NL-18-020, Core Operating Limits Report for Cycle 24

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Core Operating Limits Report for Cycle 24
ML18107A214
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 04/10/2018
From: Vitale A
Entergy Nuclear Northeast
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-18-020
Download: ML18107A214 (14)
v • d • e


Text

-===* Entergy:

NL-18-020 April 10, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Dear Sir or Madam:

Core Operating Limits Report for Cycle 24 Indian Point Nuclear Generating Unit No.2 Docket No. 50-247 License No. DPR-26 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 Entergy Nuclear Operations, Inc. (Entergy) as holder of License No. DPR-26 is providing in the Enclosure a copy of the Core Operating Limits Report (COLR) for Indian Point Nuclear Generating Unit No. 2 Cycle 24. 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:

2-GRAPH-RPC-6, Revision: 19 Core Operating Limits Report cc:

I Mr. David Lew, Acting Regional Administrator, NRC Region 1 Mr. Richard V. Guzman, Senior Project Manager, NRR/DORL, NRC Ms. Alicia Burton, 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-18-020 2-GRAPH-RPC-6, Revision: 19 Core Operating Limits Report ENTERGY NUCLEAR OPERATIONS, INC.

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

=-Entergy Nuclear Northeast J.

2-GRAP.

COREOPER Approved By:

Team2A Procedure Owner Procedure Use Is:

Iii Continuous D Reference a Information Control Copy:. ___

Effective Date: 'flzt~I b This procedure is Quality Related Page 1 of 12

  • ion 19

. FIT (COLR)

PARTIAL REVISION

CORE OPERATING LIMITS REPORT (COLR) 1.0 REASON FOR REVISION REVISION

SUMMARY

(Page 1 of 1)

No: 2-GRAPH-RPC-6 Rev: 19 Page 2 of 12 1.1 Incorporate EC-70606 changes for LBDCR # U2-COLR-2018-01 as directed by LR-LAR-2014-00082 CA-9.

2.0

SUMMARY

OF CHANGES 2.1 Editorial and Formatting changes (no rev bars).

No: 2-GRAPH-RPC-6 Rev: 19 CORE OPERATING LIMITS REPORT (COLR)

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) Instrumentation......................................... 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:

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

No: 2-GRAPH-RPC-6 Rev: 19 CORE OPERATING LIMITS REPORT (COLA)

Page 4 of 12 NOTE The data presented in this report applies to Cycle 24 ONLY and may NOT be used for other cycles of operation. Changes to the following sections, attachments, and figures are administratively controlled in accordance with Technical Specifications Section 5.6.5. Any technical change to this document may require an evaluation to be performed in accordance with 1 OCFR 50.59.

TS 2.1.1 Reactor Core Sls In MODES 1 and 2, 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% dk/k.

TS 3.1.3 Moderator Temperature Coefficient (MTC)

The MTC upper limit SHALL be ~ 0.0 Ak/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 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 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: 2-GRAPH-RPC-6 Rev: 19 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.

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 (Fg(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 F0.

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 (~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 ) }

L ___ _

No: 2-GRAPH-RPC-6 Rev: 19 CORE OPERATING LIMITS REPORT (COLR)

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. 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:

CAUTION The following RCS T AVG limits SHALL be decreased one degree for each degree that the full power T AVG is less than 565°F. For example, if the full power T AVG 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 ~ressure ~ 2216 psia

b.

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

c.

Reactor Coolant System Total Flow Rate~ 348,300 gpm TS 3.9.1 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

~ 2050 ppm or that which is sufficient to provide a shutdown margin ~ 5% Ak/k.

CORE OPERATING LIMITS REPORT (COLR)

(Page 1 of 1)

Overtemperature AT Allowable Value No: 2-GRAPH-RPC-6 Rev: 19 Page 7 of 12 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 (measured by hot leg and cold leg RTDs).

AT o is the loop specific indicated AT at RTP, °F.

s is the Laplace transform operator, sec*1*

T is the measured RCS average temperature, °F.

T' is the loop specific indicated T avg at RTf>, s 572 °F.

P is the measured pressurizer pressure, psig.

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

K1 S: 1.22

't1 ~ 25 sec K2 ~ 0.020/°F

't2 ~ 3 sec

. f1(£1I) = -1.97 {30 + (qt - qb)}

Oo/oof RTP 2.25 {(qt - qb) - 7}

Ks ~ 0.00070/ psig when q. - qb ~ -30% RTP when -30% RTP < qt - qb ~ 7% RTP 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.

CORE OPERATING LIMITS REPORT (COLR)

Overpower AT Allowable Value (Page 1 of 1)

N9: 2-GRAPH-RPC-6 Rev: 19 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 RCS AT, °F.

AT o is the loop specific indicated AT at RTP, °F.

sis the Laplace transform operator, sec*1*

T is the measured RCS average temperature, °F.

,.., is the loop specific indicated T avg at RTP, s 572 °F.

~s 1.074 ta:2'!10sec Ks :2'! 0.0188/°F for increasing T avg 0/°F for decreasing T avg Ks :2'! 0.0015/°F when T > r

0/°F when T s T"

l, No: 2-GRAPH-RPC-6 CORE OPERATING LIMITS REPORT (COLR) 660 640 620 600 580 560 Page 9 of 12 Figure 1 Reactor Core Safety Limit - Four Loops in Operation (Page 1 of 1) 2440psla ACCEPTABLE CONSEQUENCES UNACCEPTABLE CONSEQUENCES 540+-........ _._+-........ _._+-........ _._-+--'......... _._+-'__..._._....... __..._.._........ __........._.

0

.2

,4

,6

,8 1.2 FRACTION OF RATED POWER Rev: 19

No: 2-GRAPH-RPC-6 Rev: 19 CORE OPERATING LIMITS REPORT (COLR) 225 - ":::;j P"1 (6.6, 223)

~

BANKB I (0, 209.1) 200

-! 175 a:

C I 150 f § z

125 0 E U)

. 0 l:L 100

~

~'

m (0, 86.1)

C 75 0 a:

50 25 0

0 10 Page 10 of 12

~

~ I Figure 2 Rod Bank.Insertion Limits (Four Loop Operation}

100 Step Overlap (Page 1 of 1}

(64.9, 223) I

~

I.,

BANKC

~

~

~

BANKO 1 (17.5, 0)

I

'f' 20 30 40 50 60 70 80 Power Lev~I (Percent of Rated Power)

I 100, 174)..

90 100

No: 2-GRAPH-RPC-6 Rev: 19 CORE OPERATING LIMITS REPORT (COLR) 1.2

~

1

~ 0.8 as

u.

a, C *-

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as 0.6 Cl)

CL,,

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N *--as E

0.4 0 z 0.2 0

0 Page 11 of 12 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 2

4 6

8 10 Core Height (ft) 12

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

Page 12 of 12 Figure 4 Axial Flux Difference Envelope Limits (Page 1 of 1)

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f.

. :1

  • Power Level
  • Tech* Spec:' Envelope..
  • 90

-11.0 11.0 80

-16.0 16.0 70

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-31.0 31.0

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10 20.

30 40'

-Axial Flux Difference Rev: 19

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