NL-17-023, Revision to the Core Operating Limits Report

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Revision to the Core Operating Limits Report
ML17061A024
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 02/22/2017
From: Vitale A
Entergy Nuclear Northeast
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-17-023
Download: ML17061A024 (28)
v • d • e


Text

-===* Entergx NL-17-023 February 22, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 254 6700 Anthony *J Vitale Site Vice President

SUBJECT:

Revision to the Core Operating Limits Report for Indian Point Nuclear Generating Unit Nos. 2 and 3 Docket No. 50-247 and 50-286 License No. DRP-26 and DRP-64

REFERENCES:

1) USN RC Letter, "Indian Point Nuclear Generating Unit Nos. 2 and 3 -

Issuance of Amendment RE: Conditional Exemption from End-of-Life Moderator Temperature Coefficient (CAC Nos. MF7193 and MF7195 (November 15, 2016) (ML 1621/ML 1621/ML16215A243)

Dear Sir or Madam:

In Reference 1, the NRC issued the Amendment No. 285 to Facility Operating License No.

DPR-26 for the Indian Point Nuclear Generating Unit No. 2 and Amendment No. 261 to Facility Operating License No. DPR-64 for the Indian Point Nuclear Generating Unit No. 3.

The amendments revise TS 3.1.3, "Moderator Temperature Coefficient (MTC)," and TS 5.6.5, "Core Operating Limits Report (COLR}," to allow exemption from the normally required near end-of-llfe MTC measurement by placing a set of conditions on reactor core operation.

The purpose of this letter is to provide a revision to the COLR report for Indian Point Nuclear Generating Unit Nos. 2 and 3 changes due to the above Amendments. This report is submitted in accordance with Technical Specification 5.6.5_d.

There are no new commitments being made in this submittal.

Should you have any questions concerning this report, please contact Mr. Robert W.

Walpole, Licensing Manager, at (914) 254-6710.

Sincerely, AJV/mm

Enclosures:

NL-17-023 Dockets 50-247 and 50-286 Pages 2 of 2

1. Indian Point Nuclear Generating Unit No. 2 COLR: "2-GRAPH-RPC-6 Revision 18"
2. Indian Point Nuclear Generating Unit No. 3 COLR: "3-GRAPH-RPC-16 Revisiori 9"

. cc:

Mr. Daniel H. Dorman, Regional Administrator. Region I, NRC Mr. Douglass Pickett, Senior Project Manager, NRR/DORL, NRC Ms. Bridget Frymire, New York State Department of Public Service Mr. John B. Rhodes, President and CEO NYSERDA NRC Resident Inspector's Office

/

to NL-17-023 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 COLR: "2-GRAPH-RPC-6 REVISION 18" ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247

~Entergy Nuclear Northeast Approved By:

Procedure Use Is:

Iii' Continuous D Reference D Information Control Copy: ___

Effective Date:/.,;i. /1 f/201 Ip Page 1 of 12 This procedure is Quality Related

  • ion 18

~ *:QRT (COLA) 0 0

f:W~~~~--~~~~~-i:P*erat\\.O~

Team 2A Procedure Owner PARTIAL REVISION

CORE OPERATING LIMITS REPORT (COLA) 1.0 REASON FOR REVISION 1 REVISION

SUMMARY

(Page 1 of 1)

No: 2-GRAPH-RPC-6 Rev: 18 '.

Page 2 of 12 1.1 Incorporate LBDCR# U2-COLA-2016-002 markup.

2~

SUMMARY

OFCHANGES 2.1 Revised TS 3.1.3 for wording from NL~15-144 Attachment 4.

No: 2-GRAPH-RPC-6 Rev: 18 CORE OPERATING LIMITS REPORT (COLR)

Page 3 of 12

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TABLE OF CONTENTS SECTION PAGE TS 2.1.1 Reactor Core SLs...................... :::................................................................... 4 TS 3.1.1 Shutdown Margin (SOM).......................... !...................................................... 4

  • TS 3.1.3. Moderator Temperature Coefficient (MTC)..................................................... 4 TS 3.1.5 Shutdown Bank Insertion Limits...................................................................... 5
  • TS 3.1.6 Control Bank Insertion Limits.......................................................................... 5 TS 3.2.1 Heat Flux Hot Channel Factor (Fa(Z))............................................................. 5 N

TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FAH)....................... ;...... ~............. 5 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)

Methodology)................................................................................................'.. 6 TS 3.3. 1 Reactor Protection System (RPS) Instrumentation......................................... 6 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits......................................................................................... 6 TS 3.9.1 Refueling Boron Concentration.... :.................................................... :............. 6 Attachments:

Figures:

Figure 1 Figure 2 Figure 3 Figure 4 Overtemperature ~T Allowable Value............................................ 7 Overpower~ T Allowable Value.......... ;........................................... 8 Reactor Core Safety Limit - Four Loops in Operation.................... 9 Rod Bank Insertion Limits.................................. ~.......................... 10 Hot Channel Factor Normalized Operating Envelope.................... 11 Axial Flux Difference Envelope Limits........................................... 12

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No: 2-GRAPH-RPC-6 Rev: 18 CORE OPERATING LIMITS REPORT (COLR)

Page 4 of 12

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NOTE The data presented in this report applies to Cycle 23 ONLY and may NOT be used for other cycles of operation. Any technical change to this document may require a Safety Evaluation to be performed in accordance with 1 O CFR 50.59 TS 2.1.1 Reactor Core Sls In MODES 1 and 21 the combination of thermal power level, pressurizer pressure, and highest loop average coolant temperature SHALL not exceed the limits shown in Figure 1.

The safety limit is exceeded if the point defined by the combination of Reactor Coolant System average temperature and power level is at any time above* the appropriate pressure line.

TS 3.1.1 Shutdown Margin (SOM)

The shutdown margin SHALL be greater than or equal to 1.3% ~k/k.

. TS 3.1.3 Moderator Temperature Coefficient CMTC)

The MTC upper limit SHALL be s 0.0.O.k/k/°F at hot zero power.

The MTC lower limit SHALL be less negative than or equal to:

-36.5 pcm/°F@ 300 ppm

-43.0 pcm/°F@

60 ppm

-45.5 pcm/~F@

O ppm The Revised Predicted near EOL 300 ppm MTC SHALL be calculated using the algorithm contained in WCAP-137 49-P-A:

Revised Predicted MTC = Predicted MTC + AFD Correctio~f -3pcm/°F If the Revised Predicted MTC is less negative than SR 3.1.3.2 300 ppm surveillance limit and all benchmark data contained in the surveillance procedure are met, then an.MTC measurement in accordance with SR 3.1.3.2 is not required to be performed.

.. *~

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No: 2-GRAPH-RPC-6 Rev: 18 CORE OPERATING LIMITS REPORT (COLR)

Page 5 of 12.

TS 3.1.5 Shutdown Bank Insertion Limits

. The Shutdown Banks SHALL be fully withdrawn when the reactor is in MODE 1 and MODE 2. Shutdown Banks with a group step counter demand position~ 223 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.

I !

TS 3.1.6 Control Bank Insertion Limits The Control Bank Insertion Limits for MODE 1 and MODE 2 with kett ~ 1.0 are as indicated

. in Figure 2. Control Bank Insertion Limits apply to the step counter demand position.

Each Control Bank shall be considered fully withdrawn at ~ 223 steps.

TS 3.2.1 Heat Flux Hot Channel Factor (Fa<Z>)

NOTE

  • P is the fraction of Rated Thermal Power (ATP) at which the core is operating.

K(Z) is the fraction given in Figure 3 AND Z is the core height location of Fa.

  • I IF P >.5, Fa(Z). s (2.30/ P) x K(Z)

. IF.P s.5, Fa(Z)* ::;; (4.60) x K(Z)

TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F~H}

NOTE P is the fraction of Rated Thermal Power (ATP) at which the core is operating.

F~ s 1.65 { 1 + 0.3 ( 1 - P ) }

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No: 2-GRAPH-RPC-6 Rev: 18 CORE OPERATING LIMITS REPORT (COLR)

Page 6 of 12

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i:-s 3.2.3 Axial Flux Difference (AFDl (Constant Axial Offset Control (CAOCl Methodology)

The Indicated limit is the Target Band; i.e., the Target+/- 5%

The AFD SHALL be maintained within the ACCEPTABLE OPERATION* portion of Figure 4, as required by TS 3.2.3.

TS 3.3.1 Reactor Protection System (RPS) Instrumentation*

1. Overtemperature L\\T Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1.

Refer to Attachment 1.

2. *Overpower L\\T Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 6, No.ta 2.

Refer to Attachment 2.

TS 3.4.1 RCS Pressure. Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits The following DNB related parameters are applicable in MODE 1:

CAUTION The following RCS T AVG limits should be decreased one degree for each degree that the full power T AVG is less than 565°F. For example, if the full power TAvG is equal to 562°F, then the RCS average TAvG limit is s 565.1°F and the highest loop TAVG limit is s 568.1°F.

a.

Pressurizer Pressure c:: 2216 psia

b.

Reactor Coolant System average T AVG $ 568.1°F and highest loop T AVG s 571.1°F for full powerTAvG of 565.0°F c;

Reactor Coolant System Total Flow Rate ~ 348,300 gpm TS 3.9.1 Refueling Boron Concentration When required by Technical Specification 3.9.1, the minimum boron concentration in the RCS, Refueling Canal, and Reactor Cavity SHALL be the more restrictive of either c:: 2050 ppm of that which is sufficient to provide a shutdown margin ~ 5% L\\k/k.

    • . "~f.1 No: 2-GRAPH-RPC-6 Rev: 18 CORE OPERATING LIMITS REPORT (COLR)

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(Page 1 of 1)

Page 7 of 12 Overtemperature 4T Allowable Value The Overtemperature 4T Function Allowable Value SHALL NOT exceed the Technical Specification Table 3.3.1-1, Note 1 value.

The following provides the comput~d value:

Where:

8T is measured RCS AT,'<>F (measured by hot leg and cold leg RTDs).

4To is tfie loop specific indicated AT at ATP, °F.

s is the Laplace transform operator, sec*1*

Tis the measured RCS average temperatur~!**°F.

T' is the loop specific indicated Tavg at RTP, s 572 °F.

P is.the measured pressurizer pressure, psig.

P' is the nominal RCS operating pressure, ~ 2235 psig.

K1s1.22 t1~25 sec K2 ~ 0.020/°F t2 s 3 sec f1(AI) = -1.97 {30 + (q, - qb)}

0% of ATP 2.25 {(q, - qb) - 7}

Ka ~ 0.00070/ psig when q1 - qb s -30% RTP when -30% ATP < q1 - Qb ~ 7% RTP, when q, - qb > 7% ATP Where q1 and Qb are percent RTP in the upper and lower halves of the core, respectively, and q1 + Qb is the total THERM~L POWER in percent ATP.

1:'

I CORE OPERATING LIMITS REPORT (COLR)

Overpower.dT Allowable Value (Page 1of1)

No: 2-GRAPH-RPC-6 Rev: 18 Page 8 of 12 c~

The Overpower.dT Function Allowable Value SHALL NOT exceed the Technical Specification Table 3.3.1-1, Note 2 value.

The following provides the computed value:

Where:

.dT is measured,RCS.dT/°F.

a To is the loop specific indicated a T at ATP, °F.

sis the Laplace trahsform operator, sed~

1 Tis the measured RCS average temperature, °F.

T" is the loop specific indicated Tavg at ATP, s 572.(,F.

Ki s 1.074

-'t3 ~ 10 sec Ks ~ 0.0188/°F for increasing T avg 0/°F for decreasing T avg Ke~ 0.0015/°F when T > T" O/~F when T s T"

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No: 2-GRAPH-RPC-6 CORE OPERATING LIMITS REPORT (COLR)

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660 640 620 600 580 560 Page 9 of 12 Figure 1 Reactor Core Safety Limit - Four Loops in Operation (Page 1of1)

  • 2440 psla ACCEPTABLE CONSEQUENCES

. ~

UNACCEPTABLE CONSEQUENCES

~0-1-~l~**,......,..-1-**~*~*~*--+-----_._...._..---..i**_._~*-+-~i*~*........

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No: 2-GRAPH-RPC-6 CORE OPERATING LIMITS REPORT (COLA)

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Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 100 Step Overlap (Page 1 of 1)*.

(64.9, 223) I

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  • Figure 3 Hot Channel Factor Normalized Operating Envelope (For S. G. Tube Plugging up to 5%)

(Page 1 of 1)

FQ = 2.30 FQ k(z)

Elev {ft}

2.30 1.0 0.0 2.30 1.0 6.0.

2.30 1.0 12.0

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6 8

10.

Core Height (ft) 12 Rev: 18 If I*

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No: 2-GRAPH-RPC-6 CORE OPERATING LIMITS REPORT (COLA)

Page 12of12 Figure4

  • Axial Flux Difference Envelope Limits (Page 1 of 1) 100'~* ~~~~~~~~~--r-r-.,....

Power.level Tech Spec Envelope 95 90 85

65 60 55 40

.UNACCEPTABLE

'OPERATION.. "

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  • 11.0 11.0

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-31.0 31.0 UNACCEPTABLE OPERATION Vari8hle Target

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10 20 30 Axial Flux Difference 40

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Rev: 18 to NL-17-023

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Indian Point Nuclear Generating Unit No. 3 COLR: "3-GRAPH-RPC-16 Revision 9"

_(

ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286

~Entergy Nuclear Northeast Approved By:

Team 38 Procedure Owner Procedure Use Is:

li'.J Continuous D Reference D Information PARTIAL REVISION Control Copy: ___

Effective Date: J :.i./1f/ 2-.()H..p Page 1 of 12 This Procedure is Quality Related

~.:

No: 3'."GRAPH-RPC-16

. CORE OPERATING LIMITS REPORT 1.0.

REASON FOR REVISION Page 2 of 12 REVISION

SUMMARY

(Pag~ 1 of 1) 1.1 Incorporate LBDCR# U3-COLR-2016-001 markup.

2.0

SUMMARY

OF CHANGES 2.1 Revised TS 3.1.3 for wording from NL-15-144 Attachment 4.

Rev: 9

CORE OPERATING LIMITS REPORT No: 3-GRAPH-RPC-16 Rev: 9 Page 3of12 TABLE OF CONTENTS SECTION PAGE

  • TS 2.1.1 Reactor. Core SLs..................................................................................................... 4 TS 3.1.1 Shutdown Margin (SOM)....... '................... ~................................................................ 4 TS 3.1.3 Moderator Temperature Coefficient (MTC)........................................ :..................... 4.

TS 3.1.5 Shutdown Bank Insertion Limits................... -............................................................ 5 TS 3.1.6 Control Bank Insertion Limits.......................................... :........................................ 5 TS 3.2.1 Heat Flux Hot Channel Factor (Fa(Z))................. '.................................................... 5 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ~

....................................................... 5 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC) Methodology). 6 TS 3.3.1 RPS Instrumentation............................................................................................. ~.. 6 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) -

  • Limits.............................. ~...................................................... ~... ~............................................. 6 TS 3.9.1 Refueling Boron Concentration................ ~..............................................................,_.. 6 ATTACHMENTS OVERTEMPEAATURE f1T ALLOWABLE VALUE........................................... 7,OVERPOWER f1T ALLOWABLE VALUE.-........................................................ 8 FIGURES

. Figure 1 Reactor Core Safety Limit-Four Loops in Operation......................... ~..................,.9 Figure 2 Rod Bank Insertion Limits......................... *............................................................... 1 O Figure 3 Hot Channel Factor Normalized Operating Envelope................ :............................ 11 Figure 4 Axial Flux Difference Envelope Limits.................................................................... 12

CORE OPERATING LIMITS REPORT No: 3-GRAPH-RPC-16 Rev: 9 Page 4 of 12 NOTE The data presented in this report applies to Cycle 19 ONLY and may NOT be used for other cycles of operation. Also, it applies only to operation at a maximum power level of 3188.4 MWt. Any technical change to this document may require a Safety Evaluation to be perfonned in accordance with 10 CFR 50.59.

TS 2.1.1 Reactor Core Sls In MODE 1 and 2, the combination of thennal power level, pressurizer pressure, and Reactor Vessel inlet temperature SHALL not exceed the limits shown in Figure 1. The safety limit.is exceeded if the point defined by the combination of Reactor VesseJ inlet temperature and power level is at any time above the appropriate press'ure line.

TS 3.1.1 Shutdown Margin (SOM)

The-shutdown margin SHALL be greater than or equal to 1.3% ~k/k.

TS 3.1.3 Moderator Temperature Coefficient CMTC)

The MTC upper limit SHALL be s 0.0 Ak/k/°F at hot zero power.

The MTC lower limit SHALL be less negative than or equal to:

-38.0 pcm/°F

@ 300 ppm

-44.5 pcm/°F 60 ppm

-47.0 pcm/°F 0 ppm The Revised Predicted near EOL 300 ppm MTC SHALL be calculated using the algorithm-contained in WCAP-137 49-P-A:

Revised Predicted MTC = Predicted MTC + AFD Correction + -3pcm/°F If the Revised Predicted MTC is less negative than SR 3.1.3.2 300 ppm surveillance limit and all benchmark data contained in the surveillance procedure are met, then an MTC measurement in accordance with SR 3.1.3.2 is not required to be perfonned.

CORE OPERATING LIMITS REPORT No: 3-GRAPH-RPC-16 Rev:9 Page 5 of 12 TS 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks SHALL be fully withdrawn when the reactor is_ in MODE 1 and MODE 2.

Shutdown Banks with a group step counter demand position ~ 225 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.

- TS 3.1.6 Control Bank Insertion Limits The Control Bank Insertion Limits for MODE 1 and MODE 2 with kett ;:: 1.0 are as indicated in Figure 2. Control Bank Insertion Limits apply-to the step counter demand position.

Each control bank shall be considered fully withdrawn at 2: 225 steps.

TS 3.2.1 Heat Flux Hot Channel Factor (Fa (Z)l NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.

K(Z) is the fraction given in Figure 3 and Z is the core height location of F0.

IF P >.5, Fo(Z) s (2.30 IP) x K(Z)

IF P s.5, Fa(Z) _.s (4.60) x K(Z)

TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ~

, NOTE Pis the fraction of Rated Thermal Power (RTP) at which the core is operating.

F~H s 1.65 { 1 + 0.3 ( 1 - p ) }

CORE OPERATING LIMITS REPORT No: 3-GRAPH-RPC-16 Rev: 9 Page 6 of 12

, TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)

Methodology)

The Indicated limit is the Target Band; i.e., the Target+/- 5%

The AFD shall be maintained within the ACCEPTABLE OPERATION portion of Figure 4, as required by TS 3.2.3.

TS 3.3.1 RPS Instrumentation

1. Overtemperature 8T Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1
2. Overpower 8 T Refer to Attachment 1 Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 6, Note 2 Refer to Attachment 2 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits The following DNB related parameters are applicable in MODE 1:

CAUTION The RCS loop T avg limit should be decreased one degree for each degree that the full power Tavg is less than 572°F. For example, if the cycle full power Tavg is equal to 570°F, then the RCS loop Tavg limit is s 574.7°F.

a.

Reactor Coolant System loop Tavg ::; 576.7°F for full-power T avg= 572.0~F

b.

Pressurizer Pressure;:::: 2204 psig

c.

Reactor Coolant System Total Flow Rate~ 364,700 gpm TS 3.9.1 Refueling Boron Concentration When required by Technical Specifi.cation 3.9.1, the minimum boron concentration in the RCS, Refuel Canal, and Reactor Cavity SHALL be the more restrictive of either ~ 2050 ppm or that which is sufficient to provide a shutdown margin 2'. 5% dk/k.

CORE OPERATING LIMITS REPORT (Page 1 of 1)

OVERTEMPERATURE AT ALLOWABLE VALUE No: 3-GRAPH-RPC-16 Rev: 9 Page 7 of 12 The Overtemperature AT Function AUowable Value SHALL NOT exceed the Technical Specification Table 3.3.1-1, Note 1 value.

The following provides the computed value:

Where:

AT is measured RCS AT, °F (measured by hot leg and cold leg RTDs).

AT 0 is the loop specific indicated AT at ATP, °F.

s is the Laplace transform operator, sec*1*

)"is the measured RCS average temperature, °F.

T' is the loop specific indicated Tavg at ATP, °F s; 572.0°F.

. P is the measured pressurizer pressure, p~ig.

P' is the nominal RCS operating pressure, ;;?: 2235 psig.

K1s;1.26

't1 ;;?: 25.0 sec K2 ;;?: 0.022/°F t2 s3.0 sec f1(AI) = 4.00[ -15.75 - (qt-qb)J 0%of ATP

+3.33[(qt - qb) - 6.9]

K3 ~ 0.00070/psi when qt - qb s-15.75% ATP when -15. 75% ATP < qt - qb s; 6.9% ATP when qt-qb > 6.9% ATP Where-qt and qb are percent ATP in the upper and lower halves of the core, respectively, and qt+ qb is the total THERMAL POWER in percent ATP.

CORE OPERATING LIMITS REPORT (Page 1 of 1)

OVERPOWER.AT ALLOWABLE VALUE No: 3-GRAPH-RPC-16 Rev: 9 Page 8 of 12 The Overpower AT Function Allowable Value SHALL NOT exceed the Technical Specification Table 3.3.1-1, Note 2 value.

The following provides the computed value:

Where:

AT is measured A.CS £\\T, °F (measured by hot leg and cold leg RTDs).

t.iT0 is the loop specific indicated AT at ATP, °F; s is the Laplace transform operator, sec~

1 T is the measured RCS average temperature, °F.

T" is the loop specific indicated Tavg at ATP, °F ~ 572.0°F.

Kt s 1.1 O

  • Ks ~ 0.0175/°F for increasing T Ks ~ 0.0015/°F when T > T" "t'3 ~ 10 sec f2(AI} = 0 0/°F for decreasing T 0/°F when T s T..

CORE OPERATING LIMITS REPORT No: 3-GRAPH-RPC-16 Page 9 of 12 Figure 1

' Reactor Core Safety Limit - Four Loops in Operation (Page 1 of 1) 544 1-r--;r--1-1--1--+--t--1-- -

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~------.................. ---1_...*__..__.___.__,_._,_*_,__.__._ ___ _._......_.....__ ___ _._-l--'--1 to 100 JJD 120 Reactor Power (Percent of 3216 MWt)

[ConservatJve relat.lve to 3188.4 MWt; use as*ls for operation at 3188.4 MWt]

Rev: 9

CORE OPERATING LIMITS REPORT No: 3-GRAPH-RPC-16 Rev: 9 230 220 210 200 190 180 170 c:

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CORE OPERATING LIMITS REPORT No: 3-GRAPH-RPC-16 Page 12 of 12 Figure 4 Axial Flux Difference Envelope Limits (Page 1 of 1) 100-.-~~~~~~~~.---.r1r=======r======;==;=====~

Pawer Level TeCll Spec Envelope 95 90

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-10 0

10 20 30 40 Axial Flux Difference Rev: 9

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