NL-07-060, Revised Core Operating Limits Report
| ML071410432 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/15/2007 |
| From: | Jones T Entergy Nuclear Indian Point 3, Entergy Nuclear Northeast |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| NL-07-060 | |
| Download: ML071410432 (42) | |
Text
EnterMy Nuclear Northeast Indian Point Energy Center
---Entergy 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 T.R. Jones Manager, Licensing Tel 914 734 6670 May 15, 2007 Re: Indian Point Unit 3 Docket No. 50-286 NL-07-060 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Revised Core Operating Limits Report for Indian Point Unit 3
Dear Sir/Madam:
Please find the Core Operating Report (COLR) for Indian Point Unit 3 Cycle 15 in Enclosure 1.
The COLR complies with the Indian Point 3 Technical Specifications (TS) 5.6.5.d including the cycle-specific operating limits required for the operation of Indian Point Unit 3. Also, two mid-cycle revisions to the Cycle 14 COLR are provided in Enclosure 2. This transmittal provides the information required by TS 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. T.R. Jones, Manager, Licensing at (914) 734-6670.
Manager, Licensing Indian Point Energy Center : Indian Point 3 COLR - Cycle 15 : Indian Point 3 COLR - Cycle 14 Mid-Cycle Revisions 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 3 A1{wI
ENCLOSURE 1 TO NL-07-060 Indian Point 3 Cycle 15 COLR ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
NcEntergy--- Procedure Use Is: Control Copy:
Nuclear Northeast EI Continuous Effective Date:
0 Reference El Information Page 1 of 11 3-G VU- I )n: 0 CORE C TING LIMITS CYCLE 15
'0*
Approved By:
/ ,y /'ý 11-11, 1
Proce6re Sponsor, DM/De Team 3B e raO Procedure Owner NEW PROCEDURE
No: 3-GRAPH-RPC-16 Rev: 0 CORE OPERATING LIMITS FOR CYCLE 15 Page 2 of 11 TABLE OF CONTENTS Section Title Paae Pane 1.0 TS 2.1.1 SAFETY LIMITS (SLS) .................................................................. 3 2.0 TS 3.1.1 SHUTDOWN MARGIN (SDM) ................................ 3 3.0 TS 3.1.3 MODERATOR TEMPERATURE COEFFICIENT (MTC) ............... 3 4.0 TS 3.1.5 SHUTDOWN BANK INSERTION LIMITS ..................................... 4 5.0 TS 3.1.6 CONTROL BANK INSERTION LIMITS ........................................ 4 6.0 TS 3.2.1 HEAT FLUX HOT CHANNEL FACTOR (Fo(Z)) ............................ 4 7.0 TS 3.2.2 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (FNAH) ....... 4 8.0 TS 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (CONSTANT AXIAL OFFSET C O NTRO L (CAO C ) .................................................................................... 5 9.0 TS 3.3.1 RPS INSTRUMENTATION .......................................................... 5 10.0 TS 3.4.1 RCS PRESSURE, TEMPERATURE AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS .............................................. 5 11.0 TS 3.9.1 REFUELING BORON CONCENTRATION ................................... 5 Figures and Attachments:
FIGURE 1, REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION ...... 6 FIGURE 2, ROD BANK INSERTION LIMITS vs RATED THERMAL POWER ...... 7 FIGURE 3, HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE ...... 8 FIGURE 4, AXIAL FLUX DIFFERENCE ENVELOPE LIMITS ................................. 9 OVERTEMPERATURE AT/ OVERPOWER AT .................................... 10
No: 3-GRAPH-RPC-16 Rev:0 CYCLE 15 CORE OPERATING LIMITS FOR Page 3 of 11 NOTE The Core OperatingLimits Report (COLR), including any mid-cycle revisions or supplements thereto, SHALL be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
The data presented in this report applies to Cycle 15 ONLY and SHALL NOT be used for other cycles of operation. Any technical change to this document requires a Safety Screen OR Evaluation to be performed in accordance with 10 CFR 50.59.
> The Technical Specification (TS) references shown next to each Factor OR Limit in this COLR, are there to identify the corresponding sections in TS, which refer to the COLR.
1.0 TS 2.1.1 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, REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION. 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.
2.0 TS 3.1.1 Shutdown Margin (SDM)
The SDM SHALL be greater than or equal to 1.3 % Ak/k (MODE 2, 3, 4 and 5 with Keft < 1.0).
3.0 TS 3.1.3 Moderator Temperature Coefficient (MTC)
MODE 1, 2 with Keff >_1.0: MTC upper limit SHALL be < 0.0 Ak/k/°F at hot zero power MODE 1, 2 and 3 : MTC lower limit SHALL be > -38.0 pcm/OF @ 300 ppm
>-44.5 pcm/°F @ 60 ppm
> -47.0 pcm/0 F @ 0 ppm The Cycle 15 NuPOP may be referenced for the predicted MTC.
No: 3-GRAPH-RPC-16 Rev: 0 CORE OPERATING LIMITS FOR CYCLE 15 Page 4 of 11 4.0 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 (Mode 2 with any Control bank not fully inserted). Shutdown Banks with a group step counter demand position > 225 steps are considered fully withdrawn due to the bank demand position being above the top of the active fuel. (Not applicable during SR 3.1.4.2).
5.0 TS 3.1.6 Control Bank Insertion Limits The Control Banks Insertion Limits for MODE 1 and MODE 2 with KEFF > 1.0 are as indicated in Figure 2, ROD BANK INSERTION LIMITS vs RATED THERMAL POWER.
Control Bank Insertion Limits apply to step counter demand position (Not applicable during SR 3.1.4.2).
Control Bank Overlap Pattern: MODE 1 and MODE 2 with KEFF > 1. (TS 3.1.6.B)
Withdraw: A, B, C, D Insert : D, C, B, A Control Bank Overlap (TS 3.1.6.B): 104 steps Control Bank Fully Withdrawn Position (TS 3.11.6.B): 230 steps 6.0 TS 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))
NOTE K(Z) is the fraction given in FIGURE 3, HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE, AND Z is the core height location of Fa.
MODE 1: IF P > .5, Fo(Z) < (2.50 / P) x K(Z)
IF P < .5, Fa(Z) 5 (5.00) x K(Z) 7.0 TS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN ýH.
NOTE P is the fraction of Rated Thermal Power (RTP) at which the core is operating.
MODE 1:
FN*H< 1.70 {1 + 0.3 ( 1 - P)
No: 3-GRAPH-RPC-16 Rev: 0 CYCLE 15 CORE OPERATING LIMITS FOR Page 5 of 11 8.0 TS 3.2.3 Axial Flux Difference (AFD) (Constant Axial Offset Control (CAOC)
MODE 1 with RTP > 15%, the Indicated limit is the Target Band; i.e., the Target + 5%.
The AFD SHALL be maintained within the acceptable operation limits of Figure 4, AXIAL FLUX DIFFERENCE ENVELOPE LIMITS, as required by TS 3.2.3.
9.0 TS 3.3.1 RPS Instrumentation MODE 1 and MODE 2:
As per Attachment 1, OVERTEMPERATURE AT/ OVERPOWER AT:
Overtemperature AT: Allowable Value as referenced in Technical Specifications Table 3.3.1-1, Function 5, Note 1. REFER TO Attachment 1.
Overpower AT
- Allowable Value as referenced in Technical Specifications Table 3.3.1 -1, Function 6, Note 2. REFER TO Attachment 1.
10.0 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 < 572.0°F and highest loop TAVG < 576.70 F
- b. Pressurizer Pressure __2204 psig
- c. Reactor Coolant System Total Flow Rate _ 364,700 gpm 11.0 TS 3.9.1 Refueling Boron Concentration MODE 6:
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
No: 3-GRAPH-RPC-16 Rev: 0 CORE OPERATING LIMITS FOR CYCLE 15 Page 6 of 11 FIGURE 1 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION (Page 1 of 1) 680 620 600 660 660 10 20 30 40 50 60 70 80 90 100 110 70O Reactor Power (Percent of 3216 MWt)
No: 3-GRAPH-RPC-16 Rev: 0 CORE OPERATING LIMITS FOR CYCLE 15 Page 7 of 11 FIGURE 2 ROD BANK INSERTION LIMITS vs RATED THERMAL POWER (Page 1 of 1)
(Four Loop Operation) 104 Step Overlap 230 220 34.3,2306.323
-76.34,223 7; 210 200 190 -. BAN B 1 Ej 180 170 160 CL 150 0,12t -- B--A K-
..... -~- -- - .. - ~- ,,. - -
140 U) 130 (0 120 110 0.
0) cc) 100 90 7......... ...-..-- - ------ +/--- ......
80
....... T - ------
70 60 42,0 50 40 30 20 10 0
0 10 20 30 40 50 60 70 80 90 100 Power (% of Rated Thermal Power)
No: 3-GRAPH-RPC-16 Rev: 0 CORE OPERATING LIMITS FOR CYCLE 15 Page 8 of 11 FIGURE 3 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE (Page 1 of 1)
(For S/G Tube Plugging up to 10%)
1.2 0.0, 1.00 6.0, 1.00 1 wI 1.,0.9251 0.8 - ...........
"s 0.6 A.... .........
N 0.4 ......
0.2 0
0 2 4 6 8 10 12 Core Elevation (feet)
No: 3-GRAPH-RPC-16 Rev: 0 CORE OPERATING LIMITS FOR CYCLE 15 Page 9 of 11 FIGURE 4 AXIAL FLUX DIFFERENCE ENVELOPE LIMITS (Page 1 of 1)
I C
1~~
0 0~
'V 30 -20 -10 0 10 20 30 40 Axial Flux Difference
No: 3-GRAPH-RPC-16 Rev: 0 FOR CYCLE 15 CORE OPERATING LIMITS Page 10 of 11 ATTACHMENT 1 OVERTEMPERATURE AT/ OVERPOWER AT (Page 1 of 2)
The Overtemperature AT Function Allowable Value SHALL not exceed the following:
NOTE For limitations on the maximum trip Set point, see Technical Specification 3.3.1.
AT < ATo { K1 - K2 [(1 + T1S)/(1 + T 2S)] (TAVG - T') + K3 (P - P') - f1(AI) )
Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
ATo is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec'.
TAVG is the measured RCS average temperature, OF.
T' is the loop specific indicated TAVG at RTP, OF < 572.0 OF.
P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, > 2235 psig KI *1.26 K2 > 0.022/OF K3 > 0.00070/psig
,i Ž25.0 sec T2 - 3.0 sec fl(AI) = -4.00{15.75 + (qt- qb)} when qt - qb < - 15.75% RTP 0% of RTP when -15.75% RTP < qt - qb *- 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: 0 FOR CYCLE 15 CORE OPERATING LIMITS Page 11 of 11 ATTACHMENT 1 OVERTEMPERATURE AT/ OVERPOWER AT (Page 2 of 2)
The Overpower AT Function Allowable Value SHALL not exceed the following:
NOTE For limitations on the maximum trip Set point, see Technical Specification 3.3.1.
AT < ATo { K4 - K5 [(,t 3 s)/(1 + t3S)](TAvG) - K6(TAVG - T') - f2 (AI) )
Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs),
ATo is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec1 .
TAVG is the measured RCS average temperature, OF.
T" is the loop specific indicated TAVG at RTP, OF < 572.0 OF.
K4 < 1.10 K5 ->0.0175/°F for increasing TAVG K6 > 0.0015/°F when TAVG > T" 0/0 F for decreasing TAVG 0/°F when TAVG < T" T3 = 10 sec f2 (AI) = 0
ENCLOSURE 2 TO NL-07-060 Indian Point 3 Cycle 14 COLR Mid-Cycle Revisions ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286
Procedure Use Is: Control Copy:
-"- g 0 Continuous Nuclear Northeast 0 Reference Effective Date: 31L/,?bo(P
[3 Information Page 1 of 14 3-POP-2.3, Revision 16 CORE OPEANG LIMITS .OR.CYCLE14 Approved By:
Procedure Sponsor, D.M/I Team 3B Procedure Owner EDITORIAL REVISION
REVISION
SUMMARY
(Page 1 of 1) 1.0 REASON FOR REVISION 1.1 Corrected t3 expression T3 >- 10 sec. (CR-IP3-2005-05151, Editorial 4.6.13).
2.0
SUMMARY
OF CHANGES 2.1 Changed the value T3 for Overpower AT on Attachment 5 from t3 > 10 sec to T3 = 10 sec. to ensure Unit 3 Technical Specifications, The Unit 3 Core Operating Limits Report and 3-POP-2.3 are consistent until Unit 3 Technical Specifications are corrected. (CR-IP3-2005-05151, Editorial 4.6.13).
No: 3-POP-2.3 Rev: 16 CORE OPERATING LIMITS FOR CYCLE 14 Page 3 of 14 TABLE OF CONTENTS Section Title Page 1.0 P UR P O S E ............................................................................................... . . 4 2.0 PRECAUTIONS AND LIMITATIONS .......................................................... 4 3.0 PR ER EQ U IS ITES ....................................................................................... 4 4.0 P R O C ED U R E ............................................................................................. 5 5.0 D E FIN IT IO N S ............................................................................................. 8 6.0 RE FE R EN C ES ........................................................................................... 8 7.0 RECORDS AND DOCUMENTATION ........................................................ 8 Attachments , CONTROL ROD INSERTION LIMITS vs RATED THERMAL POWER ..... 9 , K(z) NORMALIZED FQ(z) AS A FUNCTION OF CORE HEIGHT ...... 10 , AXIAL FLUX DIFFERENCE ENVELOPE LIMITS .................................... 11 , REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION..... 12 . OVERTEMPERATURE AT/ OVERPOWER AT .................................... 13
1.0 PURPOSE 1.1 This procedure establishes the cycle specific safety limits for the reactor fuel.
1.2 This procedure applies to Cycle 14 fuel.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 The data presented in this report applies to Cycle 14 Only and SHALL NOT be used for other operating cycles.
2.2 This data is applicable from completion of cycle 14 core reload until initiation of the cycle 15 core reload.
NOTE The Core Operating Limits Report (COLR), including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
2.3 IF a part of this procedure is changed which affects information contained in the COLR {Definition 5.1), THEN SUBMIT a copy of this approved procedure to the Site Licensing Manager for transmittal to the NRC per TS: 5.6.5 {Reference 6.1.1) 2.4 COLR data is provided by Reactor Engineering per procedure RA-25, Control of Core Operating Limits Report.
3.0 PREREQUISITES None
4.0 PROCEDURE 4.1 The following are Core Operating Limits for the Cycle 14 reactor fuel:
Table 4.1 CORE OPERATING LIMITS FOR CYCLE REACTOR FUEL PARAMETER VALUE CORRESPONDING APPLICABILITY T.S.
Hot Channel Factor at 2.5 3.2.1 Mode 1 Rated Thermal Power, (B.3.2.1 for FQ (Z) mathematical (Measured via flux formula, error mapping) tolerances, and measurement by flux mapping)
Height Dependent FQ (Z) Refer to Attachment 2 3.2.1 Mode 1 Multiplier K (Z), referred to as "fraction" Hot Channel Factor at 3.2.2 Mode 1 Rated Thermal Power, FAH N for Vantage + 1.70 for 15x15 Upgrade 1.70 Power Factor Multiplier for 3.2.2 Mode 1 FAH = PFAH PFAH for 0.00 < P < 1.0 0.3 Equation for FAHN FAHN <- FAHRTP(1+ PFAH (1-P)) 3.2.2, B3.2.2, B2.1.1 Mode 1 (Measured via flux for variable mapping) definitions and error tolerances Axial Flux Difference Band +/-5% 3.2.3 Mode 1 with Width Refer to Attachment 3 3.2.3 Thermal Power
> 15%
Table 4.1 CORE OPERATING LIMITS FOR CYCLE REACTOR FUEL PARAMETER VALUE CORRESPONDING APPLICABILITY T.S.
Axial Flux Difference -11%, +11% 3.2.3 Mode 1 with Envelope Limits at 90% Refer to Attachment 3 Thermal Power power > 15%
Axial Flux Difference +/-1% 3.2.3 Mode 1 with Envelope Increase for each Refer to Attachment 3 Thermal Power 2% of rated thermal power > 15%
< 90% RTP but Ž50% RTP Shutdown Bank Insertion _ 225 Steps withdrawn 3.1.5 Mode 1 Limits (Indicated) Mode 2 with any Control bank not fully inserted.
N/A during SR 3.1.4.2 Control Bank Insertion Refer to Attachment 1 3.1.6 Mode 1 Limits Mode 2 with Keff
>_1.0 N/A during SR 3.1.4.2 Control Bank Overlap Withdraw: A, B, C, D 3.1.6, B3.1.6 Mode 1 Pattern Insert: D, C B, A Mode 2 with Keff
> 1.0 Control Bank Overlap 104 Steps 3.1.6, B3.1.6 Mode 1 Mode 2 with Keff
> 1.0 Control Bank Fully 230 Steps 3.1.6, B3.1.6 Mode 1 Withdrawn Position Mode 2 with Keff
> 1.0 Shutdown Margin -a1.3% AK/ K 3.1.1, 3.1.8 Mode 2 during physics tests Mode 2 with Keff
< 1.0 Modes 3, 4, 5
No: 3-POP-2.3 Rev: 16 CORE OPERATING LIMITS FOR CYCLE 14 Page 7 of 14 Table 4.1 CORE OPERATING LIMITS FOR CYCLE REACTOR FUEL PARAMETER VALUE CORRESPONDING APPLICABILITY T.S.
Reactor Coolant System More restrictive of: 3.9.1 Mode 6 and Refueling Cavity Boron >_2050 ppm Concentration OR concentration that provides a SDM Ž_5% AK/K Moderator Temperature @ 300 ppm > - 38.0 pcm/°F 3.1.3 Modes 1, 2, 3 for Coefficient Limits Lower: lower limit
@ 60 ppm > - 44.5 pcm/°F
@ LCO Ž_- 47.0 pcm/°F Upper: < 0.0 AK/ K OF Mode 1 and Mode 2 with Keff
> 1.0 for upper limit Reactor Core Safety Limits Refer to Attachment 4 2.1.1 Modes 1 and 2 Overtemperature AT Limit Refer to Attachment 5 3.3.1 Modes 1 and 2 and Overpower AT Limit RCS Pressure Indicated Pressurizer 3.4.1 Mode 1 Pressure _>2204 psig Temperature Indicated RCS average 0 loop temperature < 576.7 F for full power Tavg =
572.0°F Flow Departure from Minimum measured RCS Nucleate Boiling (DNB) total flow rate _>364,700 Limits gpm.
5.0 DEFINITIONS 5.1 Core Operating Limits Report (COLR) - the parts of this procedure which satisfy the requirements of T.S. 1.1, 5.6.5.
6.0 REFERENCES
6.1 Commitment Documents 6.1.1 Technical Specification 5.6.5.
6.2 Development Documents 6.2.1 NRC Generic Letter 88-16 6.2.2 Indian Point Unit 3 Cycle 14 Reload Safety Evaluation, March 2005 6.2.3 Core Operating Limits Report for Cycle 14, Rev. 0.
6.2.4 Technical Specification 2.1.1, 3.1.1, 3.1.3, 3.1.5, 3.1.6, 3.1.8, 3.2.1, 3.2.2, 3.2.3, 3.3.1, 3.4.1, 3.9.1, B.2.1.1, B3.4.1.
6.2.5 Technical Specification 5.6.5.
6.2.6 NRC Safety Evaluation Report for T.S. Amendment 103.
6.3 Interface Documents RA-25, Control of Core Operating Limits Report 7.0 RECORDS AND DOCUMENTATION None
ATTACHMENT 1 CONTROL ROD INSERTION LIMITS vs RATED THERMAL POWER (Page 1 of 1) 230 220 210 200 190 180 170 160 CD 150 CL.
-60 140
-c
- 0- 130 U, 120 0~
110 100 90 80 70 60 50 40 30 20 10 0
0 10 20 30 40 50 60 70 80 90 100 Power (% of Rated Thermal Power)
No: 3-POP-2.3 Rev: 16 CORE OPERATING LIMITS FOR CYCLE 14 Page 10 of 14 ATTACHMENT 2 K(z) NORMALIZED FQ(z) AS A FUNCTION OF CORE HEIGHT (Page 1 of 1) 1.2 1m ----=
N 0.8 ..
0 LL Core Height K(z) FQ 0.0 1.0 2.50 0.6 --
6.0 1.0 2.50 -I- - ________________
12.0 0.925 2.31 0) 0.4 z
0.2 -
.4-0 0 2 4 6 8 10 12 Core Elevation (ft)
No: 3-POP-2.3 Rev: 16 CORE OPERATING LIMITS FOR CYCLE 14 Page 11 of 14 ATTACHMENT 3 AXIAL FLUX DIFFERENCE ENVELOPE LIMITS (Page 1 of 1) 100 95 90 85 80 0
75 cu 70 65 60 55 50 30 -20 -10 0 10 20 30 40 Axial Flux Difference
No: 3-POP-2.3 Rev: 16 CORE OPERATING LIMITS FOR CYCLE 14 Page 12 of 14 ATTACHMENT 4 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION (Page 1 of 1) 680 660 640 u-O 620 a)
W CL 600 E
I-580 540 520 560 0 10 20 30 40 50 60 70 80 90 100 110 120 Reactor Power (Percent of 3216 MWt)
No: 3-POP-2.3 Rev: 16 FOR CYCLE 14 CORE OPERATING LIMITS Page 13 of 14 ATTACHMENT 5 OVERTEMPERATURE AT/ OVERPOWER AT (Page 1 of 2)
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.
AT < ATo [K1 - K 2 [(1 + T1 s)/(1 + t 2 s)] (Tavg - T') + K3 (P - P') - f1(AI)]
Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
ATo is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec-1.
Tavg is the measured RCS average temperature, OF.
T' is the loop specific indicated Tavg at RTP, OF < 572.0 OF.
P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, >_2235 psig Kj < 1.26 K2 > 0.022/°F K3 > 0.00070/psi
, > 25.0 sec "r2 _<3.0 sec fi(AI) = -4.00{15.75 + (qt - qb)} when qt - qb < - 15.75% RTP 0% of RTP when -15.75% RTP < qt - qb < 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-POP-2.3 Rev: 16 CORE OPERATING LIMITS FOR CYCLE 14 Page 14 of 14 ATTACHMENT 5 OVERTEMPERATURE AT/ OVERPOWER AT (Page 2 of 2)
The Overpower AT Function Allowable Value SHALL not exceed the following:
AT < ATo (K4 - K5 [(T3s)/(1 + 13s)](Tavg) - K6(Tavg - T") ) - f2 (AI)
Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
ATo is the loop specific indicated AT at RTP, IF.
s is the Laplace transform operator, sec1.
Tavg is the measured RCS average temperature, OF.
T" is the loop specific indicated Tavg at RTP, *F < 572.0 OF.
K4 < 1.10 K5 --0.0175/°F for increasing Tavg K6 > 0.0015/°F when Tavg > T 0/0 F for decreasing Tavg 0/°F when Tavg < T T3 = 10 sec f2 (AI) = 0
Procedure Use Is: Control Copy:
Entergy 0 Continuous Nuclear Northeast o Reference Effective Date: //9/05 0 Information Page 1 of 14 15 CORE C TING LIMITS I YCLE 14 iA A"
Approved By:
" *-/6 0
Procedure Sp/sor, DM/[
eratiOi~Ž Team 3B Procedure Owner EDITORIAL REVISION
REVISION
SUMMARY
(Page 1 of 1) 1.0 REASON FOR REVISION 1.1 Corrected T3 expression T3 _>10 sec. (CR-IP2-2005-02150, Editorial 4.6.13).
2.0
SUMMARY
OF CHANGES 2.1 Corrected T3 expression in Attachment 5 from T3 - 10 sec to '13 >_ 10 sec to agree with Technical Specifications. This was a typographical error in both the COLR and Technical Specifications for IP3. (CR-IP2-2005-02150, Editorial 4.6.13).
TABLE OF CONTENTS Section Title Pace 1.0 P UR P O S E .................................................................................................. 4 2.0 PRECAUTIONS AND LIMITATIONS ........................................................... 4 3.0 PR ER EQ UIS ITES ........................................................................................ 4 4.0 P R O C E D UR E .............................................................................................. 5 5.0 D E F INIT IO N S .............................................................................................. 8 6.0 R E FE R E NC ES ............................................................................................ 8 7.0 RECORDS AND DOCUMENTATION ......................................................... 8 Attachments , CONTROL ROD INSERTION LIMITS vs RATED THERMAL POWER ..... 9 , K(z) NORMALIZED FQ(z) AS A FUNCTION OF CORE HEIGHT ...... 10 , AXIAL FLUX DIFFERENCE ENVELOPE LIMITS ................................. 11 , REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION ..... 12 . OVERTEMPERATURE AT/ OVERPOWER AT .................................... 13
1.0 PURPOSE 1.1 This procedure establishes the cycle specific safety limits for the reactor fuel.
1.2 This procedure applies to Cycle 14 fuel.
2.0 PRECAUTIONS AND LIMITATIONS 2.1 The data presented in this report applies to Cycle 14 Only and SHALL NOT be used for other operating cycles.
2.2 This data is applicable from completion of cycle 14 core reload until initiation of the cycle 15 core reload.
NOTE The Core Operating Limits Report (COLR), including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
2.3 IF a part of this procedure is changed which affects information contained in the COLR {Definition 5.1), THEN SUBMIT a copy of this approved procedure to the Site Licensing Manager for transmittal to the NRC per TS: 5.6.5If{Reference 6.1.1) 2.4 COLR data is provided by Reactor Engineering per procedure RA-25, Control of Core Operating Limits Report.
3.0 PREREQUISITES None
4.0 PROCEDURE 4.1 The following are Core Operating Limits for the Cycle 14 reactor fuel:
Table 4.1 CORE OPERATING LIMITS FOR CYCLE REACTOR FUEL PARAMETER VALUE CORRESPONDING APPLICABILITY T.S.
Hot Channel Factor at 2.5 3.2.1 Mode 1 Rated Thermal Power, (B.3.2.1 for F0 (Z) mathematical (Measured via flux formula, error mapping) tolerances, and measurement by flux mapping)
Height Dependent FQ (Z) Refer to Attachment 2 3.2.1 Mode 1 Multiplier K (Z), referred to as "fraction" Hot Channel Factor at 3.2.2 Mode 1 Rated Thermal Power, FAH N for Vantage + 1.70 for 15x15 Upgrade 1.70 Power Factor Multiplier for 3.2.2 Mode 1 FAH = PFAH PFAH for 0.00*_< P*< 1.0 0.3 Equation for FAHN FAHN FAHRTP (1+ PFAH (1-P)) 3.2.2, B3.2.2, B2.1.1 Mode 1 (Measured via flux for variable mapping) definitions tolerances and error Axial Flux Difference Band +5% 3.2.3 Mode 1 with Width Refer to Attachment 3 3.2.3 Thermal Power
> 15%
Table 4.1 CORE OPERATING LIMITS FOR CYCLE REACTOR FUEL PARAMETER VALUE CORRESPONDING APPLICABILITY T.S.
Axial Flux Difference -11%, +11% 3.2.3 Mode 1 with Envelope Limits at 90% Refer to Attachment 3 Thermal Power power > 15%
Axial Flux Difference +/-1% 3.2.3 Mode 1 with Envelope Increase for each Thermal Power 2% of rated thermal power Refer to Attachment 3 > 15%
< 90% RTP but Ž 50% RTP Shutdown Bank Insertion Ž!225 Steps withdrawn 3.1.5 Mode I Limits (Indicated) Mode 2 with any Control bank not fully inserted.
N/A during SR 3.1.4.2 Control Bank Insertion Refer to Attachment 1 3.1.6 Mode 1 Limits Mode 2 with Keff
> 1.0 N/A during SR 3.1.4.2 Control Bank Overlap Withdraw: A, B, C, D 3.1.6, B3.1.6 Mode 1 Pattern Insert: D, C B, A Mode 2 with Keff
>_ 1.0 Control Bank Overlap 104 Steps 3.1.6, B3.1.6 Mode 1 Mode 2 with Keff
___1.0 Control Bank Fully 230 Steps 3.1.6, B3.1.6 Mode 1 Withdrawn Position Mode 2 with Keff
>1.0 Shutdown Margin > 1.3% AK/ K 3.1.1, 3.1.8 Mode 2 during physics tests Mode 2 with Keff
< 1.0 Modes 3, 4, 5
Table 4.1 CORE OPERATING LIMITS FOR CYCLE REACTOR FUEL PARAMETER VALUE CORRESPONDING APPLICABILITY T.S.
Reactor Coolant System More restrictive of: 3.9.1 Mode 6 and Refueling Cavity Boron > 2050 ppm Concentration OR concentration that provides a SDM >_5% AK/K Moderator Temperature @ 300 ppm > - 38.0 pcm/°F 3.1.3 Modes 1, 2, 3 for Coefficient Limits Lower: lower limit
@ 60 ppm > - 44.5 pcm/°F
@ LCO _ - 47.0 pcm/°F Upper: < 0.0 AK/ K OF Mode 1 and Mode 2 with Keff 2> 1.0 for upper limit Reactor Core Safety Limits Refer to Attachment 4 2.1.1 Modes 1 and 2 Overtemperature AT Limit Refer to Attachment 5 3.3.1 Modes 1 and 2 and Overpower AT Limit RCS Pressure Indicated Pressurizer 3.4.1 Mode 1 Pressure >_2204 psig Temperature Indicated RCS average loop temperature < 576.7 0 F for full power Tavg =
572.0°F Flow Departure from Minimum measured RCS Nucleate Boiling (DNB) total flow rate > 364,700 Limits gpm.
5.0 DEFINITIONS 5.1 Core Operating Limits Report (COLR) - the parts of this procedure which satisfy the requirements of T.S. 1.1, 5.6.5.
6.0 REFERENCES
6.1 Commitment Documents 6.1.1 Technical Specification 5.6.5.
6.2 Development Documents 6.2.1 NRC Generic Letter 88-16 6.2.2 Indian Point Unit 3 Cycle 14 Reload Safety Evaluation, March 2005 6.2.3 Core Operating Limits Report for Cycle 14, Rev. 0.
6.2.4 Technical Specification 2.1.1, 3.1.1, 3.1.3, 3.1.5, 3.1.6, 3.1.8, 3.2.1, 3.2.2, 3.2.3, 3.3.1, 3.4.1, 3.9.1, B.2.1.1, B3.4.1.
6.2.5 Technical Specification 5.6.5.
6.2.6 NRC Safety Evaluation Report for T.S. Amendment 103.
6.3 Interface Documents RA-25, Control of Core Operating Limits Report 7.0 RECORDS AND DOCUMENTATION None
ATTACHMENT 1 CONTROL ROD INSERTION LIMITS vs RATED THERMAL POWER (Page 1 of 1) 230 220 734.3,230 7.,3 210 I p 11 200 190 180 SBANKB -100,176 c 170 cu 160 150 CL.
140
-c 130 120 0,126 rANCC CD) 0~
110 :r BANKD cu~
.-0 100 0 90 W-80 70 60 50 40 30 20 10 0
0 10 20 30 40 50 60 70 80 90 100 Power (% of Rated Thermal Power)
No: 3-POP-2.3 Rev: 15 CORE OPERATING LIMITS FOR CYCLE 14 Page 10 of 14 ATTACHMENT 2 K(z) NORMALIZED FQ(z) AS A FUNCTION OF CORE HEIGHT (Page 1 of 1) 1.2 1
~0.8 0
u-
- 20.6
- 0 z
0.2 0
0 2 4 6 8 10 12 Core Elevation (ft)
No: 3-POP-2.3 Rev: 15 CORE OPERATING LIMITS FOR CYCLE 14 Page 11 of 14 ATTACHMENT 3 AXIAL FLUX DIFFERENCE ENVELOPE LIMITS (Page 1 of 1) 101 95 90 85 10 80 0.
(0 75 a-70 65 60 55 50 30 -20 -10 0 10 20 30 40 Axial Flux Difference
No: 3-POP-2.3 Rev: 15 CORE OPERATING LIMITS FOR CYCLE 14 Page 12 of 14 ATTACHMENT 4 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION (Page 1 of 1) 680 660 640 620 C-
- 4) 600 E
I-580 C')
> 560 LA 0
W X.
520 500 0 10 20 30 40 50 60 70 80 90 100 110 120 Reactor Power (Percent of 3216 MWt)
No: 3-POP-2.3 Rev: 15 FOR CYCLE 14 CORE OPERATING LIMITS Page 13 of 14 ATTACHMENT 5 OVERTEMPERATURE AT/ OVERPOWER AT (Page 1 of 2)
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.
AT < ATo [K1 - K2 [(1 + U1s)/(1 + T 2s)] (Tavg - T') + K3 (P - P') - fi(AI)]
Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
ATo is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec-1 .
Tavg is the measured RCS average temperature, OF.
T' is the loop specific indicated Tavg at RTP, 0F < 572.0 OF.
P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, Ž_2235 psig K1 *1.26 K2 > 0.022/°F K3 > 0.00070/psi 1 >- 25.0 sec "12 _<3.0 sec f(Al) = -4.00{15.75 + (qt-qb)} when qt - qb < - 15.75% RTP 0% of RTP when -15.75% RTP < qt - qb < 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-POP-2.3 Rev: 15 FOR CYCLE 14 CORE OPERATING LIMITS Page 14 of 14 ATTACHMENT 5 OVERTEMPERATURE AT/ OVERPOWER AT (Page 2 of 2)
The Overpower AT Function Allowable Value SHALL not exceed the following:
AT < ATo (K4 - K5 [(T3S)0(1 + t3s)](Tavg) - K6(Tavg - T") ) - f2 (AI)
Where: AT is measured RCS AT, OF (measured by hot leg and cold leg RTDs).
ATo is the loop specific indicated AT at RTP, OF.
s is the Laplace transform operator, sec1.
Tavg is the measured RCS average temperature, OF.
T" is the loop specific indicated Tavg at RTP, OF < 572.0 OF.
- 1.10 K5 Ž- 0.0175/°F for increasing Tavg T K4 K6 - 0.0015/°F when avg > T" 0/°F for decreasing Tavg 0/ 0F when Tavg < T" 3 Ž10
_ sec f2(Al) = 0