ML19106A052

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Submittal of Core Operating Limits Report for Cycle 21
ML19106A052
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 04/04/2019
From: Vitale A
Entergy Nuclear Northeast
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
3-GRAPH-RPC-16, Rev. 11
Download: ML19106A052 (14)
v • d • e


Text

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Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-0249 Tel (914) 254-6700 Anthony J Vitale Site Vice President NL-19-034 April 4, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Core Operating Limits Report for Cycle 21 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 21. 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/mm

Enclosure:

3-GRAPH-RPC-16, Revision: 11 Core Operating Limits Report cc: Mr. David Lew, Regional Administrator, NRC Region 1 Mr. Richard V. Guzman, Senior Project Manager, NRR/DORL, NRC Ms. Alicia Barton, President and CEO, NYSERDA (w/o Attachment)

  • Ms. Bridget Frymire, New York State Dept. of Public Service (w/o Attachment)

NRC Resident Inspector's Office

ENCLOSURE TO NL-19-034 3-GRAPH-RPC-16, Revision: 11 Core Operating Limits Report ENTERGY NUCLEAR OPERATIONS, INC.

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

AE

~

  • ntergy

- Procedure Use Is:

Control Copy: _ _ __

ii Continuous Effective Date: %3[:Jo.lf:f'.

r,..ruclear :t'ilortheast D Reference Page 1 of 12 D lnfonnation This Procedure is Quality Related Approved By:

o-*- -0 Team38 Perat\o'O' Procedure Owner PARTIAL REVISION

No: 3-GRAPH-RPC-16 Rev: 11 CORE OPERATING LIMITS REPORT Page 2 of 12 REVISION

SUMMARY

(Page 1 of 1) 1.0 REASON FOR REVISION 1.1 Incorporate Cycle 21 changes. (EC-76679).

1.2 LBDR #3-COLR-2019-001 2.0

SUMMARY

OF CHANGES 2.1 Made minor editorial changes.

2.2 Revised TS 2.1.1 and NOTE per markup.

2.3 Revised TS 3.1.3 per markup.

2.4 Revised TS 3.1.5 per markup.

2.5. Revised TS 3.1.6 per markup.

2.6 Revised TS 3.4.1 per markup.

2.7 Revised TS 3.9.1 per markup.

No: 3-GRAPH-RPC-16 Rev: 11 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 (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 {F~H) ..................................................... 5

  • TS* 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Constant Axial Offset Control (CAOC)

Methodology) ............: ....................................................................:......................................... 6 TS 3.3.1 Reactor Protection System (RPS) lnstrument~tion .: ................................................ 6 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits ...... ,..................................................~ .............................................................................. 6 TS 3.9.1 Boron Concentration ................................................................................................ 6 ATTACHMENTS Attachment 1 OVERTEMPERATURE '1T ALLOWABLE VALUE ........................................... 7 Attachment 2 OVERPOWER '1T 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: 11 CORE OPERATING LIMITS REPORT  ;*

Page 4 of 12 NOTE The data presented in this report applies to Cycle 21 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. Changes to this document are administratively controlled in accordance with Technical Specification Section 5.6.5.

TS 2.1.1 Reactor Core Sls In MODES 1 and 2, the combination of thermal power level, Reactor Vessel inlet temperature, and pressurizer pressure SHALL NOT exceed the limits shown ih 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% Llk/k.

TS 3.1.3 Moderator Temperature Coefficient {MTC}

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

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

-38.0 pcm/°F @ 300 ppm boron

-44.5 pcm/°F @ 60 ppm boron

-47.0 pcm/°F @ 0 ppm boron The Revised Predicted near EOL 300 ppm MTC SHALL be calculated using the algorithm contained in WCAP-13749-P-A:

Revised Predicted MTC = Predicted MTC + AFD Correction + -3 pcm/°F If the Revised Predicted MTC is less negative than the SR 3.1.3.2 300 ppm surveillance limit and all the 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.

No: 3-GRAPH-RPC-16 Rev: 11 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 in MODE 2 with any cqntrol bank not fully inserted. 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 ~ 225 steps.

Control Bank withdrawal sequence is A-B-C-D. The insertion sequence is the reverse of the withdrawal sequence.

TS 3.2.1 Heat Flux Hot Channel Factor {Fg (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.

IF P > .5, Fa(Z) S (2.30 / P) 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 (F:Hl NOTE P is the fraction of Rated Thermal Power (ATP) at which the core is operating.

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

No: 3-GRAPH-RPC-16 Rev: 11 CORE OPERATING LIMITS REPORT 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 Reactor Protection System (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. Ov~rpower 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 CAUTION The RC_S loop Tavg limit SHALL be decreased one degree for each degree that the*

full power Tavg is less than 570°F..

The following DNB related parameters are applicable in MODE 1:

a. Pressurizer Pressure ~ 2204 psig
b. Reactor Coolant System loop Tavg s; 574.7°F for full power Tavg = 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 Reactor Coolant System and the refueling cavity (which includes the refueling canal) 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: 11 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:

Where: AT is measured RCS AT, °F.

AT0 is the indicated AT at RTP, °F.

s is the Laplace transform operator, sec*1.

T is the measured RCS average temperature, °F.

T' is the nominal Tavg at RTP, S 572.0°F.

P is the measured pressurizer pressure, psig.

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

K1 s 1.26 K2 ~ 0.022/°F Ka ~ 0.00070/psig

't1 ~ 25.0 sec 't2 s 3.0 sec f1(AI) = 4.00[ -15.75 *- (qt - qb)] when qt- qb s-15.75% RTP 0% of RTP when -15.75% RTP < qt-qb s 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.

No: 3-GRAPH-RPC-16 Rev: 11

, CORE OPERATING LIMITS REPORT Page 8 of 12 Attachment 2 (Page 1 of 1)

OVERPOWER .&T ALLOWABLE VALUE The Overpower .&T Function AllowaQle Value SHALL NOT exceed the Technical Specification Table 3.3.1-11 Note 2 value. *

  • The following provides the computed value:

4 T S, ATo [Ki - Ks [(t3s)/(1 + t3S)](T) - Ks(T - T') - f2(AI)]

Where: AT is measured RCS AT1°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, s 572.0°F.

Ki S 1.10 Ks ~ 0.0175/°F for increasing Tavg Ks ~ 0.0015/°F when T > r" 0/°F for decreasing Tavg 0/°F when T s r" t3 ~ 10 se~

f2(AI) = 0

No: 3-GRAPH-RPC-16 Rev: 11 CORE OPERATING LIMITS REPORT Page 9 of 12

,. Figure 1 Reactor Core. Safety Limit - Four Loops in Operation (Page 1 of 1) 680 247 01 *si a uN, .c CE P1 Al Ile

.._ I ,. ,.,.. s t:r :a.1 "p I II ~

660 r...... ~ .

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...... ....... 7 ........ I

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r--,.... f""',.. .... I

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r 1-520 II' :1

'. *- - ... NI i;t: t, 600 0 10 30 so 60 70 80 IIO 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: 11 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 I I ,. I I I 34.3,230 I I : 76.3,230:

220 I

,.I 210 I 200 I

,I '

I 190 I

,.,I ' I

-e 180 I I

BANKB I I  : 100.116 I

C 170

,.I ' ~

== I I

,I 160

,I ' ~

"C

.r::. 150

,.I ' ,I

~ ,'I en 140 ~

I a.

I Q) en 130

J I '

120 0,126 I

~

BANKC ,I C

.Q

t:::

110 ,I

, I

~

en 0

a..

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100 90

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, I BANKO I

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C ca 80 ~

CD

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"C 70 0 ~

a: , I 60 ~

50 , I I

I 40 30 I

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~ I 20 , I I

I I-' i 10 I I 0,0 : I I 42,0 I 0

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

No: 3-GRAPH-RPC-16 Rev: 11 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 1

~.

.e ""

I C.>

0.8 IL C)

~

C a.

Cl) 0.6 FQ FQ =2.30 k(z) Elev (ft)

'C Cl) 2.30 1.0 0.0

  • -'ii N

2.30 1.0 6.0 E 0.4 2.30 1.0 j2.0

""0 z

0.2 0

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

No: 3-GRAPH-RPC-16 Rev: 11 CORE OPERATING LIMITS REPORT Page 12 of 12 Figure 4 Axial Flux Difference Envelope Limits (Page 1 of 1)

I PowerLevef Tech Spec Envelope I .% .  %

90 -11.0 11.0 I

I BO 70

-16.0

-21.0 16.0 21.0 I 60 -26.0 26.0 i 50 ~1.0 31.0 I

I

.UNACCEP.TABLE UNACCEPTABLE

  • oPERATION., *, ,- -*OPE~T19~ ....

ACCEPTABLE OP.ERATION

.t 60

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50 ...: - ............-...--...-..-......-...~*',._....,....__""""""....-.........------_,,.~-.,,t

-40 -30 -20 -10 0 10 20 40 Axlal Flux Difference *

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