR Revision

--- Dorne Press Rise (psi) afety Valfe Flow 3C 0- Relief Va Flow

-. Bypass Valve Row U*2 00 12100.0 I10.0 0.0 - -I* -

0.0 3.0 6.0 0.0 3.0 6.0 Tum= (sec) Time (sec)

E a

9U

-100.0 4 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Figure 4 Plant Response to Turbine Trip w/o Bypass (MOC ICF (HBB))

Page 24

VERMONT YANKEE 0000-0035-6443-SRLR R*Inad 94A Reviqion 0 Reload 24 2MO.0

-e W~uton FILtz'10

-- A~e Surfac Float RwLD

.~Core Let Flow

-- Core 'Let Subcooling 150.0 S10D.0 50.0 0.0 0.0 10.0 20.0 30.0 40.0 50.0 0.0 10.0 20.0 30.0 40.0 50.0 Time (sec) Time (sec) 150.0 U

100.0 5

C U

50.0 0.0 0.0 10.0 20.0 30.0 40.0 50.0 0.0 10.0 20.0 30.0 40.0 50.0 Tine (sec) Tfm* (sec)

Figure 5 Plant Response to Inadvertent HPCI L8 (MOC ICF (HBB))

Page 25

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 U

0.04I 0.0 10.0 20.0 30.0 0.0 10.0 2D.0 30.0 Tune (sec) Time (Sec) 150.0 V.

2 0

50.0 0.0 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Tune (see) Time (sec)

Figure 6 Plant Response to FW Controller Failure (EOC ICF (HBB))

Page 26

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 100.0

- 0.0 0.0 3.0 6.0 0.0 &( 6.0 Time (sec) Tuner (Sec) 1.0 U

0 .0

-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Tune (sec) Time (sec)

Figure 7 Plant Response to Load Rejection w/o Bypass (EOC ICF (HBB))

Page 27

VERMONT YANKEE 0000-0035-6443-SRLR w

Dome

.fety Press

-e-- Sa- Rise (psi)

Vah Flow 3C o.o.- Relief VaFlow

-- Bypass WV-e Row 0.0 102 lf3 0.0 0.0 3.0 6.0 0.0 &e 6.0 Tune (see) Tinm (sec)

I U

6 I

0.0 3.0 6.0 0.0 3.0 6.0 Tune (sec) Time (sec)

Figure 8 Plant Response to Turbine Trip w/o Bypass (EOC ICF (HBB))

Page 28

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 V

0.0 10.0 20.0 30.0 40.0 50.0 0.0 10.0 20.0 30.0 40.0 50.0 Time (sec) Time (sec) 150.0-6 10500.0 50.0-0.0 10.0 20.0 30.0 40.0 50.0 0.0 10.0 20.0 30.0 40.0 50.0 Time (see) Time (sec)

Figure 9 Plant Response to Inadvertent HPCI !L8 (EOC ICF (HBB))

Page 29

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 10 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Time (see) Tum (see)

E3 Lev(inch-REF-SEP-SKRI"

-*- Vessel Steam Flow 150.01

50.0 U.U i I I - - A -'-

0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 T-ue (see) Time (sec)

Figure 10 Plant Response to FW Controller Failure (MOC MELLLA (HBB))

Page 30

VERMONT YANKEE 0000-0035-6443-SRLR P*l*nA )A Rpviv~rnt A

--- Dome Press Rise (psi)

--- Safe VMale F'kN

-ReidWve FAm

--- Bypass \vae Row

.02W.0 100.0 100.0 t U.U 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tume (sec) 0 VJ 0.0 30 6.0 0.0 3.0 6.0 Time (sec) Time (sec)

Figure I I Plant Response to Load Rejection w/o Bypass (MOC MELLLA (HBB))

Page 31

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Nmutcg F1lux 10 Doe Press Rise (psi) x~ Am Surface Weda RLDx S

---Relief Vaele Flow Vale Flo 300.0 i

-& Core Irilet Flowv

-%- Bypass Vale Flow 150.0 200~.0 I100.0 100.0

(- - - 75-0.0 3.0 6.0 0.0 3.0 6.0 Tune (sec) Tine (sec)

E 0.0 3.0 6.0 0.0 3.0 6.0 Tmne (sec) Time (sec)

Figure 12 Plant Response to Turbine Trip w/o Bypass (MOC MELLLA (HBB))

Page 32

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 4J 100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) T-me (sec) 150.0

,01000 C C

S C

L) 50.0 I 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Tune (sec)

Figure 13 Plant Response to Inadvertent HPCI 1L8 (MOC MELLLA (HBB))

Page 33

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 200.0 150.0 10D.0 50.0 0.0 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Tnre (sec) Time (sec) 150.0 100.0 r

0 0

50.0 0.0 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Ti'm (sec) Tine (sec)

Figure 14 Plant Response to FW Controller Failure (EOC MELLLA (HBB))

Page 34

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 100.0 0.02-0.0 3.0 6.0 0.0 3.0 6.0 Tinm (sec) T-m~ (Sec)

G, I-i 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (see)

Figure 15 Plant Response to Load Rejection w/o Bypass (EOC MELLLA (HBB))

Page 35

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0

- Dcme Press Rise (psi)

-- -*-Relief SafetyVa Flow VaKoe Raw

-.- Bypass Vave Flow

, 2W0.0 100.0 0.01 0 x.

0.0 3.0 6.0 0.1 3.0 6.0 Tine (sec) Time (Sec) o=

ov U 0J 2J 0.0 3.0 6.0 0.0 3.0 6.0 TI'Me (sec) Time (sec)

Figure 16 Plant Response to Turbine Trip w/o Bypass (EOC MELLLA (HBB))

Page 36

VERMONT YANKEE 0000-0035-6443-SRLR D ý I w"~A IA IDn- I ; ý ;-l A Sb 0.0 10.0 20.0 0.0 10.0 20.0 Tinr (sec) Tune (sec)

C 0

U Sb 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Ture (see)

Figure 17 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA (HBB))

Page 37

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 4J 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0

-Tme (sec) Time (sec) 150.0 100.0 U

0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Thmi (sec) T-ue (see)

Figure 18 Plant Response to FW Controller Failure (EOC ICF (UB))

Page 38

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 200.0

-R NautronnFux/I10 x*~Aw.e Surface t-oat Flux

--- Core kInet Raw~~

150.01 11 4100.0 50.0 t-0.0 3.0 6.0 0.0 3.0 6.0 Tfnf (sec) T'mx (sec)

E 0

0.0 3.0 6.0 0o 3.0 6.0 Tine (sec) Time (sec)

Figure 19 Plant Response to Load Rejection w/o Bypass (EOC ICF (UB))

Page 39

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0

- Dome Press Rise (psi)

- - Safety VaKe Floa 300.0 *---RefiefVve Row

-.- Bypass Va\ke FRc 200.0 100.01 f-0.0 3.0 6.0 0.0 3.0 6.0 Tine (sc) Time (sec) 200.0 100.0O V

0.0

-1000.

0.0 3.0 6.0 0.0 3.0 6.0 Tune (Sec) Tine (see)

Figure 20 Plant Response to Turbine Trip w/o Bypass (EOC ICF (UB))

Page 40

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 ID..i 100 25.0

- - ---- 0 0.0 10.0 20.0 30.0 40.0 50.0 0.0 10.0 20.0 30.0 40.0 50.0 Tinr (sec) -rne(Sec) 150.0 a

10 100.0 Ia 0.

20 U

S U

0.0 10.0 20.0 30.0 40.0 50.0 0.0 10.0 20.0 30.0 40.0 50.0 Tinm (sec) Time (Sec)

Figure 21 Plant Response to Inadvertent HPCI /L8 (EOC ICF (UB))

Page 41

VERMONT YANKEE 0000-0035-6443-SRLR Relmnd 24 Revision 0 200.0 aB- NeUtr Flux / 10

--x- Ave SurfacHe-at Flux

-A Core InA Flow

-- Core Inrd Subcooing 150.0.

U 50.0t 3 S S R E3 E3 .3 Oan "

0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 T-ru (Sec) Time (sec)

I 0

U U

0.0 10.0 20.0 0.0 10.0 20.0 Tine (sec) Time (sec)

Figure 22 Plant Response to FW Controller Failure (EOC MELLLA (UB))

Page 42

VERMONT YANKEE 0000-0035-6443-SRLR

!0.1I.A 9A

-s- Dane Press Rise (psi)

SafetyVae Flo 3W0.0 -Relief Wh~eFlow,

-- Bypass \kd~e Row 200.0 100.0 0.0 3.0

-.0 6.0 0.0 0 0

77Z---- 3.0

ý 6.0 Tin= (sec) Time (Sec) a UC C

100.0 I

C 0.0 3.0 6.0 0.0 3.0 6.0 TMne (see) Time (sec)

Figure 23 Plant Response to Load Rejection w/o Bypass (EOC MELLLA (UB))

Page 43

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision. 0 300.0 200.0 100.0

-- 0.oe 0.0 3.0 6.0 0.0 &o 6.0 Time (Sec) Ti'm (see) 200.0 Q0

,,0 100.0 0.0

-100.0 0.0 3.0 6.0 0.0 3.0 60 Time (sec) Time (sec)

Figure 24 Plant Response to Turbine Trip w/o Bypass (EOC MELLLA (UB))

Page 44

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0

.5 U

C2. 100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Tine (see) Thef (Se) 150.0 1.0 . -- Scran Reacd

- Total ReactiVI o, 0.0 "0100.0

-1.0 50.0 0-0 10.0 0.0 10.0 20.0 T¶==m (sec) Tine (see)

Figure 25 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA (UB))

Page 45

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 0.0 4.0 8.0 0.0 4.0 8.0 Tmne (sec) Time (sec)

'4 100.0 5C U

0.0 4.0 8.0 0.0 4.0 8.0 Time (sec) Time (see)

Figure 26 Plant Response to MSIV Closure (Flux Scram) - ICF (HBB)

Page 46

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 0.0 4.0 8.0 0.0 4.0 8.0 Time (see) Time (sec) 200.0 100.0 T

0.0

-100.0 0.0 4.0 8.0 0.0 4.0 8.0 Tmue (sec) Tine (sec)

Figure 27 Plant Response to MSIV Closure (Flux Scram) - MELLLA (HBB)

Page 47

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Appendix A Analysis Conditions The reactor operating conditions and the pressure relief and safety valve configuration used in the reload licensing analysis for this plant and cycle are presented in Tables A-I and A-2 below.

Table A-1 Reactor Operating Conditions Analysis Value Parameter ICF LCF NFWT NFWT Thermal power, MWt 1912.0 1912.0 Core flow, Mlb/hr 51.4 47.5 Reactor pressure (core mid-plane), psia 1041.4 1039.8 Inlet enthalpy, Btu/lb 520.9 518.6 Non-fuel power fraction 0.036 0.036 Steam flow, Mlb/hr 7.92 7.91 Dome pressure, psig 1010.0 1010.0 Turbine pressure, psig 946.4 946.5 Table A-2 Pressure Relief and Safety Valve Configuration Number of Lowest Setpoint Valve Type Valves (psig)

Safety/Relief Valve 4 1113.0 Spring Safety Valve 3 1277.0 Page 48

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision .0 Appendix B Decrease in Core Coolant Temperature Events The Loss of Feedwater Heating (LFWH) event and Inadvertent High Pressure Coolant Injection (HPCI)

Startup event are the only cold water injection AOOs checked on a cycle-by-cycle basis.

The Loss-of-Feedwater Heating event was analyzed at the EPU power level (1912 MWt) using the BWR Simulator Code. The use of this code is permitted in GESTAR II. The transient plots, neutron flux and heat flux values normally reported in Section 9 are not an output of the BWR Simulator Code; therefore, those items are not included in this document. The OLMCPR result is shown in Section 11.

An ODYN analysis has been performed for the inadvertent High Pressure Coolant Injection (HPCI)

Startup event as part of the reload licensing analysis. Therefore, inadvertent HPCI calculations assuming a L8 trip were performed. The OLMCPR results are shown in Section 1I.

Page 49

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Appendix C ARTS Power and Flow Operating Limits Adjustments The Vermont Yankee plant uses the PANAC II methodology, so it does not have thermal-mechanical MAPLHGR limits. This plant requires the use of LHGRFAC multipliers (power and flow dependent multipliers on LHGR) to ensure that off-rated AOO thermal-mechanical criteria are met. The LHGRFAC multipliers also provide adequate protection for the off-rated LOCA conditions since a constant local peaking factor is used in the LOCA evaluation. Off-rated MAPLHGR multipliers are not required.

The ARTS power and flow dependent operating limits for all operating flexibility options are provided in References C-1, C-2 and C-3. Due to Cycle 25 having no plant specific changes, including no safety limit change from that assumed in Cycle 24, no adjustments were made to the MCPR(p) and MCPR(f) limits curves. Figures C-1 through C4 provide the power and flow dependent limits for VY Cycle 25 at EPU conditions.

References C-1 Vermont Yankee Nuclear Power Station APRM/RBMiTechnical Specifications / Maximum Extended Load line Limit Analysis (ARTS/MELLLA), NEDC-33089P, March 2003.

C-2 Entergy Nuclear Operations Incorporated Vermont Yankee Nuclear Power Station Extended Power Uprate, GE-NE-0000-001 1-7129-01, Rev. 0, Project Task Report, Task T0900, July 2003.

C-3 StatisticallyBased Rod Withdrawal ErrorAnalysisfor Vermont Yankee Nuclear Power Station, GE-NE-0000-00l16-345 1-RO, July 2003.

Page 50

VERMONT YANKEE 0000-0035-6443-SRLR ID.I, -4'A SRevision 0 2.80

> 60% Flow 2.60 2.40

< 60% Flow 2.20 Operating Limit MCPR (P) = K(P) x Operating Limit MCPR (100)

For P < 23%: No Thermal Limits Required 2.00 For 23% < P< 25%, >60% Flow:

OLMCPR(P) = 2.48 - 0.034 x (P - 25%)

For 23% <P < 25%, < 60% Flow:

OLMCPR(P) = 2.07 - 0.026 x (P - 25%)

E. 1.80 a

For 25%:5 P <45%: K(P) = 1.550 - 0.0135 x (P - 25%)

For 45% < P < 100%: K(P) = 1.280 -0.00509 x (P -45%)

' 1.60 ForP>100%: K(P)= 1.00 1.40 1.20 1.00 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Power (% Rated)

Figure C-1 Power Dependent K(P) / MCPR(P) Limits For EPU Page 51

VERMONT YANKEE 0000-0035-6443-SRLR Vop*1r~A)

Revision 0 1.10 1.00 0.90 00,,

0.80 60% 1 Flow I 0.70 4-LHGR(P) = LHGRFAC(P) x LHGRstd 0.60 Where LHGRstd = Rated LHGR limits For P< 23%: No Thermal Limits Required 5 0.50 _N I

> 60% Flow For 23% < P <25%, >60% Flow:

LHGRFAC(P) = 0.586 + 0.0084 x (P - 25%)

For 23% <P<25%, < 60% Flow:

LHGRFAC(P) = 1.0 + 0.00523 x (P - 100%)

For25% < P < 100%:

0.40 1 1 LHGRFAC(P) =1.0 + 0.00523 x (P - 100%)

For P > 100%: LHGRFAC(P) = 1.0 0.301 i t i 0.20 20 25 I

30 35 40 45 50 55 60 65 Power (% Rated) 70 75 80 85 90 95 00 11 Figure C-2 Power Dependent LHGRFAC(P) Multiplier for EPU Page 52

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 1.10 1.00 Max Flow= 109.5%

0.90

, 0.80 U.

w, 0.70 LHGR(F) = LHGRFAC(F) X LHGRstd LHGRstd = STANDARD LHGR LIMITS U.

For W (% Rated Core Flow) > 30%

And Max Runout Flow < 109.5%

0.60 LHGRFAC(F) = The Minkium of EITHER 1.0 OR { 0.8737 x (Wi 100) + 0.2779)

W = % Rated Core Flow 0.50 0.40 0.30 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)

Figure C-3 LHGR Flow Factor LHGRFAC(F) for EPU Page 53

VERMONT YANKEE 0000-0035-6443-SRLR P10.1A !)A Revision 0 1.8 f - For W(C) (% Rated Core Flow) > 30%

1.7 MCPR(F) = MAX(1.20, A(F)

  • W(C) 1100 + B(F))

Max Runout Flow < 109.5%

A(F) = - 0.602 B(F) = 1.747 1.6

-~p p- - I - -.-

E S 1.5 Iz 1.4 Maximum Flow Rate 109.5%

4 1.3 1.2 1.1 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)

Figure C-4 Flow Dependent MCPR Operating Limit MCPR(F) for EPU Page 54

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Appendix D Implementation of Extended Power Uprate (EPU)

To provide the Vermont Yankee Nuclear Power Station (VYNPS) with operating improvements, analyses were performed to increase the rated power from 1593 MWt to 1912 MWt. Reference D-1 provides the basis for operation of VYNPS at Extended Power Uprate (EPU), i. e., 1912 MWt conditions. The required OLMCPRs are provided in Section 11.

References D- I Safety Analysis Report for Vermont Yankee Nuclear Power Station Constant Pressure Power Uprate, NEDC-33090P, Rev. 0, September 2003.

Page 55

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Appendix E Stability Solution Option 1-D Exclusion and Buffer Regions at EPU Condition The stability Option I-D Exclusion Region and Buffer Region were calculated for Vermont Yankee Cycle 25 operation at the EPU (Extended Power Uprate) conditions. The ehdpoints of the regions are defined in Table E-1. The region boundaries are defined using the Generic Shape Function (GSF),

Equation E-1. The regions are shown on the Vermont Yankee Cycle 25 power/flow map in Figure E-I.

These regions are valid up to an end of cycle exposure of 13,930 MWd/ST.

Table E-1: Exclusion and Buffer Region Endpoints' Exclusion Region Power Flow

(% rated) 2 (% rated) 3 A 66.26 52.25 B 35.69 31.27 Buffer Region Power Flow 2 (% rated) 3

(% rated)

A 70.10 57.25 B 30.69 31.17 I. Point "A" is on the High Flow Control Line (HFCL) and point "B" is on the Natural Circulation Line (NCL).

For Vermont Yankee Cycle 25, the HFCL is the Maximum Extended Load Line Limit Analysis (MELLLA) boundary.

2. Rated core power is 1912 MWt.
3. Rated core flow is 48 Mlb/hr.

Equation E-1: Generic Shape Function I[w-wo +(w-w P= (L,PB II W "-.

PB2 where, P = a core thermal power value on the region boundary (% of rated),

W = the core flow rate corresponding to power, P, on the region boundary (% of rated),

Page 56

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 PA = core thermal power at point A (% of rated),

PB = core thermal power at point B (% of rated),

WA = core flow rate at point A (% of rated), and WB = core flow rate at point B (% of rated).

Core Flow (Mlb/hr) 0 5 10 13 20 25 30 35 40 45 50 55 120 k N~am61 A oo 22D0 8 : M ri-iPwnp Sp~d C. 153.3% Pow.. 360M 4 Flow 01 D158%P-1 4 Flow 1111O1 1100 2000 0 4113%P-11i 75.M4Flow %Flow D E .91 E:B100.0%Po-1t 1000 V. 03.3% Pow/ 100.04 Flow

r. '.000% Po1 , WA 4 Fl~ow law0 P: 813% Pow-ol070, RFow MELLLA Upper Boundary Line 90o .0 le11 7% P-d107.01,4 Flow(1) S E' ___ 3 v I 18.7%P-1/lOOAl 4 , low~l)

K 1:157% Pool 327A tFlow(i) 1600 so Wdo wto t- pump c0ot.on

-NOt. (11):V prot~on kw. OvsImis~ft fwidu 90er IHo.

  • 70 I
  • Exaujslor nRegion 1400]

~60~ 83.3% EPURodLne o me (1100% OLTP Rod Line)

  • Buffer Reg iion 1200~
  • 0 renased Core Flow Region

~40 *Minimum Pump Spi 600 30

  • Natural Cimulatio Minimum Power Line (1) 20 400 A 8 0o 100%E.Pu 1912IVA 100ACo.
  • 10 VF J I I 0 10 20 30 40 50 60 70 so 90 100 110 120 Core Flow (%)

Figure E-1: Exclusion and Buffer Regions on the EPU Power/Flow Map Page 57

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Appendix F List of Acronyms Acronym Description ACPR Delta Critical Power Ratio Ak Delta k-effective 2RPT Two Recirculation Pump Trip ADS Automatic Depressurization System ADSOOS Automatic Depressurization System Out of Service AOO Anticipated Operational Occurrence APRM Average Power Range Monitor ARTS APRM, Rod Block and Technical Specification Improvement Program BOC Beginning of Cycle BSP Backup Stability Protection Btu British thermal unit BWROG Boiling Water Reactor Owners Group COLR Core Operating Limits Report CPR Critical Power Ratio DIVOM Delta CPR over Initial MCPR vs. Oscillation Magnitude DR Decay Ratio DS/RV Dual Mode Safety/Relief Valve ECCS Emergency Core Cooling System EEOC Extended End of Cycle ELLLA Extended Load Line Limit Analysis EOC End of Cycle EOR End of Rated (All Rods Out I00%Power / 100%Flow / NFWT)

ER Exclusion Region FFWTR Final Feedwater Temperature Reduction FMCPR Final MCPR FOM Figure of Merit FWCF Feedwater Controller Failure FWTR Feedwater Temperature Reduction GDC General Design Criterion GESTAR General Electric Standard Application for Reactor Fuel GETAB General Electric Thermal Analysis Basis GSF General Shape Function HAL Haling Bum HBB Hard Bottom Bum HBOM Hot Bundle Oscillation Magnitude HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line HPCI High Pressure Coolant Injection Page 58

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Acronym Description ICA Interim Corrective Action ICF Increased Core Flow IMCPR Initial MCPR IVM Initial Validation Matrix L8 Turbine Trip on high water level (Level 8)

LCF Low Core Flow LHGR Linear Heat Generation Rate LOCA Loss of Coolant Accident LPRM Local Power Range Monitor LRHBP Load Rejection with Half Bypass LRNBP Load Rejection without Bypass LTR Licensing Topical Report MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ MELLLA Plus MOC Middle of Cycle MRB Maximal Region Boundaries MSIV Main Steam Isolation Valve MSIVOOS Main Steam Isolation Valve Out of Service MTU Metric Ton Uranium MWd Megawatt day MWd/ST Megawatt days per Standard Ton MWd/MT Megawatt days per Metric Ton MWt Megawatt Thermal NBP No Bypass NCL Natural Circulation Line NFWT Normal Feedwater Temperature NOM Nominal Burn NTR Normal Trip Reference OLMCPR Operating Limit MCPR OOS Out of Service OPRM Oscillation Power Range Monitor Pdome Peak Dome Pressure PsI Peak Steam Line Pressure Pv Peak Vessel Pressure PCT Peak Clad Temperature PHE Peak Hot Excess PLHGR Peak Linear Heat Generation Rate PLUOOS Power Load Unbalance Out of Service PRFDS Pressure Regulator Failure Downscale PROOS Pressure Regulator Out of Service Q/A Heat Flux RBM Rod Block Monitor RC Reference Cycle RCF Rated Core Flow Page 59

VERMONT YANKEE 0000-0035-6443-SRLR Reload 24 Revision 0 Acronym Description RFWT Reduced Feedwater Temperature RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS Recirculation Pump Trip Out of Service RV Relief Valve RVM Reload Validation Matrix RWE Rod Withdrawal Error SC Standard Cycle SL Safety Limit SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation SRLR Supplemental Reload Licensing Report S/RV Safety/Relief Valve SRVOOS Safety/Relief Valve(s) Out of Service SS Steady State SSV Spring Safety Valve STU Short Tons (or Standard Tons) of Uranium TBV Turbine Bypass Valve TBVOOS Turbine Bypass Valves Out of Service TCV Turbine Control Valve TCVOOS Turbine Control Valve Out of Service TCVSC Turbine Control Valve Slow Closure TLO Two Loop Operation TRF Trip Reference Function TSIP Technical Specifications Improvement Program TTHBP Turbine Trip with Half Bypass TTNBP Turbine Trip without Bypass UB Under Burn Page 60

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