JAFP-05-0125, Core Operating Limits Report Revisions 17 & 18 (Cycle 17 Updates)

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Core Operating Limits Report Revisions 17 & 18 (Cycle 17 Updates)
ML052430192
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 08/17/2005
From: Ted Sullivan
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-05-0125
Download: ML052430192 (66)
v • d • e


Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

eel James A. Fitzpatrick NPP RO. Box 110

/I ter7 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 August 17, 2005 T.A. Sullivan JAFP-05-01 25 Site Vice President - JAF United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Core Operating Limits Report Revisions 17 & 18 (Cycle 17 updates)

Dear Sir; Attached are Revisions 17 (effective date 07/27/2005) and 18 (effective date7/29/2005) to the James A. FitzPatrick (JAF) Core Operating Limits Report (COLR). These reports are being submitted in accordance with Technical Specifications (TS) 5.6.5.

Revision 17 of the COLR incorporated changes as a result of APRM setpoint changes and Rod Block Monitor setpoint clarifications that were implemented during JAF's current Cycle 17 operation. These changes were previously analyzed in the JAF reload analysis completed by Global Nuclear Fuel (GNF) for Cycle 17. Also included were changes to the stability portion of the reload analysis.

As a result of installation problems encountered with new APRM flow reference cards, Revision 18 to the COLR was issued to remove the specific changes associated with the new cards, which were not installed. Also, the stability portion of the reload analysis, previously acceptable up to 6000 MWD/ST, was extended to 9000 MWD/ST and the COLR updated accordingly.

Editorial corrections and administrative changes, that do not alter the intent of the COLR, were also included in both Revisions 17 and 18.

There are no commitments contained in this letter.

Questions concerning this letter or the attachments may be addressed to Mr. William Drews, Reactor Engineering Superintendent, at (315) 349-6562.

Very truly yours, A - - - ~

T. A. SULLIVAN Site Vice President TAS:GB:dr Attachments as stated ELI1

cc: Mr. Samuel Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory'Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident Inspector U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, New York 13093 Mr. John P. Boska, Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission' Mail Stop 0-8C-2 Washington, DC 20555

E~ntergy NuclearNortheast ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT CORE OPERATING LIMITS REPORT REVISION 17 APPROVED BY: William Drews (

zQ-REACTOR ENGINEERING SUPERINTENDENT DATE: 4 APPROVED BY: Kevin Mulligan by) DATE: A z1/

GENERAL MANAGER - PLANT OPERATIOI,-)

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ........................................ 3 2.0 APPLICABILITY ........................................ 3

3.0 REFERENCES

........................................ 3 4.0 DEFINITIONS ........................................ 4 5.0 RESPONSIBILITIES ..... 5............................

6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS ........................................ 5 7.0 PROCEDURE .... 6.............................

7.1 Operating Limit MCPR .............................................. 6 7.2 Average Planar Linear Heat Generation Rate (APLHGR) ............ .......... 8 7.3 Linear Heat Generation Rate (LHGR) ............................................. 8 7.4 APRM Trip Settings ............................................ 9 7.5 RBM Upscale Rod Block Trip Setting ............................................ 10 7.6 Stability Option 1-D Exclusion Region and Buffer Zone ........................ 11 7.7 Kf- Flow Dependent MCPR Limit ............................................. 11 8.0 FIGURES AND TABLES ................... 12 9.0 EXHIBITS ................... 13 P

Rev. No. 17 Page 2 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 17 of the James A.

Fitzpatrick Nuclear Power Plant. The following limits are addressed:

  • Operating Limit Minimum Critical Power Ratio (MCPR)
  • Flow Dependent MCPR Limits
  • Average Planar Linear Heat Generation Rate (APLHGR)
  • Linear Heat Generation Rate (LHGR)
  • Flow-Biased Average Power Range Monitor (APRM) and Rod Block Monitor (RBM)

Settings

  • Stability Option ID Exclusion Region 2.0 APPLICABILITY The plant shall be operated within the limits specified in this report. If any of these limits are exceeded, the corrective actions specified in the Technical Specifications shall be taken.

3.0 REFERENCES

3.1 JAFNPP Administrative Procedure 12.05, Control of Core Operating Limits Report.

3.2 JAFNPP Technical Specifications.

3.3 Design Change Package ER-JF-03-0155, Cycle 17 Core Reload 3.4 RAP-7.3.17, Core Monitoring Software and Database Changes.

3.5 Plant Operation Up To 100% Power With One Steam Line Isolated, JAF-SE-96-035.

3.6 James A. FitzPatrick Nuclear Power Plant Kf Curve Update, GE-NE-J11-03426-00-01, September 1998.

3.7 General Electric Standard Application for Reload Fuel, NEDE-24011-P-A-14 3.8 GNF Report, Supplemental Reload Licensing Report forJames. A. FitzPatrick Reload 16 Cyclel7, 0000-0026-1984SRLR, Rev.0, Class I, September, 2004.

3.9 JAF-SE-00-032, Rev.0, Extended Loadline Limit Analysis (ELLLA) Implementation.

Rev. No. 17 Page 3 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 3.10 JAF-RPT-MISC-04054, Rev.0, Operation under Extended Loadline Limit Analysis (ELLLA) and Power Uprate 3.11 GE Letter, R. Kingston to P. Lemberg, Scram Time Versus Notch Positions for Option B, REK-E: 02-009, May 28,2002 3.12 GE Report, James A. FitzPatrick Nuclear Power Plant Final Feedwater Temperature Reduction NEDC-33077, September 2002.

3.13 JD-02-122, Final Feedwater Temperature Reduction Implementation.

3.14 GE Report, GE14 Fuel Design Cycle-Independent Analyses for J. A. Fitzpatrick Nuclear Power Plant, GE-NE-0000-0002-1752-O1P, Rev. 0, DRF 0000-0002-1752, September 2002.

3.15 GNF Report, GNF Report, Fuel Bundle Information Report for James A. FitzPatrick Reload 16 Cycle 17, 0000-0026-1984FBIR, Revision 0, September 2004.

3.16 GNF Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 15 Cyclel6, 0003-9220SRLR, Rev.0, Class I, August, 2002.

3.17 GNF Letter, Updated SLMCPRs for JAF Cycle 17, February 28, 2005 3.18 JF-03-00402, ARTS/MEOD Phase I Implementation 3.19 JAF-RPT-MISC-04489, Rev.2, Power-Flow Map Report 3.20 GENE-0000-0030-4847-Rl, March2005, Option 1D Exclusion Region Evaluation for FitzPatrick Cycle 17 4.0 DEFINITIONS 4.1 Average Planar Linear Heat Generation Rate (APLHGR):

The APLHGR shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the fuel rods in the specified assembly at the specified height divided by the number of fuel rods in the fuel assembly at the height.

4.2 Fraction of Limiting Power Density:

The ratio of the linear heat generation rate (LHGR) existing at a given location to the design LHGR. The design LHGR is given in Table 8.2.

4.3 Linear Heat Generation Rate(LHGR):

The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

Rev. No. 17 Page 4 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 4.5 Minimum critical power ratio OMCPR):

The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

4.6 Rated Recirculation Flow:

That drive flow which produces a core flow of 77.0 x 106 lb/hr.

5.0 RESPONSIBILITIES NOTE: See AP-12.05 (Reference 3.1).

5.1 Shift Manager:

Assure that the reactor is operated within the limits described herein.

5.2 Reactor Engineering Superintendent:

Assure that the limits described herein are properly installed in the 3D-Monicore databank used for thermal limit surveillance (Reference 3.4) 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS Not Applicable Rev. No. 17 Page 5 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 7.0 PROCEDURE 7.1 Operating Limit MCPR During operation, with thermal power > 25% of rated thermal power (RTP), the Operating Limit MCPR shall be equal to or greater than the limits given below.

7.1.1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR) 7.1.2 The Operating Limit MCPR shall be determined based on the following requirement:

7.1.2.1. The average scram time to notch position 36 shall be:

t AVE - B 7.1.2.2. The average scram time to notch position 36 is determined as follows:

n TAVE zn Ngr WHERE:

n = Nuirmber of surveillance tests performed to date in the cycle, Ni = Number of active rods measured in the surveillance i ri = Average scram time to notch position 36 of all rods measured in surveillance test i.

Rev. No. 17 Page 6 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 7.1.2.3. The adjusted analysis mean scram time is calculated as follows:

aB(sec)=u+l.65U N, ENi i=1 WHERE:

p = Mean of the distribution for the average scram insertion time to the dropout of notch position 36 = 0.830 sec.

C = Standard deviation of the distribution for average scram insertion time to the dropout of notch position 36 = 0.019 sec.

N, = The total number of active rods measured in Technical Specification SR 3.1.4.4.

The number of rods to be scram tested and the test intervals are given in Technical Specification LCO 3.1.4, Control Rod Scram Times 7.1.3 When requirement of 7.1.2.1 is met, the Operating Limit MCPR shall not be less than that specified in Table 8.1, Table 8.1.A, Table 8.1.B or Table 8.1.C as applicable.

7.1.4 WHEN the requirement 7.1.2.1 is not met (i.e. TB < TAVE), THEN the Operating Limit MCPR values (as a function of t) are given in Figure 8.1, Figure 8.1.A, Figure 8.1.B or Figure 8.1.C as applicable.

(TAVE -TO (TA - TB)

WHERE:

TAVE = The average scram time to notch position 36 as defined in 7.1.2.2.

TB = The adjusted analysis mean scram time as defined in 7.1.2.3.

TA = the scram time to notch position 36 as defined in Technical Specification Table 3.1.4-1.

Rev. No. 17 Page 7 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 NOTE: IF the operating limit MCPR obtained from these figures is determined to be less than the operating limit MCPR found in 7.1.3, THEN 7.1.3 shall apply.

7.1.5 During single-loop operation, the Operating Limit MCPR shall be increased by 0.02.

7.1.6 During reactor power operation with core flow less than 100 percent of rated, the Operating Limit MCPR shall be multiplied by the appropriate Kf specified in Figure 8.2.

7.2 Average Planar Linear Heat Generation Rate (APLHGR) 7.2.1 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) 7.2.2 . During operation, with thermal power > 25% rated thermal power (RTP),

the APLHGR shall be within the limits given in Tables 8.3 and 8.3.A (Figures 8.3 and 8.3.A) for the appropriate fuel type.

7.2.3 During single loop operation, the APLHGR for each fuel type shall not exceed the values given in 7.2.2 above multiplied by the appropriate value (0.78 for GE12 and GE14 fuel).

7.3 Linear Heat Generation Rate (LHGR) 7.3.1 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR) 7.3.2 During operation, with thermal power > 25% rated thermal power (RTP),

the LHGR for each fuel rod as a function of axial location and exposure shall be within limits based on applicable LHGR limit values given in Tables 8.2 and 8.2.A for appropriate fuel and rod type.

7.3.3 During single loop operation, the LHGR for each fuel type shall not exceed the values given in 7.3.2 above multiplied by the appropriate value (0.78 for GE12 and GE14 fuel).

Rev. No. 17 Page 8 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 7.4 APRM Trip Settings 7.4.1 APRM Flow Referenced Flux Scram Trip Setting (Run Mode) 7.4.1.1. Technical Specifications:

LCO 3.2.4, Average Power Range Monitor (APRM) Gain and Setpoint LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation 7.4.1.2. When operating in Mode 1, the APRM Neutron Flux-High (Flow Biased)

Trip setting shall be for two loop operation:

S< (%RTP) = 0.38*W+61.0% 0< W < 24.7%

S< (/C RTP) = 1.15*W+42.0% 24.7< W < 47.0%

S< (% RTP) = 0.63*W+73.7% 47.0< W <68.7%

S< (/C RTP) = 117.00% (Clamp) W > 68.7%

for single loop operation:

S< (% RTP) = 0.38*W+57.9% 0< W < 32.7%

S< (C/o RTP) = 1.15*W+32.8% 32.7< W < 50.1%

S< (/o RTP) = 0.58*W+61.3% 50.1< W < 95.9%

S< (/CRTP) = 117.00% (Clamp) W > 95.9%

WHERE:

S = Setting in percent of rated thermal power; W = Recirculation flow in percent of rated; I

I NOTE: Compliance with the "Allowed Region of Operation" on the Power-Flow Map, Figure 3.7-1 of the FSAR is defined by the equation 0.58W + 50%

and is individually controlled and assures boundaries are not exceeded during normal operation.

7.4.1.3. In the event of operation with a Maximum Fraction of Limiting Power Density (MvFLPD) greater than the Fraction of Rated Power (FRP), the setting shall be modified as follows for two loop operation:

S< (% RTP) = (0.38*W+61.0%)(FRP/MFLPD) 0< W <24.7%

S< (/o RTP) = (1.15*W+42.0%)o(FRP/MFLPD) 24.7< W < 47.0%

S< (/C RTP) = (0.63*W+73.7%)(FRP/MFLPD) 47.0< W < 68.7%

S< (%CRTP) = (117.00%(Clamp))(FRP/MFLPD) W > 68.7%

Rev. No. 17 Page 9 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 for single loop operation:

S< (ho RTP) = (0.38*Wd+57.9%)(FRP/MFLPD) 0< W < 32.7%

S< (%a RTP) = (1.15*Wd+32.8%)(FRP/MFLPD) 32.7< W < 50.1%

S< (/o RTP) = (0.58*Wd+61.3%)(FRP/MFLPD) 50.1< W <95.9%

S.< (% RTP) = (117.00% (Clamp))(FRP/MFLPD) W > 95.9%

WHERE:

FRP = Fraction of Rated Power; MFLPD = Maximum Fraction Of Limiting Power Density, see Definition 4.4.

The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.

7.4.2 APRM Neutron Flux-High (Flow Biased) Rod Block Trip Setting (Relocated to the Technical Requirements Manual) 7.5 RBM Upscale Rod Block Trip Setting 7.5.1 Technical Specification LCO 3.3.2.1, Control Rod Block Instrumentation 7.5.2 The RBM upscale rod block trip setting shall be:

S < 0.66W + K for two loop operation; S < 0.66W + K - 0.66 AW for single loop operation; WHERE:

S = rod block setting in percent of initial; W = Loop flow in percent of rated K = Any intercept value may be used because the RBM intercept value does not effect the MCPR Operating Limit and the RBM is not assumed to function to protect the Safety Limit MCPR.

AW = Difference between two loop and single loop effective drive flow at the same core flow.

NOTE: If K can be any value, then K - 0.66AW can also be any value, and the trip setting adjustment for single loop operation is not necessary.

Rev. No. 17 Page 10 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 7.6 Stability Option 1-D Exclusion Region and Buffer Zone.

7.6.1 Technical Specification LCO 3.4.1, Recirculation Loops Operating 7.6.2 The reactor shall not be intentionally operated within the Exclusion Region given in Figure 8.4 when the SOLOMON Code is operable.

7.6.3 The reactor shall not be intentionally operated within the Buffer Zone given in Figure 8.4 when the SOLOMON Code is inoperable.

7.7 K: - Flow Dependent MCPR Limit Figure 8.2 is the Kf limit. Values of Kf are obtained using the following equation (see Reference 3.6):

Kf = MAX [1.0, A - SLOPE

  • WT]

WHERE:

WT = Core Flow as % of Rated, 30% < VWI < 100%

SLOPE = (AF/100/OLMCPR ) * (SLMCPR /SLMCPR generic)

A = (BF/OLMCPR ) * (SLMCPR /SLMCPR generic)

SLMCPR generic = 1.07 SLMCPR = Technical Specification LCO 2.1.1, Reactor Core SLs OLMCPR= The lowest value obtained from Figures 8.1, 8.1A, 8.1.B and 8.1.C as per 7.1.4, or, if the note in 7.1.4 applies, then 7.1.3 requirement must be met.

AF, BF = Coefficients for the Kf curve listed below:

Scoop Tube Setpoint % AF BF 102.5 0.571 1.655 107.0 0.586 1.697 112.0 0.602 1.747 117.0 0.632 1.809 All coefficients apply to Manual Flow Control Mode Rev. No. 17 Page 11 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 8.0 FIGURES AND TABLES 8.1 FIGURES Figure 8.1. MCPR Operating Limit Versus T for GE12 and GE14.

Figure 8.1A. MCPR Operating Limit Versus X for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service for GE12 and GE14.

Figure 8.1.B MCPR Operating Limit Versus r for Operation with Turbine Bypass Valves Out of Service Figure 8.1.C MCPR Operating Limit Versus T for Operation with Final Feedwater Temperature Reduction Figure 8.2 Kf Factor Figure 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel Figure 8.3.A Exposure Dependent APLHGR Limit for GE12 Fuel Figure 8.4 Stability Option 1D Exclusion Region Figure 8.5 Exposure Dependent LHGR Limit for GE14 Fuel.

Figure 8.5A Exposure Dependent LHGR Limit for GE12 Fuel.

Figure 8.6. Cycle 17 Loading Pattern, Full Core by Bundle Design Figure 8.7 Users Guide Rev. No. 17 Page 12 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 8.2 TABLES Table 8.1 MCPR Operating Limit for Incremental Cycle Core Average Exposure Table 8.1.A MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service Table 8.1.B MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service Table 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction Table 8.2 Maximum LHGR - GE14 Table 8.2.A Maximum LHGR - GE12 Table 8.3 APLHGR Limits for GE14 Fuel Table 8.3.A APLHGR Limits for GE12 Fuel 9.0 EXHIBITS NONE Rev. No. 17 Page 13 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure Cycle 17 Exposure Range All Fuel Types BOC to <EOC - 2.7 GWD/ST 1.39 EOC -2.7 GWD/ST 1.43 to EOC Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: 1. When entering a new Exposure Range, check the current value oft to assure adjustment per Step 7.1.4

2. Applicable for any value of K, see Step 7.5.2 Rev. No. 17 Page 14 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.1.A MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service All Fuel Types Cycle 17 Exposure Range BOC to <EOC-2.7 GWD/ST 1.41 EOC - 2.7 GWD/ST 1.45 to EOC Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: 1. When entering a new Exposure Range, check the current value of t to assure adjustment per Step 7.1.4

2. Applicable for any value of K, see Step 7.5.2 Rev. No. 17 Page 15 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 I .

TABLE 8.1.B MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service Cycle 17 Exposure Range All Fuel Types ALL 1.47 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

Technical Specification LCO 3.7.6, Main Turbine Bypass System For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: 1. When entering a new Exposure Range, check the current value of t to assure adjustment per Step 7.1.4

2. Applicable for any value of K, see Step 7.5.2 Rev. No. 17 Page 16 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction Cycle 17 Exposure Range All Fuel Types At EOC only (see below) { 1.43 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: 1. When entering a new Exposure Range, check the current value oft to assure adjustment per Step 7.1.4

2. Applicable for any value of K, see Step 7.5.2 MCPR Operating Limits in this table apply when at reduced feedwater temperature near end-of-cycle, see JD-02-122 (Reference 3.14) for further information.

Rev. No. 17 Page 17 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.2 Maximum LHGR - GE14 Peak Pellet Exposure UO2 LHGR Limit GWd/ST kW/ft 0.00 13.40 14.51 13.40 57.61 8.00 63.50 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/ST kW/ft 0.00 12.26 12.28 12.26 55.00 7.32 60.84 4.57 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)

Design features of the fuel assemblies in the Cycle 17 core are provided in References 3.3, 3.16 For single loop operation these LHGR values shall be multiplied by 0.78 Linearly interpolate for LHGR at intermediate exposure Rev. No. 17 Page 18 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.2.A Maximum LHGR - GE12 Peak Pellet Exposure U0 2 LHGR Limit GWd/ST kW/ft 0.00 11.80 13.24 11.80 63.50 6.39 Peak Pellet Exposure Most Limiting Gadolinia L-HGR Limit GWd/ST kW/ft 0.00 11.35 11.69 11.35 63.50 6.20 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)

Design features of the fuel assemblies in the Cycle 17 core are provided in References 3.3, 3.16 For single loop operation these LHGR values shall be multiplied by 0.78 Linearly interpolate for LHGR at intermediate exposure Rev. No. 17 Page 19 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 TABLE 8.3.A Exposure Dependent APLHGR Limit for GE12 Fuel Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 10.62 13.24 10.62 24.20 10.62 63.50 6.39 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)

For single loop operation these APLHGR values shall be multiplied by 0.78 Linearly interpolate for APLHGR at intermediate exposure Rev. No. 17 Page 20 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.1 MCPR Operating Limit Versus T For All Fuel Types 1.65 BOO to EOC17 - 2.7 GWd/St 1.60 -*-U- EOC17 7-2.7 GWd/St to EOC17 . _ 41 1.60

.- 11 , 0-0.

1.55 2

JE

-J 1.50 _ ,1.50 1.43 _ _ - -. -

.2 - -

E. 1.45 _ _

0) 0o 1.40 4 _- __ _

l1.39 T.35 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 17).

Rev. No. 17 Page 21 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.1A MCPR Operating Limit Versus X For Operating Above 75% of Rated Thermal Power with Three Steam Lines in Service For all Fuel Types

-0 -BOC to EOC17 - 2.7 GWd/St 1.65 T-IILIFPL 7i 1.62

-_ EOC17 - 2.7 GWd/St to EOC17 1.60 W

1.55

._c >1.52

-j 1.50 4-A__ ___

. .. s ,

CD E I I -

1.45 ** 4 4 .4- 4 4- 4 a1) I- -

0.

0 1.40' -1 4-4 4 4 4-+ 4 4 1.35 1 4-4 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 17).

Rev. No. 17 Page 22 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.1.B MCPR Operating Limit Versus ¶ for Operation with Turbine Bypass Valves Out of Service 1.65 1.64 a-1.6

.c E

-J 1.55 c)

CL 1.5 0

0.

1.45 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 I

Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 17).

Rev. No. 17 Page 23 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.1.C MCPR Operating Limit Versus 'r for Operation with Final Feedwater Temperature Reduction 1.65 I!1.60 ITTi 1.6 C._

0) 1.55 E _1 l 1 Cn 1.5
0. l4_1_.-

1.45 0

.._ LIA 0 0.1 I

0.2 0.3 I

0.4 0.5 0.6 0.7 0.8 0.9 1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 17).

Rev. No. 17 Page 24 of 32

7 -

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.2 Kf Factor Cycle 17 Kf Curve for Scoop Tube Stops at 112%

Considers Two Loop and Single Loop Operation, MOC and EOC MCPR Limits The cormbination of MOC MCPR llnit and SLO produces the most Unmungr, curve. This set of data deternines the r 1 curve used In the 3D-MONICORE 1.15 - . dalabank. May be changed when EOC MCPR linits apply. Choice of Single Loop 1.14 -K values Is for ease of SLO. Two loop linits are not significantly different.

1.13 SLMICPR = 1.07 (TLO) 1.09 (SLO)

OLMCPR(TLO)J 1.39 (BOC to MOC). 1.43 (MOC to EOC) 1.12 OLMCPR(SLO) 1.41 (1BOCto MOC). 1.45 (MOC to EOC) 1.11 K4 rray be adjusted as needed to provide protection against the SLO Purnp Seizure event. The OLMCPR below the SLO core flow Urnit of 58% mrust be 1.10 greater than or equal to 1.43. The OLMCPR at MOC.SLO Is 1.41 for GE14. so K, Q \equation 1.09 ameat be greater than orequal to 1.01418 at 58% flow. Intercept value of the 1.08 below was adjusted to meet the SLO Purnp Seizure requirement.

References:

y 1.07 1.VICURVE UPDATE. GE-NEJi103426-00-01. 10116/98 0 2\.GE14 Fuel Design Cycle-Independent Analyses for JAFNPP.

1.06 GE-NE-.0D000200Z1752.01 P.Septeirber 2002 1.05 1.04 3. Supplemental Reload Ucensing Report br James A. FitzPatrick Reload 16 Cycde17, 0000-0026-19US4RLR. Rev.0. Class I. Septenber. 2004.

Equaion of Cyde lK 17 rcurve:

1.03 \ wK,.MAX( 1.0 1.26644 .0.43493(% Core Flow100))

1.02 1.01 1.00 0.99 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Core Flow, % rated I + MOC+SLO 3 EOC+SLO A MOC+TLO X EOC+TLO O Pump Seizure Point Kf Umit Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

See Section 7.7 NOTE: Kf for Single Loop Operation is slightly greater than for Dual Loop Operation limits.

Therefore, Kf calculated for Single Loop Operation is more conservative and will be applied to Dual Loop Operation as well.

Rev. No. 17 Page 25 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel 14 13 12 11 10 9

8

§j7 6

5 4

3 2

I 0

0 5 10 15 20 25 30 35 40 45 50 55 60 65 Planar Exposure, GWDIST Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)

For single loop operation these APLHGR values shall be multiplied by 0.78.

Rev. No. 17 Page 26 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.3.A Exposure Dependent APLHGR Limit for GE12 Fuel 0 5 10 15 20 25 30 35 40 45 50 55 60 65 Planar Exposure, GWD/ST Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)

For single loop operation these APLHGR values shall be multiplied by 0.78.

Rev. No. 17 Page 27 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.4 Stability Option 1-D Exclusion Region 110 100 0

(a 20 25 30 35 40 45 50 55 60 65 70 0 Flow, % rated Rev. No. 17 Page 28 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.5 Exposure Dependent LHGR Limit for GE14 Fuel 14 13 12 11 10 9

18 7

6 5

4 3

2 1

0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 PELLET EXPOSURE GWD1ST Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)

This curve represents the limiting exposure dependent LHGR values per Reference 3.16 Design features of the fuel assemblies in the Cycle 17 core are provided in Reference 3.3 FIGURE 8.5.A Exposure Dependent LHGR Limit for GE12 Fuel Rev. No. 17 Page 29 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 14-13-12-11 10 9

8 6

.5-4 3-2 I

o.

0 5 10 15 20 25 30 35 40 45 50 55 60 65 PELLET EXPOSURE GWDIST Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)

This curve represents the limiting exposure dependent LHGR values per Reference 3.16 Design features of the fuel assemblies in the Cycle 17 core are provided in Reference 3.3 Rev. No. 17 Page 30 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.6 Cycle 17 Loading Pattern by Bundle Design 52 [(DE] D EBo E]

50 D 1 El 1 MIDE3 F1 E r North 48 F][DE][mE] [F]F 2G]FG nEFj[3E] i 1[DEE[FE]EjE]ff 48 46 mon WTlSUSE E-0 E-1 7T mni E-IE -171 [Ell 44 [Egj[0 [DL[D [0li L[D E] [DE1[ E11[ 1[o E1[D Al [0 [DE f]

42 IEMI EIE] Ml[ E1,E I-TI- E-IE] 0T[ FIDEA ENE ElFIDlnE 40 nD[E]2 a[lE] [lE]I F21 A [DE~orj 10DD 1 E1 38 E I [FEII88FI sjz ED FII IEl 1[ El FEI II3 1E E 36 [a pg D AnI [1 A E]JO[01[D D[D 31f [iE] D E]S[D E]JE] Eg[DI E]1D 1[DIE 34 IDTM IE sE-mET[F E-F] SmST lE

-IE TFI I l ElETIE- i 310-FI IElJl[ Eno 32 32

[0~i[E]I[ [0~

iE] i 3E[lm[P[ g~ iEE~ F§lgm~

28 _t((D 1[E] E)I[DE]J]F 1[E D51 CM1[El~o FAIE][ADEG] B 26 [0 FID [m l FID EnTm Eno T ET [E] E (] BEGODTE01[OD 24 [ED][ DIg MB iE] nCEA F]~ AE][E] E] E] EA]E1 BF AE]l

[D E][E1A [AD1[

22 mTE FTu1070 N~ El N T[

MTRET R T 1E lllE[

20 nD gmEmEgEgEg@g11gE B Dll1 18 WEl E-1 m 0--j F IE mDlE -FD0 EI[E EII-- I lF0[D EI1F lF0W l16 [D D[1E] E] [D EA]~[lE))I E][ DE] nGIE DIE] D[3D~E]L[D[ [F]i[E 14 12 [DIE] [3E] E]J[Dl E]ll[D [Dli ]E~ [01 An 0]( E]lgEg~ [D IIF[

10 IEIsFEI LF E1 F 1LD- EI E1 ]EIEl FE E] EDE[F [Eff FME]IE] A][D[ [DI[D [K]I[DE]Eil E]ID E3o [

6 TEN DUE E3 1 O9EM EMS EJFr D (El Frm 010 4 m[Eflmg [lE~ ElE mlE 2 10 F21 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 Fuel Type A-GE14-Pl ODNAB405-16GZ-10OT-150-T6(Cycle 17) E=GE12-P lODSB407-14G6.0-lOOT-150-T6 (Cycle 15)

B=GE14-P lODNAB405-15G6.0-lOOT-150-T6 (Cycle 17) F=GE14-P lODNAB405-16GZ-l OOT-150-T6 (Cycle 16)

C=GE12-P lODSB405-16GZ-IOOT-150-T6 (Cycle 15) G=GE 14-P 1ODNAB405-16GZ-l OOT-150-T6 (Cycle 16)

D=GE12-PlODSB405-17GZ-lOOT-150-T6 (Cycle 15)

Rev. No. 17 Page 31 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.7 USERS GUIDE The COLR defines thermal limits for the various operating conditions expected during the cycle. At the start of the cycle the 3D-Monicore databank contains limits for;

  • Cycle exposure range of BOC to < EOC17 - 2.7 GWD/ST
  • T=0
  • Dual recirculation pump operation
  • Four steam line operation, and
  • Final Feedwater Temperature Reduction The following is a table that offers a check to assure the correct limits are applied when operating states or conditions change.

Change in Operating State Change in Limits Procedure Reference Cycle Exposure - See Table 8.1(8.1 A for 3SL) or Figure 8.1 EOC17 - 2.7 GWD/ST for T

  • 0(8.1.A for 3SL) for change in OLMCPR changes to EOC values MCPR. None at cycle exposure of 12.0 GWD/ST Kr limit may be changed in recognition of higher OLMCPR.

Scram Time Test Results such that XT#0 Use newX and see Figure 8.1 or 8.1.A for Option B lisits for 0LMCPR must 3SL. Kf limit may be changed in RAP-7.4.1 beOpio B interpolated fo O.CP with limts recognition of hte

.iitA mustttno Option higher OM OLMCPR.

Single Loop Operation Increase MCPR Limits by 0.02, or change I

The SLMCPR increases by 0.02 and acceptance criterion in ST-SE to 0.98. Kr therefore OLMCPR limits increase does not change. ST-5E, by 0.02. MFLPD and MAPLHGR Verify that 3D-Monicore has recognized I are reduced by a multiplier in SLO. the idle recirculation loop and is applying the SLO MFLPD and MAPLHGR multiplier of 0.78.

Three Steam Line Operation (3SL) Increase OLMCPR according to Table OLMCPR values increase by 0.02 8.1.A or Figure 8.1.A(@

  • 0). Kr limit may None when operating on 3. L be changed in recognition of higher OLMCPR.

Operation with Turbine Bypass Increase OLMCPR according to Table Valves Out-of-Service 8.1.B or Figure 8.1.B(t

  • 0). Kf limit may None OLMCPR values increase, no be changed in recognition of higher LHGR change required OLMCPR.

Operation under Final Feedwater Increase OLMCPR according to Table Temperature Reduction 8.1.C or Figure 8.1.C(t

  • 0). Kflimit may None OLMCPR values increase, no be changed in recognition of higher LHGR change required OLMCPR.

Rev. No. 17 Page 32 of 32

- -7 -

---. nte~rgy

-Nothas Nuler NuclearNortheast ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT CORE OPERATING LIMITS REPORT REVISION 18 APPROVED BY: William Drews

',,12, --- DATE: Z7/:, Ac 5 REACTOR ENGINEERING SUPERINTENDENT

-2 7 -1 C.V APPROVED BY: Kevin Mulligan DATE:

GENERAL MANAGER - PLANT OPERATIONS

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ....................................... 3 2.0 APPLICABILITY ....................................... 3

3.0 REFERENCES

....................................... 3 4.0 DEFINITIONS ........................................ 3 5.0 RESPONSIBILITIES ........................................ 3 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS ...................................... 3 7.0 PROCEDURE ....................................... 3 7.1 Operating Limit MCPR ............................................ 3 7.2 Average Planar Linear Heat Generation Rate (APLHGR) ...................... 3 7.3 Linear Heat Generation Rate (LHGR) ............................................. 3 7.4 APRM Trip Settings .............................................. 3 7.5 RBM Upscale Rod Block Trip Setting ............................................. 3 7.6 Stability Option 1-D Exclusion Region and Buffer Zone ......................... 3 7.7 Kf - Flow Dependent MCPR Limit ............................................. 3 8.0 FIGURES AND TABLES ................... 3 9.0 EXHIBITS .................... 3 Rev . No. 18 Page 2 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 17 of the James A.

FitzPatrick Nuclear Power Plant. The following limits are addressed:

  • Operating Limit Minimum Critical Power Ratio (MCPR)
  • Flow Dependent MCPR Limits
  • Average Planar Linear Heat Generation Rate (APLHGR)
  • Linear Heat Generation Rate (LHGR)
  • Flow-Biased Average Power Range Monitor (APRM) and Rod Block Monitor (RBM)

Settings

  • Stability Option ID Exclusion Region 2.0 APPLICABILITY The plant shall be operated within the limits specified in this report. If any of these limits are exceeded, the corrective actions specified in the Technical Specifications shall be taken.

3.0 REFERENCES

3.1 JAFNPP Administrative Procedure 12.05, Control of Core Operating Limits Report.

3.2 JAFNPP Technical Specifications.

3.3 Design Change Package ER-JF-03-0155, Cycle 17 Core Reload 3.4 RAP-7.3.17, Core Monitoring Software and Database Changes.

3.5 Plant Operation Up To 100% Power With One Steam Line Isolated, JAF-SE-96-035.

3.6 James A. FitzPatrick Nuclear Power Plant Kf Curve Update, GE-NE-J1 1-03426-00-01, September 1998.

3.7 General Electric Standard Application for Reload Fuel, NEDE-24011-P-A-14 3.8 GNF Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 16 Cyclel7, 0000-0026-1984SRLR, Rev.0, Class I, September, 2004.

3.9 JAF-SE-00-032, Rev.0, Extended Loadline Limit Analysis (ELLLA) Implementation.

Rev. No. 18 Page 3 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 3.10 JAF-RPT-MISC-04054, Rev.0, Operation under Extended Loadline Limit Analysis (ELLL1A).

and Power Uprate 3.11 GE Letter, FitzPatrick APRM Flow Biased Rod Block and Scram Setpoints, NSA01-273, July 3, 2001 3.12 GE Letter, R. Kingston to P. Lemberg, Scram Time Versus Notch Positions for Option B, REK-E: 02-009, May 28, 2002 3.13 GE Report, James A. FitzPatrick Nuclear Power Plant Final Feedwater Temperature Reduction NEDC-33077, September 2002.

3.14 JD-02-122, Final Feedwater Temperature Reduction Implementation.

3.15 GE Report, GE14 Fuel Design Cycle-Independent Analyses forJ. A. Fitzpatrick Nuclear Power Plant, GE-NE-0000-0002-1752-OIP, Rev. 0, DRF 0000-0002-1752, September 2002.

3.16 GNF Report, GNF Report, Fuel Bundle Information Report forJames A. FitzPatrick Reload 16 Cycle 17, 0000-0026-1984FBIR, Revision 0, September 2004.

3.17 GNF Report, Supplemental Reload Licensing Report forJames A. FitzPatrick Reload 15 Cyclel 6, 0003-9220SRLR, Rev.0, Class I, August, 2002.

3.18 GNF Report, Validation of FitzPatrick Cycle 16 Exclusion and Buffer Region Application for Cycle 17 Operation Up to 9000 MWD/ST Exposure, GE-NE-0000-0033-3112-Rl,July 2005 3.19 GNF Letter, Updated SLMCPRs forJAF Cycle 17, February 28, 2005 4.0 DEFINITIONS 4.1 Average Planar Linear Heat Generation Rate (APLHGR):

The APLHGR shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the fuel rods in the specified assembly at the specified height divided by the number of fuel rods in the fuel assembly at the height.

4.2 Fraction of Limiting Power Density:

The ratio of the linear heat generation rate (LHGR) existing at a given location to the design LHGR. The design LHGR is given in Table 8.2.

4.3 Linear Heat Generation Rate(LHGR):

The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

Rev. No. 18 Page 4 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 4.4 Maximum Fraction of Limiting Power Density (MFLPD):

The MFLPD shall be the largest value of the fraction of limiting power density in the core.

The fraction of limiting power density shall be the LHGR existing at a given location divided by the specified LHGR limit for that bundle type.

4.5 Minimnum critical power ratio (MCPR):

The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

4.6 Rated Recirculation Flow:

That drive flow which produces a core flow of 77.0 x 106 lb/hr.

5.0 RESPONSIBILITIES NOTE: See AP-12.05 (Reference 3.1).

5.1 Shift Manager:

Assure that the reactor is operated within the limits described herein.

5.2 Reactor Engineering Superintendent:

Assure that the limits described herein are properly installed in the 3D-Monicore databank used for thermal limit surveillance (Reference 3.4) 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS Not Applicable Rev. No. 18 Page 5 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 7.0 PROCEDURE 7.1 Operating Limit MCPR During operation, with thermal power > 25% of rated thermal power, the Operating Limit MCPR shall be equal to or greater than the limits given below.

7.1.1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR) 7.1.2 The Operating Limit MCPR shall be determined based on the following requirement:

7.1.2.1. The average scram time to notch position 36 shall be:

A VE -tB 7.1.2.2. The average scram time to notch position 36 is determined as follows:

n VrAVE n Nir i=i WHERE:

n = Number of surveillance tests performed to date in the cycle, Ni = Number of active rods measured in the surveillance i

-i = Average scram time to notch position 36 of all rods measured in surveillance test i.

Rev. No. 18 Page 6 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 7.1.2.3. The adjusted analysis mean scram time is calculated as follows:

TB(sec)=/u+1.6 5o N, l zNij i=.

WHERE:

p. = Mean of the distribution for the average scram insertion time to the dropout of notch position 36 = 0.830 sec.

a = Standard deviation of the distribution for average scram insertion time to the dropout of notch position 36 = 0.019 sec.

N. = The total number of active rods measured in Technical Specification SR 3.1.4.4.

The number of rods to be scram tested and the test intervals are given in Technical Specification LCO 3.1.4, Control Rod Scram Times 7.1.3 When requirement of 7.1.2.1 is met, the Operating Limit MCPR shall not be less than that specified in Table 8.1, Table 8.1.A, Table 8.1.B or Table 8.1.C as applicable.

7.1.4 WHEN the requirement 7.1.2.1 is not met (i.e. -B <'rAVE), THEN the Operating Limit MCPR values (as a function of T) are given in Figure 8.1, Figure 8.1 A, Figure 8.1.B or Figure 8.1.C as applicable.

(TAVE - TB)

(TA - TB)

WHERE:

TAVE = The average scram time to notch position 36 as defined in 7.1.2.2.

TB = The adjusted analysis mean scram time as defined in 7.1.2.3.

TA = the scram time to notch position 36 as defined in Technical Specification Table 3.1.4-1.

Rev. No. 18 Page 7 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 NOTE: IF the operating limit MCPR obtained from these figures is determined to be less than the operating limit MCPR found in 7.1.3, THEN 7.1.3 shall apply.

7.1.5 During single-loop operation, the Operating Limit MCPR shall be increased by 0.02.

7.1.6 During reactor power operation with core flow less than 100 percent of rated, the Operating Limit MCPR shall be multiplied by the appropriate Kf specified in Figure 8.2.

7.2 Average Planar Linear Heat Generation Rate (APLHGR) 7.2.1 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) 7.2.2

  • During operation, with thermal power > 25% rated thermal power, the APLHGR shall be within the limits given in Tables 8.3 and 8.3.A (Figures 8.3 and 8.3.A) for the appropriate fuel type.

7.2.3 During single loop operation, the APLHGR for each fuel type shall not exceed the values given in 7.2.2 above multiplied by the appropriate value (0.78 for GE12 and GE14 fuel).

7.3 Linear Heat Generation Rate (LHGR) 7.3.1 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR) 7.3.2 During operation, with thermal power > 25% rated thermal power, the LHGR for each fuel rod as a function of axial location and exposure shall be within limits based on applicable LHGR limit values given in Tables 8.2 and 8.2A for appropriate fuel and rod type.

7.3.3 During single loop operation, the LHGR for each fuel type shall not exceed the values given in 7.3.2 above multiplied by the appropriate value (0.78 for GE12 and GE14 fuel).

Rev. No. 18 Page 8 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 7.4 APRM Trip Settings 7.4.1 APRM Flow Referenced Flux Scram Trip Setting (Run Mode) 7.4.1.1. Technical Specifications:

LCO 3.2.4, Average Power Range Monitor (APRM) Gain and Setpoint LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation 7.4.1.2. When operating in Mode 1, the APRM Neutron Flux-High (Flow Biased)

Trip setting shall be:

S < 0.58W + 66% for two loop operation; S < 0.58W + 66% - 0.58 AW for single loop operation; WHERE:

S = Setting in percent of rated thermal power; W = Recirculation flow in percent of rated; AW = Difference between two loop and single-loop effective drive flow at the same core flow.

NOTE: Concerning APRM Neutron Flux-High (Flow Biased) Rod Block and Scram Trip settings: Reference 3.11 establishes Equivalent Analytical Limits for these settings. The nominal trip setpoint S < 0.58W + 62%

(with clamp at 117%) for the Scram. Compliance with the "Allowed Region of Operation" on the Power-Flow Map, Figure 3.7-1 of the FSAR is defined by the equation 0.58W + 50% and is individually controlled and assures boundaries are not exceeded during normal operation.

7.4.1.3. In the event of operation with a Maximum Fraction of Limiting Power Density (MFLPD) greater than the Fraction of Rated Power (FRP), the setting shall be modified as follows:

S < (0.58W + 66%)(FRP/MFLPD) for two loop operation; S < (0.58W + 66% - 0.58 AW)(FRP/MFLPD) for single-loop operation; WHERE:

FRP = Fraction of Rated Power; MFLPD = Maximum Fraction Of Limiting Power Density, see Definition 4.4.

The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.

Rev. No. 18 Page 9 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 7.4.2 APRM Neutron Flux-High (Flow Biased) Rod Block Trip Setting (Relocated to the Technical Req'uirements Manual) 7.5 RBM Upscale Rod Block Trip Setting 7.5.1 Technical Specification LCO 3.3.2.1, Control Rod Block Instrumentation 7.5.2 The RBM upscale rod block trip setting shall be:

S < 0.66W + K for two loop operation; S < 0.66W + K - 0.66 AW for single loop operation; WHERE:

S = rod block setting in percent of initial; W = Loop flow in percent of rated K = Any intercept value may be used because the RBM intercept value does not effect the MCPR Operating Limit I

AW = Difference between two loop and single loop effective drive flow at the same core flow.

7.6 Stability Option 1-D Exclusion Region and Buffer Zone. I 7.6.1 Technical Specification LCO 3.4.1, Recirculation Loops Operating 7.6.2 The reactor shall not be intentionally operated within the Exclusion Region given in Figure 8.4 when the SOLOMON Code is operable.

7.6.3 The reactor shall not be intentionally operated within the Buffer Zone given in Figure 8.4 when the SOLOMON Code is inoperable.

Rev. No. 18 Page 10 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 7.7 Kf - Flow Dependent MCPR Limit Figure 8.2 is the Kf limit. Values of Kf are obtained using the following equation (see Reference 3.6):

Kf = MAX [1.0, A - SLOPE

  • WT]

WHERE:

WI' = Core Flow as % of Rated, 30% < WT < 100%

SLOPE = (AF/100/OLMCPR ) * (SLMCPR /SLMCPR generic)

A = (BF/OLMCPR ) * (SLMCPR /SLMCPR generic)

SLMCPPR generic = 1.07 SLMCPR = Technical Specification LCO 2.1.1, Reactor Core SLs OLMCPR= The lowest value obtained from Figures 8.1, 8.l.A, 8.1.B and 8.1.C as per 7.1.4, or, if the note in 7.1.4 applies, then 7.1.3 requirement must be met.

AF , BF = Coefficients for the Kf curve listed below:

Scoop Tube Setpoint % AF Br 102.5 0.571 1.655 107.0 0.586 1.697 112.0 0.602 1.747 117.0 0.632 1.809 All coefficients apply to Manual Flow Control Mode Rev. No. 18 Page 11 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 8.0 FIGURES AND TABLES 8.1 FIGURES Figure 8.1. MCPR Operating Limit Versus X for GE12 and GE14.

Figure 8. .A. MCPR Operating Limit Versus t for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service for GE12 and GE14.

Figure 8.1.B MCPR Operating Limit Versus T for Operation with Turbine Bypass Valves Out of Service Figure 8.1.C MCPR Operating Limit Versus X for Operation with Final Feedwater Temperature Reduction Figure 8.2 Kf Factor Figure 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel Figure 8.3.A Exposure Dependent APLHGR Limit for GE1 2 Fuel Figure 8.4 Stability Option ID Exclusion Region Figure 8.5 Exposure Dependent LHGR Limit for GE14 Fuel.

Figure 8.5.A Exposure Dependent LHGR Limit for GE12 Fuel.

Figure 8.6. Cycle 17 Loading Pattern, Full Core by Bundle Design Figure 8.7 Users Guide Rev. No. 18 Page 12 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 8.2 TABLES Table 8.1 MCPR Operating Limit for Incremental Cycle Core Average Exposure Table 8.1.A MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service Table 8.1.B MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service Table 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction Table 8.2 Maximum LHGR - GE14 Table 8.2.A Maximum LHGR - GE12 Table 8.3 APLHGR Limits for GE14 Fuel Table 8.3.A APLHGR Limits for GE12 Fuel 9.0 EXHIBITS NONE Rev. No. 18 Page 13 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure Cycle 17 Exposure Range All Fuel Types BOC to <EOC - 2.7 GWD/ST 1.39 EOC - 2.7 GWD/ST 1.43 to EOC Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: 1. When entering a new Exposure Range, check the current value of -t to assure adjustment per Step 7.1.4

2. Applicable for any value of K, see Step 7.5.2 Rev. No. 18 Page 14 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.1.A MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service Cycle 17 Exposure Range J All Fuel Types BOC to <EOC - 2.7 GWD/ST 1.41 EOC - 2.7 GWD/ST 1.45 to EOC Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: 1. When entering a new Exposure Range, check the current value ofT to assure adjustment per Step 7.1.4

2. Applicable for any value of K, see Step 7.5.2 Rev. No. 18 Page 15 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.1.B MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

Technical Specification LCO 3.7.6, Main Turbine Bypass System For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: 1. When entering a new Exposure Range, check the current value of X to assure adjustment per Step 7.1.4

2. Applicable for any value of K, see Step 7.5.2 Rev. No. 18 Page 16 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction Cycle 17 Exposure Range All Fuel Types At EOC only (see below) j 1.43 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: 1. When entering a new Exposure Range, check the current value of T to assure adjustment per Step 7.1.4

2. Applicable for any value of K, see Step 7.5.2 MCPR Operating Limits in this table apply when at reduced feedwater temperature near end-of-cycle, see JD-02-122 (Reference 3.14) for further information.

Rev. No. 18 Page 17 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.2 Maximum LHGR - GE14 Peak Pellet Exposure UO2 LHGR Limit GWd/ST kW/ft 0.00 13.40 14.51 13.40 57.61 8.00 63.50 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/ST kW/ft 0.00 12.26 12.28 12.26 55.00 7.32 60.84 4.57 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)

Design features of the fuel assemblies in the Cycle 17 core are provided in References 3.3, 3.16 For single loop operation these LHGR values shall be multiplied by 0.78 Linearly interpolate for LHGR at intermediate exposure Rev. No. 18 Page 18 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.2.A Maximum LHGR - GE12 Peak Pellet Exposure U0 2 LHGR Limit GWd/ST kW/ft 0.00 11.80 13.24 11.80 63.50 6.39 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/ST kW/ft 0.00 11.35 11.69 11.35 63.50 6.20 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)

Design features of the fuel assemblies in the Cycle 17 core are provided in References 3.3, 3.16 For single loop operation these LHGR values shall be multiplied by 0.78 Linearly interpolate for LHGR at intermediate exposure a

Rev. No. 18 Page 19 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 TABLE 8.3.A Exposure Dependent APLHGR Limit for GE12 Fuel Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 10.62 13.24 10.62 24.20 10.62 63.50 6.39 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)

For single loop operation these APLHGR values shall be multiplied by 0.78 Linearly interpolate for APLHGR at intermediate exposure Rev. No. 18 Page 20 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.1 MCPR Operating Limit Versus r For All Fuel Types 1.05

-) -BOC to EOC17 - 2.7 GWd/St 1.60

-_- EOC17 - 2.7 GWd/St to EOCI7 _ 1.60 a:

0~

C-,

1.55

.- 1 E .--

1.50 - _1 _ 4s1.50

-jCn 1.43 1.45 W-a) -- -- -- -- --

0 1.40 >_ _ -_

1.39

-1 .

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 17).

Rev. No. 18 Page 21 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.1.A MCPR Operating Limit Versus r For Operating Above 75% of Rated Thermal Power with Three Steam Lines in Service For all Fuel Types 1.62 a:

0 Q

aJ 1.52 cm 0-a) 0o 0 0.1 0.2 0.3 .0.4 0.5 0.6 0.7 0.8 0.9 1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 17).

Rev. No. 18 Page 22 of 32

- w CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.1.B MCPR Operating Limit Versus X for Operation with Turbine Bypass Valves Out of Service

- BOCI7 to EOCI7 ICF-TBVOOS 1.65 _ . . . .

a:

a-S~t1 .64 0 1.6 4 4 I* 4 4 I. ----------I-ME C 1.55

- to C.5 a) 1.5 -4: 4 4 4 + + +

0o 1.45 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I IC Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 17).

Rev. No. 18 Page 23 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.1.C MCPR Operating Limit Versus T for Operation with Final Feedwater Temperature Reduction

. arc W

a-U 1.6 1.60 (n

I~I I I I l-i 1.55--

I< -~

,E

-C 1.5 2

C.E 1.45 a) 1.4 , . . .

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 IC Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given in Section 7.1.5.

NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 17).

Rev. No. 18 Page 24 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.2 Kf Factor Cycle 17 Kf Curve for Scoop Tube Stops at 112%

Considers Two Loop and Single Loop Operation, MOC and EOC MCPR Limits The comnabon of MOC MCPR list and SLO produces the most limting K, 1.15 _ _curve. ThisMay databank. set of be data deternines changed the K, when EOC curvelisits MCPR used apply.

In the 3D-MONICORE Choice of Single Loop 1.14 K,values Is for ease of SLO. Two loop lmits are not significantly different.

1.13 SLMCPR = 1.07 (TLO), 1.09 (SLO)

OLMCPR(TLO) = 139 (BOC to MOC). 1.43 (MOC to EOC) 1.12 OLMCPR(SLO) - 1.41 (BOC to MOC), 1.45 (MOC to EOC) 1.11 K;,ray be adjusted as needed to provide protection against the SLO Pump 1 10 \ Seizure event. The OLMCPR below the SLO core flow lirrit of 58%must be I .IU greater than or equal to 1.A3. The OLMCPR at MOC+SLO Is 1.41 for GE14. so K, 1.09 must be greater than or equal to 1.01418 at 58% flow. Intercept value of the 1.08 equation below was adjusted to meet the SLO Punp Seizure requirement.

References:

1.07 1. K,CURVE UPDATE, GE-NE-JI 1.03426-00-01. 10/1681B 1 .06 2.GE14 Fuel Design Cycle-independent Analyses for JAFNPP.

1.u6 GE-NE40004-0002-1752-01 P. September 2002 1 r05 1.04 )rA3. Supplemental Reload Ucensing Report for James A. FitzPatrick Reload 16 Cycle17, 000040026-1984SRLR. Rev.0, Class I.September. 2004.

1 4 Equation of Cycle 17 K( curve:

1.03  ? . K,= MAX( 1.0.1126644 -0.43493'(% Core Flow/100))

1.02 1.01 1.00 >9 0.99 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Core Flow, % rated

+ MOC+SLO O EOC+SLO A MOC+TLO X EOC+TLO 0 Pump Seizure Point Kf Limitl Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

See Section 7.7 NOTE: Kf for Single Loop Operation is slightly greater than for Dual Loop Operation limits.

Therefore, Kf calculated for Single Loop Operation is more conservative and will be applied to Dual Loop Operation as well.

Rev. No. 18 Page 25 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel 14 13 12 11 10 9

8 1~7 6

5 4

3 2

I 0

0 5 10 15 20 25 30 35 40 45 50 55 60 65 Planar Exposure, GWD/ST Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)

For single loop operation these APLHGR values shall be multiplied by 0.78.

Rev. No. 18 Page 26 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.3.A Exposure Dependent APLHGR Limit for GE12 Fuel 14 -_

13 -

12 -

11 10-9.-

8-

~57-6-

5-4-

3-2 I

0-0 5 10 15 20 25 30 35 40 45 50 55 60 65 Planar Exposure, GWD/ST Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)

For single loop operation these APLHGR values shall be multiplied by 0.78.

Rev. No. 18 Page 27 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.4 Stability Option 1-D Exclusion Region THE EXCLUSION REGION SHOWN BELOW IS APPLICABLE TO A CYCLE 17 EXPOSURE OF 9000 MWD/ST (see CR-JAF-2004-04360) I 100

's

-.1 20 25 30 35 40 45 50 55 60 65 70

% rated Flow Technical Specification LCO 3.4.1, Recirculation Loops Operating References 3.17, 3.18 Rev . No. 18 Page 28 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.5 Exposure Dependent LHGR Limit for GE14 Fuel 14 13 12 11 10 9

'8

§j 7 6

5 4

3 2

1 0

0 5 10 15 20 25 30 35 40 45 50 55 60 65 PELLET EXPOSURE GWDIST Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)

This curve represents the limiting exposure dependent LHGR values per Reference 3.16 Design features of the fuel assemblies in the Cycle 17 core are provided in Reference 3.3 FIGURE 8.5.A Exposure Dependent LHGR Limit for GE12 Fuel Rev. No. 18 Page 29 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 14 13-12-11 10 9

8-6

.5 4-3-

2 0~

0 5 10 15 20 25 30 35 40 45 50 55 60 65 PELLET EXPOSURE GWDIST Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)

This curve represents the limiting exposure dependent LHGR values per Reference 3.16 Design features of the fuel assemblies in the Cycle 17 core are provided in Reference 3.3 Rev. No. 18 Page 30 of 32

CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.6 Cycle 17 Loading Pattern by Bundle Design 52 ED] Q Q ( [ D[

50 m DO ID North 48 [EBoE][E [E]E EA] [ G 01[(F] EG][ G 0[ (E][ El[_]D 48 46Im mEl 1 0-TIE M1 Et171[ [B1E EN Din

[gEl El 44 [P11[ E][E] [DIE] SlEJL [E] SS1[2E]S DMS D1E j 42 AAAl A MmA 01[E FJ[D I8 l 1E]

[B1E E111 rJI[ Fal 40 ED] [lE] L[El [EE]FIE]JE j[lE] 1[D EA] [E E]E 1 [01 EA]fG][E[Dff 36 E [0TE E]tAnE [E] 1E]I E]IEiJER El[El E8IFF 0 32 34 Elmt I-n E [E] RgT Em M ~m EgEm[ ml~ mI~ m~~m] m 32 1COJ GA CA 8FI Ef 1 A GA A F DC 30 m E I [3t71D N -T E-11 E 1E IEl [Po ME El Eg EI D-TE- ~Eg

- I IniF[ [ -3F I [II 28 DM[E][ E~lMB DI DO31 g10 R [QOf Eil IDE~ EA][ (El E]I[D E11 1[Ef 26 DE1 E-T ETE l [E -FDIE I}E I[mtE-111

[I E- -][FoE1PE E1FEI D DE-1 ElE 24 E]I[

F [AGAG FAD AED[A FA[

AjI[D EFAD E]J[D [A B [EF AD] DO 22 ITIEH A 0 AI E F1 Am G A I TJ 20gp EE I13Elm Eg[ gi Eg lWm EllEl [El (El ElE 18 W

[E [3E-1F[DI ON PO21 Erg PEtI 1(P E-17E- pgE- X E-1 EI E+ Eil E 16 r~ D(iFF1 [E A E]E E [1g 20 14 'LIP 'P[

[DfF] AE](E A [CoI~i C A][]

l~ E~E]

__]EI S Lf [lEl AA GD [AD[E [D F[D IESEIl[1 IDl Ell (Elm[Elg D

12 FI[g[2]E [AlE] A [AE] EA] [D ]J[E m]EIE][Dl E]J[DE)) ElE][D

  • o EI] Elio ME FED E1[ Elln El COO CFO [IE]

8 mD [DE] F[E1EA F EA][E] E[BE] [E]EA [DEE]JE] [3Ezj @1] mD 6 NE ['l [PE] Erm T[P E FNlE [5E1FD19 EF1I EITI [10F10 4 m[E] EmE [El[~j(E] [E]Jff [E][ m[Em 2 2 12I ETDe EN[ [IEDElEIE]

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 Fuel Type A=GE14-P IODNAB405-16GZ-10OT-150-T6(Cycle 17) E=GE I2-P I ODSB407-14G6.0-1OOT-1 50-T6 (Cycle 15)

B3=GE14-P lODNAB405-15G6.0-lOOT-150-T6 (Cycle 17) F=GE14-P 1ODNAB405-16GZ-l OOT-150-T6 (Cycle 16)

C=GE 12-P IODSB405-16GZ-l OOT-150-T6 (Cycle 15) G=GE14-P 1ODNAB405-16GZ-l OOT-150-T6 (Cycle 16)

D=GE12-P1ODSB405-17GZ-1OOT-150-T6 (Cycle 15)

Rev. No. 18 Page 31 of 32

'6 CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.7 USERS GUIDE The COLR defines thermal limits for the various operating conditions expected during the cycle. At the start of the cycle the 3D-Monicore databank contains limits for;

  • Cycle exposure range of BOC to < EOCI7 -2.7 GWD/ST
  • 0=0
  • Dual recirculation pump operation
  • Four steam line operation, and
  • Final Feedwater Temperature Reduction The following is a table that offers a check to assure the correct limits are applied when operating states or conditions change.

Change in Operating State Change in Limits Procedure Reference Cycle Exposure.= See Table 8.1 (8.1.A for 3SL) or Figure 8.1 EOC17 - 2.7 GWD/ST for t

  • 0(8.1.A for 3SL) for change in OLMCPR changes to EOC values MCPR None at cycle exposure of 12.0 GWD/ST Kr limit may be changed in recognition of l higher OLMCPR.

Scram Time Test Results such that Use new r and see Figure 8.1 or 8.1MA for Option B limits for OLMCPR must 3SL Kr limit may be changed in RAP-7.4.1 be intepla with fopton A lmits recognition of higher OLMCPR.

be interpolated with Option A ltmits Single Loop Operation Increase MCPR Limits by 0.02, or change The SLMCPR increases by 0.02 and acceptance criterion in ST-5E to 0.98. Kr therefore OLMCPR limits increase does not change. RAP-7.4.2, by 0.02. MFLPD and MAPLHGR Verify that 3D-Monicore has recognized ST-5E, are reduced by a multiplier in SLO. the idle recirculation loop and is applying RAP-7.3.25 the SLO MFLPD and MAPLHGR multiplier of 0.78.

Three Steam Line Operation (3SL) Increase OLMCPR according to Table OLMCPR values increase by 0.02 8.1.A or Figure 8.1.A('r

  • 0). Kf limit may None e be changed in recognition of higher when operatng on 3SL OLMCPR.

8 Operation with Turbine Bypass Increase OLMCPR according to Table Valves Out-of-Service 8.1.B or Figure 8.1.B('r # 0). Kr limit may None OLMCPR values increase, no be changed in recognition of higher LHGR change required OLMCPR.

Operation under Final Feedwater Increase OLMCPR according to Table Temperature Reduction 8.1.C or Figure 8.1.C(r # 0). Kr limit may None OLMCPR values increase, no be changed in recognition of higher LHGR change required OLMCPR.

Rev. No. 18 Page 32 of 32

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