NL-08-114, Revised Core Operating Limits Report for Indian Point Unit 2

Revised Core Operating Limits Report for Indian Point Unit 2

ML082040580
Person / Time
Site:	Indian Point
Issue date:	07/11/2008
From:	Robert Walpole Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-08-114
Download: ML082040580 (13)

Text

SEntergy Enteray Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 July 11, 2008 Re: Indian Point Unit 2 Docket No. 50-247 NL-08-114 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Revised Core Operating Limits Report for Indian Point Unit 2

Dear Sir/Madam:

Please find attached Core Operating Report (COLR) for Indian Point Unit 2 Cycle 19 in accordance with the Indian Point 2 Technical Specifications 5.6.5.d. Enclosure 1 provides the cycle-specific operating limits for the operation of Indian Point Unit 2.There are no new commitments being made in this submittal.

If you have any questions or require additional information, please contact my office at (914) 734-6710.Sincerely Robert W. Walpole Manager, Licensing Indian Point Energy Center Enclosure 1: Indian Point 2 COLR -Cycle 19 cc: Mr. Samuel J. Collins, Regional Administrator, NRC Region I Mr. John Boska, Senior Project Manager, NRC NRR DORL NRC Resident Inspector's Office, Indian Point 2-4c O-D /LA4 ENCLOSURE 1 TO NL-08-114 Indian Point 2 Cycle 19 COLR ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247 NEntergy Nuclear Northeast Procedure Use Is: o Continuous o Reference EZ Information Control Copy: Effective Date: 12%Page 1 of 11 2-GRAP1H#RPC-6, Revision:

12 CORE OPERATING LIMITS REPORT (COLR)This procedure is excluded from further Li--100 Reviews Approved By: Procedurd Sponsor, RPO/Team Staff-Procedure Owner Designee Date PARTIAL REVISION Indian Point Unit 2 Cycle 19 COLR Page 2I of I I TABLE OF CONTENTS SI ECTION PAGE TS 2.0 Safety Limits (SLs) .........................................

3 TS 3.1.1 Shutdown Margin (SDM) ........................................................................................

3 TS 3.1.3 Moderator Temperature Coefficient (MTC) .......................................................

3 TS 3.1.5 Shutdown Bank Insertion Limits .........................................................................

3 TS 3.1.6 Control Bank Insertion Limits .................................................................................

4 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FAH ..................................................

4 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)M ethodo logy) ........................................................................................................

..4 TS 3.3.1 RPS Instrumentation

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5 TS 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (D N B ) L im its ..................................................................................................................

5 TS 3.9.1 Refueling Boron Concentration

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5 ATTACHMENTS:

Attachment 1 Overtemperature AT & Overpower AT Allowable Values .....................

6 FIGURES Figure 1 Reactor Core Safety Limit -Four Loops in Operation

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8 Figure 2 Rod Bank Insertion Limits ...................................................................................

9 Figure 3 Hot Channel Factor Normalized Operating Envelope ......................

10 Figure 4 Axial Flux Difference Envelope Limits .................................................................

11 Indian Point Unit 2 Cycle 19 COLR Page 3 of II TS 2.0 Safety Limits (SLs)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 19 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 Safety Limits (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 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 1 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.

Indian Point Unit 2 Cycle 19 COLR Page 4 of 11 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.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 Fa.IF P > .5, FQ(Z) < (2.50/ P) x K(Z)IF P .5, FQ(Z) _ (5.00) x K(Z)TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor FNH FNH< 1.70 { 1 + 0.3(1- P)}TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)Methodologv)

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 19 COLR Page 5 of 11 TS 3.3.1 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 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 - 568.1OF and highest loop TAVG- 571 .'IF 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, Refuel 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 19 COLR Page 6 of II 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 Technical Specification 3.3.1.A T A{To K, (1+ K2s 'S)[T'T']+K,(P" P')-f,(AI)}( 1 + T 2 S)Where: AT is measured RCS AT, 'F (measured by hot leg and cold leg RTDs).AT 0 is the loop specific indicated AT at RTP, OF.s is the Laplace transform operator, sec-'.T is the measured RCS average temperature, OF.T' is the loop specific indicated TAVG at RTP, IF.P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, > 2235 psig K1 < 1.22 K2 > 0.020/°F K3 _> 0.00070/psig x, 1 > 25 sec T 25 3 sec f 1 (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 19 COLR Page 7 of II Attachment 1 (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 Technical Specification 3.3.1.AT <-AT,, KK.5 (1 3 s) T -K,(T-T')-f,(A Where: AT is measured RCS AT, OF.ATo is the loop specific indicated AT at RTP, °F.s is the Laplace transform operator, sec 1.T is the measured RCS average temperature, OF.T is the loop specific indicated TAVG at RTP, OF.K4< 1.074 K5 > 0.01 88/°F for increasing TAVG O/0 F for decreasing TAVG K6 > 0.0015/°F when T > T" 0/°F when T< T-3 _ 10 sec f 2 (AI) = 0 Indian Point Unit 2 Cycle 19 COLR Page 8 of II Figure 1 Reactor Core Safety Limit -Four Loops in Operation (Page 1 of 1.)680 -2440 psia UNACCEPTABLE OPERATION 660 640 620 a/> 2250 psla ca 600 --~2000 psia 1860 psia 580 ACCEPTABLE 560 OPERATION 540 FRACTION OF RATED POWER Indian Point Unit 2 Cycle 19 COLR Page 9 of II Figure 2 Rod Bank Insertion Limits (Four Loop Operation) 100 Step Overlap (Page I of 1)4 cc 0.P CL, z M 0 zr 225 200 175 150 125 100 75 (66 ',23 ;j (6~ ~ 66 --)BA :KB:: IA 7 :_-::I I 00e7 I v" i0I NKCil I B I I 0 , : I I 1OF: : 00,'. : : :: : .I: .- -1): : _00: 1 1,00 1 -. .of A OF : r: : _-50 25 0 0 .10 20 30 40 50 60 70 Power Level (Percent of Rated Power)80 90 100 Indian Point Unit 2 Cycle 19 COLR Page 10 of I I Figure 3 Hot Channel Factor Normalized Operating Envelope (For S. G. Tube Plugging up to 10%)(Page 1 of I)1.2 1.0 N 1-1 0 UL CL"a 4.N E 0 z 0.8 0.6 0.4 0.2 0 0 2 4 6 8 Core Height (ft)10 12 Indian Point Unit 2 Cycle 19 COLR Page II of II Figure 4 Axial Flux Difference Envelope Limits (Page I of 1)100 95 90 85"° 80 0 fl 75 70 65 60 55 50-40 20 -10 0 10 20 30 40 Axial Flux Difference