JAFP-14-0067, Core Operating Limits Report, Revision 27 (Cycle 21)

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Core Operating Limits Report, Revision 27 (Cycle 21)
ML14148A179
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Site: FitzPatrick Constellation icon.png
Issue date: 05/28/2014
From: Adner C
Entergy Nuclear Northeast, Entergy Nuclear Operations
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Document Control Desk, Office of Nuclear Reactor Regulation
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JAFP-14-0067
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Proprietary Information Withhold Per 10 CFR 2.390 Entergy Nuclear Northeast

~ Entergy Entergy Nuclear Operatio ns, Inc .

James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 TP.I 1 1!1-1 4 2 -1840 Chris Adner Regu latory Assu rance Ma nage r - JAF JAFP-14-0067 May 28, 2014 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Core Operating Lim its Report, Revision 27 (Cycle 21)

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-059

Dear Sir or Madam ,

Enclosed is Revision 27 to the James A. FitzPatrick (JAF) Core Operating Limits Report (COLR). This revision incorporates changes resulting from a reload analysis completed by Global Nuclear Fuel (GNF) for Cycle 21 operations and removal of Cycle 21 exposure limitation of 11 ,000 MWD/ST per Tech Spec Amendment No. 305. This is submitted in accordance with JAF Technical Specifications (TS) 5.6.5 .

The enclosed documentation contains proprietary information. GNF, as the owner of the proprietary information, has executed the enclosed affidavit, which identifies that the information has been handled and classified as proprietary, is customari ly held in confidence , and has been withheld from public disclosure. Entergy hereby requests that the enclosed proprietary information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390 and 9.1 7. A non-proprietary version of the documentation is also provided.

There are no commitments contained in this report.

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

Very truly y Chris Adner Regulatory Assurance Manager CA/mh

Enclosure:

1. Core Operating Limits Report, Revision 27 (Propri etary)
2. Core Operati ng Limits Report, Revision 27 (Non-Prop rietary) cc: next page to this lette r contains Proprietary Information that shou ld be withheld from public disclosure per 10 CFR 2.390. W hen separated from Enclosure 1 there are no applicable with holding crite ria.

Proprietary Information Withhold Per 10 CFR 2.390 JAFP-14-0067 Page 2 of 2 cc: (w/out enclosure)

Regional Administrator, NRC Region 1 Mr. Douglas V. Pickett, NRC Senior Project Manager NRC Resident Inspector, JAFNPP Mr. John Rhodes, President and CEO, NYSERDA Ms. Bridget Frymire, New York State Dept. of Public Service Document Components 00 Cover Letter, JAFP-14-0067 01 COLR, Rev 27 (Proprietary) 02 COLR, Rev 27 (Non-Proprietary) to this letter contains Proprietary Information that should be withheld from public disclosure per 10 CFR 2.390. When separated from Enclosure 1 there are no applicable withholding criteria.

JAFP-14-0067 ENCLOSURE 2 Core Operating Limits Report Revision 27 (Non-proprietary Version)

(26 Pages Including Contents)

The GNF proprietary information is identified by a dotted underline inside double square brackets. ((This sentence is an example.{3})) A (( marking at the beginning of a table, figure, or paragraph closed with a )) marking at the end of the table, figure or paragraph is used to indicate that the entire content between the double brackets is proprietary. In each case, the superscript notation {3} refers to Paragraph (3) of the affidavit provided in Enclosure 1, which provides the basis for the proprietary determination.

JAFP-14-0067 Enclosure 2 Contents Core Operating Limits Report 25 Pages

~ Entergy ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT CORE OPERATING LIMITS REPORT REVISION 27 APPROVED BY: William Drews ~PL ~

REACTOR ENGINEERING SUPERVISOR APPROVED BY ~ DATE:'f(,;f~/51' GENE NAGE ANT OPERATIONS

CORE OPERATING LIMITS REPORT CYCLE 21 REVISION RECORD Revision Cycle Date Description COLR Rev. 27 extends applicability range for 27 21 Apr. 2014 operation to the end of Cycle 21.

Summary of Changes Rev. 27 Effective upon final approval Cycle 21 exposure limit of 11,000 MWD/ST for operation placed in COLR Rev. 26 was removed with the TS Amendment approval of the modified TS definition of "Shutdown Margin (SDM) to require calculation of the SDM at the reactor most reactive state throughout the operating cycle.

Rev. 26 Effective 10/03/2012 Applicable for use during Cycle 21 Operation. Revision issued to update this document for FitzPatrick Reload 20 Cycle 21 cycle dependent data.

Removed any GE14 fuel design type pertinent information and references as this fuel design was discharged at EOC20.

GESTAR reference updated to the latest revision 19 (Ref.

3.7).

Update to cycle specific references.

One new reference added that removed cycle exposure limitation in the stability analysis results for Exclusion and Buffer Zones (3.18).

Cycle 21 COLR cycle exposure applicability range of 0 GMD/ST to 11 GWD/ST for operation was added.

Content of TABLE 8.4 defining MCPR Operating Limit for Final Feedwater Temperature Reduction was deleted as FWTR will not be utilized in Cycle 21.

PRIME Gad fuel rods suppression is reported in the LHGR table This revision record and summary added.

Rev. No. 27 Page 2 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE ............................................................................................................................................. 4 2.0 APPLICABILITY................................................................................................................................. 4

3.0 REFERENCES

..................................................................................................................................... 4 4.0 DEFINITIONS .................................................................................................................................... 5 5.0 RESPONSIBILITIES .......................................................................................................................... 6 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS ........................................................................ 6 7.0 PROCEDURE ...................................................................................................................................... 7 7.1 Operating Limit MCPR ........................................................................................................................ 7 7.2 Average Planar Linear Heat Generation Rate (APLHGR) ............................................................ 9 7.3 Linear Heat Generation Rate (LHGR) ............................................................................................ 10 7.4 APRM Allowable Values (Digital Flow Cards) .............................................................................. 11 7.5 RBM Upscale Rod Block Allowable Value ..................................................................................... 12 7.6 Stability Option 1-D Exclusion Region and Buffer Zone. ........................................................... 12 8.0 TABLES AND FIGURES ................................................................................................................ 12 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure .................... 13 TABLE 8.2 MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service ................... 14 TABLE 8.3 MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service..................................................................................................................................... 15 TABLE 8.4 MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction.NOT UTILIZED in CYCLE 21 ............................................................... 16 TABLE 8.5 Exposure Dependent APLHGR Limits ............................................................................ 17 TABLE 8.6 Maximum LHGR ................................................................................................................... 18 Figure 8.1 MCPR(F) Factor ........................................................................................................................ 19 Figure 8.2 K(P), OLMCPR(P) Factor ....................................................................................................... 20 Figure 8.3 Flow-Dependent LHGR Multiplier, LHGRFAC(F) ........................................................... 21 Figure 8.4 Power-Dependent LHGR Multiplier, LHGRFAC(P) ........................................................ 22 Figure 8.5 Stability Option 1-D Exclusion Region ................................................................................. 23 Figure 8.6 Cycle 21 Loading Pattern by Bundle Design ........................................................................ 24 9.0 USERS GUIDE .................................................................................................................................. 25 Rev. No. 27 Page 3 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 21 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)

Allowable Values

  • 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-113, Licensing Basis Document Change process 3.2 JAFNPP Technical Specifications 3.3 EC32096, Cycle 21 Core Reload 3.4 EN-DC-503, 3D Monicore New Cycle Update and Databank Maintenance.

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

3.6 GE Report, J.A. FitzPatrick Nuclear Power Plant APRM/RBM/Technical Specifications /

Maximum Extended Operating Domain (ARTS/MEOD), NEDC-33087P, Revision 1, September 2005 3.7 General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-19, May 2012; and the U.S. Supplement, NEDE-24011-P-A-19-US, May 2012.

3.8 GNF Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 20 Cycle 21, 0000-0100-9172-SRLR, Revision 0, Class I, July, 2012. [EC38736, ECH-NE-12-00062 R0]

3.9 GNF2 Fuel Design Cycle-Independent Analyses for Entergy FitzPatrick, GE Report, GEH-0000-0074-2662-R1, June 2010. [EC23634, JAF-RPT-08-00013 R1]

3.10 Licensing Topical Report, ODYSY Application for Stability Licensing Calculations Including Option I-D and II Long Term Solutions, NEDE-33213P-A, April 2009 Rev. No. 27 Page 4 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 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 deleted 3.15 GNF Report, Fuel Bundle Information Report for James A. FitzPatrick Reload 20 Cycle 21, 0000-0100-9172-FBIR, Revision 0, July 2012. [EC38820, ECH-NE-12-00063 R0]

3.16 JF-03-00402, ARTS/MEOD Phase 1 Implementation 3.17 JAF-RPT-MISC-04489, Rev.7, Power-Flow Map Report 3.18 GE Hitachi, Effect of Cycle Extension on the Reload Stability Analyses for Options I-D, II and III, 0000-0125-2402-R0, November 2010 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 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.

4.3 Minimum 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.

4.4 Rated Recirculation Flow :

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

Rev. No. 27 Page 5 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 5.0 RESPONSIBILITIES NOTE: See EN-LI-113 (Reference 3.1) 5.1 Shift Manager:

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

5.2 Reactor Engineering Supervisor:

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 Final Feedwater Temperature Reduction will not be utilized in the Cycle 21 operation.

Rev. No. 27 Page 6 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 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:

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

n N

i =1 i i AVE = n N

i =1 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. 27 Page 7 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 7.1.2.3 The adjusted analysis mean scram time is calculated as follows:

1/2

º

<< N1 >>

B ( sec ) = + 1.65 << n >>

<< Ni >>

<<¬ i=1 >>1/4 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 = 0.019 sec.

N1 = 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 Table8.1, Table8.2, Table8.3, or Table8.4 as applicable for

= 0.

7.1.4 WHEN the requirement 7.1.2.1 is not met (i.e. AVE > B), THEN the Operating Limit MCPR values (as a function of ) are given in Tables 8.1, 8.2, 8.3, or 8.4 as applicable.

( AVE B)

=

( A B)

WHERE:

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

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

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

Rev. No. 27 Page 8 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 7.1.5 During single-loop operation, the Operating Limit MCPR shall be increased by 0.03.

7.1.6 The Operating Limit MCPR is the greater of the flow and power dependent MCPR operating limits, MCPR(F) and MCPR(P).

Operating Limit MCPR = MAX (MCPR(P), MCPR(F))

The flow dependent MCPR operating limit, MCPR(F), is provided in Figure 8.1.

For core thermal powers equal to or greater than 25%, MCPR (P) is the product of the rated Operating Limit MCPR presented in Tables 8.1, 8.2, 8.3, or 8.4 and the K (P) factor presented 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 Table 8. 5 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 (0.85 for GNF2 fuel, per Ref. 3.8).

Rev. No. 27 Page 9 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 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 applicable limiting LHGR values for each fuel rod as a function of axial location and exposure shall be the smaller of the power and flow dependent LHGR limits multiplied by the applicable power and flow adjustment or the LHGR limit multiplied by 0.85 (for GNF2) when in single loop operation.

LHGR limit = MIN (LHGR (P), LHGR (F)).

Power-dependent LHGR limit, LHGR (P), is the product of the LHGR power dependent LHGR limit adjustment factor, LHGRFAC (P), shown in Figure 8.4 and the LHGRstd in Table 8.6.

LHGR (P) = LHGRFAC(P) x LHGRstd The flow-dependent LHGR limit, LHGR (F), is the product of the LHGR flow dependent LHGR limit adjustment factor, LHGRFAC (F), shown in Figure 8.3 and the LHGRstd in Table 8.6.

LHGR (F) = LHGRFAC(F) x LHGRstd Rev. No. 27 Page 10 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 7.4 APRM Allowable Values (Digital Flow Cards) 7.4.1 APRM Flow Referenced Flux Scram Allowable Value (Run Mode) 7.4.1.1 Technical Specifications:

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)

Allowable Value shall be for two loop operation:

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

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

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

S (% RTP) = 117.00% (Clamp) W > 68.7%

for single loop operation:

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

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

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

S (% RTP) = 117.00% (Clamp) W > 95.9%

WHERE:

S = Allowable value in percent of rated thermal power; W = Recirculation flow in percent of rated; 7.4.2 APRM Neutron Flux-High (Flow Biased) Rod Block Allowable Value (Relocated to the Technical Requirements Manual)

Rev. No. 27 Page 11 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 7.5 RBM Upscale Rod Block Allowable Value 7.5.1 Technical Specification LCO 3.3.2.1, Control Rod Block Instrumentation 7.5.2 The RBM upscale rod block allowable value shall be:

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

S = rod block allowable value 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 affect the MCPR Operating Limit and the RBM is not assumed to function to protect the Safety Limit MCPR.

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

NOTE: If K can be any value, then K - 0.66W can also be any value, and the allowable value 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 8.5 when the SOLOMON Code is operable.

7.6.3 The reactor shall not be intentionally operated within the Buffer Zone given in Figure 8.5 when the SOLOMON Code is inoperable.

8.0 TABLES AND FIGURES 8.1 Following pages present Tables 8.1 through 8.6, and Figures 8.1 through 8.6. Exact tables and figures names are listed in the Table of Content on page 3.

Rev. No. 27 Page 12 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure GNF2 (Reload 19 & 20) GNF2 (Reload 18)

BOC to MOC MOC to EOC BOC to MOC MOC to EOC

=0 1.42 1.46 1.43 1.46

>0.0 0.1 1.43 1.47 1.43 1.47

>0.1 0.2 1.44 1.48 1.44 1.48

>0.2 0.3 1.45 1.49 1.45 1.49

>0.3 0.4 1.46 1.50 1.46 1.50

>0.4 0.5 1.47 1.51 1.47 1.51

>0.5 0.6 1.48 1.52 1.48 1.52

>0.6 0.7 1.49 1.53 1.49 1.53

>0.7 0.8 1.50 1.54 1.50 1.54

>0.8 0.9 1.51 1.55 1.51 1.55

>0.9 1 1.52 1.56 1.52 1.56 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.

The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of to assure adjustment per Step 7.1.4

2. Applicable for any value of K, see Step 7.5.2 Rev. No. 27 Page 13 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 TABLE 8.2 MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service GNF2 BOC to MOC MOC to EOC

=0 1.44 1.48

>0.0 0.1 1.45 1.49

>0.1 0.2 1.46 1.50

>0.2 0.3 1.47 1.51

>0.3 0.4 1.48 1.52

>0.4 0.5 1.49 1.53

>0.5 0.6 1.50 1.54

>0.6 0.7 1.51 1.55

>0.7 0.8 1.52 1.56

>0.8 0.9 1.53 1.57

>0.9 1 1.54 1.58 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.

The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of to assure adjustment per Step 7.1.4

2. Applicable for any value of K, see Step 7.5.2 Rev. No. 27 Page 14 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 TABLE 8.3 MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service GNF2 BOC to EOC

=0 1.51

>0.0 0.1 1.52

>0.1 0.2 1.53

>0.2 0.3 1.54

>0.3 0.4 1.55

>0.4 0.5 1.56

>0.5 0.6 1.57

>0.6 0.7 1.58

>0.7 0.8 1.59

>0.8 0.9 1.60

>0.9 1 1.61 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.

The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of to assure adjustment per Step 7.1.4

2. Applicable for any value of K, see Step 7.5.2 Rev. No. 27 Page 15 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 TABLE 8.4 MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction 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.

The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of 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 3.13) for further information.

Rev. No. 27 Page 16 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 TABLE 8.5 Exposure Dependent APLHGR Limits GNF2 Fuel Types Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 13.78 13.24 13.78 17.52 13.78 60.78 7.50 63.50 6.69 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)

For single loop operation these APLHGR values shall be multiplied by 0.85 for GNF2 fuel.

Linearly interpolate for APLHGR at intermediate exposure.

Rev. No. 27 Page 17 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 TABLE 8.6 Maximum LHGR Maximum LHGR - GNF2 Peak Pellet Exposure, GWD/ST UO2 LHGR Limit, kW/ft

((° ° ° ° °°°°°

°°°°° °°°°°

°°°°° °°°°°

°°°°° ° ° ° ° ° ° ° ° ° ))

Peak Pellet Exposure, GWd/ST Most Limiting Gadolinia LHGR Limit, kW/ft

((° ° ° ° ° °°°°°

°°°°° °°°°°

°°°°° °°°°°

°°°° ° ° ° ° ° ° ° ° ° ))

Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)

Design features of the fuel assemblies in the Cycle 21 core are provided in References 3.3, 3.15.

LHGRstd values in the above Table 8.6 are subject to Power and Flow dependent adjustments per Section 7.3 For single loop operation these LHGR values shall be multiplied by 0.85 (for GNF2 fuel)

Linearly interpolate for LHGR at intermediate exposure Rev. No. 27 Page 18 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 Figure 8.1 MCPR(F) Factor 1.70 )RU0D[LPXP)ORZRI

)RU7/2

)ORZ0&35 )



1.60





Flow Dependent MCPR - MCPR(F)

)RU6/20&35 ) LQFUHDVHVE\IRUDOOIORZV 1.50 1.40 1.30 1.20 1.10 20 30 40 50 60 70 80 90 100 110 Core Flow (% rated)

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

Reference 3.8 Rev. No. 27 Page 19 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 Figure 8.2 K(P), OLMCPR(P) Factor 2.8 Operating Limit MCPR (P) = K(P)

  • Operating Limit MCPR(100) 2.7 For P<25%: No Thermal Limits Monitoring Required, No 2.6 limits specified 2.5 For 25%P<P(Bypass), P(Bypass)=29%

OLMCPR(P)=2.31+0.0125*(29%-P), Flow60%

2.4 OLMCPR(P)=2.58+0.0275*(29%-P), Flow>60%

2.3 For PP(Bypass)

K(P)=1.390+0.0118*(40%-P), 29%P<40%

2.2 K(P)=1.189+0.0101*(60%-P), 40%P<60%

K(P) Multiplier for P29%;

K(P)=1.056+0.00532*(85%-P), 60%P<85%

2.1 K(P)=1.00+0.00373*(100%-P), 85%P<100%

2.0 1.9 OLMCPR(P) for P<Pbypass 1.8 1.7 1.6 1.5 1.4 1.3 1.2 1.1 1.0 20 30 40 50 60 70 80 90 100 110 3RZHU UDWHG See Table 8.1, 8.2, 8.3,and Table 8.4 for Operating Limit MCPR(100)

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

Reference 3.8, 3.9 Rev. No. 27 Page 20 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 Figure 8.3 Flow-Dependent LHGR Multiplier, LHGRFAC(F) 1.10 1.00 APLHGR/LHGR Flow Factor - MAPFACf and LHGRFACf 0.90 0.80 0.70 0.60 LHGR(F)=LHGRFACf*LHGRstd Max Flow = 112%

Flow LHGRFACf 0.50 30% 0.626 85% 1.000 110% 1.000 0.40 0.30 30 40 50 60 70 80 90 100 110 Flow, % rated See Table 8.6 for LHGRSTD value Reference 3.8, 3.9 Rev. No. 27 Page 21 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 Figure 8.4 Power-Dependent LHGR Multiplier, LHGRFAC(P) 1.1 1.0 0.9 0.8 LHGRFAC(P)

0.7 LHGRFACp

For P<25%, No Thermal Limits Required Pbypass = 29% Pow er 0.6 for <29%P, >60%F LHGRFACp = 0.531+0.0045*(P-29) 0.5 for <29%P, 60%F LHGRFACp = 0.58 0.4 for 29%P100%

LHGRFACp = 1.000+0.00528*(P-100) 0.3 20 30 40 50 60 70 80 90 100 Power, % rated See Table 8.6 for LHGRSTD values Reference 3.8, 3.9 Rev. No. 27 Page 22 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 Figure 8.5 Stability Option 1-D Exclusion Region See References 3.17 and 3.8 for details Reference 3.18 generically removes cycle exposure limitation statement in the Supplemental Reload Licensing Report stability analysis.

Rev. No. 27 Page 23 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 Figure 8.6 Cycle 21 Loading Pattern by Bundle Design North Rev. No. 27 Page 24 of 25

CORE OPERATING LIMITS REPORT CYCLE 21 9.0 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 limits are set for;

  • Cycle exposure range of BOC to MOC
  • = 0
  • Dual recirculation pump operation
  • Four steam line operation, and
  • Normal Feedwater Temperature The following is a table that offers a check to assure the correct limits are applied when operating states or conditions change.

Procedure Change in Operating State Change in Limits Reference Cycle Exposure = EOR21 - 3.144 GWD/ST EN-DC-503 OLMCPR changes to EOC values at cycle See Table 8.1 for 0 for change in transition to exposure of 10.683 GWD/ST. Databank will MCPR. EOC limits will use 10.500 GWD/ST to account for occur uncertainties. automatically Scram Time Test Results such that 0 Use new and see Table 8.1, 8.2, RAP-7.4.1 Option B limits for OLMCPR must be 8.3,and Table 8.4.

interpolated with Option A limits Single Loop Operation Increase MCPR Limits by 0.03, or The SLMCPR increases by 0.03 and, change acceptance criterion in ST-40D therefore OLMCPR limits increase by 0.03. (Step 8.2.19) to 0.97.

LHGR and MAPLHGR are reduced by a Verify that 3D-Monicore has ST-40D multiplier in SLO. recognized the idle recirculation loop and is applying the SLO LHGR and MAPLHGR multipliers of 0.85 for GNF2.

Three Steam Line Operation (3SL) Increase OLMCPR according to Table 8.2. None Operation with Turbine Bypass Valves Out-of-Service Increase OLMCPR according to Table OLMCPR values increase, no LHGR change 8.3. None required Operation under Final Feedwater Temperature Reduction Not utilized in Cycle 21 operation None Rev. No. 27 Page 25 of 25

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