to 2-graph-rpc-6, rev. 14, core operating limits report (colr) · enclosure 1 to nl-12-022...

EntergyEntergy Nuclear NortheastIndian Point Energy Center450 Broadway, GSBP.O. Box 249Buchanan, N.Y. 10511-0249Tel (914) 254-6710

Robert WalpoleLicensing Manger

NL-12-022

April 3, 2012

U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001

SUBJECT: Revised Core Operating Limits ReportIndian Point Nuclear Generating Unit No. 2Docket No. 50-247License No. DPR-26

Dear Sir or Madam:

Enclosure 1 to this letter provides Entergy Nuclear Operations Core Operating LimitsReport (COLR) for Indian Point 2 Cycle 21. This report is submitted in accordance withTechnical Specification 5.6.5.d.

There are no new commitments contained in this letter. If you have any questions or requireadditional information, please contact me at 914-254-6710.

Sincerely,

RW/mb

cc: next page

ACLE,

NL-12-022Docket No. 50-247

of 2

Enclosure: 1. 2-GRAPH-RPC-6, Rev. 14, Core Operating Limits Report (COLR)

cc: Mr. William Dean, Regional Administrator, NRC Region 1Mr. John Boska, Senior Project Manager, NRC NRR DORLIPEC NRC Resident Inspector's OfficeMr. Francis J. Murray, President and CEO, NYSERDA (w/o enclosure)Mrs. Bridget Frymire, New York State Department of Public Service

ENCLOSURE 1 TO NL-12-022

2-GRAPH-RPC-6, Rev. 14,Core Operating Limits Report (COLR)

ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT UNIT 2 NUCLEAR POWER PLANT

DOCKET No. 50-247

NEnoteasNuclear Northeast

Procedure Use Is:

n Continuous

0 Reference

0 Information

Control Copy:

Effective Date: jZ1.-2o/a.

Page 1 of 12

CORE 0

Approved By:

, ý.I- (ý I eA4WProcedure Sponsor, Rý

Team StaffProcedure Owner

PARTIAL REVISION

REVISION SUMMARY(Page 1 of 2)

1.0 REASON FOR REVISION

1.1 Incorporate Cycle 21 changes per EC 22302 (NF-IP-1 1-38)

2.0 SUMMARY OF CHANGES

2.1 Updated applicable cycle to cycle 21 in introductory statement on page 4.[Editorial 4.6.13]

2.2 The COLR MTC upper limit (TS 3.1.3) was changed from < 0.0 Ak/k/0F to

< 0.0 Ak/k/°F to be consistent with Technical Specifications. [Editorial 4.6.13]

2.3 Added "g" to "psig" for variable K3 in Attachment 1 of COLR. [Editorial 4.6.13]

Indian Point Unit 2Cycle 21 COLRPage 3 of 12

TABLE OF CONTENTS

SECTION PAGE

TS 2.1.1 Reactor Core SLs ....................................................................................... 4

TS 3.1.1 Shutdown Margin (SDM) ............................................................................ 4

TS 3.1.3 Moderator Temperature Coefficient (MTC) ............................................... 4

TS 3.1.5 Shutdown Bank Insertion Limits ................................................................ 4

TS 3.1.6 Control Bank Insertion Limits ..................................................................... 5

TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) ....................................................... 5TS 32.2 Nucear nthlpyRiseHotCha nelFactor (FANH) ...................................... ...... 5TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Fatr NFH

TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)M ethodology) ............................................................................................ . . 5

TS 3.3.1 Reactor Protection System (RPS) Instrumentation .................................... 6

TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from NucleateBoiling (D N B) Lim its ................................................................................... 6

TS 3.9.1 Refueling Boron Concentration .................................................................. 6

Attachments:

Attachment 1

Attachment 2

Figures:

Figure 1

Figure 2

Figure 3

Figure 4

Overtemperature AT Allowable Value ......................................... 7

Overpower AT 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


The data presented in this report applies to Cycle 21 ONLY and may NOT be used forother cycles of operation. Any technical change to this document requires a SafetyEvaluation to be performed in accordance with 10 CFR 50.59.

TS 2.1.1 Reactor Core SLs

In MODES 1 and 2, the combination of thermal power level, pressurizer pressure, andhighest 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 CoolantSystem average temperature and power level is at any time above the appropriatepressure line.

TS 3.1.1 Shutdown Margin (SDM) /

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

TS 3.1.3 Moderator Temperature Coefficient (MTC)

The MTC upper limit SHALL be •0.0 Ak/k/IF 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@ 0 ppm

TS 3.1.5 Shutdown Bank Insertion Limits

The Shutdown Banks SHALL be fully withdrawn when the reactor is in MODE 1 andMODE 2. Shutdown Banks with a group step counter demand position _ 223 steps areconsidered fully withdrawn because the bank demand position is above the top of theactive fuel.


TS 3.1.6 Control Bank Insertion Limits

The Control Bank Insertion Limits for MODE 1 and MODE 2 with keff > 1.0 are as indicatedin 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 (Fo(Z))

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 FQ.

IF P> .5, FQ(Z) < (2.50/P) x K(Z)

IF P< .5, FQ(Z) < (5.00) x K(Z)

TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNH)

NOTE

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

FNH < 1.70 {1+0.3(1-P)}

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 ofFigure 4, as required by TS 3.2.3.


TS 3.3.1 Reactor Protection System (RPS) Instrumentation

1. Overtemperature AT

2. Overpower AT

Allowable Value as referenced in Technical SpecificationsTable 3.3.1-1, Function 5, Note 1.Refer to Attachment 1.

Allowable Value as referenced in Technical SpecificationsTable 3.3.1-1, Function 6, Note 2.Refer to Attachment 2.

TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from NucleateBoiling (DNB) Limits

The following DNB related parameters are applicable in MODE 1:

a. Reactor Coolant System average TAVG < 568.1°F and highest loop TAVG < 571.1OFfor full power TAVG of 565.0°F

b. Pressurizer Pressure Ž 2216 psiac. 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 theRCS, Refueling Canal, and Reactor Cavity SHALL be the more restrictive of either_> 2050 ppm or that which is sufficient to provide a shutdown margin > 5% Ak/k.

Indian Point Unit 2

Cycle 21 COLRPage 7 of 12

Attachment 1(Page 1 of 1)

Overtemperature AT Allowable Value

The Overtemperature AT Function Allowable Value SHALL NOT exceed the TechnicalSpecification Table 3.3.1-1, Note 1 value.

The following provides the computed value:

AT <AT0 Ki-K2(I+ r+s) IT-Ti +K 3 (P -P)-f(A}

Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).

AT 0 is the loop specific indicated AT at RTP, OF.

s is the Laplace transform operator, sec1 .

T is the measured RCS average temperature, OF.

T' is the loop specific indicated Tavg at RTP, < 572 OF.

P is the measured pressurizer pressure, psig.

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

K1 < 1.22 K2 -> 0.020/°F K3 _> 0.00070/ psigt1; 2! 25 sec T2 < 3 sec

fd(Al) = -1.97 {30 + (qt - qb)) when qt - qb:< -30% RTP0% of RTP when -30% RTP < qt - qbt <7% RTP2.25 {(qt - qb) - 7) when qt - qb > 7% RTP

Where qt and qb are percent RTP in the upper and lower halves of the core,respectively, and qt + qb is the total THERMAL POWER in percent RTP.


Attachment 2(Page 1 of 1)

Overpower 'AT Allowable Value

The Overpower AT Function Allowable Value SHALL NOT exceed the TechnicalSpecification Table 3.3.1-1, Note 2 value.

The following provides the computed value:

AT < AToK4-Ks('33s T - K 6 (T-T")-f 2 (AI)}

Where: AT is measured RCS AT, OF.

ATo is the loop specific indicated AT at RTP, OF.

s is the Laplace transform operator, sec1.

T is the measured RCS average temperature, OF.

T is the loop specific indicated Tavg at RTP, < 572 OF.

K4 < 1.074 K5 Ž 0.0188/°F for increasing Tavg K 6 > 0.0015/°F when T >O/OF for decreasing Tavg 0/1F when T < T"

T3 -Ž 10 sec

f2(AI) = 0

Indian Point Unit 2

Cycle 21 COLRPage 9 of 12

Figure 1

Reactor Core Safety Limit - Four Loops in Operation

(Page 1 of 1)

680

2440 psla

UNACCEPTABLE

660 CONSEQUENCES

640

620

> 2250 psia

6002000 psla

1860 psia

580

ACCEPTABLE560 +...

540

FRACTION OF RATED POWER


Figure 2Rod Bank Insertion Limits

(Four Loop Operation)100 Step Overlap

(Page 1 of 1)

225

200

• 175

150Zn0uI-

z 125

05(00a- 100

z

0 75M

(6.6,223BANK B

(0, 2 9.i-

or

J • 4

BANK C

J OF

i i

50

25

0

V1

I I I I 1 1 1 (17.5,0)

40 50 60 70 80 90 100 10 20 30 0Power Level (Percent of Rated Power)


Figure 3

Hot Channel Factor Normalized Operating Envelope(For S. G. Tube Plugging up to 10%)

(Page 1 of 1)

1.2 --

0.0,1.0001.0 -,, ,- -,, ,,,,- ,,,, ,_

12.0, 0.925

N 0.8

U

u. 0.6

Cu

-0.4

NIF = 2.50, - F_-_q kz Elev (ft)

0 2.50 1.0 0.0E 2.50 1.0 6.00 0.2 - - 2.31 0.925 12.0Z

0 '-'

0 2 4 6 8 10 12

Core Height (ft)


Figure 4Axial Flux Difference Envelope Limits

(Page 1 of 1)

95

90

85

80

0

70

65

60

55

50

-40 -30 -20 -10 0 10 20 30 40

Axial Flux Difference

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