ML20236V770
| ML20236V770 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/31/1998 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20236V767 | List: |
| References | |
| NUDOCS 9808040196 | |
| Download: ML20236V770 (41) | |
Text
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i Administrative Technical Requirements Appendix A (Amendment 18)
LaSalle Unit 1 Cycle 8 Core Operating Limits Report and Reload Transient Analysis Results July 1998 1
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9900040196 900728 r PDR ADOCK 05000373 p
PDR:;
i Administrative Technical Requirements - Appendix A i
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Section 1 i
LaSalle Unit 1 Cycle 8 i
Core Operating Limits Report July 1998 l
1
1 Administrative Technical Requiram:nts - Appendix A L1C8 Core Operating Limits Report i
Issuance of Changes Summary Affected Affected Summary of Changes Date Section Pages I
All All Original issue (Cycle 8) 3/96 All All Format Changes 7/98 Addition of Reload Transient Analysis Results section Changes to Thermal Limits to allow for changed RR FCV minimum position setpoint, changed APRM flux scram analytical value, operation at less than rated pressure and deletion of automatic flow controllimits.
i Change to EOOS combinations allowing for operation with one TCV stuck closed in various combinations.
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1 LaSalle Unit 1 Cycle 8 i
July 1998
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- Administrative Technical Requirements - Appendix A L1C8 Core Operating Limits Report 1
l Table of Contents l
1 I
j References.
.. iii 1
Average Planar Linear Heat Generation Rate (3/4.2.1).
...........................1-1 1.1 Tech Spec Reference.......
.11 1.2 Description..
..11 2
Minimum Critical Power Ratio (3/4.2.3)..
. 2-1 1
1 2.1 Tech Spec Reference..................
.2-1 2.2 Description................
. 2-1 3
Linear Heat Generation Rate (3/4.2.4)..............
. 3-1 3.1 Tech Spec Reference......
.3-1 3.2 Description.
. 3-1 4
Control Rod Withdrawal Block Instrumentation (3/4.3.6).
..............................41 4.1 Tech Spec Reference.
... 4-1
!.2 Description.
. 4-1 i
5 Allowed Modes of Operation (B 3/4.2.3).
. 5-1 5.1 Tech Spec Reference....
.... 5-1 5.2 Description..
.. 5-1 I
LaSalle Unit 1 Cycle 8 ii July 1998 u_________________________-_
Administrative Technical Requirements - Appendix A l
L1CB Core Operating Limits Report References 1.
Commonwealth E' 2.on Company Docket No. 50-373, LaSalie County Station, Unit 1 Facility Operating IJcense, License No. NPP-11.
2.
Letter from D. M. Crutchfield to All Power Reactor Licensees and Applicants, Generic Letter 88-16; Conceming the Removal of Cycle-Specific Parameter Limits from Tech Specs, dated October 4,1988.
3.
Suoolemental Reload License Submittal for LaSalle County Station Unit 1 Reload 7 Cycle 8, Rev.1, May 1998.
4.
Neutronics Licensino Report for LaSalle Unit 1 Reload 7. Cvele 8, BND:95-163, December 7,1995.
5.
LaSalle County Station, Units 1 and 2, SAFER /GESTR LOCA Loss-of-Coolant-Accident Analysis, NEDC, 32258P, October 1993 (latest approved revision).
6.
General Electric Standard Acolication for Reactor Fuel (GESTAR), NEDE-24011-P-A (latest approved version).
7.
Extended Ooeratino Domain and Eauipment Out-of Service for LaSalle County Station Units 1 and 2, NEDE-31455 (latest approved version).
i 8.
Eauioment Out-of-Service in the Increased Core Flow Domain for LaSalle County Station Units 1 and 2, GE-NE-l 187-62-1191 (latest approved version).
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9.
Evaluation of a Postulated Slow Turbine Control Valve Closure Event for LaSalle County Station. Units 1 and 2, GE-NE-187-13-0792, Revision 2 July 1998.
90.
ARTS Improvement Proaram Analysis for LaSalle Units 1 and R, NEDC-31531P, December 1993 and Supplement 1, June 1998.
11.
Letter from Hoa Hoang (GE) to Dave Henry (Comed), "LaSalle Recirculation Pump Trip Out-of Service with Feedwater Temperature Reduction," February 1,1995.
12.
Analysis of EFPC Coastdown With Load Followina for LaSalle 1 and 2, GENE-637-016-0693, June,1993.
13.
GE document, DRF AOO-05525, " Safety Evaluation for Feedwater Temperature Variation at LaSalle County Station Units 1 and 2", February 8,1993.
14.
Letter from R. W. Tsai (Comed, Nuclear Fuel Services) to D. A. Henry (Comed, LaSalle Station), "LaSalle Units 1 and 2 Operating Limits with Multiple Equipment Out-of Service (EOOS)*, April 6,1995.
15.
Lattice-Decendent MAPLHGR Report for LaSalle County Station Unit 1 Reload 6 Cvele 7. 23A7231 AA, Rev. O, December 1993. (Reloaded exposed fuel only) 16.
Lattice-Dependent MAPLHGR Report for LaSalle County Station Unit 1 Reload 7 Cvele 8,24A5180AA, Rev. O, December 1995. (New fuel only) 17.
On-Site Review 98-331, "t FSAR Chunges to Sections 7.7.5.2.2 and 15.2.1.1: Abnormal Modes of EHC/ Turbine Operation *.
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LaSalle Unit 1 Cycle 8 iii July 1998
Administrative Technical Requirements - Appendix A L1C8 Core Operating Limits Report 1
Average Planar Linear Heat Generation Rate (APLHGR) (3/4.2.1) 1.1 Tech SoeC
Reference:
Tech Spec 3.2.1 1.2
==
Description:==
The MAPLHGR Limit is determined from Table 1.1, and is either MAPLHGRp or MAPLHGRr, whlChever iS lower at any given power, flow Condition.
TABLE 1.1 anoperable Equipment MAPLHGS.
- MAPLHGR, WRh Core Thermal Power > or = 25%
All Flow Ranges No EOOS Fuel-Type MAPLHGR Limit determined per Table 1.2, Fuel-Type MAPLHGR Limit determined per Table 1.2, muRiplied by MAPFAC, from Figure 1.2-1 multiplied by MAPFAC, from Figure 1.2-3 One SRV OOS / TCV Stuck Closed Fuel-Type MAPLHGR Limit determined per Table 1.2, FueLType MAPLHGR Limit determined per Table 1.2, multiplied by MAPFAC, from Figure 1.21 muniplied by MAPFAC, from Figure 1.2-3 Feedwater Heater (s) 00S '/ One Fuel-Type MAPLHGR Limit determined per Tsble 1.2, FueLType MAPLHGR Limit dvermined per Table 1.2, SRV OOS / TCV Stuck Closed muniphed by MAPFAC, from Figure 1.21 multiplied by MAPFAC, from Figure 1.2-3 Turbine Bypass OOS / One SRV Fuel-Type MAPLHGR Limit determined per Table 1.2, Fuel-Type MAPLHGR Limit determined per Table 1.2, OOS multiplied by MAPFAC,
FueLType MAPLHGR Limit determined per Table 1.2, Fuel-Type MAPLHGR Limit determined per Table 1.2, TCV Stuck Closed / Feedwater multiplied by MAPFAC, from Figure 1.21 multiplied by MAPFAC, from Figure 1.2-3 Heater (s) OOS' EOC RPT OOS / TCV(s) Slow Fuel-Type MAPLHGR Limit determined per Table 1.2, Fuel Type MAPLHGR Limit determined per Table 1.2, Closure / One SRV OOS /
multiplied by MAPFAC, from Figure 1.2-2 multiplied by MAPFAC, from Figure 1.2-3 Feedwater Heater (s) OOS' Single RR Loop / One SRV OOS /
FueLType MAPLHGR LimR determined per Table 1.2, Fuel-Type MAPLHGR Limit determined per Table 1.2, TCV Stuck Closed multiplied by MAPFAC, from Figure 1.2-1 multiplied by o.4, which is MAPFAC, for Single Loop Operation 1.
Up to 100 F reduction (to 320 F) in feedwater temperature allowed at full power with Feedwater Heaters Out-of-Service (reduction varies at off-rated power levels). Up to 13*F reduction in feedwater temperature from nominal allowed at all power levels without feedwater heaters Considered Out-of Service.
LaSalle Unit 1 Cycle 8 1-1 July 1998
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Administrative Technical Requirements - Appendix A L1C8 Core Operating Limits Report l
TABLE 1.2 Table for Fuel-Type Fuel Type Cycle First Number of 1
MAPLHGR Limits inserted Bundles 1.2 1 GE98-P8CWB303-9GZ-100M-150-T 5
108 1.2-2 GE9B-P8CWB313-9GZ-100M-150-CECO 6
128 1.2-3 GE98-P8CWB314-9GZ-100M-150-CECO 6
72 l
1.2-4 G E98-P8CWB322-11 GZ-100M-150-C ECO 7
104 1.2-5 GE98-P8CWB320-9GZ-100M 150-CECO 7
104 1.2-6 GE98-P8CWB343-12GZ-80M 150-CECO 8
104 1.2-7 GE9B-P8CWB342-10GZ-80M-150-CECO 8
144 1
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LaSalle Unit 1 Cycle 8 12 July 1998
l Administrative Technical R:quircmsnts - App ndix A l
L1C8 Cora Op:: rating Limits R port 1
l Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) vs.
Average Planar Exposure for Fuel Type GE9B-P8CWB303-9GZ-100M-150-T Table 1.2-1 Bundle Type 10 Exposure (MWD /ST)
Lattice Specific MAPLHGR (kw/ft)
P8CWLO71 P8CWL327 P8CWL338 P8CWL327 P8CWLO71 NOG 9G5.0 4G5.0/5G4.0 4G5.0/5G4.0 93E O
12.74 11.98 11.35 12.01 12.74 200 12.67 12.05 11.39 12.08 12.67 1000 12.48 12.17 11.48 12.22 12.48 2000 12.42 12.37 11.67 12.43 12.42 3000 12.41 12.56 11.90 12.61 12.41 4000 12.44 12.69 12.16 12.78 12.44 5000 12.46 12.81 12.38 12.91 12.46 6000 12.49 12.92 12.56 13.03 12.49 7000 12.51 13.04 12.75 13.15 12.51 8000 12.54 13.16 12.94 13.27 12.54 9000 12.55 13.29 13.13 13.37 12.55 10000 12.57 13.41 13.29 13.47 12.57 12500 12.41 13.49 13.33 13.51 12.41 l
15000 12.04 13.18 13.05 13.20 12.04 20000 11.27 12.54 12.46 12.55 11.27 25000 10.49 11.84 11.87 11.84 10.49 35000 8.95 10.35 10.54 10.36 8.95 45000 6.15 9.02 9.14 9.02 6.15 46850 5.21 5.21 51460 5.90 51790 5.82 51850 5.81 Lattice Type 28 21 22 23 24 Lattice No.
733 884 885 886 887 i
LaSalle Unit 1 Cycle 8 1-3 July 1998
Administrative Tcchnical Requirem:ints - Appendix A
{
L1C8 Cora Operating Limits Report l
i Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) vs.
Average Planar Exposure for Fuel Type GE9B-P8CWB313-9GZ-100M-150-CECO
{
Table 1.2-2
[
Be,dle Type 11 1
l Exposure (MWD /ST)
Lattice Specific MAPLHGR (kw/ft)
P8CWLO71 P8CWL339 P8CWL350 P8CWL350 P8CWL339 P8CWLO71 NOG 7G4.0 2G4.0/5G3.0 4G4.0/5G3.0 2G4.0/5G3.0 9GE O
12.74 12.34 11.79 11.32 12.35 12.74 200 12.67 12.39 11.84 11.40 12.40 12.67 1000 12.48 12.49 11.96 11.55 12.52 12.48 2000 12.42 12.63 12.12 11.73 12.68 12.42 3000 12.41 12.74 12.28 11.92 12.83 12.41 4000 12.44 12.85 12.40 12.11 12.96 12.44 5000 12.46 12.97 12.49 12.27 13.10 12.46 6000 12.49 13.10 12.58 12.39 13.19 12.49 7000 12.51 13.22 12.67 12.52 13.29 12.51 8000 12.54 13.34 12.76 12.65 13.37 12.54 9000 12.55 13.38 12.84 12.78 13.45 12.55 i
10000 12.57 13.38 12.91 12.89 13.41 12.57 12500 12.41 13.36 12.85 12.85 13.36 12.41 15000 12.04 13.01 12.56 12.56 13.01 12.04 l
20000 11.27 12.34 11.98 11.97 12.33 11.27 25000 10.49 11.69 11.38 11.37 11.69 10.49 35000 8.95 10.46 10.12 10.11 10.46 8.95 j
45000 6.15 9.12 8.53 8.50 9.13 6.15 46850 5.21 5.21 50360 5.84 50390 5.85 51860 5.84 51880 5.84 Lattice Type 29 30 31 32 33 34 Lattice No.
733 1577 1578 1579 1580 1581 l
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LaSalle Unit 1 Cycle 8 1-4 July 1998 l
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Administrative Technical Rcquiremants - Appendix A L1C8 Core Operating Limits Report l
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) vs.
Average Planar Exposure for Fuel Type GE9B-P8CWB314-9GZ-100M-150-CECO Table 1.2-3 Bundle Type 12 Exposure (MWD /ST)
Lattice Specific MAPLHGR (kw/ft)
P8CWLO71 P8CWL339 P8CWL350 P8CWL350 P8CWLO71 NOG 7G4.0 7G4.0 9G4.0 9GE O
12.74 12.34 11.77 11.50 12.74 200 12.67 12.39 11.83 11.55 12.67 l
1000 12.48 12.49 11.94 11.66 12.48 2000 12.42 12.63 12.08 11.80 12.42 3000 12.41 12.74 12.22 11.93 12.41 4000 12.44 12.85 12.37 12.07 12.44 5000 12.46 12.97 12.47 12.20 12.46 6000 12.49 13.10 12.56 12.34 12.49 7000 12.51 13.22 12.65 12.49 12.51 8000 12.54 13.34 12.74 12.64 12.54 9000 12.55 13.38 12.83 12.79 12.55 10000 12.57 13.38 12.90 12.90 12.57 1
12500 12.41 13.36 12.84 12.84 12.41 15000 12.04 13.01 12.55 12.55 12.04 20000 11.27 12.34 11.97 11.97 11.27 25000 10.49 11.69 11.38 11.38 10.49 35000 8.95 10.46 10.12 10.11 8.95 45000 6.15 9.12 8.51 8.46 6.15 46850 5.21 5.21 50260 5.85 50370 5.84 51860 5.84 Lattice Type 35 36 37 38 39 Lattice No.
733 1577 1582 1583 1584 l
l LaSalle Unit 1 Cycle 8 15 July 1998
1 Administrative Technical Requiramants - Appendix A L1C8 Coro Operating Limits Report Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) vs.
Average Planar Exposure for Fuel Type G E9B-P8CWB 322-11 GZ-100M-150-C ECO Table 1.2-4 Bundle Type 1 Exposure (MWD /ST)
Lattice Specific MAPLHGR (kw/ft) 1 P8CWLO71 P8CWL345 P8CWL362 P8CWL362 P8CWL345 P8CWLO71 NOG SG5.0/4G4.0 9G4.0 2GS.0/9G4.0 9G4.0 11GE O
12.74 12.09 11.65 11.25 12.11 12.74 l
200 12.67 12.13 11.70 11.32 12.15 12.67 l-1000 12.48
-12.22 11.83 11.46 12.25 12.48 2000 12.47 12.35 12.00 11.61 12.39 12.42 3000 12.41 12.48 12.14 11.77 12.54 12.41 4000 12.44 12.62 12.28 11.94 12.70 12.44 5000 12.46 12.77 12.43 12.11 12.86 12.46 6000 12.49 12.90 12.58 12.29 13.02 12.49 7000 12.51 13.03 12.73 12.46 13.19 12.51 8000 12.54 13.16 12.88 12.64 13.33 12.54 i
9000 12.55 13.30 13.01 12.82 13.43 12.55 10000 12.57 13.42 13.12 12.98 13.44 12.57 l-12500 12.41 13.41 13.08 13.04 13.40 12.41 15000 12.04 13.05 12.78 12.77 13.06 12.04 l
20000 11.27 12.38 12.16 12.16 12.40 11.27 l
25000 10.49 11.74 11.51 11.51 11.76 10.49 35000 8.95 10.52 10.22 10.22 10.53 8.95 45000 6.15 9.13 8.75 8.68 9.13 6.15 46850 5.21 5.21 50680 5.86 50830 5.85 51870 5.83 51910 5.83 Lattice Type 40 41 42 43 44 45
(
Lattice No.
733 1817 1818 1819 1820 1821 L
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LaSalle Unit 1 Cycle 8 1-6 July 1998 i
j Administrative Technical Rcquircm::nts - Appendix A L1C8 Coro Op rating Limits Report l
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) vs.
Average Planar Exposure for Fuel Type GE9B-P8CWB320-9GZ-100M-150-CECO 4
Table 1.2-5 Bundle Type 2 Exposure (MWD /ST)
Lattice Specific MAPLHGR (kw/ft)
P8CWLO71 P8CWL346 P8CWL358 P8CWL358 P8CWL346 P8CWLO71 NOG 4GS.0/3G4.0 7G4.0 2GS.0/7G4.0 7G4.0 9GE2 0
12.74 12.05 11.62 11.10 12.09 12.74 200 12.67 12.09 11.64 11.15 12.14 12.67 1000 12.48 12.19 11.73 11.27 12.25 12.48 2000 12.42 12.32 11.86 11.44 12.39 12.42 3000 12.41 12.44 11.99 11.62 12.53 12.41 4000 12.44 12.57 12.13 11.80 12.67 12.44 5000 12.46 12.70 12.27 11.96 12.81 12.46 2
6000 12.49 12.83 12.42 12.09 12.89 12.49 7000 12.51 12.97 12.54 12.23 12.98 12.51 8000 12.54 13.07 12.62 12.37 13.07 12.54 9000 12.55 13.15 12.70 12.51 13.15 12.55 10000 12.57 13.20 12.77 12.66 13.22 12.57 12500 12.41 13.19 12.70 12.67 13.20 12.41 15000 12.04 12.89 12.40 12.40 12.90 12.04 20000 11.27 12.29 11.82 11.82 12.30 11.27 25000 10.49 11.69 11.25 11.25 11.70 10.49 35000 8.95 10.46 10.07 10.07 10.46 8.95 45000 6.15 9.09 8.35 8.26 9.09 6.15 i
46850 5.21 5.21 49790 5.87 49990 5.86
)
51490 5.88 51500 5.88 Lattice Type 46 47 48 49 50 51 Lattice No.
733 1812 1813 1814 1815 1816 l
l-LaSalle Unit 1 Cycle 8 1-7 July 1998 l
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Administrative Technical Requircmnnts - Appendix A L1C8 Cora Operating Limits Rcport i
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) vs.
Average Planar Exposure for Fuel Type GE9B-P8CWB343-12GZ-80M-150-CECO i
I Table 1.2-6 l
Bundle Type 4 l
l Exposure (MWD /ST)
Lattice Specific MAPLHGR (kw/ft)
P8CWLO71 P8CWL3F3 P8CWL390 P8CWL390 P8CWLO71 NOG 10G5.0 10G5.0 12G5.0 12GE l
I O
12.66 11.69 11.37 10.92 12.66 l
200 12.59 11.71 11.43 10.99 12.59 1000 12.40 11.78 11.55 11.13 12.40 2000 12.34 11.95 11.72 11.33 12.34 3000 12.34 12.16 11.91 11.54 12.34 4000 12.37 12.40 12.11 11.76 12.37 5000 12.40 12.67 12.32 12.00 12.40 6000 12.43 12.90 12.53 12.24 12.43 i
7000 12.46 13.05 12.76 12.49 12.46 8000 12.48 13.21 12.98 12.75 12.48 j
9000 12.50 13.37 13.13 13.01 12.50 l
10000 12.51 13.54 13.30 13.22 12.51 l
12500 12.35 13.75 13.60 13.57 12.35 15000 11.98 13.48 13.23 13.21 11.98 20000 11.20 12.71 12.40 12.37 11.20 1
25000 10.42 11.92 11.60 11.57 10.42 35000 8.87 10.36 10.09 10.06 8.87 45000 6.00 8.95 8.66 8.64 6.00 46610 5.19 5.19 51270 5.65 l
51300 5.63 52260 5.70 Lattice Type 1
2 3
4 5
Lattice No.
732 2083 2004 2085 2086 LaSalle Unit 1 Cycle 8 18 July 1998 L-_______________
Administrative Technical Rcquiromants - Appendix A i
L1C8 Cora Op3 rating Limits Report Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) vs.
Average Planar Exposure for Fuel Type GE98-P8CWB342-10GZ-80M-150-CECO Table 1.2-7 1
Bundle Type 5 l
Exposure (MWD /ST)
Lattice Specific MAPLHGR (kw/ft)
P8CWLO71 P8CWL363 P8CWL388 P8CWL388 P8CWL363 P8CWLO71 NOG 8G5.0 8G4.0 2G5.0/8G4.0 8G4.0 10GE O
12.66 12.04 12.25 11.72 12.09 12.66 200 12.59 12.08 12.28 11.77 12.12 12.59 1000 12.40 12.16 12.35 11.87 12.22 12.40 2000 12.34 12.28 12.45 12.00 12.37 12.34 3000 12.34 12.42 12.55 12.13 12.53 12.34 1
4000 12.37 12.57 12.65 12.27 12.70 12.37 l
5000 12.40 12.73 12.76 12.41 12.88 12.40 6000 12.43 12.89 12.87 12.56 13.07 12.43 7000 12.46 13.06 12.98 12.72 13.27 12.46 8000 12.48 13.24 13.10 12.88 13.47 12.48 9000 12.50 13.42 13.21 13.05 13.65 12.50 10000 12.51 13.61 13.31 13.21 13.76 12.51 12500-12.35 13.79 13.35 13.31 13.82 12.35 15000 11.98 13.50 13.06 13.05 13.51 11.98 20000 11.20 12.79 12.47 12.45 12.79 11.20 25000 10.42 11.95 11.67 11.63 11.95 10.42 35000 8.87 10.37 10.08 10.04 10.37 8.87 l
I 45000 6.00 8.96 8.66 8.63 8.96 6.00 46610 5.19 5.19 51070 5.69 51180 5.65 52160 5.72 5.72 Lattice Type 6
7 8
9 10 11
_ Lattice No.
732 2087 2088 2089 2090 2091 l
l LaSalle Unit 1 Cycle 8 19 July 1998 i
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l Administrative Technical Requirements - Appendix A L1C8 Core Operating Limits Report l
t I
2 Minimum Critical Power Ratio (3/4.2.3) 2.1 Tech Soec
Reference:
2.2
==
Description:==
The Goveming MCPR Operating Limit is determined from Teble 2.1, and is either MCPRp or MCPRr, whichever is greater at any given power, flow condition. These limits are not applicable for Automatic RR Flow Control.
TABLE 2.1
- MCPR, MCPR, inoperable Equipment With Core Thermal Power > or a W th Core Therme! Power > or = 30%
All Flow Ranges (Combination Number - Figuree 25% and < 30%
. 2,2-1 and 2.2 2)
No EOOS (#1)
MCPR, from Figure 2.2-3 OLMCPR' from Figure 2.21or Figure 2.2 2'.
MCPR, from Figure 2.2-G multiphed by K, from Figure 22-3 One SRV OOS /TCV Stuck Closed MCPR, from Figure 2.2-4 OLMCPR' from Figure 22-ior Figure 2.2-2, MCPR, from Figure 2.24 8
(#3) -
multiplied by K, from Figure 2.2-4 Foodwater Hester(s) OOS '/ One MCPR, from Figure 2.2-4 OLMCPR' from Figure 2.2-tor Figure 2.2-2, MCPR, from Figure 2.24 2
SRV OOS 1TCV Stuck Closed (#3) multiplied by K, from Figure 2.2-4 Turbme Byness OOS / One SRV MCPR, from Figure 22-4 OLMCPR' from Figure 22-ior Figure 2.2-2, MCPRr from Figure 2.24 8
OOS (#4) multiphed by K, from Figure 2.2 4 EOC-RPT OOS / One SRV OOS /
MCPR, from Figure 2.2-4
' OLMCPR' from Figure 2.2-1or Figure 22-2',
MCPR, from Figure 2.24 TCV Stuck Closed / Fee.1weter multiplied by K, from Figure 2.2-4 Hester(s) OOS'(#5)
EOC-RPT OOS / TCV(s) Slow The greater of either:
OLMCPR' from Figure 22-ior Figure 2.2-2',
MCPR, from Figure 2.24 Closurei One SRV OOS / Feedwater multiplied by K, from Figure 224 3
Hester(s) OOS'(#6)
- 1. OLMCPR from F.gure 2.2-Ior 8
Figure 2.2 2, multipised by K, from Figure 2.2-5 i
MCPR, from Figure 2.2 4 OLMCPR' from Figure 2.2-ior Figure 2.2-P'.
MCPR, = 2.2
' TCV Stuck Closed (#7) multiplied by K, from Figure 22-4 l
1.
Up to 100*F reduction (to 320*F) in feedwater temperature allowed at full power with Feedwater Heaters Out-of-l Service (reduction varies at off-rated power levels). Up to 13*F reduction in feedwater temperature from nominal l
allowed at all power levels without feedwater heatars considered Out-of Service.
2.
If, durin0 Unit Coastdown, power operation exceeding the equilibrium power level is desired, then Figure 2.2-2 shall be used.
I 3.
OLMCPR is the full power MCPR limit.
LaSalle Unit 1 Cycle 8 21 July 1998
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Administrative Technical Requirements - Appendix A l
L1C8 Core Operating Limits Report 1
3 Linear Heat Generation Rate (3/4.2.4) 3.1 Tech Soec
Reference:
3.2
==
Description:==
The LHGR Limit is 14.4 kw/ft for fuel types:
1.
GE9B-P8CWB303-9GZ-100M-150-T 2.
GE98-P6CWB313 9GZ-100M-150-CECO I
3.
GE98-P8CWB314-9GZ 100M-150-CECO l
4.
G E9B-P8CWB322-11 GZ-100M-150-C ECO I
5.
GE9B-P8CWB320-9GZ-100M-150-CECO i
6.
GE98-P8CWB343-12GZ-80M-150-CECO l
7.
GE98-P8CWB342-10GZ-80M-150-CECO i
l l
I l
J LaSalle Unit 1 Cycle 8 3-1 July 1998 u_-------------_--_-_-_
l 1
Administrative Technical Requirements - Appendix A L1C8 Core Operating Limits Report i
4 Control Rod Withdrawal Block Instrumentation (3/4.3.6) 4.1 Tech Spec
Reference:
Tech Spec Table 3.3.6-2.
4.2
==
Description:==
The Rod Block Monitor Upscale instrumentation Setpoints are determined from the relationships shown below:
ROD BLOCK MONITOR UPSCALE TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE Two Recirculation Loop Operation *
< or = 0.66 W + 45%"
< or = 0.66 W + 48%"
Single Recirculation Loop Operation *
< or = 0.66 W + 39.7%"
< or = 0.66 W + 42.7%"
l This setpoint may be lower and will still comply with the RWE Analysis.
Clamped, with an allowable value not to exceed the allowable value for recirculation loop drive flow (W) of 100%.
L:Salle Unit 1 Cycle 8 4-1 July 1998
Administrative Technical Requirements - Appendix A L1C8 Core Operating Limits Report 5
Allowed Modes of Operation (B 3/4.2.3) 5.1 Tech Soec
Reference:
Tech Spec Bases Section B 3/4.2.3.
5.2
==
Description:==
The Allowed Modes of Operation with combinations of Equipment Out-of-Service (EOOS) are as described in Table 5.1 below.
TABLE 5.1 OPERATING REG 40N inoperable Equiprnent Standard ELLLA ICF FFWTR No EOOS Yes Yes Yes Yes One SRV OOS Only Yes Yes Yes Yes Feedwater Hester(s) OOS ' / One SRV OOS Yes Yes' Yes N/A Turbine Bypass 005 / One SRV OOS Yes Yes Yes Yes EOGRPT OOS / OM SRV OOS Yu Yu Yu Yu EOC-RPT OOS / One SRV OOS / Feedwater Hester(s) OOS' Yes Yes*
Yes N/A EOC-RPT OOS / TCV(s) Slow Closure / One SRV OOS Yes Yes Yes Yes EOC-RPT OOS / TCV(s) Slow Closure / One SRV OOS /
Yes Yes*
Yes N/A Feedwater Hester(s) OOS 8
I-TCV Stuck Closed Yes*
Yes Yes Yes Single RR Loop / One SRV OOS Yes Yes N/A No 1.
Up to 100 F reduction (to 320*F) in feedwater temperature allowed at full power with Feedwater Heaters Out-of-Service (reduction varies at off-rated power levels). Up to 13*F reduction in feedwater temperature from nominal allowed at all power levels without feedwater heaters considered Out-of-Service.
2.
If operating with Feedwater Heaters Out-of Service, operation in ELLLA is supported by current transient analyses, but administratively prohibited due to core stability concems.
3.
TCV Stuck Closed may be in combination with any EOOS(s) except TBVOOS or TCV(s) Slow Closure. If in combination with other EOOS(s), Thermal Limits may require adjustment for the other EOOS(s) as designated in Sections 1 and 2.
4.
Operation is only allowed when less than 10.5 million Ibm /hr steam flow and when average position of 3 open TCVs is less than 50% open.
(
LaSalle Unit 1 Cycle 8 5-1 July 1998
Administrative Technical Requirements - Appendix A Section 2 LaSalle Unit 1 Cycle 8 Reload Transient Analysis Results July 1998 l
Administrative Technical Requirements - Appendix A L1C8 Reload Transient Analysis Results Table of Contents Attachment Preparer Document 1
Comed Neutronics Licensing Report 2
General Electric Supplemental Reload Licensing Report 3
General Electric ARTS Improvement Program Analysis, Supplement 1 (Excerpts) h 4
General Electric TCV Slow Closure Analysis (Excerpts) l-5 Comed Additional Reload Transient Analysis Information (Excerpts) i l
l l
LaSalle Unit 1 Cycle 6 July 1988
., ~.
Administrative Technical Requirements - Appendix A L1C8 Reload Transient Analysis Results LaSalle Unit 1 Cycle 8 Neutronics Licensing Report l
l LCSalle Unit 1 Cycle 8 -
July 1998 l
J_-- __ _ _2_ _ _
-i-
.ou...s NUCLEAR FUEL SERVICES DEPARTMENT NUC12AR DESIGN INFORMA110N TRANSMTITAL E SAFETY RELATED Orismsung Organmuon NDIT No.
960014 j
O NON-SAFETYREIATED E NuciarFuelServices Rev. No.
I I
O REOUIATORYRELATID O Other(epecify)
Page 1 of 7 l
Station laSalle Unit 1
Cycle 8 Genanc To: LaSalleconstalFils I
i Subject Final ?!auenmues Licensma Report (NLR) for f Ab 1 Cycle 8 Theodore P. Shannon 3 //
Preparer p's Signanus Dats b__ _
7M 3 fir /9(
Gearse Touvannes Reviewer Reviewer's SO4 Date M
s w.N J/n/w.,
l nonaids che NFS Supervisor NFS Supervisor's Si., assure Date Status orlaformauen E Verified O Unverir.d l
O Engmeannshdgement Method and Schedule of Verifmetion for Unverified NDITs:
Deempuan ofinformauen: The NLR cornaans MCPR values l'or sandens sonnanos, the reference care loedag, the standry liquid corarol systern shutdown capabihty, maxunum exposure imut W--~. and spent fuel pool and fresh fuel vault criticahty
. His is Rev. I of the NLR. The Rev. O NLR was not issued as an NDIT.
Purpons of tnformatiotr Support Urut 1 Cycle g Startup Source ofinformauart BWR Design cale note: BNDL 96414, BNDL95439 l
i S,'
- ' Dunnbutiert David A Henry Deborah A Worthmston, NDrr File i
l CHRON No: gg ggyg l
l
N2utronics Licensing Rzport LaSclle 1 Cycle 8 NDIT Nn. 960014 - Rtvisien 1 Licensing Basis This document,in conjunction with Reference 1, provides the licensing basis for LaSalle 1 Reload 7, Cycle 8. The analyses for this document are in References 2 - 9.
Table of Contents 1.
Reference Core Loading 2.
Calculated Core Effective Multiplication and Control System Worth -
No Voids, 20*C 3.
Standby Liquid Control System Shutdown Capability 4.
Core wide ADO Analysis Results 5.
Local Rod Withdrawal Error With Limiting. Instrument Failure 6.
Loading Error Results 7.
Cycle MCPR Values for Non pressurization Events 8.
Control Rod Drop Analysis Results 9.
Maximum Exposurc Limit Compliance 10.
Spent Fuel Pool and Fresh Fuel Vault Criticality Compliance 11.
References I
l Page 2 of 7 pA/ft G-r ll'Il9
LaS;lle 1 Neutranics Licensing Rtpsrt Cycle 8 NDIT No. 960014 - Revisien 1 1.
Reference Core Loading Cycle initial Bundle Name Loaded
- Bundles Enrichment GE9B-P8CWB303-9GZ-100M 150-T 5
108 3.03 GE98-P8CWB314 9GZ-100M 150-CECO 6
72 3.14 GE98-P8CWB313-9GZ-100M-150 CECO 6
128 3.13 GE98-P8CWB322-11GZ-100M 150-CECO 7
104 3.22 GE98-P8CWB320-9GZ-100M 150-CECO 7
104 3.20 GE98-P8CWB343-12GZ 80M 150-CECO 8
104 3.43 GE98-P8CWB342-10GZ-80M 150-CECO 8
144 3.42 Cycle N-1 core average exposure at end of cycle:
25,791 mwd /ST Cycle N-1 core average exposure at end of cycle for shutdown considerations:
25,291 mwd /ST Cycle N 1 core incremental exposure at end of cycle:
11,100 mwd /ST Cycle N-1 core incremental exposure at end of cycle for shutdown considerations:
10,600 mwd /ST Cycle N core incremental exposure at end of cycle:
10,600 mwd /ST l
2.
Calculated Core Effective Multiplication and Control System Worth -
No Voids,20*C j
Beginning of Cycle Keffective Uncontrolled 1.120 Fully Controlled 0.966 Strongest control rod out 0.987 Beginning of Cycle Shutdown Margin, MK 1.27 Minimum Shutdown Margin, MK 1.27 R, Maximum increase in Cold Core Reactivity with Exposure into Cycle, MK 0.00 l
Cycle incremental Exposure Corresponding to Minimum Shutdown Margin R Value O mwd /ST Please note that these values may change slightly between this report and the Startup Report due to actual plant operation, i
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y >ld E
LaS:lla 1 N:utr:nics Lic:nsing R:p:rt Cyc!e 8 NDIT No. 960014 - R: vision 1 3.
Standby Liquid Control System Shutdown Capability Boron Shutdown Margin (%AK) com 20*C. Xenon Free 660 4.85 The B 10 enrichment to be used in the SLCS for LaSalle 1, has been changed from 18.9% to 45%. Conservatively, a concentration of 800 ppm of natural Boron was used for this reload licensing analysis because the actual Technical Specification minimum Boron Concentration (including allisotopes)is no less than 660 ppm.
The methodology documented in NFD-ND 9001 Appendix B, Procedure 8.3 was used.
4.
Core-wide AOO Analysis Results l
Flux Q/A ACPR Event f%NBR)
(%NBR)
GE9.B Loss of Feedwater Heating 118 122 0.16 Loss of feedwater heating event analyzed at 100% Rated Power,'87% Rated Flow, and an assumed inlet temperature decrease of 145 *F. The event was analyzed from BOC to EOC.
5.
Local Rod Withdrawa! Error With Limiting instrument Failure l
Rod Block Rod Position ACPR l
Readina (ft. withdrawn)
GE91 104 4.5 0.17 105 5.0 0.20 106
' 6.0 0.23 107 8.5 0.28 108 9.5 0.28 109 10.0 0.28 j
110 10.5 0.28 UNBLOCKED 12.0 0.28 Setpoint recommended: UNBLOCKED Page 4 of 7 M 3Qt, tiriu g
LaSille 1
, N;utrcnics Liccnsing R:p3rt Cycla 8 NDIT No. 960014 - Rrvisi:n 1 6.
Loading Error Results The fuelloading error includes both the mislocated bundle event and the disoriented bundle event. GE indicated in Reference 10 that if the operating limit MCPR will be >= 1.28 (as it will be for this cycle), then the mislocated bundle analysis is not required. Use of this bounding value of 1.28 implies a ACPR of 0.21, which is reported here for the fuel loading error. The ACPR for the disoriented bundle event is less than 0.21. Therefore, the fuel loading error event is bounded by the 1.28 MCPR for the mislocated bundle event and its associated 0.21 ACPR.
Event ACfg Fuel Loading Error.
0.21 7.
Cycle MCPR Values for Non-pressurization Events Exposure range: BOC to EOC MCPR Loss of Feedwater Heating 1.23 Rod Withdrawal Error 1.35 (for unblocked RBM setpoint)
Fuel Loading Error 1.28 These MCPR Operating Limits are based on a MCPR Safety Limit of 1.07.
8.
Control Rod Drop Analysis Results LaSalle is a banked position withdrawal sequence plant, so the control rod drop accident (CRDA) analysis is not required for startups or normal operation. NRC approval is documented in References 11 and 12. However,in order to allow the l
l site the option of inserting control rods using the simplified control rod sec;uence i
shown in Table 1, a control rod drop accident analysis was performed for the simplified sequence. The results demonstrate that the 280 cal /gm Technical Specification Limit is not exceeded. The simplified sequence is thus valid for LaSalle 1 Cycle 8.
9.
Maximum Exposure Limit Compliance l
l The maximum nodal exposure achieved during LaSalle 1 Cycle 8 is 45507 mwd /ST. This corresponds to 88% of the design limit. The maximum nodal i
exposure occurs in the bundle located at 09-42 in node 10. This value ensures that no exposure limits will be reached during normal cycle operation.
.Page 5 of 7 p Thd';
7.
La5:lle 1 N:utrcnics Licensing R:p:rt Cycle 8 NDIT Ns. 960014 - Rivision 1 10.
Spent Fuel Pool and Fresh Fuel Vault Criticality Compliance I
l Fresh Fuel Type Peak Fuel Uncontrolled Storage Limit Reactivity GE9B-P8CWB34312GZ 80M-150-CECO 1.218 1.29 GE98-P8CWB342-10GZ 80M-150-CECO 1.245 1.29 The fresh fuel complies with the reactivity criteria for new fuel vault and spent fuel pool storage as described in Reference 13.
11.
References 1.
GE Proprietary Document 24A5180, " Supplemental Reload Licensing Report for LaSalle County Station Unit 1 Reload 7, Cycle 8" draft.
2.
Commonwealth Edison Calculation Note # BNDL:95-014.
3.
Commonwealth Edison Calculation Note # BNDL:95-023, i
4.
Commonwealth Edison Calculation Note # BNDL:95-024.
4 5.
Commonwealth Edison Calculation ' ote # BNDL:95 025.
N l
l 6.
Commonwealth Edison Calculation Note # BNDL:95-027.
7.
Commonwealth Edison Calculation Note # BNDL:95-038.
8.
Commonwealth Edison Calculation Note # BNDL:95-039.
l 9.
Commonwealth Edir.on Calculation Note # BNDL:96-014.
10.
GE Technical Design Procedure,"Mislocated Bundle CPR," TDP-0038, Rev. O, F. T. Bolger, issued February 1995.
l 11.
GE Proprietary Document NEDE 24011-P-A, " General Electric Standard l
Application for Reactor Fuel", as amended and approved.
i 12.
Commonwealth Edison Document NFSR-0085," Benchmark of BWR Nuclear Design Methods", as supplemented and approved.
13.
" Spent Fuel Rack and New Fuel Vault Reactivity Limits for LaSalle County Station, Supplement 1", letter, Jack M. Dolter to Dr. Ron J. Chin, NFS:BSS:92143, August 21,1992.
89* 0 I
%luf%
g ilnh w-______-____--_-_
r_ _.
-7 LaSalla 1 NIutr:nics Lic;nsing R:p::rt Cycle 8 NDIT No. 960014 - R vision 1 Table 1 l
LSICS Shutdown Seauence Insertion BPWS Rod Group (Bank)
CSTnments 10 or 9 48 - 00 Either Group 10 or 9 may be inserted first.
8 48-00 Groups 10 and 9 must be fully inserted prior to insertion of any group 8 rod.
7 48-12 All group 8 rods must be fully inserted prior to insertion of any group 7 rods.
7 12 00 All group 7 rods must be banked at 12 before continuing insertion to 00.
5 or 6 48 00 Groups 5 and 6 may be Inserted without banking anytime after Groups 9 and 10 have been inserted and before Group 4.
4 48 00 All group 5-10 rods must be fully inserted prior to insertion of any group 4 rods.
38 48- 00 All group 4 rods must be fully inserted prior to insertion of any group 3B rods.
3A 48 00 All group 3B rods must be fully inserted prior to insertion of any group 3A rods.
2 48-00 Analyzed by Standard BPWS 1
48 00 Analyzed by Standard BPWS Page 7 of 7 g
il"I;
( -r
Administrative Technical Requirements - Appendix A L1C8 Reload Transient Analysis Results l
l 1
i LaSalle Unit 1 Cycle 8 Supplemental Reload Licensing Report l
l l
l.
t-LaSalle Unit 1 Cycle 8 July 1998
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