ML062970347

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Core Operating Limits Report Revision 21 (Cycle 18)
ML062970347
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 10/16/2006
From: Richard Plasse
Entergy Nuclear Northeast, Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP 06-0150
Download: ML062970347 (30)
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Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP P.O. Box 110 Entegy Lycoming, NY 13093 Tel 315 342 3840 October, 16, 2006 JAFP 06-0150 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 Revision 21 (Cycle 18)

Dear Sir or Madam:

Attached is Revision 21 to the James A. FitzPatrick Core Operating Limits Report (COLR). This report is submitted in accordance with Technical Specifications (TS) 5.6.5.

Revision 21 of the COLR incorporates reload analysis completed by Global Nuclear Fuel (GNF) for Cycle 18 operations. In addition, editorial corrections and administrative changes are included that do not alter the intent.

There are no commitments contained in this report.

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

Very truly yours, Ric Pl~as e'L

  • Regulatory Compliance Manager RP/tp Attachment as stated cc:

USNRC Regional Administrator, Region I USNRC Project Manager USNRC Resident Inspector

LEntergy Nuclear Northeast ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT CORE OPERATING LIMITS REPORT REVISION 21 William Drews l4.~L~4Lv ~

APPROVED BY:

DATE:

,a LO f*

I!REACTOR ENGINEERING SUPERINTENDEI Keyin Muiga aJY-ý IT APPROVED BY:

1'J

~

GENERAL MANAGER - PLANT OPERATIONS

CORE OPERATING LIMITS REPORT CYCLE 18 TABLE OF CONTENTS SECTION PAGE 1.0 PU RPO SE... ;.............................

................................................. 3 2.0 APPLICABILITY...............................................................................................

3

3.0 REFERENCES

3 4.0 D EFIN ITION S..................

.............. o

................................................................ 4 5.0 RESPONSIBILITIES............................................

5 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS............................................

5 7.0 PROCED U RE..............................................................

.................................. 6 7.1 Operating Limit MCPR................................0..................................... 6 7.2 Average Planar Linear Heat Generation Rate (APLHGR).................. 8 7.3 Linear Heat Generation Rate (LHGR).........................

8 7.4 APRM Trip Settings (Digital Flow Cards).....................

.8 7.5 RBM Upscale Rod Block Trip Setting..:...........

.......... 10 7.6 Stability Option 1-D Exclusion Region amd Buffer Zone............... 10 7.7 Kf - Flow Dependent MCPR Limit............................................... 11 8.0 FIGURES AND TABLES........

............ 12 9.0 EXH IBITS.................................

................... 13 Rev. No. 21 Page 2 of 29

CORE OPERATING LIMITS REPORT CYCLE 18 1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 18 of the James A.

FitzPatrick Nuclear Power Plant. The following limits are addressed:

Operating Limit Minimum Critical Power Ratio (MCPR)

Flow Dependent MCPR Limits e, Average Planar Linear Heat Generation Rate (APLHGR) e 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 EN-LI-1 13, Licensing Basis Document Change process' 3.2 JAFNPP Technical Specifications.,

3.3 Design Change Package E8-jF-06-13005, Cyclel18Core Reload 3.3,4 ENN-DC-503, 3D Monicore New Cycle Update and Databank Maintenance.

3.5

-.Plant Operation Up To 100% Power With One Steam Line IsolatedjAF -SE-96-035.

316 James A. FitzPatrick Nuclear Power Plant Kf'Curve Update, GE-NE-J 11-03426-00-01, September 1998.

3.7 General Electric Standard Application for Reload Fuel, NEDE-2401 I-P-A-15 3.8 GNF Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 17 Cycle 18, 0000-0049-7976SRLR, Rev.0, Class 1, July, 2006.

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

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 Rev. No. 21 Page -

o 2

CORE OPERATING LIMITS REPORT CYCLE 18 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, GEl4 Fuel Design Cycle-Independent Analyses'forj. A. Fitzpatrick Nudear Power Plant, GE-NE-0000-0002-1752-01P, Rev. 0, DRF 0000-0002-1752, September 2002.

3.15 GNF Report, GNF Report, Fuel Bundle Information Report for James A. FitzPatrick Reload 17 Cycle 18, 0000-0049-7976FBIR, Revision 0, July 2006.

3.16 Not Used 3.17 Not Used 3.18 JF-03-00402, ARTS/MEOD Phase I Implementation 3.19 JAF-RPT-MISC-04489, Rev.2, Power-Flow, Map Report 3.20 Not Used 3.21 Not Used 3.22 GE Letter, FitzPatrick APRM Flow Biased Rod Block and Scram Setpoints, NSA01-273, July 3, 2001 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.

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.

Rev., No. 21 Page 4 of 29

CORE OPERATING LIMITS REPORT CYCLE 18 4.5 Minimum ciitical power ratio (MCPR):m-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 actualassembly operating power.

4.6 Rated Recirculatio, Flow':*

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

5.0 RESPONSIBILITIES NOTE:

See EN-LI-1 13 (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 3:

3.'

7-

.3 3

....G " * ;

I Rev. No. 21 Page

_5

'of 29

CORE OPERATING LMITS REPORT CYCLE 18 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 scramtime to notch position 36 shall be:

A VE B

7A.2.2.

The average scram time to notch position 36 is determined as follows:

XNar1 ZAVE =

'i= I WHERE:

n

=

Number of surveillance tests performed to date in the

cycle, N

='

Number of active rods. measured in the surveillance i T*i

=

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

Rev. No. -21 2

Page _L of 29

CORE OPERATING LIMITS REPORT CYCLE 18 7.1.2.3.

The adjusted analysis mean scram time is calculated as follows:

112 i=1 WHERE:

=

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

(

=

Standard deviation of the distribution for average scram insertion time to the dropout of notch position 36 '=O0.09'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

-A.8.1.Cas:aplicable.

7.1.4 WHEN the requirement 7.1.2.1 isnot met (i.e. 'tB <

AvE), 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.

WHERE:

TAvW =

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. 21 Page-,I7 of' 29.

CORE OPERATING LIMITS REPORT CYCLE 18 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 ICPR shall be multiplied by the appropriate Kf' specified in Figure'8.2.'

7.2 Average Planar Linear Heat Generation Rate (APLH-GR) 7.2.1 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) 7.2.2 During operation, with thermal power 2:25% rated thermal power (RTp),

the APLHGR shall be within the limits given in Table 8. (Figure 8.3) 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 GE14 fuel).

7.3 Linear Heat Generation Rate (LHGR) 7.3.1 Technical Specification LCO :3.2.3, Linear Heat Generation Rate (LI=IGR) 7.3.2, During operation,'with, thettilpower > 25% ated thermal power (RTP),

the LHGR for each fuel rod as a funaion of axial location and exposure shall be within limits based on applicable LHGR limit values given in Table 8.2 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 GE14 fuel).

7.4 APRM Trip Settings (Digital Flow Cards) 7.4.1 APRM Flow, Referenced Flux Scram Trip Setting (Run Mode) 4.1.1.

Technical Specifcations.

LCO:3.2.4,*Avirage Power Range Mniltor (APRM) Gain and Setpoint LCO 3.3.1.1, Reactor Protection System1 (RPS), Instrumentation 7.4.1.2.

When operating in Mode 1, the APRM Neutron Flux-High (Flow Biased)

Trip setting shall be Rev. No. 21.

Page'8. of 22

CORE OPERATING LIMITS REPORT CYCLE 18 for two loop operation:

S< (C/o RTP) = 0.38*W+61.0%/o S< (% RTP) = l.15*W+42.0%

S< ()a RTP) = 0.63*W+73.71%

S< (C/o RTP) = 117.00% (Clamp)

'for stigle looP operation:

'8"S (% RTP) = 0.38*,W+57.9%.

S5< (C/ RTP) = 1.15*W+32.8%

S<* (%/ RTP) = 0.58*W+61;3%

S< (% RIP) = 117.00% (Clamp) 0< W *24.7%

24.7< W _47.0%

47.0< W *68.7%

W > 68.7%

0< W *32.7%

32.7< W 5 50.1%

,50.1< W < 95.9%

W > 95.9%

NOTE:

7.41.3..

WHERE:

S

=

Setting in percent of rated thermal power; W

Recirculation flow in percent of rated; 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.,

rIn 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 -

for two loop operation:

S< (0/ RTP) = (0.38*W+61.0%)(FRP/MFLPD) 0< W -,24.

S

(% RTp) = (1.15*"W+42.0%)(FRP/MFLPD) 24.7< W <

S_< (% RTP) = (0.63*W+73.7%)(FRP/MFLPD) 47.0< W <

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

for single loop operation:.

S< (0/o RTP) = (0.38*Wd+57.9 0/%)(FRP/MFLPD) 0< W *32."

S5 (0% RTP) = (.15*W

d3218o8%)(F

/MFLPO) 32.7< W<:

S< (%/a RTP) = (0.58*Wa+61.3%)(0/ýD/MFP) 50.1< W.-

S< '(% RTP). = (I1700% (Ck-.np))(FRP/MFLPD) W > 95.9%

WHERE:

7%

47.0%

68.7%

70%

50.1%

95.9%

FRI Fraction of Rated Power;

  • 'i

.:r R6v. No.--21; Page'9of 29

CORE OPERATING LIMITS REPORT CYCLE 18 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.

APRM Neutron Flux-High, (Flow Biased) Rod Block Trip Setting (Relocated to the Technical Requireme nts Manual)'

7.4.2 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.nmay be used because-the RBM intercetpi(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.

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.

Rev. No. 21 Page 10 of 29

CORE OPERATING LIMITS REPORT CYCLE 18 7.7 Kf - Flow Dependent MCPR Limit-Figure 8.2 isthe Kf limit. Values of K are obtained using the following equation (see Reference 3.6):

K

=' MAX[1.0,A SLOPEW11 WHERE:

WT

=

Core Flow as % of Rated, 30%: < WT 5 100%

SLOPE, (AF/O0/OLMCPR ) * (SLMCPR /SLMCPR geer ic)

A

=

(8F/OLMCPR (SLMCPR /SLMCPR generic)

SLMCPR generic = 1.07 SLMCPR Technical Specificatlon LCO 2.1.1, Reactor Core SLs OLMCPR The lowest value obtained from Figures 8.1, 8.1.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 %

Ar 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. 21 Page 1I1 of 29'

CORE OPERATING LIMITS REPORT CYCLE 18 8.0 FIGURES AND TABLES 8.1 FIGURES Figure 8.1.

Figure 8.1.A.

Figure 8.1.B Figure 8.1.C Figure 8.2 Figure 8.3 Figure 8.4 Figure 8.5 Figure 8.6.

Figure 8.7 MCPR Operating Limit Versus T for GE14.

MCPR Operating Limit"Versus T for Operadon,above 75% of Rated Thermal Power with Three Steam Lines in Service for GE14.

MCPR Operating Limit Versus T for Operation with Turbine Bypass Valves Out of Service MCPR Operating Limit Versus T for Operation.with Final Feedwater Temperature Reduction Kf Factor Exposure Dependent APLHGR Limit for GE14 Fuel Stability Option 1-D Exclusion Region Exposure Dependent LHGR Limit for GE14 Fuel.

Cycle 18 Loading Pattern, Full Core by Bundle Design Users Guide I,

Rev. No. 21 Page 12 of 29

CORE OPERATIN(

8.2 TABLES Table 8.1 Table 8.1.A Table 8.1.B Table 8.1.C Table 8.2 Table 8.3 3 LIMITS REPORT CYCLE 18 MCPR Operating Limit for Incremental Cycle Core Average Exposure MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service MCPR Operating Limit for Operation with Turbine Bypass Valves, Out of Service MCPR Operating Limit for Operation with Final Feedwater Temperature

,Riduidi6n Maximum LHGR - GE14 APLI-iGR Limits for GE14 Fuel 9.0 EXHIBITS NONE Rev. No. 21 Page 13_.I of 29

CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure All Fuel Types Cycle 18 Exposure Range-BOC to EOC 1.44 NA NA 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. 21 Page 14 of 29

CORE OPERATING LIMITS REPORT CYCLE 18 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 Aft Fuel Types

..,Cycle 18 Exposure Range Fuel T BOC to EOC 1.46 NA NA 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. 21 Page 1_.f5 29

CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.LB MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service, All Fuel Types Cycle 18 Exposure Rarge' ALL 1.48 Technical Specification LCO 3.2.2, Minim*um 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 ofT to assure adjustment per Step 7.1.4 2., Applicable for any value of K, see Step 7.5.2 Rev. No.- 21 Page 16 of 29

'CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.LC MCPR Operating Limit for Operation with*Final Feedwater Temperature Reduction Cycle 18 Exposure Range All Fuel Types At EOC only (see below) 1.44 Technical Specification LCO 3.2.2, Miaimum 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 ti table apply when at reduced feedwater temperature near end-of-cycle, see JD-02-122 (Reference 3.13) for further information.

Rev. No. 21 Page 127 of 29*

CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.2 Maximum LHGR - GE14 Peak Pellet Exposure U0 2, 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 I

Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LI"IGR)

Design features of the fuel assemblies in the Cycle 18 core are provided in References 3.3, 3.15 For single loop operation these LHGR values shall be multiplied by 0.78 Linearly interpolate for LHGR at intermediate exposure Page 18 of 29 Rev. No. 21 P

CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.3' Eiposure DehpedentAPLHGR Limit for GE1l4 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 63.5 5.00..

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. 21 Page 19 of 29

CORE OPERATING LIMITS REPORT CYCLE 18

,FIGURE 8.1 MCPR Operating Limit Versus T' For All Fu6el Types`

BOC to EDC18 - 3.5 GWc/St DC18-3.5 GWd/St.to EBG18 1.65 1.60 1,.61 1.55-S 1.50-144 1.50

':1.45

~-

1.40 1.35 n

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.58

  • 0,9% 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 Upscae Rod Block trip level setting then 7.1.3 shall apply.

Rev. No. 21 Page 2k of 29

CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.1.A MCPR Operating Limit Versusr For Operating Above 75% of Rated Thermal.Power.with Three Steam Lines in Service For all Fuel Types

-o-- ý BOC to E=C18 -'3.5 GWd/St

-U-DC1 8 -3.5 GWd/St to WC1 8 a-C.)

a" E

1.63 1.52 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, MiniaiAum' Critical Power Ratio (NMCPR)

For single loop 6peration, 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 Rev., No.' 21 Page 21 of 29

CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.1.B MCPR Operating Limit Versus T for Operation with Turbine Bypass Valves Out of Service c0 1.7 1.65 1.6 1.55 1.5 1.45 1.65 0

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

't Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

For single loop operation, these limits shall be increased as given mi 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,--

Rev.,No., 21 Page 22 of 29

CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.1.C MCPR Operating Limit VersusT for Operation with FinalFeedwater

..Temperature Reduction cc 0) 1.65 1.6 1.55 1.5 1.45 1.4 1.61 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 Reiý. No'. 21 Page 23 of 29

CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.2 Kf Factor Cycle 18 KI Curve for Scoop Tube Stops at 112%

Considers Two Loop and SingleLoop Operation, MOC and EOCMCPR Limits 1.10-1.09 1.08 1.07-1.06 1.051

-+-- MOC.SLO K

K K

K K

03 EOC+SLO A MOC+rLO X EOC+rLO iThe combination of MOC MCPIR Umit and SLO produces mte most limiting K&

curve.

This set of data determines the KI curve used in the 30-MONICORE databank.

May be changed when EOC MCPR Omits apply. Choice of Single Loop Ks values is for ease of SLO. Two loop Omits are not significantly different. NOTE: Cycdl 18 MOC and EOC limits are equal, so above discussion does not apply, but left as reminder if any changes to Omits.

SLMCPR = 1.07 (TLO), 1.09 (SL0) - see SRLR for MCPR limits OLMCPR(TLO) = 1.44 (BOC to MOC). 1.44 (MOC to EOC)

OLMCPR(SLO) - 1.48 (BOC to MOC), 1.46 (MOC to EOC)

K&

may be adjusted as needed to provide protection against the SLO Pump Seizure event. For GE14, the OLMCPR below the SLO core flow limit of 58% must be greater than 1.43"(SLMCPR/1.12), or 1.392. In Cycle 18'the OLMCPR at MOC+SLO is 1.46 for GE14, so no K& adjustment is required,,

References:

I. K&

CURVE UPDATE, GE-NE-JI 1-03426-00-01, 10116198

2. GE14 Fuel Design Cycle-Independent Analyses for JAFNPP, GE-NE.0000-O002-1752-01P, September 2002 Equation of Cycle 18 K4 curve:

K,= MAX( 1.0, 1.2189 - 0.42004"(% Core Flow/1 00)),

hi 1.04 1.03 1.02 1.01 1.00-0.99 1 30 35 40 45 150 55 60, 65 70 Core Flow, % rated 75 80 85 90 95 100 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)

See Section 7,7 NOTE:

KE 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., 21 PPage 24 of 29

CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.3 Ex osure Dependent APLHGR Limit for GE14 Fuel 14

.13.

12

,ii 10 9

2 15 20 25 30 35 40 45 50-55 60 Planar Exposure, GWD/ST 65 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.

SI

-I."f~"*t.'¶.~'

I'

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Rev. No. 21 Page 25-of 29

CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.4 Stability Option 1-D Exclusion Region 110 100 90 80 0

0 70 60 50 40 30 20 20 25 30 35 40 45 50 55 60 65 70 Flow, % rated Rev. No. 21 Pe of Page 26 of 29

CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.5 Exposure Dependent LHGR Limit for GEI 4 Fuel 14 13 12 11 10 9

8 6

5 4

3 2

1 0

0 5

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

This curve represents the limiting exposure dependent LHGR values per Reference 3.15 Design features of the fuel assemblies in the Cycle 18 core are provided in Reference 3.3 I

Rev. No. 21 Page 2" of 29

CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.6 Cycle 18 Loading Pattern by Bundle Design North 52 M]

0 I

48 ME]__

rj

ý o

48 I

E nME

~

l 32TI M

MuI-11100EEiY 2 80

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f ] (

Wf m M f l1 l i E

W [

428

_9 of]__E DE I

Elf-,E1 I

ffID91F)E 240 Et0EJi W~ MO MIM Mff 226 IIll9IE Milo Miff M91W w

m m

wMBw 0

3l E

5 E

72 E9 11 139 15 E17 19 21 23 25 27 29 313 53T9414 54E9 R_ ___ __

NE FelRTyp

-J rmE i nE)m -

N A=GE 2

14 EODNB4OS Miff] MIoT-MI0T6-79 (Ccl 15 E=24PODA45 o E0 MZ-lOOT-I 50-T-6 (yce 8

B=E1-IONB45 10.0 OO-15-6-73 Ccl

)

=E1-IONB4S I6Z-lOT 506252 (Ccer6 C= E1 -PI D A 4O -1 0.0 4 50 1G. - O T-1 0 6 29 5 F GE1 -

OD A 4 5 I6 Z OO -10EN2 6 Cyl 6

(Ccl 18)M m

T 5

Rev., No. _a Page 28 of 29

CORE OPERATING LIMITS REPORT CYCLE 18 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. EQC18 Dual recirculation pump operationf'

  • Four steam line operation, and Final Feedwater Temperature Reduo ti The following is a table that offers a check to0.assuie the correct limits are applied when operating states or conditions change.

Change in Operating; State.

C.-",:Change in Limits Procedure Reference Cycle Exposure'=

See.Table 8.1 orVFigure8.1 for T, 0 for None EOC18 - 3.5:GWD/ST changenm-MCPL..

OLMCPRgchanges to EOC values K( limit mU-be changed in recognition of at cycle exposure of 12.0 GWD/ST higher OLMCPR.,

Scram Time Test. Results such that TO* 0

'Use new. and see figure 8..'Kr limitr Option B limits for OLvMCPR must be changedin recogiition of higher

,Ap-7'4.l be interpolated with Option A limits. OLCP" Single Loop Operation Increase MCPR Limits by.0.02, or change The SLMCPR increases by 0.02 and acceptance, criterion in ST-SE.to.0.98.,K.

therefore OLMCPk limits.increase does not change....

ST-5E by 0.02. MFLPD and MAPLHG-R Verify that 3D-Monicori' has recognized are reduced by a multiplier in SLO.

the idle recircilation loop and is apolyihg the SLO MFLPD and MAPLHGR multiplier of 0.78.

Three Steam Line Operation (3SL)

Increase OLMCPR according to Table OLMCPR values Opreraso b0 8..A or Figure 8.1A(r

  • 0). Kf limit mag None whenop tinca by 02 be changed in recognition of higher when operating on 3SL OLMCPR.

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

  • 0). K limit mNo OLMCPR values increase, no be changed in recognition of higoein LHGR change. required OLMCPR..

Operation under Final Feedwater IncreaseOLMCPR according toTable*..

Temperature Reduction 8.1.CorFigure8.1.C(O)).Krlimit',

OLMCPR values increase, no be changed in" recognition of higher None LHGR change required.

OLMCPR..

Rev. No. 21 Page 2_9 of 29

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