JAFP-06-0180, Core Operating Limits Report, Revision 22
| ML070030006 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/27/2006 |
| From: | Jim Costedio Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-06-0180 | |
| Download: ML070030006 (30) | |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP
-- EntieW P.O. Box 110 Lycoming, NY 13093 Tel 315 342 3840 December 27, 2006 JAFP-06-0180 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 Core Operating Limits Report, Revision 22
Dear Sir/Madam:
Attached is Revision 22 to the James A. FitzPatrick (JAF) Core Operating Limits Report (COLR). This report is submitted in accordance with Technical Specifications (TS) 5.6.5.
Revision 22 of the COLR clarifies setpoint terminology and revises the term 'trip setting' to
'allowable value' to be consistent with the TS and the Technical Requirements Manual (TRM).
There were no changes to the actual values.
In addition, editorial corrections and administrative changes were included that do not alter the intent.
There are no commitments contained in this letter.
Questions concerning this submittal may be addressed to Mr. William Drews, Reactor Engineering Superintendent, at (315) 349-6562.
Very truly yours, Costedio Regulatory Compliance Manager JC/TP
Attachment:
as stated cc: Regional Administrator, Region I Mr. John P. Boska U. S. Nuclear Regulatory Commission Plant Licensing Branch I-1 475 Allendale Road Division of Operating Reactor Licensing King of Prussia, PA 19406-1415 Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Office of the Resident Inspector Mail Stop O-8-C2 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 P. 0. Box 136 Lycoming, NY 13093 Ato
-Enterg--
NuclearNortheast ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT CORE OPERATING LIMITS REPORT REVISION 22 APPROVED BY: William Drews a,__
REACTOR ENGINEERING SUPERINTENDENT DATE: I__i APPROVED BY: Kevin Mulligan TE: z GENERAL MANAGER - PLANT OPERATIONS I
CORE OPERATING LIMITS REPORT CYCLE 18 TABLE OF CONTENTS SECTION PAGEý 1.0 PU RP O SE ......................................................................................... ...................... 3 2.0 APPLICABILITY ................................................................................................ 3
3.0 REFERENCES
................................................................................................. 3 4.0 DEFINITIONS ........................................ I......................................................... 4 5.0 RESPONSIBILITIES ......................................................................................... 5 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS ........................................... 5 7.0 PROCEDURE .................................................................................................... 6 7.1 Operating Limit MCPR ....................................................................... 6 7.2 Average Planar Linear Heat Generation Rate (APLHGR) ................. 8 7.3 Linear Heat Generation Rate (LHGR) ............................................... 8 7.4 APRM Allowable Values (Digital Flow Cards) .................................... 8 7.5 RBM Upscale Rod Block Allowable Value ......................................... 10 7.6 Stability Option 1-D Exclusion Region and Buffer Zone ................... 10 7.7 Kf - Flow Dependent MCPR Limit .................................................... 11 8.0 FIGURES AND TABLES ................................................................................ 12 9.0 EX H IB IT S ........................................................................................................ 13 Rev. No. 22 Page 2 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 18 of the James A.
FitzPatrick Nuclear Power Plant. The following limits are addressed:
- Operating Limit Minimum Critical Power Ratio (MCPR)
- Flow Dependent MCPR Limits
- Average Planar Linear Heat Generation Rate (APLHGR)
- Linear Heat Generation Rate (LHGR)
Allowable Values
- Stability Option ID Exclusion Region 2.0 APPLICABILITY The plant shall be operated within the limits specified in this report. If any of these limits are exceeded, the corrective actions specified in the Technical Specifications shall be taken.
3.0 REFERENCES
3.1 EN-LI-1 13, Licensing Basis Document Change process 3.2 JAFNPP Technical Specifications.
3.3 Design Change Package ER-JF-06-13005, Cycle 18 Core Reload 3.4 ENN-DC-503, 3D Monicore New Cycle Update and Databank Maintenance.
3.5 Plant Operation Up To 100% Power With One Steam Line Isolated, JAF-SE-96-035.
3.6 James A. FitzPatrick Nuclear Power Plant Kf Curve Update, GE-NE-J11-03426-00-01, September 1998.
3.7 General Electric Standard Application for Reload Fuel, NEDE-2401 1-P-A-15 3.8 GNF Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 17 Cycle 18, 0000-0049-7976SRLR, Rev.0, Class I, July, 2006.
3.9 JAF-SE-00-032, Rev.0, Extended Loadline Limit Analysis (ELLLA) Implementation.
3.10 JAF-RPT-MISC-04054, Rev.0, Operation under Extended Loadline Limit Analysis (ELLLA) and Power Uprate 3.11 GE Letter, R. Kingston to P. Lemberg, Scram Time Versus Notch Positions for Option B, REK-E: 02-009, May 28, 2002 Rev. No. 22 Page 3 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 3.12 GE Report, James A. FitzPatrick Nuclear Power Plant Final Feedwater Temperature Reduction NEDC-33077, September 2002.
3.13 JD-02-122, Final Feedwater Temperature Reduction Implementation.
3.14 GE Report, GEI4 Fuel Design Cycle-Independent Analyses for J. A. Fitzpatrick Nuclear Power Plant, GE-NE-0000-0002-1752-01P, Rev. 0, DRF 0000-0002-1752, September 2002.
3.15 GNF Report, GNF Report, Fuel Bundle Information Report for James A. FitzPatrick Reload 17 Cycle 18, 0000-0049-7976FBIR, Revision 0, July 2006.
3.16 Not Used 3,17 Not Used 3.18 JF-03-00402, ARTS/MEOD Phase 1 Implementation 3,19 JAF-RPT-MISC-04489, Rev.2, Power-Flow Map Report 3.20 Not Used 3.21 Not Used 3.22 GE Letter, FitzPatrick APRM Flow Biased Rod Block and Scram Setpoints, NSA01-273, July 3, 2001 4.0 DEFINITIONS 4.1 Average Planar Linear Heat Generation Rate (APLHGR):
The APLHGR shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the fuel rods in the specified assembly at the specified height divided by the number of fuel rods in the fuel assembly at the height.
4.2 Fraction of Limiting Power Density:
The ratio of the linear heat generation rate (LHGR) existing at a given location to the design LHGR. The design LHGR is given in Table 8.2.
4.3 Linear Heat Generation Rate(LHGR):
The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
4.4 Maximum Fraction of Limiting Power Density (MFLPD):
The MFLPD shall be the largest value of the fraction of limiting power density in the core.
The fraction of limiting power density shall be the LHGR existing at a given location divided by the specified LHGR limit for that bundle type.
Rev. No. 22 Page 4 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 4.5 Minimum critical power ratio (MCPR):
The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
4.6 Rated Recirculation Flow:
That drive flow which produces a core flow of 77.0 x 106 lb/hr.
5.0 RESPONSIBILITIES NOTE: See EN-LI-1 13 (Reference 3.1) 5.1 Shift Manager:
Assure that the reactor is operated within the limits described herein.
5.2 Reactor Engineering Superintendent:
Assure that the limits described herein are properly installed in the 3D-Monicore databank used for thermal limit surveillance (Reference 3.4) 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS Not Applicable Rev. No. 22 Page 5 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 7.0 PROCEDURE 7.1 Operating Limit MCPR During operation, with thermal power > 25% of rated thermal power (RTP), the Operating Limit MCPR shall be equal to or greater than the limits given below.
7.1.1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR) 7.1.2 The Operating Limit MCPR shall be determined based on the following requirement:
7.1.2.1. The average scram time to notch position 36 shall be:
"CAVE r-B 7.1.2.2. The average scram time to notch position 36 is determined as follows:
n SNi-i i= 1 TA VE- =n i=1 WHERE:
n = Number of surveillance tests performed to date in the cycle, Ni = Number of active rods measured in the surveillance i Average scram time to notch position 36 of all rods measured in surveillance test i.
Rev. No. 22 P Page 6 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 7.1.2.3. The adjusted analysis mean scram time is calculated as follows:
1/2 N,
i-B(sec)= /+1.657 n INi i=J WHERE:
.= Mean of the distribution for the average scram insertion time to the dropout of notch position 36 = 0.830 sec.
= Standard deviation of the distribution for average scram insertion time to the dropout of notch position 36 = 0.019 sec.
N1 The total number of active rods measured in Technical Specification SR 3.1.4.4.
The number of rods to be scram tested and the test intervals are given in Technical Specification LCO 3.1.4, Control Rod Scram Times 7.1.3 When requirement of 7.1.2.1 is met, the Operating Limit MCPR shall not be less than that specified in Table 8.1, Table 8.1.A, Table 8.1..B or Table 8.1.C as applicable.
7.1.4 WHEN the requirement 7.1.2.1 is not met (i.e. CB < cAV), THEN the Operating Limit MCPR values (as a function of c) are given in Figure 8.1, Figure 8.1.A, Figure 8.1.B or Figure 8.1.C as applicable.
(TAVE - TB)
(TA -TB)
WHERE:
TAVE = The average scram time to notch position 36 as defined in 7.1.2.2.
TB = The adjusted analysis mean scram time as defined in 7.1.2.3.
TA = the scram time to notch position 36 as defined in Technical Specification Table 3.1.4-1.
Rev. No. 22 Pagev 7 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 NOTE: IF the operating limit MCPR obtained from these figures is determined to be less than the operating limit MCPR found in 7.1.3, THEN 7.1.3 shall apply.
7.1.5 During single-loop operation, the Operating Limit MCPR shall be increased by 0.02.
7.1.6 During reactor power operation with core flow less than 100 percent of rated, the Operating Limit MCPR shall be multiplied by the appropriate Kf specified in Figure 8.2.
7.2 Average Planar Linear Heat Generation Rate (APLHGR) 7.2.1 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) 7.2.2 During operation, with thermal power > 25% rated thermal power (RTP),
the APLHGR shall be within the limits given in Table 8. (Figure 8.3) for the appropriate fuel type.
7.2.3 During single loop operation, the APLHGR for each fuel type shall not exceed the values given in 7.2.2 above multiplied by the appropriate value (0.78 for GE14 fuel).
7.3 Linear Heat Generation Rate (LHGR) 7.3.1 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR) 7.3.2 During operation, with thermal power > 25% rated thermal power (RTP),
the LHGR for each fuel rod as a function of axial location and exposure shall be within limits based on applicable LHGR limit values given in Tables 8. for appropriate fuel and rod type.
7.3.3 During single loop operation, the LHGR for each fuel type shall not exceed the values given in 7.3.2 above multiplied by the appropriate value (0.78 for GE14 fuel).
7.4 APRM Allowable Values (Digital Flow Cards) 7.4.1 APRM Flow Referenced Flux Scram Allowable Value (Run Mode) 7.4.1.1. Technical Specifications:
LCO 3.2.4, Average Power Range Monitor (APRM) Gain and Setpoint LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation 7.4.1.2. When operating in Mode 1, the APRM Neutron Flux-High (Flow Biased)
Allowable Value shall be Rev. No. 22 Page 8 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 for two loop operation:
S< (% RTP) = 0.38*W+61.0% 0< W *24.7%
S< (% RTP) = 1.15*W+42.0% 24.7< W < 47.0%
S< (% RTP) = 0.63*W+73.7% 47.0< W - 68.7%
S< (% RTP) = 117.00% (Clamp) W > 68.7%
for single loop operation:
S< (% RTP) = 0.38*W+57.9% 0< W *32.7%
S:5 (% RTP) = 1.15*W+32.8% 32.7< W _ 50.1%
S< (%RTP) = 0.58*W+61.3% 50.1< W _ 95.9%
S< (% RTP) = 117.00% (Clamp) W > 95.9%
WHERE:
S = Allowable value in percent of rated thermal power; I
W = Recirculation flow in percent of rated; NOTE: Compliance with the "Allowed Region of Operation" on the Power-Flow Map, Figure 3.7-1 of the FSAR is defined by the equation 0.58W + 50%
and is individually controlled and assures boundaries are not exceeded during normal operation.
7.4.1.3. In the event of operation with a Maximum Fraction of Limiting Power Density (MFLPD) greater than the Fraction of Rated Power (FRP), the allowable value shall be modified as follows for two loop operation:
S< (C1 RTP) = (0.38*W+61.0%)(FRP/MFLPD) 0< W-< 24.7%
S_ (% RTP) (1.15*W+42.0%)(FRP/MFLPD) 24.7< W -<47.0%
S_< (%RTP) (0.63*W+73.7%)(FRP/MFLPD) 47.0< W _<68.7%
S*_ (%RTP) (117.00%(Clamp))(FRP/MFLPD) W > 68.7%
for single loop operation:
S< (% RTP)= (0.38*Wd+57.9%)(FRP/MFLPD) 0< W
- 32.7%
S< (% RTP) = (1.15*Wd+32.8%)(FRP/MFLPD) 32.7< W -<50.1%
S< (% RTP)= (0.58*Wd+61.3%)(FRP/MFLPD) 50.1< W _<95.9%
S_5 (% RTP) = (117.00% (Clamp))(FRP/MFLPD) W > 95.9%
WHERE:
FRP Fraction of Rated Power; Rev. No. 22 Page 9 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 MFLPD = Maximum Fraction Of Limiting Power Density, see Definition 4.4.
The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.
7.4.2 APRM Neutron Flux-High (Flow Biased) Rod Block Allowable Value (Relocated to the Technical Requirements Manual)
I 7.5 RBM Upscale Rod Block Allowable Value 7.5.1 Technical Specification LCO 3.3.2.1, Control Rod Block Instrumentation 7.5.2 The RBM upscale rod block allowable value shall be:
S < 0.66W + K for two loop operation; S < 0.66W + K - 0.66 AW for single loop operation; WHERE:
S rod block allowable value in percent of initial; W = Loop flow in percent of rated K Any intercept value may be used because the RBM intercept value does not effect the MCPR Operating Limit and the RBM is not assumed to function to protect the Safety Limit MCPR.
AW = Difference between two loop and single loop effective drive flow at the same core flow.
NOTE: If K can be any value, then K - 0.66AW can also be any value, and the allowable value adjustment for single loop operation is not necessary.
7.6 Stability Option 1-D Exclusion Region and Buffer Zone.
7.6.1 Technical Specification LCO 3.4.1, Recirculation Loops Operating 7.6.2 The reactor shall not be intentionally operated within the Exclusion Region given in Figure 8.4 when the SOLOMON Code is operable.
7.6.3 The reactor shall not be intentionally operated within the Buffer Zone given in Figure 8.4 when the SOLOMON Code is inoperable.
Rev. No. 22 Page 10 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 7.7 Kf - Flow Dependent MCPR Limit Figure 8.2 is the Kf limit. Values of Kf are obtained using the following equation (see Reference 3.6):
Kf = MAX [1.0, A - SLOPE
- WT]
WHERE:
WT = Core Flow as % of Rated, 30%/0 < WT < 100%
SLOPE = (AF/100/OLMCPR ) * (SLMCPR /SLMCPR generic)
A (BF/OLMCPR) (SLMCPR /SLMCPR generic)
SLMCPR generic = 1.07 SLMCPR Technical Specification LCO 2.1.1, Reactor Core SLs OLMCPR= The lowest value obtained from Figures 8.1, 8.1.A, 8.1.B and 8.1.C as per 7.1.4, or, if the note in 7.1.4 applies, then 7.1.3 requirement must be met.
AF, BF = Coefficients for the Kf curve listed below:
Scoop Tube Setpoint % AF BF 102.5 0.571 1.655 107.0 0.586 1.697 112.0 0.602 1.747 117.0 0.632 1.809 All coefficients apply to Manual Flow Control Mode Rev. No. 22 Page 1l of 29
CORE OPERATING LIMITS REPORT CYCLE 18 8.0 FIGURES A2 ND TABLES 8.1 FIGURES Figure 8.1. MCPR Operating Limit Versus T for GEl4.
Figure 8.1.A. MCPR Operating Limit Versus t for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service for GEI4.
Figure 8.1.B MCPR Operating Limit Versus t for Operation with Turbine Bypass Valves Out of Service Figure 8.1.C MCPR Operating Limit Versus T for Operation with Final Feedwater Temperature Reduction Figure 8.2 Kf Factor Figure 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel Figure 8.4 Stability Option 1-D Exclusion Region Figure 8.5 Exposure Dependent LHGR Limit for GE14 Fuel.
Figure 8.6. Cycle 18 Loading Pattern, Full Core by Bundle Design Figure 8.7 Users Guide Rev. No. 22 Page 12 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 8.2 TABLES Table 8.1 MCPR Operating Limit for Incremental Cycle Core Average Exposure Table 8.1.A MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service Table 8.1.B MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service Table 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction Table 8.2 Maximum LHGR - GE14 Table 8.3 APLHGR Limits for GE14 Fuel 9.0 EXHIBITS NONE Rev. No. 22 Page 13 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure All Fuel Types Cycle 18 Exposure Range BOC to EOC 1.44 NA NA Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased as given in Section 7.1.5.
NOTE: 1. When entering a new Exposure Range, check the current value of'U to assure adjustment per Step 7.1.4
- 2. Applicable for any value of K, see Step 7.5.2 Rev. No. 22 Page 14 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.1.A MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service All Fuel Types Cycle 18 Exposure Range BOC to EOC 1.46
For single loop operation, these limits shall be increased as given in Section 7.1.5.
NOTE: 1. When entering a new Exposure Range, check the current value of T to assure adjustment per Step 7.1.4
- 2. Applicable for any value of K, see Step 7.5.2 Rev. No. 22 Page 15 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.1.B MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service All Fuel Types Cycle 18 Exposure Range ALL 1.48 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
Technical Specification LCO 3.7.6, Main Turbine Bypass System For single loop operation, these limits shall be increased as given in Section 7.1.5.
NOTE: 1. When entering a new Exposure Range, check the current value of T to assure adjustment per Step 7.1.4
- 2. Applicable for any value of K, see Step 7.5.2 Rev. No. 22 Page 16 of 29
'CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction Cycle 18 Exposure Range All Fuel Types At EOC only (see below) 1.44 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased as given in Section 7.1.5.
NOTE: 1. When entering a new Exposure Range, check the current value of tv to assure adjustment per Step 7.1.4
- 2. Applicable for any value of K, see Step 7.5.2 MCPR Operating Limits in this table apply when at reduced feedwater temperature near end-of-cycle, see JD-02-122 (Reference 3.13) for further information.
Rev. No. 22 Page 17 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.2 Maximum LHGR - GE14 Peak Pellet Exposure U0 2 LHGR Limit GWd/ST kW/ft 0.00 13.40 14.51 13.40 57.61 8.00 63.50 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/ST kW/ft 0.00 12.26 12.28 12.26 55.00 7.32 60.84 4.57 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
Design features of the fuel assemblies in the Cycle 18 core are provided in References 3.3, 3.15 For single loop operation these LHGR values shall be multiplied by 0.78 Linearly interpolate for LHGR at intermediate exposure Rev. No. 22 Page 18 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)
For single loop operation these APLHGR values shall be multiplied by 0.78 Linearly interpolate for APLHGR at intermediate exposure Rev. No. 22 Page 19 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.1 MCPR Operating Limit Versusr For All Fuel Types
- 60C to C1 8 -3.5 GWd/St
- E)- DC1 8- 3.5 GWd/SttoE11 1.65 1.60- .. , 1.61 cn 1.55 E
0)
.C 1-50 1.45w
_- -- _ I
- -1.50 0*. 1.40 - -
1.35 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9
'T Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased as given in Section 7.1.5.
NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block Allowable Value then 7.1.3 shall apply.
Rev. No. 22 Page 20 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.1.A MCPR Operating Limit Versus "
For Operating Above 75% of Rated Thermal Power with Three Steam Lines in Service For all Fuel Types
-',- BOC to EOC18 - 3.5 GWd/St 1.65
-E--- EC18 - 3.5 GWd/St to EDC18 1.63 1.60 1.55 1.50
-1.52 a) a 1.451 0) 1.40' 1.35 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single -loop operation, these limits shall be increased as given in Section 7.1.5.
NOTE: Should the operating limit MCPR obtained from thiis figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block Allowable Value then 7.1.3 shall apply Rev. No. 22 Page 21 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.1.B MCPR Operating Limit Versus "r for Operation with Turbine Bypass Valves Out of Service 1.7 1.65 0) 1.65
.C) 1.6 E5 1.55
- 0) 1.5 1.45 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (-MCPR)
For single loop operation, these limits shall be increased as given in Section 7.1.5.
NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block Allowable Value then 7.1.3 shall apply Rev. No. 22 Page 22 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.1.C MCPR Operating Limit Versus t for Operation with Final Feedwater Temperature Reduction 1.65 1.6 1.61 1.55 E
i-"
- 0) 1.5
°a 1.45 0.
0) 1.4 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 IT Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased as given in Section 7.1.5.
NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block Allowable Value then 7.1.3 shall apply I Rev. No. 22 Page 23 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.2 Kf Factor Cycle 18 Kf Curve for Scoop Tube Stops at 112%
Considers Two Loop and Single Loop Operation, MOC and EOC MCPR Limits 1.10 -
-+-MOC+SLO 0 EOC+SLO A MOC+TLO X EOC+TLO i
E The combination of MOC MCPR limit and SLO produces the most limiting K1 curve.
1.09 - This set of data determines the K, curve used in the 3D-MONICORE databank.
May be changed when EOC MCPR limits apply. Choice of Single Loop KI values is for ease of SLO. Two loop limits are not significantly different. NOTE: Cycle 18 1.08 - MOC and EOC limits are equal, so above discussion does not apply, but left as reminder if any changes to limits.
1.07 SLMCPR = 1.07 (TLO), 1.09 (SLO) --- see SRLR for MCPR limits OLMCPR(TLO) = 1.44 (BOC to MOC), 1.44 (MOC to EOC)
OLMCPR(SLO) = 1.46 (BOC to MOC), 1.46 (MOC to EOC) 1.06 K, may be adjusted as needed to provide protection against the SLO Pump Seizure event. For GE14, the OLMCPR below the SLO core flow limit of 58% must be 1.05 greater than 1.43*(SLMCPR/1.12), or 1.392. In Cycle 18 the OLMCPR at MOC+SLO is 1.46.for GE14, so no K,adjustment is required.
1.04
References:
- 1. K4CURVE UPDATE, GE-NE-J11-03426-00-01, 10/16/98
\L 2. GE14 Fuel Design Cycle-Independent Analyses for JAFNPP, 1.03 GE-NE-0000-0002-1752-01 P, September 2002 Equation of Cycle 18 K, curve:
1.02 Kf = MAX( 1.0, 1.2189 - 0.42004*(% Core Flow/1 00))
1.01 1.00 U 7 i 7 0.99 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Core Flow, % rated Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
See Section 7.7 NOTE: Kf for Single Loop Operation is slightly greater than for Dual Loop Operation limits.
Therefore, Kf calculated for Single Loop Operation is more conservative and will be applied to Dual Loop Operation as well.
Rev. No. 22 Page 24 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel 14 13 12 11 10 9
8 6
5 4
3 2
1 0
0 5 10 15 20 25 30 35 40 45 50 55 60 65 Planar Exposure, GWD/ST Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)
For single loop operation these APLHGR values shall be multiplied by 0.78.
Rev. No. 2_22 Page 25 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.4 Stability Option 1-D Exclusion Region 110 100 90 80 70 0)
(0 60 50 40 30 20 20 25 30 35 40 45 50 55 60 65 70 Flow, % rated Rev. No. 22 Page 26 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.5 Exposure Dependent LHGR Limit for GE14 Fuel 14 13 12 11 10 9
8 7
6 5
4 3
2 1
0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 PELLET EXPOSURE GWD/ST Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
This curve represents the limiting exposure dependent LHGR values per Reference 3.15 Design features of the fuel assemblies in the Cycle 18 core are provided in Reference 3.3 Rev. No. 2_22 Page 27 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.6 Cycle 18 Loading Pattern by Bundle Design North 52 [ OFI[E] El E][][F]H
]I-E][F] [E]J[
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- Fuel Type A=GE14-P10DNAB405-16GZ- 100T- I 50-T6-2794 (Cycle 17) D=GE14-P1ODNAB405-16GZ-1OOT-150-T6-2906 (Cycle 18)
B=GE14-P1ODNAB405-15G6.0-1OOT-150-T6-2793 (Cycle 17) E=GE14-PIODNAB405-16GZ-1OOT-150-T6-2562 (Cycle 16)
C=GE14-P1ODNAB402-10G6.0/4G5.01/G2.0-1OOT-150-T6-2905 F=GE14-P1ODNAB405-16GZ-lOOT-150-T6-2563 (Cycle 16)
(Cycle 18)
Rev. No. 22 Page 28 of 29
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.7 USERS GUIDE The COLR defines thermal limits for the various operating conditions expected during the cycle. At the start of the cycle the 3D-Monicore databank contains limits for; a Cycle exposure range of BOC to EOC18
- =0
- Dual recirculation pump operation
- Four steam line operation, and
- Final Feedwater Temperature Reduction The following is a table that offers a check to assure the correct limits are applied when operating states or conditions change.
Change in Operating State Change in Limits Procedure Reference Cycle Exposure = See Table 8.1 or Figure 8.1 for #* 0 for None EOC18 - 3.5 GWD/ST change in MCPR.
OLMCPR changes to EOC values Kf limit mnay be changed in recognition of at cycle exposure of 12.0 GWD/ST higher OLMCPR.
Scram Time Test Results such that "r# 0 Use newt"and see Figure 8.. Kf limit may be changed in recognition of higher RAP-7.4.1 Option B limits for OLMCPR must be interpolated with Option A limits OLMCPR.
Single Loop Operation Increase MCPR Limits by 0.02, or change The SLMCPR increases by 0.02 and acceptance criterion in ST-5E to 0.98. Kf therefore OLMCPR limits increase does not change. ST-5E, by 0.02. MFLPD and MAPLHGR Verify that 3D-Monicore has recognized are reduced by a multiplier in SLO. the idle recirculation loop and is applying the SLO MFLPD and MAPLHGR multiplier of 0.78.
Three Steam Line Operation (3SL) Increase OLMCPR according to Table OLMCPR values increase by 0.02 8.1.A or Figure 8.1.A(Tr *0). Kf limit may None when opealuting on s 02 be changed in recognition of higher when operating on 3SL OLMCPR.
Operation with Turbine Bypass Increase OLMCPR according to Table Valves Out-of-Service 8.1.B or Figure 8.1.B(T #0). Kr limit may None OLMCPR values increase, no be changed in recognition of higher LHGR change required OLMCPR.
Operation under Final Feedwater Increase OLMCPR according to Table Temperature Reduction 8.1.C or Figure 8.1.C('T #0). Kf limit may None OLMCPR values increase, no be changed in recognition of higher LHGR change required OLMCPR.
Rev. No. 2__22 Page 29 of 29