NL-15-052, Revised Core Operating Limits Report for Cycle 19

Revised Core Operating Limits Report for Cycle 19

ML15118A747
Person / Time
Site:	Indian Point
Issue date:	04/21/2015
From:	Coyle L Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-15-052 3-GRAPH-RPC-16, Rev. 7
Download: ML15118A747 (15)

Text

Enterqy Nuclear Northeast Indian Point Energy Center Entergy 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel (914) 254-6700 Lawrence Coyle Site Vice President NL-15-052 April 21, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Revised Core Operating Limits Report for Cycle 19 Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64

Dear Sir or Madam:

This letter provides Entergy Nuclear Operations, Inc.'s Revised Core Operating Limits Report for Indian Point Nuclear Generating Unit No. 3 Cycle 19 changes. This report is submitted in accordance with Technical Specification 5.6.5.d.

There are no new commitments being made in this submittal. If you have any questions or require additional information, please contact Mr. Robert W. Walpole, Regulatory Assurance Manager at (914) 254-6710.

Sincerely,

Enclosure:

3-GRAPH-RPC-16, Revision: 7 Core Operating Limits Report A-ow oe-L

NL-1 5-052 Docket No. 50-286 Page 2 of 2 cc: Mr. Daniel H. Dorman, Regional Administrator, NRC Region I Mr. Douglas Pickett, NRC, Sr. Project Manager, Division of Reactor Licensing NRC Resident Inspector's Office Ms. Bridget Frymire, New York State Department of Public Service Mr. John B. Rhodes, President and CEO, NYSERDA (w/o enclosure)

ENCLOSURE TO NL-15-052 3-GRAPH-RPC-16, Revision: 7 Core Operating Limits Report ENTERGY NUCLEAR OPERATIONS, INC.

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

OEntergy Procedure Use Is: Control Copy:

Nuclear Northeast 0 Continuous Effective Date: 3//(, i5

[O Reference o Information Page 1 of 12 3-GRAPH-RPC-1.6, Revision: 7 CORE OPERATING LIMITS REPORT Approved By:

A4 KU 1A Procedure Sponsor, DM/Designee..

/

Date,

. ./

.7 Team 3B PratiO.

Procedure Owner PARTIAL REVISION

No: 3-GRAPH-RPC-16 Rev: 7 CORE OPERATING LIMITS REPORT Page 2 of 12 REVISION

SUMMARY

(Page 1 of 1) 1.0 REASON FOR REVISION 1.1 Incorporate Cycle 19 changes. The only change from the Cycle 18 COLR is an update to the applicable cycle number. (EC-45206) 2.0

SUMMARY

OF CHANGES 2.1 Changed reference from Cycle 18 to Cycle 19 in NOTE prior to TS 2.1 .1.

(EC-45206) [Editorial 4.6.13]

2.2 Deleted unnecessary bracket from F delta I formula in Attachment 1 Overtemperature Delta T Allowable Value

No: 3-GRAPH-RPC-16 Rev: 7 CORE OPERATING LIMITS REPORT Page 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 .......................................................... ;............... 5 TS 3.1.6 Control Bank Insertion Limits ........................................................................... 5 TS 3.2.1 Heat Flux Hot Channel Factor (Fo(Z)) ................................................................ 5 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 RPS Instrumentation ........................................................................................ 6 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Lim its ...................................................................................................................................... 6 TS 3.9.1 Refueling Boron Concentration ...................................................................... 6 ATTACHMENTS Attachment 1 OVERTEMPERATURE AT ALLOWABLE VALUE .................................... 7 Attachment 2 OVERPOWER AT ALLOWABLE VALUE ................................................. 8 FIGURES Figure 1 Reactor Core Safety Limit - Four Loops in Operation .................................. 9 Figure 2 Rod Bank Insertion Limits ............................................................................. 10 Figure 3 Hot Channel Factor Normalized Operating Envelope ................................. 11 Figure 4 Axial Flux Difference Envelope Limits ........................................................... 12

No: 3-GRAPH-RPC-16 Rev: 7 CORE OPERATING LIMITS REPORT 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 performed in accordance with 10 CFR 50.59.

TS 2.1.1 Reactor Core SLs In MODE 1 and 2, the combination of thermal 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 Vessel inlet temperature and power level is at any time above the appropriate pressure line.

TS 3.1.1 Shutdown Marain (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/lF at hot zero power.

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

-38.0 pcm/OF @ 300 ppm

-44.5 pcm/°F @ 60 ppm

-47.0 pcm/°F @ 0 ppm

No: 3-GRAPH-RPC-16 Rev: 7 CORE OPERATING LIMITS REPORT 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 keff > 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 > 225 steps.

TS 3.2.1 Heat Flux Hot Channel Factor (F_(_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, Fo(Z) < (2.30/ P) x K(Z)

IF P < .5, FQ(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 (RTP) at which the core is operating.

FH 5*1.65 { 1 +0.3(1- P) }

No: 3-GRAPH-RPC-16 Rev: 7 REPORT CORE OPERATING LIMITS Page 6 of 12 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)

Methodoloyv)

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 AT Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1 Refer to Attachment 1

2. Overpower AT 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:

a. Reactor Coolant System loop Tavg < 576.7 0 F for full-power Tavg = 572.0°F

b. Pressurizer Pressure Ž_2204 psig

c. Reactor Coolant System Total Flow Rate Ž 364,700 gpm TS 3.9.1 Refueling Boron Concentration When required by Technical Specification 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 _>5% Ak/k.

No: 3-GRAPH-RPC-16 Rev: 7 CORE OPERATING LIMITS REPORT Page 7 of 12 Attachment 1 (Page 1 of 1)

OVERTEMPERATURE AT ALLOWABLE VALUE The Overtemperature AT Function Allowable Value SHALL NOT exceed the Technical Specification Table 3.3.1-1, Note 1 value.

The following provides the computed value:

AT < AT. [K1 - K2 [(1 + T1 s)/(l + T2s)] (T - T') + K3 (P - P') - f1(AI)]

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

AT, 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, °F < 572.0°F.

P is the measured pressurizer pressure, psig.

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

K1 < 1.26 K2 > 0.022/°F K3 Ž-0.00070/psi

,ci > 25.0 sec T2 < 3.0 sec f1(AI) = 4.00[ -15.75 - (qt - qb)] when qt - qb < - 15.75% RTP 0% of RTP when -15.75% RTP < qt - qb < 6.9% RTP

+3.33[(qt - qb) - 6.91 when qt - qb > 6.9% RTP I 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.

No: 3-GRAPH-RPC-16 Rev: 7 CORE OPERATING LIMITS REPORT Page 8 of 12 Attachment 2 (Page 1 of 1)

OVERPOWER AT ALLOWABLE VALUE 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:

AT *< ATo [K4 - K5 [(T3s)/(1 + t 3s)](T) - K6 (T - T) - f2 (AI)]

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

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, 0F < 572.0°F.

K4 < 1.10 K5s 0.0175/OF for increasing T K6 > 0.0015/°F when T > T 0/°F for decreasing T O/°F when T < T T3 ->10 sec f 2(AI) = 0

No: 3-GRAPH-RPC-16 Rev: 7 CORE OPERATING LIMITS REPORT Page 9 of 12 Figure 1 Reactor Core Safety Limit - Four Loops in Operation (Page 1 of 1) 6W0 U..

0 0

a.

cc 0 10 20 30 Q0 50 60 70 80 90 0o 110 '20 Reactor Power (Percent of 3216 MWt)

[Conservative relative to 3188.4 MWt; use as-is for operation at 3188.4 MWt]

No: 3-GRAPH-RPC-16 Rev: 7 CORE OPERATING LIMITS REPORT Page 10 of 12 Figure 2 Rod Bank Insertion Limits (Page 1 of 1)

(Four Loop Operation) 104 Step Overlap 230 220 210 200 190 180 170 160 CL 150 140 Cl) 130 120 0.

CL) 110 Cz 100 0 90 0r 80 70 60 50 40 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 Power (Percent of 3188.4 MWt)

No: 3-GRAPH-RPC-16 Rev: 7 CORE OPERATING LIMITS REPORT Page 11 of 12 Figure 3 Hot Channel Factor Normalized Operating Envelope (For S. G. Tube Plugging up to 10%)

(Page 1 of 1) 1.2 N 1 0

I-0.8 Li-C.)

cc ______FQ =2.30 0.6 o

FQ k~z Elev (ft)

N

____2.30 1.0 0.0 2.30 1.0 6.0 E 0.4 -2.30 1.0 12.0 0

Z 0.2 0

0 2 4 6 8 10 12 Core Height (ft)

No: 3-GRAPH-RPC-16 Rev: 7 CORE OPERATING LIMITS REPORT Page 12 of 12 Figure 4 Axial Flux Difference Envelope Limits (Page 1 of 1)

CIO) 04 0~

CL.

0 0-

-40 -30 -20 -10 0 10 20 30 40 Axial Flux Difference