NL-17-043, Core Operating Limits Report for Cycle 20

Core Operating Limits Report for Cycle 20

ML17110A216
Person / Time
Site:	Indian Point
Issue date:	04/13/2017
From:	Vitale A Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-17-043
Download: ML17110A216 (14)

Text

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 NL-17-043 April 13, 2017

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U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike, TWFN-2F1 Rockville, MD 20852-2738

SUBJECT:

Core Operating Limits Report for Cycle 20 Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64

Dear Sir or Madam:

Entergy Nuclear Operations, Inc. (Entergy) as holder of License No. DPR-64 is providing in the Enclosure a copy of the Core Operating Limits Report (COLR) for Indian Point Nuclear Generating Unit No. 3 Cycle 20. 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, AJV/rl

Enclosure:

3-GRAPH-RPC-16, Revision: 10 Core Operating Limits Report 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

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J ENCLOSURETO NL-17-043 3-GRAPH-RPC-16, Revision: 10 Core Operating Limits Report

'I ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKE,:T NO. 50-286

~Entergy Procedure Use Is:

Control Copy: _ _ __

Effective Date: tt / E>} 2o '~

!'fuclear !'fortheast Ii:!' Continuous D Reference Page 1 of 12 D Information This Procedure is Quality Related Approved By:

Team3B Procedure Owner

\,

PARTIAL REVISION

No: 3-GRAPH-RPC-16 Rev: 10 CORE OPERATING LIMITS REPORT Page 2of12 REVISION

SUMMARY

(Page 1 of 1) 1.0 REASON FOR REVISION 1.1 Incorporate Cycle 20 changes. (EC-63102).

1.2 LBDR #3-COLR-2017-001 2~ SUMMARVOFCHANGES 2.1 Made minqr editorial changes.

2.2 Implemented TOC & TS Header changes to make uniform with actual TS titles.

2.3 Revised NOTE above TS 2.1.1 .for Cycle 20 and revised "Safety Evaluation" to "an eval~ation".

l 2.4 Revised TS 3. 1.3 - Changed "-3pcm" to "Predictive Correction".

2.5 Revised CAUTION in TS 3.4.1 - "572°F" to "570°F", "should" to "SHALL", deleted second sente,nce. Also reversed order of a.& b. substeps for TS consistency .

.2.6 . Revised Attachment 1 & 2 - Overtemperature AT & Overpower. AT "Where:"

substeps for TS consistency. * -.. *,.:**:* .':~'.*.

No: 3-GRAPH-RPC-16 Rev: 10 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) .................................................... :............................. I 4

TS 3.1.3 Moderator Temperature Coefficient {MTC) ................................................ ;............. 4 TS 3.1.5 Shutd.own 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 (F~H) ..................................................... 5 TS 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Constant Axial Offset Control (CAOC)

Methodolc:>gy) ............................................. .-............................................................................... 6 TS 3.3.1 Reactor Protection System (RPS) Instrumentation .... .'............................................. 6 TS 3.4.1 RCS Presswe, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits .................................................................. .'.............................. ~ .......................... :~ ......... 6 TS 3.9.1 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 ...................................................................................... 1o Figure 3 Hot Channel Factor Normalized Operating Envelope~ ............................. :.............. 11 Figure 4 Axial .Flux Difference Envelope Limits .................................................................... 12

No: 3-GRAPH-RPC-16 Rev: 10 CORE OPERATING LIMITS REPORT Page 4of12 NOTE The data presented in this report applies to Cycle 20 ONLY and may NOT be used for I.

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 an 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 MARGIN (SOM)

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

TS 3.1.3 Moderator Temperature Coefficient (MTC)

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

The MTG 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 MTG SHALL be calculated using the algorithm contained in WCAP-13749-P-A:

Revised Predicted MTC = Predicted MTG + AFD Correction + Predictive Correction If the Revised Predicted MTG is less negative than the SR 3.1.3.2 300 ppm surveillance limit and all the benchmark data contained in 1the surveillance procedure are met, then an MTG measurement in accordance wit~ SR 3.1.3.2 is not required to be performed.

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No: 3-GRAPH-RPC-16 Rev: 10

. CORE OPERATING- LIMITS REPORT Page 5of12 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 katt;:::: 1.0 are as indicated in Figure 2. Control Bank Insertion Limits apply to the step_ counter demand position. '1 .

• 'Each control bank shall be considered fully withdrawn at~ 225 steps.

TS 3.2.1 Heat Flux Hot Channel Factor <Fa (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 Fa.

IF P > .5, Fa(Z) :::; (2.~0 IP) x.K(Z)

IF P :::; .5, Fa(Z) ~ (4.60) x K(Z)

TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F~Hl NOTE

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

F~H ~ 1.65 { 1 + 0;3 ( 1 - p ) }

No: 3-GRAPH-RPC-16 Rev: 10 CORE OPERATING LIMITS REPORT Page 6of12 TS 3.2.3 AXIAL FLUX DIFFERENCE CAFDl (Constant Axial Offset Control CCAOCl 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 CRPSl Instrumentation 1.. Overtemperature AT Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Fun.ction 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 CDNB) Limits The following DNB related parameters are applicable in MODE 1:

CAUTION The RCS loop T avg limit SHALL be decreased one degree for each degree that the full power Tavg is less than 570°F.

a. Pressurizer Pressure~ 2204 psig

b. Reactor Coolant System loop Tavg ::;; 574. 7°F for fuJI power T avg= 570.0°F

c. Reactor Coolant System Total Flow Rate;::: 364,700 gpm TS 3.9.1 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 ma.rgin ;::: 5% Ak/k.

• No: 3-GRAPH-RPC-16 Rev: 10 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 compute<! value:

Where: AT is measured RCS AT, °F.

AT0 is the indicated AT at RTP, °F.

s is the Laplace transform operator, sec-1.

Tis the measured RCS average temperature, °F.

T' is the nominal Tavg at RTP, ~ 572.0°F. i I

P is the measured pressurizer pressure, psig.

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

K1~1.26 K2 ~ 0.022/°F Ks ~ 0.00070/psig

't1 ;:::: 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) - 6.9] when qt - qb > 6;9% 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.

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No: 3-GRAPH-RPC-16 Rev: 10 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 [~ - Ks [(-css)/(1 + -rss)](T) - Ks(T - T) - h(AI)]

Where: AT is measured RCS AT, °F.

AT0 is the indicated AT at RTP, 0 f.

s is the Laplace transform operator, sec-1 .

Tis the measured RCS average temperature, '0 f.

11 T is the nominal Tavg at RTP,:::;; 572.0°F.

~:::;; 1.10 Ks~ 0.0175/0 f for increasing Tavg Ks ~ 0.0015/0 f when T > T" 11 0/°F for decreasing Tavg 0/°F when T :::;; T . /

'ts ~ 10 sec f2(AI) = 0

No: 3-GRAPH-RPC-16 Rev: 10 CORE OPERATING LIMITS REPORT Page 9 of 12 Figure 1

'*Reactor Core Safety Limit- Four Loops in Operation (Page 1 of 1) 680 2!17 11si :r u .;:.. _~C ~E Pl Al SL:

r--......._

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• - -,.. 111 -- -

.,,I 660 ,_.,. ., I

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500 10 20 30 40 so 60 70 80 90 100 110 120 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: 10 CORE OPERATING LIMITS REPORT Page 10of12 Figure 2 Rod Bank Insertion Limits (Page 1 of 1)

(Four Loop Operation) 104 Step Overlap 230 I . I I , I 1* I 34.3,230 I . ~

220 I

76.3,230:

I 210. I ~

200 I ,I I ~

190 180 ~

.BANKS:

,I  : 100,176 f

-s:

c: 170 I

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,I

~ 160

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.r:. 150 J

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t::::

. 140 ,I ~

en *~

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.;  : BANKC ,,I

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+;

0 "Ci) 0 110 100

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~ 90 .; BANKO I c:

m , I .' I C!l 80

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I- ~ 0,0 : I

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42,0 II 0 10 20 30 40 50 60 70 80 90 100 Power (Percent of 3188.4 MWt)

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No: 3-GRAPH-RPC-16 Rev: 10 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

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N 1

a.:

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ca 0.8 u.

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ca

• FQ= 2.30 Cl>

a. 0.6 FQ k(z) Elev (ft}

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2.30 .1.0 0.0 ca 2.30 1.0 6.0

...0 E 0.4 2.30 1.0 12.0 z_

0.2 0

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

No: 3-GRAPH-RPC-16 Rev: 10 CORE OPERATING LIMITS REPORT Page 12 of 12 Figure 4 Axial Flux Difference Envelope Limits *

{Page 1 of 1)

,,*' . ., Pcll.\ferlevel Teen spec Envelope

• 90 -11.0 11.0 80 -1'6.0 16.0 70 -21.0 21-0 60 -26.0 26.0 50 -31.0 31.0 AJO

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