JAFP-07-0090, Core Operating Limits Report, Revision 23
| ML072120482 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/23/2007 |
| From: | Jim Costedio Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-07-0090, TAC MC9681 | |
| Download: ML072120482 (33) | |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP
- 1Entgy P.O. Box 110 Lycoming, NY 13093 Tel 315 342 3840 July 23, 2007 JAFP-07-0090 United States 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 23
Dear Sir or Madam:
Attached is Revision 23 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 23 of the COLR implements Technical Specifications Amendment No.287 dated May 17, 2007 (TAC No. MC9681).
There are no commitments contained in this letter.
Questions concerning this report may be addressed to Mr. William Drews, Reactor Engineering Superintendent, at (315) 349-6562.
Sincerely, 4r 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 James A. FitzPatrick Nuclear Power Plant P. 0. Box 136 Lycoming, NY 13093-0136 A0o0 tUa
Entergy NuclearNortheast ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT CORE OPERATING LIMITS REPORT REVISION 23 APPROVED BY: William Drews DATE: f J "7 REACTOR ENGINEERING SUPERINTENDENT APPROVED BY: Kexnl Mulligan DATE:. - "a-,
GENERAL MANAGER - PLANT OPERATION--ý-.
CORE OPERATING LIMITS REPORT CYCLE 18 TABLE OF CONTENTS SECTION PAGE 1.0 PU R P O SE ............................................................................................................... 3 2.0 APPLICABILITY ............................................................................................... 3
3.0 REFERENCES
.................................................................................................. 3 4.0 DEFINITIONS ................................................................................................. 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) ................................................. 9 7.4 APRM Allowable Values (Digital Flow Cards) .................................... 9 7.5 RBM Upscale Rod Block Allowable Value .......................................... 10 7.6 Stability Option 1-D Exclusion Region and Buffer Zone ............ 11 8.0 FIGURES AND TABLES ................................................................................. 12 9.0 E X H IB IT S ......................................................................................................... 13 Rev. No. 03 Page 2 of 32
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- 113, 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 GE Report, J.A. FitzPatrick Nuclear Power Plant APRM/RBM/Technical Specifications /
Maximum Extended Operating Domain (ARTS/MEOD), NEDC-33087P, Revision 1, September 2005 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 Rev. No. 23 Page 3 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 3.11 GE Letter, R. Kingston to P. Lemberg, Scram Time Versus Notch Positions for Option B, REK-E: 02-009, May 28, 2002 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, GE 14 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 JF-03-00402, ARTS/MEOD Phase 1 Implementation 3.17 JAF-RPT-MISC-04489, Rev.3, Power-Flow Map Report 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 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.
4.3 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.
4.4 Rated Recirculation Flow:
That drive flow which produces a core flow of 77.0 x 10' lb/hr.
Rev. No. 23 Page 4 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 5.0 RESPONSIBILITIES NOTE: See EN-LI- 113 (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. 23 Page 5 of 32
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., 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:
t <t
'AVE < B 7.1.2.2. The average scram time to notch position 36 is determined as follows:
fl Niri A"TI E it SENi WHERE:
n Number of surveillance tests performed to date in the cycle, N1 = Number of active rods measured in the surveillance i Ti = Average scram time to notch position 36 of all rods measured in surveillance test 1.
Rev. No. 23 Page 6 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 7.1.2.3. The adjusted analysis mean scram time is calculated as follows:
-1/2 YN1
-i=1 WHERE:
pt = Mean of the distribution for the average scram insertion time to the dropout of notch position 36 = 0.830 sec.
(T 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. 'TB <TrAVE), THEN the Operating Linlit MCPR values (as a function oft) 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:
TrAVE= The average scram time to notch position 36 as defined in 7.1.2.2.
TaB = 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. 2'3 Page 7 of 32.
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 The Operating Limit MCPR is the greater of the flow and power dependent MCPR operating limits, MCPR(F) and MCPR(P).
Operating Limit MCPR = MAX (MCPR(P), MCPR(F))
The flow dependent MCPR operating limits, MCPRF) is provided in Figure 8.2.A.
For core thermal powers equal to or greater than 25%, MCPR (P) is the product of the rated Operating Limit MCPR presented in Tables 8.1, 8.1.A, 8.1.B, and 8.1.C (or Figures 8.1, 8.1.A, 8.1.B, and 8.1.C when CB>
Tave) and the K (P) factor presented in Figure 8.2.B.
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)
During operation, xvith thermal power > 25% rated thermal power (RTP),
the APLHGR shall be the smaller of the power and flow dependent APLHGR limits multiplied by the applicable power and flow adjustment or the APLHGR limit multiplied by 0.78 (for GE14) when in single loop operation.
APLHGR limit = MIN (APLHGR (P), APLHGR (F)).
Power-dependent APLHGR limit, APLHGR (P), is the product of the APLHGR power dependent adjustment factor, MAPFAC (P), shown in Figure 8.6.B and the APLHGRSd in Table 8.3.
LHGR (P) = MAPFAC(P) x APLHGRstd The flow-dependent APLHGR limit, APLHGR (F), is the product of the APLHGR flow dependent adjustment factor, MIAPFAC (F), shown in Figure 8.6.A and the APLHGRSd in Table 8.3.
APLHGR (F) = IVL'PFAC (F) x APLHGR,,d Rev. No. 23 Page 8 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 7.3 Linear Heat Generation Rate (LHGR) 7.3.1 Techmical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR) 7.3.2 During operation, with thermal power > 25% rated thermal power (RTP),
the applicable limiting LHGR values for each fuel rod as a function of aXial location and exposure shall be the smaller of the power and flow dependent LHGR limits multiplied by the applicable power and flow adjustment or the LHGR limit multiplied by 0.78 (for GEI4) when in single loop operation.
LHGR limit = MIN (LHGR (P), LHGR (F)).
Power-dependent LHGR limit, LHGR (P), is the product of the LHGR power dependent LHGR limit adjustment factor, LHGRFAC (P), shown in Figure 8.6.B and the LHGR,,d in Table 8.2.
LHGR (P) = LHGRFAC(P) x LHGR,,d The flow-dependent LHGR limit, LHGR (F), is the product of the LHGR flow dependent LHGR limit adjustment factor, LHGRFAC (F), shown in Figure 8.6.A and the LHGRstd in Table 8.2.
LHGR (F) = LHGRFAC(F) x LHGRstd 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 3.3.1.1, 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 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< (% 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%
Rev. No. -')3 Page 9 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 WHERE:
S = Allowable value in percent of rated thermal power; 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.
7.4.2 APRM Neutron Flux-High (Flow Biased) Rod Block Allowable Value (Relocated to the Technical Requirements Manual) 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.
Rev. No. 2'3 Page 10 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 7.6 Stability Option 1-D Exclusion Region and Buffer Zone.
7.6.1 Techtical 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. -')3 Page 11 of 32
CORE OPER1ATING LIMITS REPORT CYCLE 18 8.0 FIGURES AND TABLES 8.1 FIGURES Figure 8.1. MCPR Operating Limit Versus 'Tfor GEl4.
Figure 8.1 .A. MCPR Operating Limit Versus 't for Operation above 75% of Rated Thern-al 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.i .C MCPR Operating Limit Versus Cfor Operation with Final Feedwater Temperature Reduction Figure 8.2.A MCPR(F) Factor Figure 8.2.B MCPR(P), K(P) 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.A Flow-Dependent APLHGR/LHGR Multiplier, NLkPFAC(F) and LHGRFAC(F)
Figure 8.6.B Power-Dependent APLHGR/LHGR Multiplier, NLMIPFAC(P) and LHGRFAC(P)
Figure 8.7 Cycle 18 Loading Pattern, Full Core by Bundle Design Figure 8.8 Users Guide Rev. No. 23 Page 12 of 32
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 MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Table 8.1.B Service Table 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction Table 8.2 Maximum LHGR - GEI4 Table 8.3 APLHGR Limits for GE14 Fuel 9.0 EXHIBITS NONE Rev,. No. 23 Page 13 of 32
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.
The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 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. 23 Page '14 of 32
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 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.
The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 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. 23 Page 15 of 32
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.
The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 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. 23 Page 16 of 32
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, Miinmum Critical Power Ratio (MVICPR)
For single loop operation, these limits shall be increased as given in Section 7.1.5.
The MCPR limits in this Table are subject to Power and Flow dependent adjustment per Section 7.1.6 NOTE: 1. When entering a new Exposure Range, check the current value of ' 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. 23 Page 17 of 32
C 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 LHGRstd values in the above Table 8.2 are subject to Power and Flow dependent adjustments per Section 7.3 For single loop operation these LHGR values shall be multiplied by 0.78 Linearly interpolate for LHGR at intenrnediate exposure Rev. No. 23 Page 18 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 TABLE 8.3 Exposure Dependent APLHGR Limit for GEl 4 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 APLHGRstd values in the above Table 8.3 are subject to Power and Flow dependent adjustments per Section 7.2 Linearly interpolate for APLHGR at intermediate exposure Rev. No. 23 Page 1_9 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.1 MCPR Operating Limit Versus C For All Fuel Types 1.65 U) 1.60 1.61 1.55 1.50 1.50 j.__ 1.45 1.40 1.35 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 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. 2ý3 Page 20 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.1.A MCPR Operating Limit Versus t For Operating Above 75% of Rated Thermal Power with Three Steam Lines in Service For all Fuel Types 1.65 1.63 1.60 1.55 1.50 1.52 0.
1.45 0) 1.40 1.35 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 T
Technical Specification LCO 3.2.2, M/inimum 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. 23 Page 21 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.1.B MCPR Operating Limit Versusc for Operation with Turbine Bypass Valves Out of Service 1.7 0y 1.65 1.65 1.6 E
0) 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 T
Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (,ICPR)
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 linmit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block Allowable Value then 7.1.3 shall apply Rev. No. 23 Page 22 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.1.C MCPR Operating Limit Versus t for Operation with Final Feedwater Temperature Reduction
- -P~rTR 1.65 1.6 -77.1 r *IuI*
Al
__ __ -~
CL 1.55 1.5 4- -
1.45 0~
1.4 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 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. 23 Page 23 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.2.A MCPR(F) Factor 1.7 For Maximum Flow of 112%
For SLO Flow,% MCPR(F) 30 1.586 1.6 0 90.86 1.220 110 1.220 C. For 2 Loop Operation 2 1.5 Flow,% MCPR(F) 30 1.566 90.86 1.200
,U I 110 1.200
- a. 1.4 _ _,_
U CL 1.3
- ~DLO
-- o- SLO 1.21 20 30 40 50 60 70 80 90 100 110 Core Flow (%rated)
Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
Rev. No. 23 Page 24 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 Figure 8.2.B K(P), OLMCPR(P) Factor 2.6 For P < 25%: No Thermal Limits Monitoring 2.5 H' Required, No limits specified M2.4 2.3 ' '1 For 25% < P < P(Bypass), P(Bypass) = 29%
v 2.3 ' 'OLMCPR(P) = 2.23, Flow < 60%
4,- 22 2.2 ,- OLMCPR(P) = 2.34+0.0125*(29%-P), Flow > 60%
21 W' 2.1 ' For P P(Bypass) o K(P) = 1.39+0.012*(40%-P), 29% 5 P < 40%
P 2.0 L K(P) = 1.15+0.012*(60%-P), 40% -5P < 60%
1 K(P) = 1.00+0.00375*(100%-P), 60% < P 1.9 a.
A 1.8 Operating Limit MCPR (P) = K(P)
- Operating Limit MCPR(100) 1.7
, 1.6 H I
.- 1.5 1.4 .................. ...
0.
"1.3- -o- OLMCPR(P), Row > 60%
-o-- OLMCPR(P), Flow < 60%
1.2 1.1 -
1.0 ,
20 30 40 50 60 70 80 90 100 110 Power (%rated)
See Tables 8.1, 8.1.A, 8.1.B, 8.1.C for Operating Limit MCPR(100)
Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
Rev. No. 23 Pag~e 25 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.3 Exposure Dependent APLHGR 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 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. 23 Page 26 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.4 Stability Option 1-D Exclusion Region 110 100 90 80 70 L:
0 60 0.
50 40 30 20 20 25 30 35 40 45 50 55 60 65 70 Flow, % rated See References 3.17 and 3.8 for details Rev. No. 23 Page 27 of 32
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__33 Page 28 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.6.A Flow-Dependent APLHGR/LHGR Multiplier, MAPFAC(F) and LHGRFAC(F) 1.0 0.
0 LHGR(F)=LHGRFAC(F)*LHGRst 0d, X f I 85% 1.00 I 0.4 110% 1.00 i 0.36d 30 40 50 60 70 80 90 100 110 Core Flow (rated)
For clarity text in Figure refers to LHGR only, however Figure applies equally to both APLHGR and LHGR See Figure 8.5 and Table 8.2 for LHGRstd value See Figure 8.3 and Table 8.3 for APLHGRstd value Rev. No. 23 Page 29 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.6.B Power-Dependent APLHGR/LHGR Multiplier, MAPFAC(P) and LHGRFAC(P) 1.1 1 .0 ...... - 0 LHGRFAC, L G R A , Above F o < Pb0 pass ..........
1.0 ----- LHGRFAC, Flow:560o
-a----LHGRFAC, Flow>60% -
- 0.9 fl' 0.8
-I I
-" 0 .70 LHGR(P) =LHGRFAC(P)*LHGRstd, LHGRstd = Rated LHGR limits
- 0. For P < 25% No Thermal Limits Monitoring L. Required 0.5 For 25%.: P < 29%
LHGRFAC(P) = 0.58, Core Flow < 60%
LHGRFAC(P) = 0.55, Core Flow > 60%
0.4 For P > 29%
LHGRFAC(P) = 1.0+0.005224*(P-100%)
0.3_, _ __ _ ,_ __ _ _ ,
20 30 40 50 60 70 80 90 100 Power, (% rated)
For clarity text in Figure refers to LHGR only, however Figure applies equally to both APLHGR and LHGR See Figure 8.5 and Table 8.2 for LHGRstd values See Figure 8.3 and Table 8.3 for APLHGRstd value Rev. No. 23 Page 30 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.7 Cycle 18 Loading Pattern by Bundle Design North
~~E 52 E]E]QEl F1 E,IEn' ED E]: IE 50 48o I'
[EE][EF 'lF F [E][ EI-E EA][A]* E-A[AD
]* [ADl [AD F] [E [E [D 46 '*- ýj 'e W - j -*-
42 IT11El D' ET I PEIIM'I D I DT PE 119911 IeFl2lI IE~lt-1 MI' PO E--1EI LJ 40 [FE]E]
[A] EA] EC] EA] [E] [E]L[E] [E] [E] E]( [CD [AD*]DD [AD [CD [E][DE] EA0 36 04 EE]Do[E]E PE[E] E+]2TE]Eim
] [ED [A] EC] EAE] E] E]
E]IE E]_E] ****[D](AD [EE E]OE 30] ELSE] ED[0M EA]
2]
32 Let6e E' -*
"P [ -] MINl [ M' 1] ElE]..EE] E1119[ E- [PE M EMP 'eE E 110*
322 E] EC]
r- [CA [D (AD EC] [AD.[D-A [A [] ] A-ECE A C-A C A C A B B 20 180 28~~ El E]r E]D BE [AE EC] [EEA D A[DE ] B CE
[AE] EC EOE]
F][D[D EA BAE l B ] [E]E D][ECE E]L[E]
[AE EC]BEC E]AE EA]
[AD[C
]D] []D EC] [AE E][D A E] FE j[ AE]E EC][BD [E]E 14 FI A AAD A9I Ai09ICA1DTP A GAG1 A E 12 AE AE C]J A][ CEE AEC] EA] AE C[ C A] C] A EA] F A F]
6 [][E EEA ] AE Aj ACE ACE AG D AC D A C A AF rEjr 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 Fuel Type A=GE 14-P 1ODNAB405-16GZ- 100T-150-T6-2794 (Cycle 17) D=GE 14-P 1ODNAB405-16GZ- I OOT- 150-T6-2906 (Cycle 18)
B=GE14-P1ODNAB405-l5G6.0-100T-150-T6-2793 (Cycle 17) E=GE14-PIODNAB405-16GZ-IOOT-150-T6-2562 (Cycle 16)
C=GE14-PIODNAB402-10G6.0/4G5.0/1G2.0-100T-150-T6-2905 F=GE14-P1ODNAB405-16GZ-100T-150-T6-2563 (Cycle 16)
(Cycle 18)
Rev. No. 2__3 Page 31 of 32
CORE OPERATING LIMITS REPORT CYCLE 18 FIGURE 8.8 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; 0 Cycle exposure range of BOC to EOC18
- = 0
- Dual recirculation pump operation
- Four steam line operation, and
- Normal Feedwater Temperature 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 EOC18 - 3.5 GWD/ST change in MCPR. None OLMCPR changes to EOC values at cycle exposure of 12.0 GWD/ST Scram Time Test Results such that RAP-7.4.1
'r # 0 Use new T and see Figures 8.1, 8.1.A, Option B limits for OLMCPR must 8.1.B, 8.1.C be interpolated with Option A limits Single Loop Operation Increase MCPR Limits by 0.02, or change The SLMCPR increases by 0.02 and acceptance criterion in ST-40D to 0.98.
therefore OLMCPR limits increase Verify that 3D-Monicore has recognized ST-40D, by 0.02. LHGR and MvLXPLHGR the idle recirculation loop and is applying are reduced by a multiplier in SLO. the SLO LHGR and IVAPLHGR multiplier of 0.78.
Three SteamLine Operation (3SL) Increase OLMCPR according to Table OLMCPR values increase by 0.02 8.1.A or Figure 8.1.A(T # 0). None when operating on 3SL Operation with Turbine Bypass Valves Out-of-Service Increase OLMCPR according to Table None OLMCPR values increase, no 8.1.B or Figure 8.I.B(,T # 0).
LHGR change required Operation under Final Feedwater Temperature Reduction Increase OLMCPR according to Table None OLMCPR values increase, no 8.1.C or Figure 8.1.C(tr # 0).
LHGR change required Rev. No. 2_3 Page 32 of 32