NL-14-057, Submittal of Core Operating Limits Report Cycle 22

Submittal of Core Operating Limits Report Cycle 22

ML14112A476
Person / Time
Site:	Indian Point
Issue date:	04/09/2014
From:	Robert Walpole Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-14-057
Download: ML14112A476 (15)

Text

- En tergy Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 Tel (914) 254-6710 Robert Walpole Licensing Manager NL-14-057 April 9, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

SUBJECT:

Core Operating Limits Report Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26

Dear Sir or Madam:

to this letter provides Entergy Nuclear Operations Core Operating Limits Report (COLR) for Indian Point 2 Cycle 22. This report is submitted in accordance with Technical Specification 5.6.5.d.

There are no new commitments contained in this letter. If you have any questions or require additional information, please contact me.

Sincerely, RW/ai cc: next page

-Acof Pip

NL-14-057 Docket No. 50-247 Page 2 of 2

Enclosure:

1. 2-GRAPH-RPC-6, Rev. 16, Core Operating Limits Report (COLR) cc:

Mr. William Dean, Regional Administrator, NRC Region 1 Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL IPEC NRC Resident Inspector's Office Mr. John B. Rhodes, President and CEO, NYSERDA (w/o enclosure)

Mrs. Bridget Frymire, New York State Department of Public Service (w/o enclosure)

ENCLOSURE 1 TO NL-14-057 2-GRAPH-RPC-6, Rev. 16, Core Operating Limits Report (COLR)

ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT UNIT 2 NUCLEAR POWER PLANT DOCKET No. 50-247

Y NuclEntes Nuclear Northeast Procedure Use Is:

[3 Continuous 0 Reference

!0 Information Control Copy:

Effective Date:

3/is/If Page 1 of 12

£ 2-GRAPH-RPC-6, Revision: 16 CORE OPERATING LIMITS REPORT (COLR)

Approved By:

Date Procedure Sponsor, RPO / Designee Team Staff Procedure Owner PARTIAL REVISION

REVISION

SUMMARY

(Page 1 of 2) 1.0 REASON FOR REVISION 1.1 Incorporate Cycle 22 changes. The only changes to the COLR are updating the cycle number.

2.0

SUMMARY

OF CHANGES 2.1 Changed note prior to TS 2.1.1 from Cycle 21 to Cycle 22.[Editorial 4.6.4]

Indian Point Unit 2 Cycle 22 COLR 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...................................................................

4 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)

M ethodo logy).............................................................................................

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

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

6 TS 3.9.1 Refueling 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 Lim its........................................................

10 Hot Channel Factor Normalized Operating Envelope................ 11 Axial Flux Difference Envelope Limits......................................

12

Indian Point Unit 2 Cycle 22 COLR Page 4 of 12 The data presented in this report applies to Cycle 22 ONLY and may NOT be used for other cycles of operation.

Any technical change to this document requires a Safety Evaluation 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, 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 (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/°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@

0 ppm 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 _Ž 223 steps are considered fully withdrawn because the bank demand position is above the top of the active fuel.

Indian Point Unit 2 Cycle 22 COLR Page 5 of 12 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 > 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, 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 (FNH)

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

FH <- 1.65 (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 of Figure 4, as required by TS 3.2.3.

Indian Point Unit 2 Cycle 22 COLR Page 6 of 12 TS 3.3.1 Reactor Protection System (RPS) Instrumentation

1. Overtemperature AT

2. Overpower AT Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1.

Refer to Attachment 1.

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 average TAVG --

< 568.1 0F and highest loop TAVG -- 571.1°F for full power TAVG of 565.0'F

b.

Pressurizer Pressure _> 2216 psia

c.

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 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.

Indian Point Unit 2 Cycle 22 COLR Page 7 of 12 (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:

{(1+

r s) [T_-..

/)

AT <ATo KI-K2 (1+ r~s) [T-T' +K3 I(A Where:

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

AT0 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, 2> 2235 psig.

K1,

1.22 K2 -> 0.020/°F K3 >- 0.00070/ psig 25 sec t 2 < 3 sec fl(AI) =

-1.97 {30 + (qt - qb)}

when qt - qb!<-30% RTP 0% of RTP when -30% RTP < qt - qb!-< 7% RTP 2.25 {(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.

Indian Point Unit 2 Cycle 22 COLR Page 8 of 12 (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!A o

4K r3s 7T-K6 (T -T") -.f (A/,)

AT*<ATojK 4 -K(I+ z 3 s)~

(/+ 1-3S)

J 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 > 0.01 88/°F for increasing Tavg K 6 > 0.001 5/°F when T > T 0/°F for decreasing Tavg 0/1F when T < T" C3 Ž 10 sec f2(AI) = 0

Indian Point Unit 2 Cycle 22 COLR Page 9 of 12 Figure 1 Reactor Core Safety Limit - Four Loops in Operation (Page 1 of 1) 680 2440 psia UNACCEPTABLE 660 CONSEQUENCES 640 620 2250 psia 600 oa 2000 psia 1860 psia 580 ACCEPTABLE 560 CONSEQUENCES 540 F

I FRACTION OF RATED POWER

Indian Point Unit 2 Cycle 22 COLR Page 10 of 12 Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 100 Step Overlap (Page 1 of 1) 0 a.

z 0~

0I-0 z

00 225 200 175 150 125 100 75 23)

BA K 8 (0, 209.1-)

OF

'00,11

ýoT_00. 174T.

Ole-NK CBýNK Ole FT__1 jor

'100 iý00

'00, If I

OF OF 011 1

(0, 86. 1) j O-e BANK D-,

.100

'100 A4 OF I L 1_1 L I I I Z

_LL LLU 50 25 0

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

1.2 N

0 I.0-LL C

N E

0 Z

1 0.8 0.6 0.4 Indian Point Unit 2 Cycle 22 COLR 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 kWz)

Elev (ft) 2.30 1.0 0.0 2.30 1.0 6.0 2.30 1.0 12.0 0.2 0

0 4

10 12 2

6 8

Core Height (ft)

Indian Point Unit 2 Cycle 22 COLR Page 12 of 12 Figure 4 Axial Flux Difference Envelope Limits (Page 1 of 1) 100 95 90 85 80 75 0~

70 65 60 55 50

-40

-30

-20

-10 0

10 20 30 40 Axial Flux Difference