JAFP-08-0106, Core Operating Limits Report, Revision 24
| ML082890546 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/10/2008 |
| From: | Eugene Dorman Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-08-0106 | |
| Download: ML082890546 (58) | |
Text
Contains Proprietary Information per 10 CFR 2.390(b)
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP P.O. Box 110 Eg Lycoming, NY 13093 Tel 315-342-3840 October 10, 2008 JAFP-08-0106 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 24
Dear Sir or Madam:
Attached is Revision 24 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 24 of the COLR incorporates changes as a result of reload analysis completed by Global Nuclear Fuel (GNF) for Cycle 19 operations. In addition, editorial corrections and administrative changes are included that do not alter the intent.
During Cycle 19 JAF will be using GNF-2 fuel. Some of the information normally contained in the COLR is considered to be proprietary by GNF. Consequently, that information, which is contained in Fuel Bundle Information Report 0000-0078-7492-FBIR Rev. 0, dated September 2008 (FIBR), is only referenced in the COLR. For your convenience Enclosure 2 provides a copy of the proprietary version of the FIBR with an affidavit from GNF attesting to its proprietary nature and Enclosure 3 provides a non-proprietary version of the FIBR.
There are no commitments contained in this letter.
Questions concerning this report may be addressed to Mr. William Drews, Reactor Engineering Supervisor, at (315) 349-6562.
Sincerely, Eugene Dorman Acting Licensing Manager ^ O ED :wd v cc: next page contains proprietary information per 10 CFR 2.390(b). When separated from the remainder of the submittal is non-proprietary.
Contains Proprietary Information per 10 CFR 2.390(b)
JAFP-08-0106 Page 2 of 2
Enclosures:
- 1) James A. FitzPatrick Nuclear Power Plant, Core Operating Limits Report Revision 24
- 2) Fuel Bundle Information Report for James A. FitzPatrick Reload 18 Cycle 19 (Proprietary)
- 3) Fuel Bundle Information Report for James A. FitzPatrick Reload 18 Cycle 19 (Non-proprietary) cc:
Regional Administrator, Region I I Mr. Bhalchandra Vaidya 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-G14 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 James A. FitzPatrick Nuclear Power Plant P. 0. Box 136 Lycoming, NY 13093-0136 Enclosure 2 contains proprietary information per 10 CFR 2.390(b). When separated from Enclosure 2 the remainder of the submittal is non-proprietary.
Contains Proprietary Information per 10 CFR 2.390(b)
JAFP-08-0106 ENCLOSURE 1 James A. FitzPatrick Nuclear Power Plant Core Operating Limits Report Revision 24 contains proprietary information per 10 CFR 2.390(b). When separated from Enclosure 2 the remainder of the submittal is non-proprietary.
Entergy NuclearNortheast ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT CORE OPERATING LIMITS REPORT REVISION 24 APPROVED BY: William Drews DATE:
REACTOR ENGINEERING SUPERVISOR APPROVED BY: Kevin Mulligan DATE:
GENERAL MANAGER - PLANT OPERATIONS
CORE OPERATING LIMITS REPORT CYCLE 19 TABLE OF CONTENTS SECTION PAGE 1.0 PU R PO SE ............................................................................................................... 3 2.0 APPLICABILITY ................................................................................................ 3
3.0 REFERENCES
................................................................................................. 3 4.0 D E FIN IT IO N S ...................................................... ................................................ 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) .................................... 9 7.5 RBM Upscale Rod Block Allowable Value .......................................... 10 7.6 Stability Option 1-D Exclusion Region and Buffer Zone ................... 10 8.0 FIGURES AND TABLES ................................................................................. 11 9.0 EX H IBIT S ....................................................................................................... 12
/
Rev. No.. 24' Page 2 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 19 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, thecorrective 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 EC2829, Cycle 19 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-24011-P-A-16 3.8 GNF Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 18 Cycle 19, 0000-0078-7492SRLR, Rev.0, Class I, September, 2008.
3.9 GE Report, GNF2 Fuel Desi.gn Cycle-Independent Analyses for Entergy Fitzpatrick, GEH-
-0000-0074-2662-00, Rev. 0, DRF 0000-0074-2662, August 2008.
Rev. No.. 24 Page 3 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 3.10 not used 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.
3113 JD-02-122, Final Feedwater Temperature Reduction Implementation.
31.14 GE Report, GE14 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, Fuel Bundle Information Report for James A. FitzPatrick Reload 18 Cycle* 19, 0000-0078-7492FBIR, Revision 0, September 2008.
3.16 JF-03-00402, ARTS/MEOD Phase 1 Implementation 3.17 JAF-RPT-MISC-04489, Rev.5, 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 106 lb/hr.
Rev. No. 24 Page 4 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 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 Supervisor:
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. 24 Page 5 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 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:
TAVE <- TB 7.1.2.2. The average scram time to notch position 36 is determined as follows:
n INi-ri i=l TA VE n XNi 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. 24 Page 6 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 7.1.2.3. The adjusted analysis mean scram time is calculated as follows:
-1/2
'rB(sec) =/u + 1.65 a Ni n
I_.Ni i=lI WHERE:
t 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. 'CB < cAvE), THEN the Operating Limit MCPR values (as a function of 'r) 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.
TB = The adjusted analysis mean scram time as defined in 7.1.2.3.
TrA the scram time to notch position 36 as defined in Technical Specification Table 3.1.4-1.
Rev. No. 24 Page 7 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 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 limit, MCPR(F), 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 TB >
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) 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 and 0.85 for GNF2 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 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 GE14) or 0.85 (for GNF2) 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 LHGRstd in Table 8.2.
Rev. No.. 24 Page 8 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 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 LHGR,,d in Table 8.2.
LHGR (F) = LHGRFAC(F) x LHGR,,d 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:
S5 (% 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%
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)
Rev. No. 24 Page 9 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 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. 24 Page 10 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 8.0 FIGURES AND TABLES 8.1 FIGURES Figure 8.1. MCPR Operating Limit Versus 'T Figure 8.1.A. MCPR Operating Limit Versus 't for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service Figure 8.13 MCPR Operating Limit Versus 't for Operation with Turbine Bypass Valves Out of Service Figure 8.1.C MCPR Operating Limit Versus tr for 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 Limits Figure 8.4 Stability Option 1-D Exclusion Region Figure 8.5 Exposure Dependent LHGR Limits Figure 8.6.A Flow-Dependent LHGR Multiplier, LHGRFAC(F)
Figure 8.6.B Power-Dependent LHGR Multiplier, LHGRFAC(P)
Figure 8.7 Cycle 19 Loading pattern, Full Core by Bundle Design Figure 8.8 Users Guide Rev. No. 24 Page 11 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 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 Table 8.3 APLHGR Limits 9.0 EXHIBITS NONE Rev. No. 24 Page 12 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure GE14 Fuel Cycle 19 Exposure Range GNF2 Fuel BOC to MOC 1.44 1.44 MOC to EOC 1.45 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.
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. 24 Page 13 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 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 GE14 Fuel Cycle 19 Exposure Range GNF2 Fuel BOC to MOC 1.45 1.46 MOC to EOC 1.47 1.46 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.. 24 Page 14 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 TABLE 8.1.B MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service Cycle 19 Exposure Range GNF2 Fuel GE14 Fuel BOC to EOC 1.48 1.46 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 oft to assure adjustment per Step 7.1.4
- 2. Applicable for any value of K, see Step 7.5.2 Rev. No. 24 Page 15 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 TABLE 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction Cycle 19 Exposure Range GNF2 Fuel GE14 Fuel At EOC only 1.45 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.
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 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. 24 Page 16 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 TABLE 8.2 Maximum LHGR - GE14 Peak Pellet Exposure, GWD/ST U0 2 LHGR Limit, kW/ft 0.00 13.40 14.51 13.40 57.61 8.00 63.50 5.00 Peak Pellet Exposure, GWd/ST Most Limiting Gadolinia LHGR Limit, kW/ft 0.00 12.26 12.28, 12.26 55.00 7.32 60.84 4.57 Maximum LHGR - GNF2 Peak Pellet Exposure, GWD/ST U0 2 LHGR Limit, kW/ft See Reference 3.15 for GNF2 LHGR limits Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
Design features of the fuel assemblies in the Cycle 19 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 0.85 (for GNF2 fuel) or 0.78 (for GEI4)
Linearly interpolate for LHGR at intermediate exposure For Cycle 19 the Peak Pellet Exposure of GNF2 fuel is limited to 45 GWD/MT (40.82 GWD/ST)
Rev. No. 24 Page 17 of 31
CORE OPERATING LIMITS REPORTC CYCLE 19 TABLE 8.3 Exposure Dependent APLHGR Limits GEl4 Fuel Types 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 GNF2 Fuel Types Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 13.78 13.24 13.78 17.52 13.78 40.82 10.40 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)
For single loop operation these APLHGR values shall be multiplied by 0.85 for GNF2 fuel or 0.78 for GE14 fuel Linearly interpolate for APLHGR at intermediate exposure Rev. No. 24 Page 18 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 FIGURE 8.1 MCPR Operating Limit VersusT For GE14 Fuel
-*--- BOC to EOCl 9 - 2.1 GWd/St.
EOC19 - 2.1 GWd/St to EOC19
.t................................. E 1 .6 0 C1 1.55 . ..... . ....... ...... ..........
IL 1.55 ...... .........................................
1.50 1 .4 5 1.43 i.......--`'-... ......--
- 7 0. 0. 1 .5 0 -.
1 .4 0 .................. ..............
3 1.39 _ _
1.35 1 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 t+
For GNF2
- --- BOC to EOC1 9 - 2.1 GWd/St EOC19- 2.1 GWd/St to BOC19 B- 9.55 1.52 .............
... . +.... .. ! ....................
+ *................... ............................
1.52 ----- - ---------------------- - v - - --------- ------- .5 1 .5 2 . . . . ... .. . .[.............. * ' *
- __
- _ +.......... +. .. . . . ........................ . . .................. ...
1.46 ....... ............ ... ......................................................
1.40 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. 24 Page 19 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 FIGURE 8.1.A MCPR Operating Limit Versus For Operating with Three Steam Lines in Service For GE14 Fuel
- ,-- BOCto EO019 - 2.1 GWd/St
- 0-- EOC1 9 - 2.1 GWd/St to EOC1 9
.62 CL 1.60 1 .55
- 1.50 .52 i 1.45 1.40 0*
1 .35 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 For GNF2 Fuel
- -- BOG to EOC19 - 2.1 GWd/St EOC19 - 2.1 GWd/SttoOC19 157 L1.54 .1 V
>I53 1.52
__ i j -;
J 1.50 i'47 1 * " _'_ ----. '
2)1.48 1.46 1.44 t-43 142,'
0 0.1 0.2 0.3 0.4 n.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. 24 Page 20 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 FIGURE 8.1.11 MCPR Operating Limit Versus c for Operation with Turbine Bypass Valves Out of Service For GE14 Fuel
-*- BOC19to EOC19TBVOOS 1 .6 I I 0~ ."- 1.63 1.60
- IE 1.55 k 1.50 -1.46,"
0 1.45 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 For GNF2 Fuel 1.60 n -.- 60 19 to -OC19 TBVOOS r 1.58
>1.58 1.56 1.54 21.52 1.48 __ _
1.50 1.48 1.46 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 1r 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. 24 Page 21 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 FIGURE 8.1.C MCPR Operating Limit Versus T for Operation with Final Feedwater Temperature Reduction For GE14 Fuel 1.65 1.60 .60
-j 1.55
- 0) 1.50 C
1.45 1.40 0 0.1 0.2 0.3 ' 0.4 0.5 0.6 0.7 0.8 0.9 1 For GNF2 Fuel 1.56 FW-R a- "I I IVV
-~
1.54 1.52 I.
"D ,1.50 0- 10-1.48
-"5 1.46 1.44 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. 24 Page 22 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 FIGURE 8.2.A MCPR(F) Factor 1.6 -i!= 112%-TLO
. For Maximum 1 1 2 % Flow of 1.6 112%
IL
- For T-O
~1.5 ----- Flow,% MCPR(F)
- 0. 30 1.566 C.) 87.54 1.220 L.4 increases by 0.02 for all flows M1.4 S. ............... ...... .. ............. ...
.1.3 41.2 1.1 1 20 30 40 50 60 70 80 90 100 110 Core Flow (% rated)
Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
Reference 3.9 Rev. No. 24 Page 23 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 Figure 8.2.B K(P), OLMCPR(P) <Factor 2.8 Operating Limit MCPR (P) = K(P)
- Operating Limit 2.7 - ------ - - -.............. M C P R (100) 2For P<25%: No Thermal Limits Monitoring Required, No limits specified
'2.5 ... ..... For 25%*P<P(Bypass), P(Bypass)=29%
OLMCPR(P)=2.29+0.0125*(29%-P), Flow*60%
OLMCPR(P)=2.56+0.0275*(29%-P), Flow>60%
For PŽP(Bypass) 2K(P)=1.390+0.0118*(40%-P), 299/6!P<40%
K(P)= 1.189+0.0101 *(60%-P), 40% *P<60%
- ] . K(P)=1.056+0.00532*7(85%-P), 60%sP<85%
2.2 K(P)= 1.00+0.00373*(100%-P), 85%!P< 100%
2.1 2.0 1 .8 ......... ..... ........ ..............
1.9 1 .7 .. .."... ....... .. ...........
1.6 1.4 1.3 1.2 1.1 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)
Reference 3.9 Rev. No. 24 Page 24 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 FIGURE 8.3 Exposure Dependent APLHGR Limit GE14 Fuel 16- -
14 12 6-i:..................................... ....................
4-2 0- ' IIII 0 5 10 15 20 25 30 35 40 45 50 55 60 65 Planar Exposure, GWD/ST GNF2 Fuel 16 14 ..........................
12- ..........................
10-8 6-4-
2-0-
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 for GE14 fuel and 0.85 GNF2 fuel.
Reference 3.8 Rev. No. 24 Page 25 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 FIGURE 8.4 Stability Option 1-D Exclusion Region 110 100 90 80 V
70 0
0 0"
o- 60 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 The Cycle 19 Exclusion Region boundary is applicable for Cycle 19 exposure up to 15750 MWD/ST Rev. No. 24 Page 26 of 31
CORE OPERATING LIMITS REPORT CYCLE, 19 FIGURE 8.5 Exposure Dependent LHGR Limit GE14 Fuel 15 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 GNF2 Fuel 15 14-13-12 -
11 - See Reference 3.15 for GNF2 LHGR limits 10- ..
9-8-
7-6-
5- U 02 only.............................
4-3-
l UO2"Tw/°Gd2 3 U02-6w/oGd2O3I ..........
2- U02-7w/oGd2O3 1-nv 0 5 10 15 20 25 30 35 40 45 50 55 60 65 PELLET EXPOSURE GWDfST 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 19 core are provided in Reference 3.3 Rev. No. 24 Page 27 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 FIGURE 8.6.A Flow-Dependent LHGR Multiplier, LHGRFAC(F) 1.10 1.00 U-z
-J 0.90 cc
< 0.80 U-C.
t- 0.70 0
.,6.
IL o 0.60 LHGR(F)=LHGRFACf*LHGRstd U- Max Flow= 112%
0 Flow LHGRFACf 0.50 30% 0.626
-J 85% 1.000
- 0. 110% 1.000 0.40 0.30 30 40 50 60 70 80 90 100 110 Flow, %rated See Figure 8.5 and Table 8.2 for LHGRstd value Reference 3.9 Rev. No. 24 Page 28 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 FIGURE 8.6.B Power-Dependent LHGR Multiplier, LHGRFAC(P)
"1"1 I I 0 .9 ...........-
1.
0.8-a-
0.6 - '
_j_ .............
... .... Pby s 29%...........
LHGRFA~p:
fFor P<25%, Nob or--%,*6% Thermal Limits Required
, , for <29%P, >60%F LHGRFACp = 0.531+0.0045"(P-29) 0.5
' for <29%P, <60%F i LHGRFACp =0.581 0.4 ...............
0.4 for 29%<P-100%
LHGRFA~p = 1.000+0.00528"(P-100) 0.34-'--
20 30 40 50 60 70 80 90 100 Power, % rated See Figure 8.5 and Table 8.2 for LHGRstd values Reference 3.9 Rev. No. 24 Page 29 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 FIGURE 8.7 Cycle 19 Loading Pattern by Bundle Design North 52 52 AD EA[A]~~~~]
I_*(LB,]_EA LA[ýf]EA]EA]+/-
[]
50 lB 48 MB[A [A]2--[B [A] DIDI
__IEC EC [A [A [AEA]EC 1+/- m
[A] EC [BE m
[A EA] [E 46 EIE111E-I1Fll[] FIIF] IEIE1FI - L E1 -:1-EIN I2910E1 42 40 *[1]ED_[] Fsc El1[cE
_4El [HE [DO F2] 19 SO] FC] E]EC] [E] [_E]
38 E8 Aj ?l19 A WEj H GF Fj 1D 01 0 IJWILC 10MW II WIEl IIFFE 36 I'EB[A] [.CgF [1.]F[Cg [gI DlIlIIE ~ )) [G][]
Ej[C ]F* *[
34 32 A] A] Am C] I]F EDl] [J]E] [G] [E]E]EC]F S]E]E][E[
M G][]EGElC J I][: El CA AMIA 32 CFI 28mm[E]DFEm__*[]
- m__*E] [E]_FIE] E][E]~GF r+
E] E]E] r r r**]m
[+/-] A]*_LE*IE F [G_JEC 26 A][9 El ID 24 EA 1 G _D] CE] [E]E] [Go [E]F EC] EG _ _$EC] EJI2 LAoA ME] RlEaN lIWF1NP9M6 mJ 22 AD [A] E_.
+/-A]
20 WE121EN"G'I 18
[EE] *__[G]E))
J]._ NI
[E]NI[G]EC]E]OW[gGE] BG[E]IN [GE] [Cgr W'EI WE
[E]EJ]
rG EII'
[A][A]D raI 16 16
+/-[A] EC]r EGr [H] [F]ED]EE] [GoE] [FE]E] EG__
[]rnoIEniIL 2C] _4 [E]--[H]
EG] [_D L
nGE]
J2 DD 14 J LiL E]L aI ~ieJ 10 P-p W ElHmIIH]
8 1I EI]
4 D A] E][A E][ [E][A]A]A] [_A] D F1_E][
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 FuelType A=GEI4-PIODNAB405-16GZ-IGOT-150-T6-2794 (Cycle 17) F=GNF2-P10DG2B377-13GZ-100T2-150-T6-3073 (Cycle 19)
B=GEI4-PIODNAB405-15G6.0-IGOT-150-T6-2793 (Cycle 17) G=GNF2-P10DG2B379-14GZ-100T2-150-T6-3074 (Cycle 19)
C=GEI4-PIODNAB402-I0G6.0/4G5.0/IG2.0-IO0T-150-T6-2905 (Cycle 18) H=GNF2-PIODG2B396-15GZ- 100T2-150-T6-3075 (Cycle 19)
D=GEI4-PIODNAB405-16GZ-I0OT-150-T6-2906 (Cycle 18) I=GNF2-PIODG2B407-6G6.0/6G5.0- 1OOT2-150-T6-3076 (Cycle 19)
E=GEI4-PIODNAB402-I0G6.0/4G5.0/IG2.0-1GOT-150-T6-2905 (Cycle 18) J=GNF2-PIODG2B394-13GZ-100T2-150-T6-3077 (Cycle 19)
Rev. No. 24 Page 30 of 31
CORE OPERATING LIMITS REPORT CYCLE 19 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;
- Cycle exposure range of BOC to EOC19 r= 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.
Procedure Change in Operating State Change in Limits Reference Cycle Exposure = EN-DC-503 EOC19 - 2.103 GWD/ST See Table 8.1 or Figure 8.1 for tr
exposure of 12.477 GWD/ST. Databank will use 12.100 GWD/ST to account for all uncertainties.
Scram Time Test Results such that Tr# 0 Option B limits for OLMCPR must be Use 1 newC and see Figures 8.1, 8.1.A, 8.1.B, RAP-7.4.1 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-40X to 0.98.
therefore OLMCPR limits increase by 0.02. Verify that 3D-Monicore has recognized the ST40X, LHGR and MAPLHGR are reduced by a idle recirculation loop and is applying the multiplier in SLO. SLO LHGR and MAPLHGR multipliers of 0.78 for GE14 and 0.85 for GNF2.
Three Steam Line Operation (3SL) Increase OLMCPR according to Table 8.1.A OLMCPR values increase by 0.02 when or Figure 8.1.A(' #0). None operating on 3SL Operation with Turbine Bypass Valves Out-of-Service Increase OLMCPR according to Table 8.1.B OLMCPR values increase, no LHGR or Figure 8.1.B(tr # 0). None change required Operation under Final Feedwater Temperature Reduction Increase OLMCPR according to Table 8.1.C OLMCPR values increase, no LHGR or Figure 8.1.C(T # 0). None change required Rev. No. 24 Page 31 of 31
Contains Proprietary Information per 10 CFR 2.390(b)
JAFP-08-0106 ENCLOSURE 3 Fuel Bundle Information Report For James A. FitzPatrick Reload 18 Cycle 19 (Non-proprietary) contains proprietary information per 10 CFR 2.390(b). When separated from Enclosure 2 the remainder of the submittal is non-proprietary.
GIr Global Nuclear Fuel A Joint Vemlire of GE. Toshiba. & Hitachi 0000-0078-7492-FBIR-NP Revision 0 Class I September 2008 Non-ProprietaryInformation Fuel Bundle Information Report for James A. FitzPatrick Reload 18 Cycle 19
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF-A) solely for use by Entergy Nuclear Northeast ("Recipient") in support of the operating license for FitzPatrick (the "Nuclear Plant").
The information contained in this report (the "Information") is believed by GNF-A to be an accurate and true representation of the facts known by, obtained by or provided to GNF-A at the time this report was prepared.
The only undertakings of GNF-A respecting the Information are contained in the contract between Recipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") and nothing contained in this document shall be construed as amending or modifying the Fuel Contract. The use of the Information for any purpose other than that for which it was intended under the Fuel Contract, is not authorized by GNF-A. In the event of any .such unauthorized use, GNF-A neither (a) makes any representation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness of the Information or that such unauthorized use may not infringe privately owned rights, nor (b) assumes any responsibility for liability or damage of any kind which may result from such use of such information.
Information Notice This is a non-proprietary version of the document 0000-0078-7492-FBIR, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( )).
Page 2
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0
- 1. Introduction and Summary This report, which supplements the Supplemental Reload Licensing Report, contains thermal-mechanical linear heat generation rate (LHGR) limits for the GNF-A fuel designs to be loaded into James A.
FitzPatrick for Cycle 19. These LHGR limits are obtained from thermal-mechanical considerations only.
Approved GNF-A calculation models documented in Reference I were used in performing this analysis.
LHGR limits as a function of exposure for each bundle of the core design are given in Appendix A. The LHGR values provided in Appendix A provide upper and lower exposure dependent LHGR boundaries which envelope the actual gadolinia dependent LHGR limits. The LHGRs reported have been rounded to two places past the decimal.
Appendix B contains adescription of the fuel bundles. Table B-i contains a summary of bundle-specific information, and the figures provide the enrichment distribution and gadolinium distribution for the fuel bundles included in this appendix.
For GNF2 thermal-mechanical analysis issues with GSTR-M applicability beyond rr
)) This is in accordance with Entergy Nuclear Northeast letter FitzPatrick Cycle 19 SRLR and GNF2 Peak Pellet Exposure Limitation, CEXO 2008-00254, August 12, 2008.
Page 3
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0
- 2. References
- 1. General Electric Standard Application for Reactor Fuel, NEDE-240 11-P-A-16, October 2007; and the U.S. Supplement, NEDE-2401 I-P-A- 16-US, October 2007.
Page 4
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 Appendix A UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P1ODNAB405-16GZ-1OOT-150-T6-2794 (GEI4C)
Bundle Number: 2794 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft 1Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((
Page 5
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GE 14-P IODNAB405-15G6.0-1OOT- 150-T6-2793 (GE 14C)
Bundle Number: 2793 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 2 GWd/MT (GWd/ST) kW/ft
((
2 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (( I].
Page 6
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 UO 2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GEl 4-P1I ODNAB405-16GZ-1 OOT- 150-T6-2906 (GE14C)
Bundle Number: 2906 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00(0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft Il ____________________
3 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((
Page 7
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GEl 4-PI ODNAB402-10G6.0/4G5.0/1 G2.0-1 OOT-1 50-T6-2905 (GEl 4C)
Bundle Number: 2905 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft 0.00 (0.00) 13.40 16.00 (14.51) 13.40 63.50 (57.61) 8.00 70.00 (63.50) 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 4 GWd/MT (GWd/ST) kW/ft
((I____________________
4 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (( 11.
Page 8
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-P10DG2B377-I 3GZ-100T2-150-T6-3073 (GNF2)
Bundle Number: 3073 Peak Pellet Exposure UO LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia 5
LHGR Limit GWd/MT (GWd/ST) kW/ft
((I____________________
5 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((
Page 9
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-PI0DG2B379-I4GZ- 100T2-150-T6-3074 (GNF2)
Bundle Number: 3074 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 6 GWd/MT (GWd/ST) kW/ft LL 6Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((
Page 10
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-PI 0DG2B396-1 5GZ-100T2-150-T6-3075 (GNF2)
Bundle Number: 3075 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 7 GWd/MT (GWd/ST) kW/ft
[R 7 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this-bundle design ((
Page ll
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-PI 0DG2B407-6G6.0/6G5.0- 100T2-150-T6-3076 (GNF2)
Bundle Number: 3076 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit' GWd/MT (GWd/ST) kW/ft
((i "Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design ((
Page 12
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 UO2/Gd Thermal-Mechanical LHGR Limits Bundle Type: GNF2-PI 0DG2B394-13GZ-100T2-150-T6-3077 (GNF2)
Bundle Number: 3077 Peak Pellet Exposure U0 2 LHGR Limit GWd/MT (GWd/ST) kW/ft Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit 9 GWd/MT (GWd/ST) kW/ft 9 Bounding gadolinia LHGR limit for all gadolinium concentrations occurring in this bundle design (( I].
Page 13
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 1 Class I Revision 0 Reload 18 Appendix B Fuel Bundle Information Table B-1 Bundle Speciflc Information WightMax Weigt Exposure Fuel Bundle Enrichment Weight Weight Max E kxs of U0 2 Of U k. at Bundle Number (wt% U-235) (kg) (kg) 200C 10 GWd/MT (GWd/ST)
GE 14-P 1ODNAB405-16GZ-100T-150-T6-2794 (GE14C)
GE14-PI ODNAB405-15G6.0-1OOT-150-T6-2793 (GEI 4C)
GE 14-P 1ODNAB405-16GZ-100T-150-T6-2906 (GEI4C)
GE 14-PI 0DNAB402-10G6.0/4G5.0/1 G2.0-1OOT- 150- 2905 T6-2905 (GEI4C)
GNF2-PI 0DG2B377-13GZ-100T2-150-T6-3073 (GNF2)
GNF2-PI 0DG2B379-14GZ-100T2-150-T6-3074 (GNF2)
GNF2-PI 0DG2B396-15GZ-100T2-150-T6-3075 (GNF2)
GNF2-P 10DG2B407-6G6.0/6G5.0-100T2-150-T6- 3076 3076 (GNF2)
GNF2-PI 0DG2B394-l 3GZ-100T2-150-T6-3077 (GNF2) 10Maximum lattice k. for the most reactive uncontrolled state plus a R
)) adder for uncertainties.
Page 14
Fitzhitrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Relonid 18 Class I Revision 0 11 Figure B-1 Enrichment and Gadolinium Distribution for EDB No. 2794 Fuel Bundle GE14-P1ODNAB405-16GZ-100T-150-T6-2794 (GE14C)
Page 15
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0
[1 Figure B-2 Enrichment and Gadolinium Distribution for EDB No. 2793 Fuel Bundle GE14-P1ODNAB405-15G6.0-1OOT-150-T6-2793 (GE14C)
Page 16
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 Figure B-3 Enrichment and Gadolinium Distribution for EDB No. 2906 Fuel Bundle GE14-P1ODNAB405-16GZ-100T-150-T6-2906 (GE14C)
Page 17
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 Figure B-4 Enrichment and Gadolinium Distribution for EDB No. 2905 Fuel Bundle GE14-P1ODNAB402-10G6.0/4G5.O/1G2.0-10OT-150-T6-2905 (GE14C)
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FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0
[1 Figure B-5 Enrichment and Gadolinium Distribution for EDB No. 3073 Fuel Bundle GNF2-P10DG2B377-13GZ-100T2-150-T6-3073 (GNF2)
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FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0 I'l 1]
Figure B-6 Enrichment and Gadolinium Distribution for EDB No. 3074 Fuel Bundle GNF2-P10DG2B379-14GZ-100T2-150-T6-3074 (GNF2)
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FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0
((
Figure B-7 Enrichment and Gadolinium Distribution for EDB No. 3075 Fuel Bundle GNF2-P10DG2B396-15GZ-100T2-150-T6-3075 (GNF2)
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b FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class I Revision 0
[r Figure B-8 Enrichment and Gadolinium Distribution for EDB No. 3076 Fuel Bundle GNF2-P10DG2B407-6G6.0/6G5.0-100T2-150-T6-3076 (GNF2)
Page 22
FitzPatrick Non-Proprietary Information 0000-0078-7492-FBIR-NP Reload 18 Class 1 Revision 0 1[
Figure B-9 Enrichment and Gadolinium Distribution for EDB No. 3077 Fuel Bundle GNF2-P10DG2B394-13GZ-100T2-150-T6-3077 (GNF2)
Page 23