ML14351A427

000N2528-SRLR, Revision 1, Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988 Mwt) / MELLLA (99-105% Flow)

ML14351A427
Person / Time
Site:	Nine Mile Point
Issue date:	01/31/2014
From:	Global Nuclear Fuel
To:	Office of Nuclear Reactor Regulation
References
NMP2L 2568 000N2528-SRLR, Rev. 1
Download: ML14351A427 (66)

Text

ATTACHMENT 2 SUPPLEMENTAL RELOAD LICENSING REPORT FOR NINE MILE POINT 2, RELOAD 14 CYCLE 15, EXTENDED POWER UPRATE (3988 MWT) / MELLLA (99-105 % FLOW)

Nine Mile Point Nuclear Station, LLC December 11, 2014

GNF Global Nuclear Fuel A Joint Venture of GE, Toshiba, & Hitachi 000N2528-SRLR Revision 1 Class I January 2014 Supplemental Reload Licensing Report for Nine Mile Point 2 Reload 14 Cycle 15 Extended Power Uprate (3988 MWt) / MELLLA (99-105% Flow)

Copyright 2014 Global Nuclear Fuel-Americas, LLC All Rights Reserved

Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1 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 Nine Mile Point Nuclear Station, LLC ("Recipient") in support of the operating license for Nine Mile Point 2 (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.

The content of this SRLR will only serve the licensing of Nine Mile Point 2 Cycle 15 EPU/MELLLA.

Page 2

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 Acknowledgement The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by GNF-A/GEH Nuclear Analysis personnel.

The Supplemental Reload Licensing Report was prepared by M. Thomas. This document has been verified by R. McCord.

Page 3

Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1 Table of Contents

1.

Plant Unique Items 5

2.

Reload Fuel Bundles 5

3.

Reference Core Loading Pattern 6

4.

Calculated Core Effective Multiplication and Control System Worth 6

5.

Standby Liquid Control System Shutdown Capability 6

6.

Reload Unique Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters 7

7.

Selected Margin Improvement Options 9

8.

Operating Flexibility Options 10

9.

Core-wide AOO Analysis Results 11

10. Rod Withdrawal Error AOO Summary 14

11.

Cycle SLMCPR and OLMCPR Summary 15

12. Overpressurization Analysis Summary 17

13. Fuel Loading Error Results 17

14. Control Rod Drop Analysis Results 17

15. Stability Analysis Results 18

16. Loss-of-Coolant Accident Results 22 Appendix A Analysis Conditions 47 Appendix B Thermal-Mechanical Compliance 48 Appendix C Decrease in Core Coolant Temperature Event 49 Appendix D Off-Rated Limits 50 Appendix E Expanded Operating Domain Analysis 56 Appendix F TRACG04 AOO Supplementary Information 58 Appendix G Interim Methods LTR (NEDC-33173P-A Revision 4) Supplemental Information 59 Appendix H List of Acronyms 62 Page 4

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision I The basis for this report is General Electric Standard Application for Reactor Fuel, NEDE-240 11-P-A-20, December 2013; and the U.S. Supplement, NEDE-2401 1-P-A-20-US, December 2013.

A proprietary Fuel Bundle Information Report (FBIR) supplements this licensing report. The FBIR specifies the thermal-mechanical linear heat generation rate limits and also provides a description of the fuel bundles to be loaded. The document number for this report is 000N0123-FBIR.

1.

Plant Unique Items Appendix A:

Appendix B:

Appendix C:

Appendix D:

Appendix E:

Appendix F:

Appendix G:

Appendix H:

Analysis Conditions Thermal-Mechanical Compliance Decrease in Core Coolant Temperature Event Off-Rated Limits Expanded Operating Domain Analysis TRACG04 AOO Supplementary Information Interim Methods LTR (NEDC-33173P-A Revision 4) Supplemental Information List of Acronyms

2.

Reload Fuel Bundles Cycle Number Fuel Type Loaded Irradiated:

GE 14-P 1OCNAB434-8G7.0/7G6.0-120T-150-T6-3233 (GE14C) 13 80 GE14-Pl0CNAB416-17GZ-120T-150-T6-3235 (GE14C) 13 12 GE 14-P 1OCNAB417-17GZ-120T-150-T6-3236 (GE 14C) 13 4

GE 14-PIOCNAB434-15GZ-120T-150-T6-4039 (GE 14C) 14 120 GE 14-P 1OCNAB422-17GZ-120T-150-T6-4041 (GE 14C) 14 60 GE 14-P0OCNAB412-15GZ-120T-1 50-T6-4040 (GE14C) 14 104 GE 14-P 1OCNAB422-17GZ-120T-150-T6-4042 (GE 14C) 14 32 GE 14-P 1 OCNAB412-14GZ-1 20T-1 50-T6-4043 (GE 14C) 14 16 New:

GE 14-P 1 OCNAB422-16GZ-1 20T-1 50-T6-4244 (GE 14C) 15 64 GE 14-P 10CNAB418-16GZ-120T-150-T6-4243 (GE14C) 15 56 GE 14-P1OCNAB419-17GZ-120T-150-T6-4242 (GE14C) 15 96 GE14-P1OCNAB418-15GZ-120T-150-T6-4241 (GEI4C) 15 56 GE 14-P I OCNAB430-14GZ-120T-1 50-T6-4240 (GE 1 4C) 15 40 GE14-P1OCNAB430-15GZ-120T-150-T6-4239 (GE14C) 15 24 Total:

1 764 Page 5

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1

3.

Reference Core Loading Pattern Core Average Cycle Exposure Exposure 34134 MWd/MT 18164 MWd/MT Nominal previous end-of-cycle exposure:

(30966 MWd/ST)

(16478 MWd/ST)

Minimum previous end-of-cycle exposure (for cold 33583 MWd/MT 17613 MWd/MT shutdown considerations):

(30466 MWd/ST)

(15978 MWd/ST) 14094 MWd/MT 0 MWd/MT Assumed reload beginning-of-cycle exposure:

(12786 MWd/ST)

(0 MWdIST)

Assumed reload end-of-cycle exposure (rated 33032 MWd/MT 18938 MWd/MT conditions):

(29966 MWd/ST)

(17180 MWd/ST)

Reference core loading pattern:

Figure 1

4.

Calculated Core Effective Multiplication and Control System Worth Beginning of Cycle, keffective Uncontrolled (20'C) 1.132 Fully controlled (20'C) 0.959 Strongest control rod out (most reactive condition, 20'C) 0.989 R, Maximum increase in strongest rod out reactivity during the cycle (Ak) 0.000 0 MWd/MT Cycle exposure at which R occurs (0 MWd/ST)

5.

Standby Liquid Control System Shutdown Capability Boron (ppm)

Shutdown Margin (Ak)

(at 20'C)

(at 1601C, Xenon Free)

Analytical Requirement Achieved 780

>0.010 0.019 Page 6

Nine Mile Point 2 I*RnnA I'A 000N2528-SR.LR RP~vicnn 1

6.

Reload Unique Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters 1 Operating domain: ICF (HBB)

Exposure range

BOC to MOC (Application Condition: 1, 3 )

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Design___

_(MWt)

(1000 lb/hr)

MCPR GE14C 1.0 1.36 1.27 0.98 7.071 126.5 1.59 Operating domain: ICF (HBB)

Exposure range

MOC to EOC (Application Condition: 1, 3)

Exposure range

BOC to EOC (Application Condition: 2 )

Peaking Factors Fuel Bundle Bundle Initial Local Radial Axial R-Factor Power Flow Design

1.

.3(MWt)

(1000 lb/hr)

MCPR GE14C 1.0 1.37 1.42 0.97 7.147 128.1 1.51 Operating domain: LCF (HBB)

Exposure range

BOC to MOC (Application Condition: 1, 3)

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Raias129 0.7 (MWt)

(1000 lb/hr)

MCPR GE14C 1.0 1.36 1.29 0.97 7.065 100.8 1.48 Operating domain: LCF (HBB)

Exposure range

MOC to EOC (Application Condition: 1, 3)

Exposure range

BOC to EOC (Application Condition: 2 )

Peaking Factors Fuel Bundle Bundle Initial Local Radial Axial R-Factor Power Flow Design I

(MWt)

(1000 lb/hr)

MCPR GE14C 1.0 1.38 1.34 0.98 7.217 100.8 1.38 1 Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.

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Nine Mile Point 2 V

1 1,A 000N2528-SR-LR PiAXAC~n I Operating domain: ICF (UB)

Exposure range

MOC to EOC (Application Condition: 1, 3)

Exposure range

BOC to EOC (Application Condition: 2 )

Peaking Factors Fuel Bundle Bundle Initial Local Radial Axial R-Factor Power Flow Design 1.28 (MWt)

(1000 lb/hr)

MCPR GE14C 1.0 1.28 1.26 0.97 6.674 129.4 1.73 Operating domain: LCF (UB)

Exposure range

MOC to EOC (Application Condition: 1, 3)

Exposure range_: BOC to EOC (Application Condition: 2)

Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow Design___

_(MWt)

(1000 lb/hr)

MCPR GE14C 1.0 1.31 1.22 0.97 6.833 101.6 1.57 Page 8

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1

7.

Selected Margin Improvement Options 2 Recirculation pump trip:

Rod withdrawal limiter:

Thermal power monitor:

Improved scram time:

Measured scram time:

Exposure dependent limits:

Exposure points analyzed:

Yes No Yes Yes (Option B)

No Yes 2

Table 7-1 Cycle Exposure Range Designation Name Exposure Range 3 BOC to MOC BOC 15 to EOR 15 - 3104 MWd/MT (2816 MWd/ST)

MOC to EOC EOR15 - 3104 MWd/MT (2816 MWd/ST) to EOC 15 BOC to EOC BOC15 to EOC15 2 Refer to the GESTAR basis document identified at the beginning of this report for the margin improvement options currently supported therein.

3 End of Rated (EOR) is defined as the cycle exposure corresponding to all rods out, 100% power/100% flow, and normal feedwater temperature. For plants without mid-cycle OLMCPR points, EOR is not applicable.

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Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1

8.

Operating Flexibility Options 4 The following information presents the operational domains and flexibility options which are supported by the reload licensing analysis.

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:

105.0%

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 16 valves)

ADS Out of Service:

Yes Turbine Bypass Valve Out of Service Yes End Of Cycle Recirculation Pump Trip Out of Service Yes Main Steam Isolation Valve Out of Service Yes Pressure Regulator Out of Service Yes 4 Refer to the GESTAR basis document identified at the beginning of this report for the operating flexibility options currently supported therein.

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Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1

9.

Core-wide AOO Analysis Results "6 Methods used: GEXL-PLUS, TRACG04 Operating domain: ICF (HBB)

Exposure range

BOC to MOC (Application Condition: 1, 3)

Uncorrected ACPR/ICPR Event Flux STP GE14C Fig.

(% rated) (% rated)

GEI4CFig.

Load Rejection w/o Bypass 545.9 110.0 0.2088 2

FW Controller Failure 517.1 112.4 0.2001 3

Operating domain: ICF (HBB)

Exposure range

MOC to EOC (Application Condition: 1, 3)

Exposure range

BOC to EOC (Application Condition: 2 )

Uncorrected ACPR/ICPR Event Flux STP GE14C Fig.

(% rated) (% rated)

Turbine Trip w/o Bypass 614.5 110.8 0.2139 4

FW Controller Failure 569.0 1

113.4 0.2108 5

Operating domain: LCF (HBB)

Exposure range

BOC to MOC (Application Condition: 1, 3)

Uncorrected ACPR/ICPR Event Flux STP GE14C Fig.

(% rated) (% rated)

Load Rejection w/o Bypass 436.7 108.4 0.2026 6

FW Controller Failure 367.9 110.3 0.1890 7

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

6 The Heat Flux Q/A (% rated) output is not available from TRACG04, so the Simulated Thermal Power (STP) (%

rated) is shown.

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Nine Mile Point 2 Reload 14 000N2528-SRLR Revision I Operating domain: LCF (HBB)

Exposure range

MOC to EOC (Application Condition: 1, 3)

Exposure range

BOC to EOC (Application Condition: 2 )

Uncorrected ACPRIICPR Event Flux STP GE14C Fig.

Event___________

(% rated) (% rated)

GEI4CFig.

Load Rejection w/o Bypass 481.1 109.3 0.2053 8

FW Controller Failure 413.9 1

111.4 0.1924 9

Operating domain: ICF with TBVOOS (HBB)

Exposure range

BOC to EOC (Application Condition: 2)

Uncorrected ACPR/ICPR Event Flux STP GE14C Fig.

(% rated) (% rated)

GEI4CFig.

FW Controller Failure 675.9 114.9 0.2294 10 Operating domain: LCF with TBVOOS (HBB)

Exposure range

BOC to EOC (Application Condition: 2)

Uncorrected ACPR/ICPR Event Flux STP GE14C Fig.

(% rated) (% rated)

GEI4CFig.

FW Controller Failure 495.3 112.9 0.2171 11 Operating domain: ICF with RPTOOS (HBB)

Exposure range

BOC to MOC (Application Condition: 3)

Uncorrected ACPR/ICPR Event Flux STP GE14C Fig.

Event_____________(% rated) (% rated)

Turbine Trip w/o Bypass 655.8 110.8 0.2249 12 FW Controller Failure 582.1 113.4 0.2156 13 Operating domain: ICF with RPTOOS (HBB)

Exposure range

MOC to EOC (Application Condition: 3)

Uncorrected ACPRIICPR Event Flux STP GE14C Fig.

Event_____________(% rated) (% rated)

Load Rejection w/o Bypass 645.5 111.7 0.2475 14 FW Controller Failure 631.6 114.3 0.2280 15 Page 12

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 Operating domain: LCF with RPTOOS (HBB)

Exposure range

BOC to MOC (Application Condition: 3)

Uncorrected ACPR/ICPR Event Flux STP GE14C Fig.

(% rated) (% rated)

Load Rejection w/o Bypass 484.2 109.1 0.1995 16 FW Controller Failure 404.8 111.1 0.1877 17 Operating domain: LCF with RPTOOS (HBB)

Exposure range

MOC to EOC (Application Condition: 3)

Uncorrected ACPRIICPR Event Flux STP GE14C Fig.

(% rated) (% rated)

Load Rejection w/o Bypass 532.2 110.1 0.1994 18 FW Controller Failure 453.7 112.2 0.1870 19 Page 13

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1

10. Rod Withdrawal Error AOO Summary The Rod Withdrawal Error (RWE) is analyzed in NEDC-33286P, Nine Mile Point Nuclear Station Unit 2 APRM/RBM/Technical Specifications / Maximum Extended Load Line Limit Analysis (ARTS/MELLLA),

Revision 0, March 2007.

RWE Results:

RBM Setpoint (%)

ACPR 108.0 0.23 111.0 0.25 114.0 0.25 117.0 0.29 Unblocked 0.25' The more limiting of the cycle specific and the generic ACPR values are reported in the table above. The RWE OLMCPR is determined by adding the ACPR for the desired RBM setpoint from the table above to the SLMCPR in Section 11.

The ARTS RWE analysis validated that the following MCPR values provide the required margin for full withdrawal of any control rod during this cycle:

For Power <

90%

For Power >

90%

MCPR > 1.70 MCPR > 1.40 The RBM operability requirements have been evaluated and shown to be sufficient to ensure that the SLMCPR and cladding 1% plastic strain criteria will not be exceeded in the event of a RWE.

7 The cycle specific unblocked response is used to validate the MCPR operating limits for a full withdrawal provided in the paragraph below the table.

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Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1

11. Cycle SLMCPR and OLMCPR Summary 8 9 Two Loop Operation (TLO) safety limit:

Single Loop Operation (SLO) safety limit:

Stability MCPR Design Basis:

ECCS MCPR Design Basis:

1.07 1.09 See Section 15 See Section 16 (Initial MCPR)

Non-pressurization Events:

Exposure range: BOC to EOC All Fuel Types Rod Withdrawal Error (117.0 % RBM Setpoint) 1.36 Loss of Feedwater Heating 1.21 Fuel Loading Error (Mislocated)

Not Limiting Fuel Loading Error (Misoriented) 1.26 Rated Equivalent SLO Pump Seizure 10 1.31 Limitin2 Pressurization Events OLMCPR Summary Table:"

Appi.T Cond.

Exposure Range Option A Option B GE14C GE14C 1

Equipment in Service BOC to MOC 1.61 1.37 MOC to EOC 1.62 1.38 2

TBV OOS BOC to EOC 1.63 1.42 3

RPT OOS BOC to MOC 1.73 1.40 MOC to EOC 1.79 1.46 8 Exposure range designation is defined in Table 7-1.

9 For SLO, the MCPR operating limit is 0.02 greater than the two loop value.

10 The cycle-independent OLMCPR for the recirculation pump seizure event for GE14C is 1.44 based on the cycle-specific SLO SLMCPR. When adjusted for the off-rated power/flow conditions of SLO, this limit corresponds to a rated OLMCPR of 1.31. This limit does not require an adjustment for the SLO SLMCPR.

" 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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Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 Pressurization Events: 12 Operating domain: ICF (HBB)

Exposure range

BOC to MOC (Application Condition: 1, 3 )

Option A Option B GE14C GE14C Load Rejection w/o Bypass 1.61 1.37 Operating domain: ICF (HBB)

Exposure range

MOC to EOC (Application Condition: 1, 3)

Exposure range

BOC to EOC (Application Condition: 2 )

Option A Option B GEI4C GE14C Turbine Trip w/o Bypass 1.62 1.38 Operating domain: ICF with TBVOOS (HBB)

Exposure range

BOC to EOC (Application Condition: 2 )

Option A Option B GEI4C GE14C FW Controller Failure 1.63 1.42 Operating domain: ICF with RPTOOS (HBB)

Exposure range

BOC to MOC (Application Condition: 3 )

Option A Option B GEI4C GE14C Turbine Trip w/o Bypass 1.73 1.40 Operating domain: ICF with RPTOOS (HBB)

Exposure range

MOC to EOC (Application Condition: 3 )

Option A Option B GE14C GEI4C Load Rejection w/o Bypass 1.79 1.46 12 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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Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1

12. Overpressurization Analysis Summary13 Pdome Pv Plant (psig)

(psig)

Response

MSIV Closure (Flux Scram) - ICF (HBB) 1277.9 1313.4 Figure 20 MSIV Closure (Flux Scram) - LCF (HBB) 1277.9 1307.0 Figure 21

13. Fuel Loading Error Results Variable water gap misoriented bundle analysis: Yes 14 Misoriented Fuel Bundle ACPR GE14-P1OCNAB434-15GZ-120T-150-T6-4039 (GE14C) 0.17 GE14-P1OCNAB422-17GZ-120T-150-T6-4041 (GE14C) 0.18 GE 14-P 1OCNAB412-15GZ-120T-150-T6-4040 (GE 14C) 0.18 GE 14-P 1OCNAB422-17GZ-120T-150-T6-4042 (GE 14C) 0.18 GE 14-P 1 OCNAB412-14GZ-120T-150-T6-4043 (GE 14C) 0.19 GE 14-P1OCNAB430-15GZ-120T-150-T6-4239 (GE14C) 0.18 GE14-P1OCNAB430-14GZ-120T-150-T6-4240 (GE 14C) 0.17 GE14-P1OCNAB418-15GZ-120T-150-T6-4241 (GE14C) 0.18 GE 14-P 1OCNAB419-17GZ-120T-150-T6-4242 (GE 14C) 0.18 GE 14-P 1OCNAB418-16GZ-120T-150-T6-4243 (GE 14C) 0.19 GE 14-P 1OCNAB422-16GZ-120T-150-T6-4244 (GE14C) 0.19

14. Control Rod Drop Analysis Results Nine Mile Point 2 is a banked position withdrawal sequence plant, so the control rod drop accident analysis is not required. NRC approval is documented in NEDE-2401 1-P-A-US.

13 Overpressure calculated at an initial dome pressure of 1020 psig.

14 Includes a 0.02 penalty due to variable water gap R-factor uncertainty.

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Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1

15. Stability Analysis Results 15.1 Stability Option III Solution Nine Mile Point 2 has implemented BWROG Long Term Stability Solution Option III using the Oscillation Power Range Monitor (OPRM) as described in Reference 1 in Section 15.4.

The plant specific Hot Channel Oscillation Magnitude (HCOM) (Reference 2 in Section 15.4) and other cycle specific stability parameters are used in the Cycle 15 Option III stability evaluation. Backup Stability Protection (BSP) regions are used by the plant in the event that the Option III OPRM system is declared inoperable.

The following Option Ill OPRM stability setpoint determination described in Section 15.2 and the implementation of the associated BSP Regions described in Section 15.3 provide the stability licensing bases for Nine Mile Point 2 Cycle 15.

15.2 Detect and Suppress Evaluation A reload Option III evaluation has been performed in accordance with the licensing methodology described in Reference 3 in Section 15.4. The stability based OLMCPR is determined for two conditions as a function of OPRM amplitude setpoint. The two conditions evaluated are: (1) a postulated oscillation at 45% rated core flow quasi steady-state operation (SS), and (2) a postulated oscillation following a two recirculation pump trip (2PT) from the limiting rated power operation state point.

The OPRM-setpoint-dependent OLMCPR(SS) and OLMCPR(2PT) values are calculated for Cycle 15 in accordance with the BWROG regional mode DIVOM guidelines described in Reference 4 in Section 15.4. The Cycle 15 Option III evaluation provides adequate protection against violation of the SLMCPR for the two postulated reactor instability events as long as the plant OLMCPR is equal to or greater than OLMCPR(SS) and OLMCPR(2PT) for the selected OPRM setpoint in Table 15.2-2.

The relationship between the OPRM Successive Confirmation Count Setpoint and the OPRM Amplitude Setpoint is provided in Table E-I of Reference 3 in Section 15.4 and Table 15.2-1.

For intermediate OPRM Amplitude Setpoints, the corresponding OPRM Successive Confirmation Count Setpoints have been obtained by using linear interpolation.

The OPRM setpoints for TLO are conservative relative to SLO and are, therefore, bounding.

Page 18

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision I Table 15.2-1 Relationship between OPRM Successive Confirmation Count Setpoint and OPRM Amplitude Setpoint Successive OPRM Confirmation Count Amplitude Setpoint Setpoint 6

>1.04 8

Ž1.05 9

>1.06 10

>1.07 11

>1.08 12

>1.09 13

>1.10 14

>1.11 15

>1.13 16

>1.14 17

>1.16 18

?1.19 19

?1.21 20

>1.24 Page 19

Nine Mile Point 2 Relnad 14 000N2528-SRLR Revision 1 Table 15.2-2 OPRM Setpoint Versus OLMCPR OPRM Amplitude OLMCPR(SS)

OLMCPR(2PT)

Setpoint 1.04 1.16 1.09 1.05 1.18 1.10 1.06 1.20 1.12 1.07 1.22 1.14 1.08 1.24 1.16 1.09 1.26 1.18 1.10 1.28 1.20 1.11 1.30 1.22 1.12 1.32 1.24 1.13 1.35 1.26 1.14 1.37 1.29 OLMCPR Off-rated Rated Power Acceptance OLMCPR OLMCPR (see Criteria

@45% flow Section 11) 15.3 Backup Stability Protection The BSP region boundaries were calculated for Nine Mile Point 2 Cycle 15 for normal feedwater temperature operation. The endpoints of the regions are defined in Table 15.3-1. The region boundaries, shown in Figure 22, are defined using the Modified Shape Function (MSF). See Reference 5 in Section 15.4.

Table 15.3-1 BSP Region Intercepts for Normal Feedwater Temperature Highest Region Boundary Power Flow Core DR Channel Intercept

(%)

(%)

DR Al 56.5 40.0

< 0.80

< 0.56 B1 41.4 29.5

< 0.80

< 0.56 A2 64.5 50.0

< 0.80

< 0.56 B2 28.7 28.9

< 0.80

< 0.56 The Cycle 15 BSP region boundaries for normal feedwater temperature operation presented herein are adequate to bound a variation in nominal feedwater temperature of +/- 20'F.

Page 20

Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1 15.4 References

1. B WR Owners' Group Long-term Stability Solutions Licensing Methodology, NEDO-31960-A, November 1995 (including Supplement 1).

2. GENE-A13-00381-05, Rev. 1, Reactor Long-Term Stability Solution Option III: Licensing Basis Hot Channel Oscillation Magnitude for Nine Mile Point 2, April 1998.

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

4. Plant-Specific Regional Mode DIVOM Procedure Guideline, GE-NE-0000-0028-9714-Ri, June 2005.

5. OD YSY Application for Stability Licensing Calculations Including Option I-D and H Long Term Solutions, Licensing Topical Report, NEDE-33213P-A, April 2009.

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Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1

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 basis results applicable to the GEI4C fuel type in the new cycle are summarized in the following table.

Table 16.1-1 Licensing Results Core-Wide Licensing Local Me-Wate Fuel Type Basis PCT Oxidation Reatio (OF)

Reaction

(°F)

(%)

(%)

GE14C 1540

< 1.00

< 0.10 The SAFER/GESTR ECCS-LOCA analysis results for the GE14C fuel type are documented in Section 16.4, Reference 1.

16.2 10CFR50.46 Error Evaluation The 10 CFR 50.46 errors applicable to the Licensing Basis PCT are shown in the following table.

Table 16.2-1 Impact on Licensing Basis Peak Cladding Temperature for GE14C 10CFR50.46 Error Notifications Number Subject PCT Impact NumberSubject (OF) 2011-02 Heat Deposition Parameter

+30 2011-03 Heat Deposition Definition

-5 2012-01 PRIME code Implementation for fuel rod T/M 0

performance, replacing GESTR Total PCT Adder (OF)

+25 After accounting for the error impact, the GEl4 Licensing Basis PCT with the total PCT adder remains below the 10CFR50.46 limit of 2200 'F.

Page 22

Nine Mile Point 2 1V I 11* A 000N2528-SR-LR

]?,,;

I 16.3 ECCS-LOCA Operating Limits The ECCS-LOCA MAPLHGR operating limits for all fuel bundles in this cycle are shown in the following table.

Table 16.3-1 MAPLHGR Limits Bundle Type(s): GE14-P10CNAB434-8G7.0/7G6.0-120T-150-T6-3233 (GEl4C)

GE14-P1OCNAB416-17GZ-120T-150-T6-3235 (GE14C)

GE14-PlOCNAB417-17GZ-120T-150-T6-3236 (GE14C)

GE14-P1OCNAB434-15GZ-120T-150-T6-4039 (GE14C)

GE 14-P 1OCNAB422-17GZ-120T-150-T6-4041 (GE 14C)

GE 14-P 1OCNAB412-15GZ-120T-150-T6-4040 (GE 14C)

GE 14-P 10CNAB422-17GZ-120T-150-T6-4042 (GE 14C)

GE14-P1OCNAB412-14GZ-120T-150-T6-4043 (GE14C)

GE14-P1OCNAB430-15GZ-120T-150-T6-4239 (GE 14C)

GE14-P1OCNAB430-14GZ-120T-150-T6-4240 (GE 14C)

GE14-PlOCNAB418-15GZ-120T-150-T6-4241 (GE14C)

GE 14-P 1OCNAB419-17GZ-120T-150-T6-4242 (GE 14C)

GE 14-P 1OCNAB418-16GZ-120T-150-T6-4243 (GE 14C)

GE 14-P 1OCNAB422-16GZ-120T-150-T6-4244 (GE 14C)

Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 12.82 16.00 14.51 12.82 21.09 19.13 12.82 63.50 57.61 8.00 70.00 63.50 5.00 The MAPLHGR limits for GE14C fuel, shown in Table 16.3-1, are unaffected by changes to the LHGR curve being implemented in the new cycle.

The power and flow dependent LHGR multipliers are sufficient to provide adequate protection for the off-rated conditions from an ECCS-LOCA analysis perspective and there is no need for MAPLHGR multipliers, in addition to off-rated LHGR multipliers.

The single loop operation multiplier on LHGR and MAPLHGR and the ECCS-LOCA analytical initial MCPR value applicable to the GE14C fuel type in the new cycle core are provided in the following table.

Page 23

Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1 Table 16.3-2 Initial MCPR and Single Loop Operation Multiplier on LHGR and MAPLHGR Single Loop Operation Fuel Type Initial MCPR Multiplier on LHGR and MAPLHGR GE14C 1.25 0.78 16.4 References The SAFER/GESTR-LOCA analysis base report(s) applicable to the new cycle core are:

References for GE14C

1. Project Task Report Constellation Generation Group Nine Mile Point Nuclear Station Unit 2 Extended Power Uprate Task T0407: ECCS-LOCA SAFER/GESTR, 0000-0080-7568-Ri, Revision 1, February 2009.

Page 24

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 7

7 7

8 7

7 7

7 7

7 8

7 7

7 8

10 10 10 10 10 10 13 13 10 10 10 10 10 10 8

7 7

13 16 15 16 15 16 16 12 12 16 16 15 16 15 16 13 7

7 7

12 16 20 14 20 12 18 12 19 19 12 18 12 20 14 20 16 12 7

7 11 15 20 20 18 10 18 12 18 12 12 18 12 18 10 18 20 20 15 11 7

7 7

9 10 10 13 16 15 16 20 14 20 20 18 12 20 10 20 11 18 13 17 10 17 13 17 10 17 10 18 10 17 10 19 11 18 12 19 11 19 12 19 12 19 19 12 19 11 19 12 18 12 19 10 19 11 18 10 17 10 17 10 17 13 17 13 17 10 20 11 18 12 20 10 20 20 18 16 20 14 13 16 15 9 10 10 7

7 8

7 7

7 10 10 10 10 15 16 15 16 12 20 14 20 18 10 18 20 10 18 10 20 18 14 18 11 10 18 10 17 19 10 17 13 11 17 10 17 17 10 17 10 11 17 11 19 19 10 19 12 12 18 12 19 17 13 19 12 17 13 19 12 12 18 12 19 19 10 19 12 11 17 11 19 17 10 17 10 11 17 10 17 19 10 17 13 10 18 10 17 18 14 18 11 10 18 10 20 18 10 18 20 12 20 14 20 15 16 15 16 10 10 10 10 8

7 7

7 7

12 16 20 14 20 12 18 12 19 19 12 18 12 20 14 20 16 12 7

7 7

13 16 15 16 15 16 16 12 12 16 16 15 16 15 16 13 7

7 8

10 10 10 10 10 10 13 13 10 10 10 10 10 10 8

7 7

7 8

7 7

7 7

7 7

8 7

7 7

1 3

5 7

9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 Fuel Type 7=GEI 4-PI OCNAB434-8G7.0/7G6.0-120T-I 50-T6-3233 (Cycle 13) 14=GE14-Pl0CNAB412-14GZ-120T-150-T6-4043 (Cycle 14) 8=GE14-PIOCNAB416-17GZ-120T-150-T6-3235 (Cycle 13) 15=GE14-PIOCNAB430-15GZ-120T-150-T6-4239 (Cycle 15) 9=GE14-PIOCNAEB417-17GZ-120T-150-T6-3236 (Cycle 13) 16=GE14-PIOCNAB430-14GZ-120T-150-T6-4240 (Cycle 15) 10=GE14-PIOCNAB434-15GZ-120T-150-T6-4039 (Cycle 14) 17=GE14-PI0CNAB418-15GZ-120T-150-T6-4241 (Cycle 15) 1 1=GE04-PIOCNAB422-17GZ-120T-l 50-T6-4041 (Cycle 14) 18=GE14-PIOCNAB419-17GZ-120T-150-T6-4242 (Cycle 15) 12=GE14-P1OCNAB412-15GZ-120T-150-T6-4040 (Cycle 14) 19=GE14-PIOCNAB418-16GZ-120T-150-T6-4243 (Cycle 15) 13=GE14-PIOCNAB422-17GZ-120T-150-T6-4042 (Cycle 14) 20=GE14-P10CNAB422-16GZ-120T-150-T6-4244 (Cycle 15)

Figure 1 Reference Core Loading Pattern Page 25

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 LRNBP ICF..TNMI-EIS KIs 140 120 100 I60 wt 60 40 20 700 400 500 200 100 a

U K

1400 1350 1300 1250~

120oj 1100 1050 1000 0

1 2

3 4

5 6

Time (sec) 160 120 80

-40 0

.40 60 4.0 3.5 50 3.0 2.5 40 2.0 30 1.0

-1.5 201

.0

'S A -0.5 10

-1.0

-1.5 0

-2.0

-80 t,,,,

i 0

1 2

3 tft~C.A.

~3~S~~'S Tirne (sa) 0 2

3 4

Time (sec) 6 Figure 2 Plant Response to Load Rejection w/o Bypass (MOC ICF (HBB))

Page 26

Nine Mile Point 2 D.1 A 1A 000N2528-SRLR D

1 FWCF ICFjNMIaES KGI is 140 120 100 u80 S

40 560 40 480 30 400 a

320 _

1201 24 0 1 160 10 1300 1200 1100 lO00 80 0

0 0

5 10 15 20 Thme (see) 0 5

10 Time (sec) 15 20 160 140 120 100 80so 40 20 40

-20

-20 T

_0 100 90 80 70 60 50 40 30 20 10 0

I S

IA

.5 U

-j 4.0 3.5 3.0 2.5 2.0 1.5 0.5 0.0

-0.5

-1.0

-1.5

-2.0

-Totld Reactivity Sawn Reeil

-Doppler Teniperature Rouvitly VoidReatvt 10 Tkme (sec) 15 20 0

5 10 Time (sec) 15 20 Figure 3 Plant Response to FW Controller Failure (MOC ICF (HBB))

Page 27

Nine Mile Point 2 D,,*1 A 1A 000N2528-SRLR D *,; e;c 1

%, uau

.1 a

ns.v II.n TTNBP KGI Is 140 120 100 480 2e0 40 TTNBP ICFTNEO-EIS 700 80 6OO 70 60 500 505 400.

30 200 20 100 10 0

0 1400 1350 1300 1250 1200~

1100 1050 1000 0

1 2

3 4

5 a

Tkne (sec) 0 2

3 4

5 6

Time (sec) 160 Stmn Flow Tubie Stwa Flow NR Ievel 120 80 so

-40 40

-40 0

1 2

3 4

5 6

sosas*

tSW.

2 Time (see) 60 50 40 30~

201j

.5 10 0

4.0 3.5 3.0 2.5 2,0 1.0.

056 0.0

-0.5

-1.0

-1.5

-2.0 2

3 Time (sec) 4 5

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

Page 28

Nine Mile Point 2 Relnod 14 000N2528-SRLR Revkinin 1 FWCF ICF.TNEO-EIS KG1 1s 140 120 100 80 U

4t60 40 20 0

40 30 20 10 1300 1200 11000 1000 5

10 15 20 Thme (sec) 0 10 Time (sec) 15 20 160 140 120 100 80 I6 40 20 0

-20

-40 0

100 90 80 70 60 50 40 30 20 10 0

U I

UI I1.

I U

4.0 3.5 3.0 2.5 2.0 1.5 1.0 0ý5

• 0.0

-0.5

-1.0

-1.5

-2.0 TOW.acbvtty Scrwm Raty Dopplr Toemprsture Rem"kv~

- -Void Rdik 10 Time (Sec) 15 20 0

5 10 Tim. (see) 15 20 Figure 5 Plant Response to FW Controller Failure (EOC ICF (HBB))

Page 29

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision I KG1 15 120 100 80 W

60 40 20 0

LRNBP MLPTNMI-EIS 480 80 70 400 so-320 5

240 40 1601 30 20 80 10 0

0 1350 1300 1250 1200IIS 1150 1050 1000 950 160 120 80 40 0

-40D

-80

-H 0

4.0 3.5 3.0 a

I SI IA 3

S

-J 2.5 2.0 1.5 1.0

~0.5 So.o

-0.5

-1.0

-1.5

-2.0 3

Tim. (sec) 0 1

2 3

Time (sac) 4 5

6 Figure 6 Plant Response to Load Rejection w/o Bypass (MOC LCF (HBB))

Page 30

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision I FWCF MLPjNM1-E1S KG1 15 140 -

120.

100-Core Inlet Flow

• ý Sarnilded Thermael Power Natanm Fhix K So 4-420 3W0 30W I

.240.

1801 120 60 1300 1200 1100

]iU, I

60 ý 4o 4-20-0 160 140 120 100 80.

~60 40 20 0

-20

-40 1000 U

5 10 Thu (sec) 15 D

100 4.0 90 3.5 3.0 80 2.5 701

~

2.0 so 11.0 40 0,5 0.0 30 K

20

-1.0 10

-1.5 0

-2.0 tttSo..O j U*jf.S,1413 Figure 7 Plant Response to FW Controller Failure (MOC LCF (HBB))

Page 31

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 LRNBP MLPJNEO-EIS KG1 15 560 1400 1350 120 480 1300 100 400 wt60 I.

320.

2401J

'2 1250~

1200j 1150 I 40 160 1100 20 80 1050 0

0 1000 160 60 4.0 120 80 40 3.5 50 3.0 2.5 40 2.0 1.5 30 1.0 0.5

201, 0.0

-0.5 10

-1.0

-1.5 0

-2.0 I--*-o leacbOWWy

-Sewvn ROaci0

-DoppWe Torenpursk RowAelty

-.Vold Rebk

-40

-W0 0

1 2

3 Time (sft) 4 5

1

,*.Q.

t.5S Figure 8 Plant Response to Load Rejection w/o Bypass (EOC LCF (HBB))

Page 32

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision I FWcF MLPTNEO-EIS KGI 15 140 120 4 100 I

U K.5 804 core Inlet Flo SmIstded Thermnal Power

- Neubmn Flux 580 40 480 30 400 320 2 4 0 9

160 10 1300 12Do 1100D 1000 soI 4o 4 20, 0

80 0

0 1

5 10 Tbm (see) 15 2 0 160 140 120 100 80 Uso 40 100 4.0 90 3.5 3.0 80 2.5 70i 2

2.0 40.

ODO 30

-0.5 20

-1.0 10

-1.5 0

-2.0 Scram React*ty Doppler Temperiure Reactivity Void Rea ty 0

-20

-40 0

5 10

.ý.

MýS,*mf Time (eei) 15 20 0

5 10 Time (sec) 15 20 Figure 9 Plant Response to FW Controller Failure (EOC LCF (HBB))

Page 33

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision I FwVcF 1CFJ-NEO-TOVOCIS KG1 15 140 120 100 40 2,0 40 80 70 80 50ws o 1140 30 20 10 0

1400 1350 1300 1250 I

1200i 1100 1050 1000 0

5 10 Tkne ("ee) 15 20 0

5 10 15 20 Time (See) 140 120 100 80 60 40 20 0

-20

-40

-60

-e Steam~ Flow Turbine Steami Flow

--a-NR level 0

5 10 15 20 100 4.0 90 3.5 3.0 8o

.1 2.5 70 so 1.0 401 0.15 0.0 30 0

-0.5 20

-1.0 10

-1.5 0

-2.0 I--*

lOKOOw

~Acty

-- a-Scram Reactivity

-Doppler Temperature Reactivity VoidReatvt

-R I

+

I 0

0 5

10 Time (sec) 15 20 Ut.*CwD 0

tnw T*me (sae)

Figure 10 Plant Response to FW Controller Failure (EOC ICF with TBVOOS (HBB))

Page 34

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 FWCF MLP_TNEO-TBVOOS KGI 15 140 120.ý 100.

C or Inbt

- Mtm~ F1 SmidThwmai Powm 560

.480

,400 U

U K

.5 804-60 40 1 S

U 320 240 160 so 1400 1350 1300 1250 12005 1150 1100 1050 1000 20 0

I I

I

-~

0 5

10 Tin. (s")

15 2 0 140 120 100 so so 40 20 10

-20

-40

-00 0

5 10 TR~tAA 13*5 *34*,

Tin. (usc) 100 4.0 90 3.5 3.0 80 2.5 706

,50 11.0 40

-0.5 0.0 30 K

-05 20

-1.0 10

-1.5 0

-2.0 15 20 0

5 10 Tine (sec) 15 20 Figure 11 Plant Response to FW Controller Failure (EOC LCF with TBVOOS (HBB))

Page 35

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 TTNSP ICFjNMI-RPTOOS KGI Is 140 120 100 v 80 40, 0

a~0 40 20

.0

-80 80 70 60 50 140 30 20 10 0

1400 1350 1300 1250 12005 1150 1100 1050 1000 4.0 3.5 3.0 2.5 2.0 1.5 1.0 U0.:

o.1 0.0

-0.5

-1.0

-1.5

-2.0 fk.m-cm" 2mmt,~

Figure 12 Plant Response to Turbine Trip w/o Bypass (MOC ICF with RPTOOS (HBB))

Page 36

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision I KGI is 140 120 100 40 20 0

FWCF ICFTNMI-RPTOOS 700 40 600 30

,500 400 01J20 3 00 e

200 10 100 0

0 1300 12D0O 11000 1000 Time (sac) 160 140 120 100 80 II 40 20 0

-20 -

.0 100 90 80 70 60 50 40 30 20 10 I

III,

-J*1 4.0 3.5 3.0 2.5 2.0 1.0

.0.5

-1.0

-1.5

-2.0 TO-

-OOW

-U-Scram Recit

-Doppler Temporours, Reactiity Void Roalvt 10 Tk (is")

0 5

10 Time (sec) 15 20 Figure 13 Plant Response to FW Controller Failure (MOC ICF with RPTOOS (HBB))

Page 37

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 LRNBP ICFTNEO-RPTOOS KGI 15 72 s so 100 90 80 70 60 40 30 20 10 0

1450 1400 1350 1300 12501 12100 1150 1100 1050 1000 950 160 120 80 U40 0

4.0 3.5 3.0 2.5 2.0 1.5 1.0 0.5 0.0

-0.5

-1.0

-1.5

-2.0

-40

-80 0

1 2

3 4

5 6

Figure 14 Plant Response to Load Rejection w/o Bypass (EOC ICF with RPTOOS (HBB))

Page 38

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 pWcF ICFjNEO-RPTOOS KGI Is 140

120, 100*

v 80 IF8

-- Core IWhat Flow Sirnuilaed Themfna Power 700 60 600 50 5oo 40 400.

2 S130 3"

20 200 1300 1250 1200 1150 1100 1050 1000 4-404 10 20 0

100 0

0 5

10 Thm (sec) 15 2 0 160 140 120 100 80 Il 40 20 0

-20 F. ~dVwgtf HMt Stearn Flo Turbine Stemn Flow NRI lel 100 4.0 90 3.5 3.0 80

.1 2.5 70" S 2.0 6 0 1.5 50 1*)1.0

-0.0

.30 49 0.5 20

-1.0 10

-1.5 0

-2.0

-40 0

5 10 I*AM-CAW-o w..

Tkne (50c) 15 20 Figure 15 Plant Response to FW Controller Failure (EOC ICF with RPTOOS (HBB))

Page 39

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 LRNBP MLPJNMI.RPTOOS K15 140 120 100 a' 60 40 20 0

58o 480 400 320 1 2 401 160 80 1400 1350 1300 1250 1200i 1100 1050 1000 0

1 2

3 4

5 6

Time (see) 160.oodwae Flow Steam Flow Turbine Steam Flow NR level 120 80 340 0

-40 0

1 2

3 4

5 6

M* ý-~

Time (ee) 60 4.0 3.5 50 3.0 2.5 40 2.0 1.5 20 1.00 1

-0.5

'a 10

-1.0

-1.5 0

-2.0 2

3 4

5 6

Tine (Sec)

Figure 16 Plant Response to Load Rejection w/o Bypass (MOC LCF with RPTOOS (HBB))

Page 40

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 FW4CF MLP..TNMI-RPTOOS KG1 4At I

120 4-100 so Ie 60 40 20 0

10fO Inlt lW

-~Simutiid Thwnii Power Neuton Flux 420 40 360 30 300 240 1 120 120 10 60 0

0 1300 1200 1100 i

1000 5

10 Tim. (sec) 15 2

160 140 120 100 80 Is 40 20 0

-20 100 4.0 90 3.5 3.0 80 i

2.5 70 2.0 so 1.0 40 10-5 0.0

• 0

-0.5 20

-1.0 10

-1.5 0

-2.0

-Scrub, Reac#Aty Doppler Temp~reure R..c*4ft

-Voi Reaht UI1/2 I

I I

-40 0

5 10 TRýCft Tike (-ec) 15 20 0

5 10 Time (sec) 15 20 Figure 17 Plant Response to FW Controller Failure (MOC LCF with RPTOOS (HBB))

Page 41

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 LRNSP MLP...NE0-RPTOOS KGI 1s 140 120 100

~60 40 20 0

Corn Inmt Flow

-- Sknudied Thwmnu Powet

~-Natka Fkm 560 80 480 70 60 400 50

• Ki 320~

1 40 24 0 A0 160 0

20 1400 1350 1300 1250 12005 1150 I 1100 1050 1

2 3

Tuim Isem) 4 5

o80 10 0

0 C

80 4.0 3.5 50 3.0 2.5 30!

1.0 H

0.5 0.0 10

-1.0

-1.5 0

-2.0 1000 Tim. (sec)

• 1 U

K 10ý-C."

MýSýWý,

Figure 18 Plant Response to Load Rejection w/o Bypass

( EOC LCF with RPTOOS (HBB))

Page 42

Nine Mile Point 2

ý1-olA 1A 000N2528-SRLR Ri-xtccinn I PWVCF MLPJTNEO-RPTOOS KG1 15 140 120 100

.80 40 20 0

0 5

10 15 20 Tin. (see) 40 30 120 lO 00 4.0 3.5 3.0 2.5

-2.0 1.0 0.5 0.0

-0.5

-1.0

-1.5

-2.0 1300 1200 1100 1000 5

10 Time (sec) 15 20 160.

140 120 100 80 160 2 0 40

-20

-40 0

100 90 80 70 60~

401 20 10 0

10 Time (sec) 15 20 10 Tine (sec)

Figure 19 Plant Response to FW Controller Failure (EOC LCF with RPTOOS (HBB))

Page 43

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 MSIVF ICF_TNEO-Ovmpress KGI 15 140 120 100 80 at 60 40 20 0

120 100 80 at 40 20 Tim. (sec) 420 100 9o 360 80 300 70 I

6 240 60 1801 40 120 30 20 60 10 0

0 60 4.0 3.5 50 3.0

,1 2.5 40 S 2.0 1.5 30 >'

1.0

-201

oo

-1.5 0

-2.0 1450 1400 1350 1300 12501 12005 1150IL 1100 1050 1000 950 Time (sGec) 0 ~- - -

U I.-~H 0

1 2

0 M..C

¶3OlIwR 3

4 Time (sec)

Figure 20 Plant Response to MSIV Closure (Flux Scram) - ICF (HBB)

Page 44

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 KGI 1s MSIVF MLPTNEO-Overpress 420 100 90 360 8o 30O 70 60 2401

" 80 40 120 3

20 oSo 10 0

0 u80 0

1450 1400 1350 1300 1250j 1200j 1150I.

1100 1050 1000 950 0

1 2

3 4

5 6

7 Time (see)

Time (see) 120-,

100 80 40 20 0

1 T*Oc.wfl ~tS 2M lSfl 60 4.0 3.5 50 3.0 2.5 U

40 2.0 l.5 30 1.0 201 0.0

-0.5 10

-1.0

-1.5 0

-2.0 Figure 21 Plant Response to MSIV Closure (Flux Scram) - LCF (HBB)

Page 45

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 0A a-U 110 100 90 80 70 60 50 40 30 20 10 0

-L Na" Urlto UnI

-a-cienue Operating Domain x ISP Scram Rejgot, Bot~ndary SP C-ontrolled Ent-eg-n Boundar

.l

+~ ~~~~~

~~ - -

A1-L L

102 0

4 06 0

0 9

0 1

2 I

a 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow(%)

Figure 22 BSP Region Boundaries Page 46

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 Appendix A Analysis Conditions The reactor operating conditions used in the reload licensing analysis for this plant and cycle are presented in Table A-1. The pressure relief and safety valve configuration for this plant are presented in Table A-2. Additionally, the operating flexibility options listed in Section 8 are supported by the reload licensing analysis.

Table A-1 Reactor Operating Conditions Analysis Value Parameter ICF LCF 15 NFWT NFWT Thermal power, MWt 3988.0 3988.0 Core flow, Mlb/hr 114.0 92.2 Reactor pressure (core mid-plane), psia 1051.0 1047.2 Inlet enthalpy, Btu/lb 530.0 525.2 Non-fuel power fraction 16 N/A N/A Steam flow, Mlb/hr 17.63 17.63 Dome pressure, psig 1020.2 1020.2 Turbine pressure, psig 975.5 975.6 Table A-2 Pressure Relief and Safety Valve Configuration Valve Type Number of Lowest Setpoint Valves (psig)

Dual Safety/Relief Valve 18 1121.0 (Relief Mode) 1200.0 (Safety Mode)

I5 The low core flow analysis condition used a bounding core flow value.

16 For TRACG methodology, the direct moderator heating is a function of moderator density.

Page 47

Nine Mile Point 2 P In-A 1A 000N2528-SRLR RPý1;cinn 1 Appendix B Thermal-Mechanical Compliance A thermal-mechanical compliance check is performed for all analyzed transients to assure that the fuel will operate without violating the thermal-mechanical design limits. These limits are designed such that reactor operation within these limits provides assurance that the fuel will not exceed any thermal-mechanical design or licensing limits during all modes of operation. The fuel thermal-mechanical limits are met for the current cycle.

Page 48

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 Appendix C Decrease in Core Coolant Temperature Event The Loss-of-Feedwater Heating event was analyzed at 100% rated power using the BWR Simulator Code. The use of this code is consistent with the approved methodology. 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.

Page 49

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 Appendix D Off-Rated Limits Off-Rated Power Dependent Limits ARTS power dependent thermal limits have been confirmed for operation with Equipment In-Service, Turbine Bypass Valves Out-Of-Service (TBVOOS), Recirculation Pump Trip Out-Of-Service (RPTOOS) and Pressure Regulator Out-Of-Service (PROOS).

The Kp/MCPRp and LHGRFACp thermal limits applicable to the Equipment In-Service, TBVOOS and RPTOOS conditions are documented in Reference D-1.

The Kp/MCPRp and LHGRFACp thermal limits applicable to the PROOS condition are documented in References D-4 and D-2. The off-rated power dependent limits provided in References D-4 and D-2 have been validated for this cycle.

The MCPRp limits provided in References D-4 and D-2 are based on a SLMCPR of 1.07; therefore, a SLMCPR adjustment is not required for this cycle. The Reference D-2 limits for PROOS below 55%

power have been adjusted as a result of the shift in fuel thermal monitor threshold and scaling of Pbypass similar to the adjustment shown in Reference D-3.

The MCPRp and LHGRFACp limits below the turbine power/scram bypass setpoint of 26% rated power have only been evaluated for core flow less than or equal to 75% of rated core flow. Therefore, the MCPRp and LHGRFACp limits below 26% power are not applicable above 75% of rated core flow.

MCPRp Limits for:

Equipment In-Service Limits for Power < 26.0%

Flow > 75.0%

Flow <75.0%

Power (%)

Limit Power (%)

Limit MCPRp MCPRp 23.0 Not Analyzed 23.0 2.47 26.0 Not Analyzed 26.0 2.39 Limits for Power >26.0%

Power (%)

Limit Kp 26.0 1.511 55.0 1.336 55.0 1.193 60.0 1.150 85.0 1.056 100.0 1.000 Page 50

Nine Mile Point 2

.1 -nA 1A 00ON2528-SRLR MCPRp Limits for:

TBVOOS Limits for Power < 26.0%

Flow > 75.0%

Flow < 75.0%

Power (%)

Limit Power (%)

Limit MCPRp MCPRp 23.0 Not Analyzed 23.0 3.27 26.0 Not Analyzed 26.0 3.00 Limits for Power > 26.0%

Power (%)

Limit Kp 26.0 1.511 55.0 1.336 55.0 1.193 60.0 1.150 85.0 1.056 100.0 1.000 MCPRp Limits for:

RPTOOS Limits for Power < 26.0%

Flow > 75.0%

Flow < 75.0%

Power (%)

Limit Power (%)

Limit MCPRp MCPRp 23.0 Not Analyzed 23.0 2.47 26.0 Not Analyzed 26.0 2.39 Limits for Power > 26.0%

Power (%)

Limit Kp 26.0 1.511 55.0 1.336 55.0 1.193 60.0 1.150 85.0 1.062 100.0 1.000 Page 51

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision I MCPRp Limits for:

PROOS Limits for Power < 26.0%

Flow > 75.0%

Flow < 75.0%

Power (%)

Limit Power (%)

Limit MCPRp MCPRp 23.0 Not Analyzed 23.0 2.47 26.0 Not Analyzed 26.0 2.39 Limits for Power > 26.0%

Power (%)

Limit Kp 26.0 1.511 90.0 1.122 90.0 1.038 100.0 1.000 LHGRFACp Limits for:

Equipment In-Service Limits for Power < 26.0%

Flow > 75.0%

Flow < 75.0%

Power (%)

Limit Power (%)

Limit 23.0 Not Analyzed 23.0 0.597 26.0 Not Analyzed 26.0 0.613 Limits for Power >26.0%

Power (%)

Limit 26.0 0.613 100.0 1.000 LHGRFACp Limits for:

TBVOOS Limits for Power < 26.0%

Flow > 75.0%

Flow < 75.0%

Power (%)

Limit Power (%)

Limit 23.0 Not Analyzed 23.0 0.535 26.0 Not Analyzed 26.0 0.556 Limits for Power > 26.0%

Power (%)

Limit 26.0 0.613 100.0 1.000 Page 52

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 LHGRFACp Limits for:

RPTOOS Limits for Power < 26.0%

Flow > 75.0%

Flow < 75.0%

Power (%)

Limit Power (%)

Limit 23.0 Not Analyzed 23.0 0.597 26.0 Not Analyzed 26.0 0.613 Limits for Power?> 26.0%

Power (%)

Limit 26.0 0.613 100.0 1.000 LHGRFACp Limits for:

PROOS Limits for Power < 26.0%

Flow > 75.0%

Flow < 75.0%

Power (%)

Limit Power (%)

Limit 23.0 Not Analyzed 23.0 0.597 26.0

--- Not Analyzed 26.0 0.613 Limnts for Power >_ 26.0%

Power (%)

Limit 26.0 0.613 90.0 0.850 90.0 0.948 100.0 1.000 Page 53

Nine Mile Point 2 Reload 14 000N2528-SRLR Revkinin I Off-Rated Flow Dependent Limits ARTS flow dependent thermal limits are documented in Reference D-1. The off-rated flow dependent limits provided in Reference D-l have been validated for this cycle.

The MCPRf limits provided in Reference D-1 are based on a SLMCPR of 1.07; therefore, a SLMCPR adjustment is not required for this cycle.

MCPRf Limits for:

Equipment In-Service Limits for a Maximum Runout Flow of 112.0%

Flow (%)

Limit MCPRf 30.0 1.66 87.3 1.25 112.0 1.25 MCPRf Limits for:

TBVOOS Limits for a Maximum Runout Flow of 112.0%

Flow (%)

Limit MCPRf 30.0 1.66 87.3 1.25 112.0 1.25 MCPRf Limits for:

RPTOOS Limits for a Maximum Runout Flow of 112.0%

Flow (%)

Limit MCPRf 30.0 1.66 87.3 1.25 112.0 1.25 MCPRf Limits for:

PROOS Limits for a Maximum Runout Flow of 112.0%

Flow (%)

Limit MCPRf 30.0 1.66 87.3 1.25 112.0 1.25 Page 54

Nine Mile Point 2 0 1 A 1A 00ON2528-SRLR V ; ;

I NIne Mile Poin*t 2"L LHGRFACf Limits for:

Equipment In-Service Limits for a Maximum Runout Flow of 112.0%

Flow (%)

Limit 30.0 0.625 85.0 1.000 112.0 1.000 LHGRFACf Limits for:

TBVOOS Limits for a Maximum Runout Flow of 112.0%

Flow (%)

Limit 30.0 0.625 85.0 1.000 112.0 1.000 LHGRFACf Limits for:

RPTOOS Limits for a Maximum Runout Flow of 112.0%

Flow (%)

Limit 30.0 0.625 85.0 1.000 112.0 1.000 LHGRFACf Limits for:

PROOS Limits for a Maximum Runout Flow of 112.0%

Flow (%)

Limit 30.0 0.625 85.0 1.000 112.0 1.000 References D-1 Nine Mile Point Nuclear Station Unit 2 - APRAMRBM/Technical Specifications / Maximum Extended Load Line Limit Analysis (ARTS/MELLLA), NEDC-33286P, Revision 0, March 2007.

D-2 Nine Mile Point Nuclear Station Unit 2 ARTS/MELLLA, Task T0900: Transient Analysis, GE-NE-0000-0055-2373-RO, Revision 0, February 2007.

D-3 Nine Mile Point Nuclear Station Unit 2 Extended Power Uprate, Task T0900: Transient Analysis, 0000-0069-6612-Ri, Revision 1, January 2009.

D-4 Nine Mile Point Nuclear Power Plant, Unit 2, TRACG Implementation for Reload Licensing Transient Analysis (T1309), 0000-0157-9895-R1, Revision 1, October 2013.

Page 55

Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1 Appendix E Expanded Operating Domain Analysis Expanded operating domain analyses were performed for Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operation, Increased Core Flow (ICF) operation up to 105% of rated core flow, turbine bypass valve out-of-service (TBVOOS), recirculation pump trip out-of-service (RPTOOS), and pressure regulator out-of-service (PROOS). The MELLLA+ analysis is bounding for the MELLLA domain.

Coastdown operation beyond full power to 40% power under conditions bounded by 105% core flow is conservatively bounded by the MCPR operating limits given in Section 11 of this document at the applicable core flow and feedwater temperature conditions in the expanded operating domain. The basis for this statement is contained in Reference E-1.

100% Core Flow (Standard Domain)

It has been established that ICF and/or MELLLA domain results bound the standard (rated core flow) domain. Therefore, a cycle-specific analysis is not performed for the standard domain.

Maximum Extended Load Line Limit Analysis The operating domain MELLLA was established for Nine Mile Point 2 in Reference E-2.

Increased Core Flow Operation with ICF throughout the operating cycle was justified for Nine Mile Point 2 in Reference E-3.

The MSIV closure event (flux scram) was analyzed at 100% rated thermal power and both 85% and 105% rated core flow at the rated dome pressure.

An operational band of - 20'F from nominal feedwater temperature is supported this cycle for all Application Conditions specified in Section 11.

Turbine Bypass Valve Out of Service (TBVOOS)

Operation with TBVOOS was justified for Nine Mile Point 2 in Reference E-3.

EOC Recirculation Pump Trip Out of Service (EOC RPTOOS)

Operation with EOC RPTOOS was justified for Nine Mile Point 2 in Reference E-3.

Pressure Regulator Out of Service (PROOS)

Operation with PROOS was addressed for Nine Mile Point 2 from a thermal limits perspective only in Reference E-3.

Page 56

Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1 References for Appendix E:

E-1 General Electric Standard Application for Reactor Fuel (GESTAR II), NEDE-2401 I-P-A-20, December 2013 and the U.S. Supplement, NEDE-2401 1-P-A-20-US, December 2013.

E-2 Safety Analysis Report for Nine Mile Point Nuclear Station Unit 2 Constant Pressure Power Uprate, NEDC-33351P, Revision 0, May 2009.

E-3 Project Task Report, Constellation Generation Group, Nine Mile Point Nuclear Station Unit 2 Extended Power Uprate, Task T0900: Transient Analysis, 0000-0069-6612-Ri, Revision 1, January 2009.

Page 57

Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1 Appendix F TRACG04 AOO Supplementary Information Reference F-I provides the results of the evaluations supporting the application of TRACG04 for AOO analyses for Nine Mile Point 2.

Section 11 of this report presents the MCPR limits based on the TRACG04 methodology of Reference F-2.

The safety evaluation report for licensing topical report NEDE-32906P (Reference F-2) concluded that the application of TRACG04 methods to AOO and overpressure transient analyses were acceptable subject to certain limitations and conditions. Nine Mile Point 2 Cycle 15 is in compliance with these limitations and conditions.

References for Appendix F F-1. Nine Mine Point Nuclear Power Plant, Unit 2, TRACG Implementation for Reload Licensing Transient Analysis (T1309), 0000-0157-9895-R1, Revision 1, October 2013.

F-2. Migration to TRACGO4/PANACll from TRACGO2/PANACIO for TRACG AOO and ATWS Overpressure Transients, NEDE-32906P, Supplement 3-A, Revision 1, April 2010.

Page 58

Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1 Appendix G Interim Methods LTR (NEDC-33173P-A Revision 4)

Supplemental Information The safety evaluation for licensing topical report NEDC-33173P-A Revision 4 (Reference G-1) concluded that the application of GEH/GNF methods to expanded operating domains was acceptable subject to certain limitations and conditions.

Several of these limitations and conditions request that additional, application-specific information be provided in the SRLR. The information provided below responds to these requests for the identified items.

Limitation and Condition 9.10/9.11 (Transient LHGR 2/3)

Limitation and Condition 9.10 states:

"Each EPU and MELLLA+ fitel reload will document the calculation results of the analyses demonstrating compliance to transient T-M acceptance criteria. The plant T-M response will be provided with the SRLR or COLR, or it will be reported directly to the NRC as an attachment to the SRLR or COLR."

Limitation and Condition 9.11 states:

"To account for the impact of the void history bias, plant-specific EPU and MELLLA+

applications using either TRACG or ODYN will demonstrate an equivalent to 10 percent margin to the fiel centerline melt and the 1 percent cladding circumferential plastic strain acceptance criteria due to pellet-cladding mechanical interaction for all of limiting AO0 transient events, including equipment out-of-service. Limiting transients in this case, refers to transients where the void reactivity coefficient plays a significant role (such as pressurization events). If the void history bias is incorporated into the transient model within the code, then the additional 10 percent margin to the fitel centerline melt and the 1 percent cladding circumferential plastic strain is no longer required. "

Appendix B documents the fact that the results for all analyzed transients demonstrate compliance with thermal-mechanical acceptance criteria.

Table G-1 summarizes the percent margin to the Thermal Overpower and Mechanical Overpower acceptance criteria.

As referenced in Appendix F the void history bias was incorporated into the transient model within the TRACG04 code, and therefore the 10 percent margin to the fuel centerline melt and the 1 percent cladding circumferential plastic strain acceptance criteria is no longer required.

Page 59

Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1 Table G-1 Margin to the Thermal Overpower and Mechanical Overpower Acceptance Criteria Criteria GE14C Thermal Overpower 28.5%

Mechanical Overpower 14.9%

Limitation and Condition 9.17 (Steady-State 5 Percent Bypass Voiding)

Limitation and Condition 9.17 states:

"The instrumentation specification design bases limit the presence of bypass voiding to 5 percent (LRPM (sic) levels). Limiting the bypass voiding to less than 5 percent for long term steady operation ensures that instrumentation is operated within the specification.

For EPU and MELLLA + operation, the bypass voiding will be evaluated on a cycle-specific basis to confirm that the void firaction remains below 5 percent at all LPRM levels when operating at steady-state conditions within the MELLLA + upper boundary.

The highest calculated bypass voiding at any LPRM level will be provided with the plant-specific SRLR. "

The bypass voiding was evaluated for the licensed core loading and confirmed that the bypass void fraction remained below 5 percent at all LPRM levels when operating at steady-state conditions within the licensed upper boundary.

Limitation and Condition 9.18 (Stability Setpoints Adjustment)

Limitation and Condition 9.18 states:

"The NRC staff concludes that the presence bypass voiding at the low-flow conditions where instabilities are likely can result in calibration errors of less than 5 percent for OPRM cells and less than 2 percent for APRM signals. These calibration errors must be accounted for while determining the setpoints for any detect and suppress long term methodology. The calibration values for the different long-term solutions are specified in the associated sections of this SE, discussing the stability methodology. "

The OPRM system will incorporate a 5% calibration error on the OPRM setpoints to address the bypass voiding uncertainty at low-flow conditions.

This calibration error has been included in the OPRM amplitude setpoints. However, the APRM calibration error required by this limitation and condition is not applicable.

Page 60

Nine Mile Point 2 000N2528-SRLR Reload 14 Revision 1 Limitation and Condition 9.19 (Void-Quality Correlation 1)

Limitation and Condition 9.19 states:

"For applications involving PANCEA(sic)/ODYN/ISCORITASC for operation at EPU and MELLLA +, an additional 0.01 will be added to the OLMCPR, until such time that GE expands the experimental database supporting the Findlay-Dix void-quality correlation to demonstrate the accuracy and petformance of the void-qualitv correlation based on experimental data representative of the current fuel designs and operating conditions during steady-state, transient, and accident conditions."

The OLMCPR limitation requiring an additional 0.01 adder on the OLMCPR does not apply to EPU or MELLLA+ licensing calculations when TRACG04 methods are used (Reference G-2). Therefore, the OLMCPR adder is not applied to Nine Mile Point 2 Cycle 15.

References for Appendix G G-1.Applicability of GE Methods to Expanded Operating Domains, NEDC-33173P-A, Revision 4, November 2012.

G-2. Migration to TRACG04 / PANA ClI firom TRACG02 / PANACIO for TRACG AO0 and ATWS Overpressure Transients, NEDE-32906P, Supplement 3-A, Revision 1, April 2010.

Page 61

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision I Appendix H List of Acronyms Acronym Description ACPR Delta Critical Power Ratio Ak Delta k-effective 2RPT (2PT)

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 BWROG Boiling Water Reactor Owners Group COLR Core Operating Limits Report CPR Critical Power Ratio DIRPT Delta MCPR over Initial MCPR for a two-Recirculation Pump Trip DIVOM Delta CPR over Initial MCPR vs. Oscillation Magnitude DR Decay Ratio DS/RV Dual Mode Safety/Relief Valve ECCS Emergency Core Cooling System ELLLA Extended Load Line Limit Analysis EOC End of Cycle (including all planned cycle extensions)

EOR End of Rated (All Rods Out 100%Power / 100%Flow / NFWT)

EPU Extended Power Uprate ER Exclusion Region FFWTR Final Feedwater Temperature Reduction FMCPR Final MCPR FOM Figure of Merit FWCF Feedwater Controller Failure FWHOOS Feedwater Heaters Out of Service FWTR Feedwater Temperature Reduction GESTAR General Electric Standard Application for Reactor Fuel GETAB General Electric Thermal Analysis Basis GSF Generic 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 ICA Interim Corrective Action ICF Increased Core Flow Page 62

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 Acronym Description IMCPR Initial MCPR IVM Initial Validation Matrix Kf Off-rated flow dependent OLMCPR multiplier Kp Off-rated power dependent OLMCPR multiplier L8 Turbine Trip on high water level (Level 8)

LCF Low Core Flow LHGR Linear Heat Generation Rate LHGRFACf Off-rated flow dependent LHGR multiplier LHGRFACp Off-rated power dependent LHGR multiplier LOCA Loss of Coolant Accident LOSC Loss of Stator Cooling LPRM Local Power Range Monitor LRHBP Load Rejection with Half Bypass LRNBP Load Rejection without Bypass LTR Licensing Topical Report MAPFACf Off-rated flow dependent MAPLHGR multiplier MAPFACp Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPRf Off-rated flow dependent OLMCPR MCPRp Off-rated power dependent OLMCPR MELLLA Maximum Extended Load Line Limit Analysis MELLLA+

MELLLA Plus MOC Middle of Cycle MRB Maximal Region Boundaries MSF Modified Shape Function MSIV Main Steam Isolation Valve MSIVOOS Main Steam Isolation Valve Out of Service MSR Moisture Separator Reheater MSROOS Moisture Separator Reheater 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 N/A Not Applicable NBP No Bypass NCL Natural Circulation Line NFWT Normal Feedwater Temperature NOM Nominal Bum NTR Normal Trip Reference OLMCPR Operating Limit MCPR OOS Out of Service Page 63

Nine Mile Point 2 D, I A IA 000N2528-SRLR V

1 Acronym Description OPRM Oscillation Power Range Monitor Pbypass Reactor power level below which the TSV position and the TCV fast closure scrams are bypassed 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 PLU Power Load Unbalance 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 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 (SRV)

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 TBSOOS Turbine Bypass System Out of Service 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 TSV Turbine Stop Valve Page 64

Nine Mile Point 2 Reload 14 000N2528-SRLR Revision 1 Acronym Description TSVOOS Turbine Stop Valve Out of Service TT Turbine Trip TTHBP Turbine Trip with Half Bypass TTNBP Turbine Trip without Bypass UB Under Bum Page 65