NL-05-022, Cycle 17 Core Operating Limit Report (COLR)

Cycle 17 Core Operating Limit Report (COLR)

ML050550110
Person / Time
Site:	Indian Point
Issue date:	02/16/2005
From:	Conroy P Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-05-022
Download: ML050550110 (14)

Text

Enteray Nuclear Northeast Indian Point Energy Center 450 Broadway. Suite 1 Entergy P.O. Box 249 Buchanan, NY 10511-0249 Patric Conroy Manager, Licensing Tel 914 734 6668 February 16, 2005 Re: Indian Point Unit 2 Docket No. 50-247 NL-05-022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, DC 20555-0001

Subject:

Indian Point Unit 2 Cycle 17 Core Operating Limit Report (COLR)

Dear Sir:

In accordance with the Indian Point 2 Technical Specifications 5.6.5.d, enclosed is the Indian Point 2 COLR for Cycle 17.

There are no new commitments being made in this submittal.

If you have any questions or require additional information, please contact Patric Conroy, Manager, Licensing at (914) 734-6668.

Sincerely, Patri Conroy Manager, Licensing Indian Point Energy Center Enclosure #1 - Indian Point 2 COLR - Cycle 17 cc: next page AOD(

NL-05-022 Docket 50-247 Page 2 of 2 cc: Mr. Patrick D. Milano, Senior Project Manager Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2 Washington, DC 20555-0001 Mr. Samuel J. Collins Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Senior Resident Inspector's Office Indian Point Unit 2 Nuclear Power Plant U.S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Resident Inspector's Office Indian Point Unit 3 U.S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511-0337

ENCLOSURE 1 TO NL-05-022 Indian Point 2 Cycle 17 COLR ENTERGY NUCLEAR OPERATIONS, INC.

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

I. I Procedure Use Is: Control Copy:

o Ente-rgy Continuous Effective Date: /' 300 Nuclear Northeast O Reference Page Iof 11 E Information

08 CORE 0 G LIMIT rS T (COLR)

This procedure is excluded from fi Mviews Approved By:

P edure Sponsor, DM/Designee Team Staff Procedure Owner PARTIAL REVISION

i. . .

Core Operating Limits Report (COLR) No: 2-GRAPH-RPC-6 Rev: 08 Page 2 of 11 Revision Summary 1.0 REASON FOR REVISION 1.1 Update document to reflect new Cycle 17 Core Operating Limits Report Revision 1 per Reactor Engineering request.

2.0

SUMMARY

OF CHANGES 2.1 Modified Attachment I (Page 1 of 2) per Reactor Engineering Markup.

2.2 Modified Attachment 1 (Page 2 of 2) per Reactor Engineering Markup

Core Operating Limits Report (COLR) No: 2-GRAPH-RPC-6 Rev: 08 Page 3 of 11 TABLE OF CONTENTS SECTION PAGE TS 2.0 Safety Limits (SIs ) ......................................................................... 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 (FQ(Z)) ......................................................................... 5 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FN ......................................................................... 5 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC) Methodology) ............... 5 TS 3.3.1 RPS Instrumentation ......................................................................... 6 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ......6 TS 3.9.1 Refueling Boron Concentration ......................................................................... 6 ATTACHMENTS Attachment 1 Overtemperature AT & Overpower AT Allowable Values .................................................... 7 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

Core Operating Limits Report (COLR) No: 2-GRAPH-RPC-6 Rev: 08 Page 4 of 11 NOTE The Technical Specification references shown next to each Factor OR Limit in this COLR, are there to identify the corresponding sections in the Technical Specifications, that refer to the COLR.

The data presented in this report applies to Cycle 17 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 2.0 Safety Limits (SLs)

In MODE 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 Mar-in (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/JF at hot zero power.

The MTC lower limit SHALL be > -36.5 pcmlF @ 300 ppm

> -43.0 pcm/F @ 60 ppm

> -45.5 pcm/F @ Oppm Reference Graph RV-12 for cycle specific predicted MTC.

TS 3.1.5 Shutdown Bank Insertion Limits The Shutdown Banks SHALL be fully withdrawn WHEN the Reactor is in MODE I AND MODE 2. Shutdown Banks with a group step counter demand position > 221 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 2 1.0 are as indicated in Figure 2. Control Bank Insertion Limits apply to the step counter demand position.

TS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

NOTE K(Z) is the fraction given in Figure 3 AND Z is the core height location of FQ.

IF P > .5, Fo(Z) * (2.50 /P) x K(Z)

IF P* .5, Fo(Z) < (5.00 )x K(Z)

TS 3.2.2 Nuclear Enthaloy Rise Hot Channel Factor FAH NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.

FAH*1.70 {1+0.3(1-P))

TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOCI Methodology The Indicated Axial Flux Difference limit is the Target Band; i.e., the Target +/-5%

The Axial Flux Difference Envelope Limits at 90 percent power are -11%, + 11% AND increase by--1% and +1%, for each 2% of rated power below 90% power, as indicated by Graph RV-10, Unit 2 Target Flux Values.

TS 3.3.1 RPS Instrumentation

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

Refer to Attachment I

2. OverDower AT Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 6, Note 2.

Refer to Attachment 1 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 < 565.1OF and highest loop Tsvg< 568.1'F

b. Pressurizer Pressure Ž 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, Refuel Canal AND Reactor Cavity SHALL be the more restrictive of either 2 2050 ppm OR that which is sufficient to provide a shutdown margin Ž 5% Ak/k.

Attachment 1 (Page 1 of 2)

Overtemperature AT The Overtemperature AT Function Allowable Value SHALL NOT exceed the following:

NOTE For limitations on the maximum trip setpoint see Tech Spec 3.3.1 AT*AT.{K,-K((+' T.s)[T-T ]+K,( P--f,(AI)}

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

ATo is the loop specific indicated AT at RTP, "F.

s Is the Laplace transform operator, sect.

T is the measured RCS average temperature, "F.

T' Is the loop specific indicated Tevg at RTP, "F.

P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, 2 2235 psig Ki s 1.22 K2Ž 0.02010 F K3Ž 0.00070/psig x, 2 25 sec 52<3 sec fj(AI) = -1.97 (30 + (qt- qb)} when qt - qbS - 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 + qo is the total THERMAL POWER in percent RTP.

Attachment I (Page 2 of 2)

Overpower AT The Overpower AT Function Allowable Value SHALL NOT exceed the following:

NOTE For limitations on the maximum trip setpoint see Tech Spec 3.3.1 A T < A T.{K-K(

K.) K, 1 -K.(T-T")-f.(A1)jT Where: AT is measured RCS AT, IF.

ATO is the loop specific indicated AT at RTP, "F.

s is the Laplace transform operator, sec'.

T Is the measured RCS average temperature, "F.

T is the loop specific Indicated Tavg at RTP, OF.

K4

• 1.074 Ks2 0.01 8810F for increasing Tag Ks > 0.001510 F when T>T O/0F for decreasing Tavg O/PF when T T'

¶3

• 10 sec f 2 (AI)=

Figure 1 Reactor Core Safety Limit - Four Loops in Operation 2440 psla UNACCEPTABLE OPERATION 05 64 1860 ps 56a--OPRTN 1880 pasi 580-ACCEPTABLE 550 OPERATION FRACTION OF RATED POWER

Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 100 Step Overlap 225 I I

i - 1 MM&M" 0 W W 3 . . . . . . . . . . r . I . I . . . . . . . . .

- - - - - - - - - - - - - 3 . . . . . . . . . . .

200 175 9-150 9-125 0.-

z I 100 I 0

I 75 I

a I

50 25 nv 0 10 . 20 30 40 50 60 70 80 90 100 Power Level (Percent of Rated Power)

Figure 3 Hot Channel Factor Normalized Operating Envelope (For SG Tube Plugging up to 10%)

1.2 1.0 a)

? 0.8 0

0L a'

lL 0 0.6 N

Cu 0

0.4 N

• 0.2 0

0 2

• 4 6 8 10 12 Core Elevation (feet)

. . .