ML20129J191
| ML20129J191 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/31/1996 |
| From: | Hull G, Reda R GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19353D955 | List: |
| References | |
| 24A5376, 24A5376-R, 24A5376-R00, NUDOCS 9611060164 | |
| Download: ML20129J191 (29) | |
Text
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O GE Nucletr Energy 24A5376 Revision 0 Class I August 1996 l
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l 24A5376,Rev. O Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 1 {
Reload 10 Cycle 11 l
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Approved /
F-s,,j Approved f RJ. Reda, Manager G.R. Hull l Fuel and Facility Licensing Fuel Project Manager i 9611060164 961101 PDR ADOCK 05000325 P PDR
%0Vof vf
BRUNSWICK 1 24A5376
. Reload 10 Rev.O i Important Notice Regarding Contents of This Report
]
Please Read Carefully
! This report was prepared by General Electric Company (GE) solely for Carolina Power and Light Company (CP&L) for CP&L's use in defining operating limits for the Brunswick Steam Electric Plant Unit 1. The information contained in this report is believed by GE to be an accurate and true representation of the facts known or obtained or provided to GE at the time this report was prepared.
The only undertakings of GE respecting information in this document are contained in the contract between CP&L and GE for nuclear fuel and related services for the nuclear
! system for Brunswick Steam Electric Plant Unit 1 and nothing contained in this document shall be construed as changing said contract. The use of this information except as de-fined by said contract, or for any purpose other than that for which it is intended, is not authorized; and with respect to any such unauthorized use, neither GE nor any of the contributors to this document makes any representation or warranty (expressed or im-plied) as to the completeness, accuracy or usefulness of the information contained in this document or that such use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such information.
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( BRUNSWICK 1 24A5376
. Reload 10 Rev.O Acknowledgement l The engineering and reload licensing analyses, which fonn the technical basis of this Supplemental Reload i Licensing Report, were perfonned by M.R. Morris. The Supplemental Reload Licensing Report was pre- I pared by M.R. Morris. This document has been verified by W.E. Russell.
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. Reload 10 Rev.O The basis for this mport is GeneralElectric Standard Applicationfor Reactor Fuel, NEDE-24011-P-A-11, November 1995; and the U.S. Supplement, NEDE-240ll-P-A-11-US November 1995.
- 1. Plant-unique Items l Appendix A: Analysis Conditions Appendix B: Main Steamline Isolation Valve Out of Service (MSIVOOS) l Appendix C: Decrease in Core Coolant Temperature Events l Appendix D: FeedwaterTemperature Reduction (FWTR)
Appendix E: Maximum Extended Operating Domain
- 2. Reload Fuel Bundles Cycle Fuel Type Loaded Number Irradiated:
GE8B-P8DQB339-1IGL80M-4WR-150-T (GE8x8EB) 7 16 GE8B-P8DQB323-10GL80M-4WR-150-T (GE8x8EB) 7 4 G E 10-P8H XB 322-I l GL70M-150-T (G E8 x8NB-3) 8 40 G E 10-P8 H X B 324-12GL70M-150-T (G E8 x8NB-3) 8 20 GE 10-P8 HXB 320-I lGL100M-150-T (GE8 x8 NB-3) 9 68 GE10-P8HXB322-11GL70M-150-T (GE8x8NB-3) 9 56 i l
GE 10-P8H XB346-12GL100M-150-T (GE8x8NB-3) 10 156 Erm GE13-P9DTB380-1IG5.0A-10Ur-146-T (GE13) 11 68 GE13-P9DTB380-10G5.0A-100T-146-T (GE13) 11 132 Total 560
- 3. Reference Core Loading Pattern i
Nominal previous cycle core average exposure at end of cycle: 27290 mwd /MT l (24757 mwd /ST)
Minimum previous cycle core average exposure at end of cycle 27045 mwd /MT from cold shutdown considerations: ( 24535 mwd /ST)
Assumed reload cycle core average exposure at beginning of 14678 mwd /MT cycle: ( 13316 mwd /ST)
Assumed reload cycle core average exposure at end of cycle: 27520 mwd /MT l (24966 mwd /ST)
Reference com loading pattem: Figure 1 i
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- 4. Calculated Core Effective Multiplication and Control System Worth - No Voids,20 C Beginning of Cycle, keffective Uncontrolled 1.108 Fully controlled 0.965 Strongest control rod out 0.986 R, Maximum increase in cold core reactivity with exposure into cycle, Ak 0.000
- 5. Standby Liquid Control System Shutdown Capability Boron Shutdown Margin (Ak)
(ppm) (20*C, Xenon Free) 660 0.036
- 6. Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters Exposure: BOC11 to EOC11-2205 mwd /MT with Increased Core Flow (ICF)
Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) i (1000lb/hr)
GE8x8NB-3 1.20 1,57 1.40 1.000 6.988 111.1 1.25 GE13 1.45 1.46 1.26 1.020 6.514 107.5 1.37 Exposure: EOC11-2205 mwd /MT to EOC11 with ICF Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR
( M W t) (1000lb/hr)
GE8x8NB-3 1.20 1.52 1.40 1.000 6.773 112.7 1.29 GE13 1.45 1.48 1.16 1.020 6.582 106.9 1.38 Exposure: EOC11-2205 mwd /MT to EOC11 with Maximum Extended Load Line Limit (MELLL)
Peaking Factors Fuel Bundle Bundle Initia!
Design Local Radial Axial R-Factor Power Flow MCPR l (MWt) (1000 lb/hr)
GE8x8NB-3 1.20 1.47 1.40 1.000 6.544 86.8 1.23 GE13 1.45 1.35 1.32 1.020 6.007 85.3 1.35 Page 5
l i BRUNSWICK 1 24A5376 Reload 10 Rev.0 Exposure: EOC11-2205 mwd /MT to EOCil with ICF and FWTR Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000lb/hr)
GE8x8hlw3 1.20 1.59 1.40 1.000 7.069 110.4 1.26 GE13 1.45 1.48 1.21 1.020 6.600 107.0 1.36 Exposure: EOCll-2205 mwd /MT to EOCll with MSIVOOS and ICF i l
Peaking Factors l Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt) (1000 lb/hr)
GE8x8NB-3 1.20 1.54 1.40 1.000 6.867 112.0 1.27 GE13 1.45 1.48 1.16 1.020 6.594 106.8 1.37 l
- 7. Selected Margin Improvement Options l
Recirculation pump trip: No Thermal power monitor: Yes l Improved scram time: Yes (ODYN Option B)
Measured scram time: No !
Exposure dependent limits: Yes Exposure points analyzed: 2 (EOCll-2205 mwd /MT and EOCl1) l l
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- 8. Operating Flexibility Options Single-loop operation: Yes Loadline limit: Yes Extended load line limit: Yes l
Maximum extended load linelimit: Yes increased core flow throughout cycle: Yes Flow point analyzed: 104.3 %
increased core flow at EOC: Yes Feedwater temperature reduction throughout cycle: Yes Temperature reduction: 110.3*F Final feedwater temperature reduction: Yes
! ARTS Pmgram: Yes Maximum extended operating domain: Yes Turbine bypass system OOS: No Safety / relief valves OOS: Yes (credit taken for 9 of 11 valves)
Main steam isolation valves OOS: Yes ;
- 9. Core-wide AOO Analysis Results Methods used: GEMINI; GEXL-PLUS l Exposure range: BOC11 to EOC11-2205 mwd /MT with ICF Uncorrected ACPR Event Flux Q/A GE8x8NB-3 GE13 Fig.
(%NBR) (%NBR)
Load Reject w/o Bypass 377 118 0.15 0.27 2 Turbine Trip w/o Bypass 384 117 0.15 0.27 3 l f
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BRUNSWICK 1 24A5376 Reload 10 Rev.0 Exposure range: EOC11-2205 mwd /MT to EOC11 with ICF Uncorrected ACPR Event Flux Q/A GE8x8NB-3 GE13 Fig. ,
l (%NBR) (%NBR)
Load Reject w/o Bypass 344 117 0.19 0.28 4 Turbine Trip w/o Bypass 471 121 0.19 0.27 5 l Exposure range: EOC11-2205 mwd /MT to EOC11 with MELLL l Uncorrected ACPR ]
Event Flux Q/A GE8x8NB-3 GE13 Fig.
(%NBR) (%NBR)
Load Reject w/o Bypass 310 117 0.12 0.24 6 Exposure range: EOC11-2205 mwd /MT to EOC11 with ICF and FWTR Uncorrected ACPR Event Flux Q/A GE8x8NB-3 GE13 Fig.
(%NBR) (%NBR)
FW Controller Failure 245 117 0.17 0.23 7 Load Reject w/o Bypass 323 116 0.16 0.26 8 Exposure range: EOC11-2205 mwd /MT to EOC11 with MSIVOOS and ICF Uncorrected ACPR Event Flux Q/A GE8x8NB-3 GE13 Fig.
(%NBR) (%NBR)
Load Reject w/o Bypass 328 116 0.17 0.28 9 Turbine Trip w/o Bypass 315 115 0.17 0.26 10
- 10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary The rod withdrawal error event in the maximum extended operating domain was originally analyzed in the GE BWR Licensing Report, Maximwn Extended Operating Domain Analysisfor Brunswick Steam Electric Plant, NEDC-31654P, dated February 1989. The MCPR limit for rod withdrawal error is bounded by the op-erating limit MCPRs presented in Section 11 of this report for RBM setpoints shown in Tables 10-5(a) or 10-5(b) of NEDC-31654P.
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BRUNSWICK 1 24A5376 Reload 10 Rev.O i 1 l l l
l i 11. Cycle MCPR Values 12 1
In agreement with commitments to the NRC(letter from M.A. Smith to Document Control Desk,10CFR Part 21, Reportable Condition, Safety Limit MCPR Evaluation, May 24,1996) a cycle-specilic Safety Limit l MCPR calculation was performed, and has been reported in both the Safety Limit MCPR and the Operating l
Limit MCPR shown below. This cycle specific SLMCPR was determined using the analysis basis docu- '
mented in GESTAR with the following exceptions:
- 1. The actual core loading was analyzed.
- 2. The actual bundle parameters (e.g., local peaking) were used.
- 3. The full cycle exposure range was analyzed.
Safety limit: 1.10 j
Single loop operation safety limit: 1.12 Non-oressurization events: 1 I
Exposure Range: BOCll to EOCll I GE8x8NB-3 GE13 l Fuel Loading firror (misofiented) 1.28 1.27 i Fuel Loading Error (mislocated) 1.29 1,29 LFWH 1.22 1.22 1
Pressurization events:
l Exposure range: BOC11 to EOC11-2205 mwd /MT with ICF3 Exposure point: EOC11-2205 mwd /MT '
Option A Option B GE8x8NB- GE13 GE8x8NB- GE13 3 3 Load Reject w/o Bypass 1.35 1.42 1.28 1.37 Turbine Trip w/o Bypass 1.35 1.42 1.28 1.37 l
- 2. De pratmg lumt MCPR for two loop operation (TLO) bounds the operating lunit MCPR for single loop operation (SLO), therefore. the operating lunit MCPR need not be changed for SLO.
- 3. The ICF Operaung Umits for the exposure range of BOCil to EOCl1-2205 mwd /MT bound the Operating Limits for the following do-mams; MELLL. ICF and IMTR. MsIVOOs and ICF.
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l Exposure range: EOC11-2205 mwd /MT to EOC11 with ICF Exposure point: EOC11 Option A Option B l
GE8x8NB- GE13 GE8x8NB- GE13 3 3 Load Reject w/o Bypass 1.35 1.48 1.31 1.40 Turbine Trip w/o Bypass 1.35 ,
1,47 1.31 1.39 Exposure range: EOC11-2205 mwd /MT to EOC11 ',ith MELLL Exposure point: EOC11 Option A Option B GE8x8NB- GE13 GE8x8NB- GE13 3 3 l Load Reject w/o Bypass 1.28 1.44 1.24 1.36 Exposure range: EOC11-2205 mwd /MT to EOC11 with ICF and FWTR Exposure point: EOC11 1 Option A Option B l GE8x8NB- GE13 GE8x8NB- GE13 3 3 FW Conueller Failure 1.31 1.43 1.28 1.35 Load Reject w/o Bypass 1.31 1.46 1.27 1.38 Exposure range: EOC11-2205 mwd /MT to EOC11 with MSIVOOS and ICF Exposure point: EOC11 Option A Option B GE8x8NB- GE13 GE8x8NB- GE13 3 3 Load Reject w/o Bypass 1.33 1.47 1.29 1.39 l Turbine Trip w/o Bypass 1.33 1.46 1.29 1.38 l
l l 12. Overpressurization Analysis Summary i
Psi Py Plant !
Event (psig) (psig) Response MSIV Closure (Flux Scram) 1291 1322 Figure 11 Page 10
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. Reload 10 Rev.O I I
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- 13. Loading Error Results 4 l
Variable water gap misoriented bundle analysis: Yes Misoriented Fuel Bundle ACPR GE8x8NB-3 0.18 )
GE13 0.17 l l
l i 14. Control Rod Drop Analysis Results l
This is a banked position withdrawal sequence plant, therefore, the control rod drop accident analysis is not required. NRC approvalis documented in NEDE-24011-P-A-US.
- 15. Stability Analysis Results j i
GE SIL-380 recommendations and GE interim corrective actions have been included in the Brunswick Steam Electric Plant Unit 1 operating procedures. Regions of restricted operation defined in Attachment I to NRC Bulletin No. 88-07, Supplement 1, Power Oscillations in Boiling Water Reactors (BWRs), are applicable to Brunswick 1.
- 16. Loss-of-Coolant Accident Results LOCA method used: SAFER /GESTR-LOCA The GE8x8EB LOCA analysis results presented in Sections 5 and 6 of Brumwick Steam Electric Plant Units 1 and 2 SAFERIGESTAR-LOCA Inss-of-Coolant AccidentAnalysis, NEDC-31624P. Revision 2, July 1990, conservatively bound the LOCA analysis of the GE8x8NB-3 fuel types. This analysis yielded a licensing basis peak clad temperature of 1533
- F, a peak local oxidation fraction of <0.30%, and a core-wide metal-wa-ter reaction of 0.046%.
An additional LOCA analysis was performed for the GE13 fuel type. The results, presented in Brunswick Steam Electric Plant Units 1 and 2 SAFERIGESTAR-LOCA Loss-of-Coolant Accident Analysis: Applica-tion to GE13 Fuel, NEDC-31624P, Supplement 3, Rev. O, January 1996, show a licensing basis peak clad temperature of 1535'F. The peak local oxidation fraction and core-wide metal-water reaction were shown to be bounded by results from the GE8x8EB LOCA analysis.
The most and the least limiting MAPLHGRs for the new GE13 fuel designs are as follows:
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- 4. Includes a 0,02 penalty due to variable water gap R-factor uncenainty.
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- 16. Loss-of-Coolant Accident Results (cont) l
- Bundle Type
- GE13-P9I7rB380-10G5.0A-100rr-146-T Average Planar Exposure MAPLHGR(kW/ft)
(GWd/ST) (GWd/MT) Most Limiting Least Limiting 0.00 0.00 11.17 11.29 0.20 0.22 11.20 11.32 1.00 1.10 11.32 11.42 l 2.00 2.20 11.49 11.56 I 3.00 3.31 11.68 11.72 l
4.00 4.41 11.88 11.89 l
5.00 5.51 12.03 12.06 6.00 6.61 12.14 12.22 l 7.00 7.72 12.25 12.38 8.00 8.82 12.36 12.55
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I 9.00 9.92 12.47 12.73 i
10.00 11.02 12.59 12.87 12.50 13.78 12.65 12.73 15.00 16.53 12.39 12.49 17.50 19.29 12.03 12.12 20.00 22.05 11.67 11.75 25.00 27.56 10.94 11.04 30.00 33.07 . 10.22 10.37 35.00 38.58 9.52 9.67 40.00 44.09 8.83 8.98 l 45.00 49.60 8.15 8.32 50.00 55.12 7.48 7.67 l
55.00 60.63 6.80 7.02 57.66 63.56 6.43 6.66 57.99 63.93 - 6.61 Page 12 l
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- 16. Loss-of-Coolant Accident Results (cont)
Bundle Type: GE13-P9DTB380-1IG5.0A-10(TT-146-T Average Planar Exposure MAPLHGR(kW/ft)
(GWd/ST) (GWd/MT) Most Limiting Least Limiting ;
0.00 0.00 10.94 11.09 l
0.20 0.22 10.99 11.13 l
1.00 1.10 11.11 11.23 1 2.00 2.20 11.29 11.38 3.00 3.31 11.49 11.55
, 4.00 4.41 11.70 11.73 5.00 5.51 11.90 11.93 6.00 6.61 12.07 12.13 7.00 7.72 12.24 12.27 8.00 8.82 12.38 12.43 9.00 9.92 12.50 12.62 10.00 11.02 12.61 12.81 12.50 13.78 12.66 12.72 15.00 16.53 12.39 12.49 17.50 19.29 12.03 12.12 20.00 22.05 11.66 11.75 25.00 27.56 10.93 11.04 30.00 33.07 10.21 10.37 35.00 38.58 9.51 9.65 40.00 44.09 8.82 8.97 45.00 49.60 8.15 8.31 50.00 55.12 7.48 7.66 55.00 60.63 6.80 7.01 57.77 63.68 6.41 6.63 57.93 63.85 -
6.61 1
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BRUNSWICK 1 24A5376
. Reload 10 Rev.0
- mMMMMMs
- mMMMMMMMMMs
- MMMMMMMMMMM
- mMMMMMMMMMMEs
- H M M M M M M M M M M M M ll:MMMMMMMMMMMMM l::MMMMMMMMMMMMM ll:MMMMMMMMMMHHH
':: M M M M M M M M M M M M M
- *MMMMMMMMMMM*
- MMMMMMMMMMM
- "MMMMMMMMM*
- *MMMMM*
IIIIIIIIII i3 5 7 e it is is i7 is 21 2325272s3i333537394: 43 45 47 4s si Fuel Type A=GE8B-P8DQB339-11GL80M-4WR-150-T (Cycle 7) F=GE10-P8HXB322-11GL70M-154T (Cycle 9)
B =G E8 B-P8 DQB 323-10G740M-4WR-150-T (Cycle 7) G=GE10-P8HXB346-12GL100M-150-T (Cycle 10)
C=GElo-P8HXB322-1IGL70M-150-T (Cycle 8) Il=G E 13-P917FB 380-10G5.0A-100T-146-T (Cycle 11)
D=GElo-P8HXB324-12GL70M-150-T (Cycle 8) I=G E 13-P9IYIB 380-11 G5.0 A-100T-146-T (Cycle 11)
E=GE10-P8HXB320-11GL100M-150-T (Cycle 9)
Figure 1 Reference Core Loading Pattern Page 14
. -, . . _ . _. . . _ . . - _ - - - - . - .. - ~- - - . - - -- --
- - \
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BRUNSWICK 1 24A5376 !
, Reload 10 Rev.O l
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1 l
1 I
i Neutron Flux VesselPress Rise (psi)
- - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - ..-
- Core inlet Flow 300.0 - --- Reliei Valve Row j --- Bypass Valve Flow
/ N.%
, /%
v \
., ) *
, %g \
g 100.0 ,' ,
N 200.0 -
- % 1
%,' $ l l $ '
, N-s g - '
50.0 -
' .. 100.0 -
j ----------__
t I l 0.0 '
O.0 O.0 3.0 6.0 0.0 3.0 6.0 Ime (sec) Emo (sec) l Level (inch-REF-SEP-SKRT) Void Reactivity
- - - Vessel Steam Flow -
- Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 -
Scram Reactivity
--- Feedwater Flow -- Total Reachvity G .
,\ ......
os
- 2 ..
g . .
V 100.0 --
.- 0.0 ., ,
- l
).
i 15 , \. .
x ;, .', ;
..* ... ........ 8 .
0.0 M .**- - V - - - - - - - - - - - - - -
h@ -1.0 -
\\g
\ .S
\
" \ ,
. \
\ .
\ l
-100.0 ' I *
-2.0 k ' ' '
O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) mme (sec)
Figure 2 Plant Response to Load Reject w/o Bypass (BOC11 to EOC11-2205 mwd /MT with ICF) i Page 15
l BRUNSWICK 1 24A5376
, Reload 10 Rev.O Neutron Flux Vessel Press Rise (psi)
- - Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --. -- Core inlet Flow 300.0 - --- Reliei Valve Flow
--- Bypass Valve Flow
/ \'
o - 'Y,/h
'., u*%
~ '
g 100.0 ,
g200.0 E ',' N s %
C . N C
' %~' $
~
50.0 -
,,, 100.0 -
j I
0.0 O.0 O.0 3.0 6.0 0.0 3.0 6.0 l Time (sec) Time (sec) ;
1 Level (inch-REF-SEP-SKRT) Void Reactmty
- - - - Vessel Steam Flow - - - Doppler Reactmty 1 200.0 - --- Turbine Steam Flow 1.0 -
Scram Reachvity
--- Feedwater Flow -
Total Reacevity
]\
l E
- y . *
- 0.0 . , , ,.
g 100.0 7 -. % ,
g l. ,.
%. \ '. 4 m t ', l', ; ,,.*~... ........ 8 % ... - j
__- . \
- 1.0 !
0.0 ---Q-------------- -
- e g ,
\
\
\ <
-2.0 ' ' I '
- 100.0 0.0 3.0 6.0 0.0 3.0 6.0 l
! Time (sec) Time (sec) l r
i Figure 3 Plant Response tolbrbine Trip w/o Bypass (BOC11 to EOC11-2205 mwd /MT with ICF) i, Page 16 i
BRUNSWICK 1 24A5376
. Reload 10 Rev.0 1
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l Neutron Flux Vessel Press Rise (psi)
Ave Surface Heat Flux - - - - - Safety Valve Flow 150.0 - --- -
Core inlet Flow 300.0 -
--- Relief Valve Flow
! --- Bypass Valve Flow l
j\.g ., / %
N s
/ ', ,* 1 ' .,
100 0 a 1 N 200.0 -
E ', N C
i
%~' -, $ -
l 50.0 -
100.0 I t
1 0.0 ' '
O.0 O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec) !
Level (inch-REF-SEP-SKRT) Void Reacevity Vessel Steam Flow - -
Doppler Reactivity 200.0 - --- Turbine Steam Flow 1.0 - -
Scram Reactnnty 1
--- Feedvater Row -- TotalReactivity I G D.
2C e*..*
g *
-- - -. 0.0 a, s
- 3 100.0 ,_, ' ~ . ,
w ( ',
- s ',1- .-
g , ', ,, s l ,, e, e
.,- . . , ...- ... g i
\, l 0.0 14 . '- 2 '- - - - - - - - - - - - - . .N -1.0 -
l e \ . 1 T \ l
- \ '
\ . j
\
' ' ' I I
- 100.0 -2.0 '
0,0 3.0 6.0 0.0 3.0 6.0 l Time (sec) Time (sec)
Figure 4 Plant Response to Load Reject w/o Bypass (EOC11-2205 mwd /MT to EOC11
, with ICF) i i
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egs7K i 1 5gg Neutron Flux Vessel Press Rise (psi)
- - Ave Surface Heat Flux - - - - Safety Valve Flow 150.0 - --- -- Core inlet Flow 300.0 l - --- Relief Valve Flow
--- Bypass Valve Flow I
l Y ';/~\
g 100.0 ,',
g 200.0 E '
- N s E C ', C 1 Ns N 1
~.
50.0 -
. 100.0 -
7------ _ __
I I !
0.0 '
oo / l ,
l 0.0 3.0 6.0 0.0 3.0 6.0 )
Time (sec) Time tsec) )
l 1
Level (inch- REF-SEP-SKRT) oid Reacbty
- - - - - Vessel Steam Flow ----- ppler Reactivity i l
200.0 - --- Turtune Steam Flow 1.0 -
- Scram Reactivity l
~ - - Feedvater Flow - Total Reachvity '
g
~ ...
m 5
y \
g 100.0 7-
., g 0.0 4 ,
,. ~. -
ce 1- ----. E
\j . . . . -
C ,, . . ,
',, ,., ..- 8
%,e.
[' ,' .......
- ~ }
g N-,-~&'-------------~~-
y.
0.0
- N -1.0 ~
\
.'. e \
E \ .
\
~
\
\
1
-100.0 ' l '
-2.0 I I '
O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 5 Plant Response to Turbine Trip w/o Bypass (EOC11-2205 mwd /MT to EOC11 with ICF)
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Neutron Rux Vessel Press Rise (psi)
- - Ave Surface Heat Flux - - - - Safety Valve Flow 150.0 - --- - Core inlet Row 300 0 - --- Relief Valve Flow
--- Bypass Wlve Flow p 100.0 ,,' '. g200.0 l
% l% \ ,/ cm y c -/ .,N c
, p -
s%~
~~~
g -
-1 .,
50.0 -
., . 100.0 -
7-----_______
j I
0.0 O.0
! 0.0 3.0 6.0 0.0 3.0 6.0 l Time (sec) Time (sec)
, Level (inch-REF-SEP-SKRT) Reactivity l - - - - Vessel Steam Flow -- - - oppler Reactivity 200.0 - -- - Turbine Stoem Flow 1.0 - -
m Reactivity
--- Feedwater Flow -
Total Reactivity w
~s m
p
[ E i y ;
- t 100.0 > 0.0 s ,. g sm .. x :
\.
i'.,...~~.-- .
~ Q, ,
e -
.. ...... 6 s ,
\,
~
- l g
0.0 4 _v _ _ 0 _ __ _ _ _ _ _ _ _ _ _ _ _ . E -1.0 -
g\
.. m
. 1
\'y\
\
l 1 .
l l I
-2.0
-100.0 O.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Time (sec)
Figure 6 Plant Response to Load Reject w/o Bypass (EOC11-2205 mwd /MT to EOCil
- with MELLL)
Page 19 i
l - _
BRUNSWICK 1 24A5376
, Reload 10 Rev.0 l
l Neutron Flux , # *J Vessel Press Rise (psi) l - - - - - Ave SurfactrfGat Flux - - - - - Safety Valve Flow l 150.0 - --- Conrniet Flow 125.0 - --- Relief Valw Row I
- # oreCinlet Subcooling --- Bypass Valve Flow
~ ~
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75.0 -
E ', \ E s
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f 50.0 -
25.0 - "*~
g.
- . - --.l...
I 0.0 '
-25.0 ' I '
O0 8.5 17.0 0.0 8.5 17.0 Eme (SeC) Eme (SOC)
Level (inch-REF-SEP-SKRT) Void Reacavity
- - - - - Vessel Steam Flow - - - - - Doppler Reacbvity 150.0 - --- Turbine Steam Flow 1.0 - --- Scram Reactmty
--- Feedwater Flow --- TotalReactivity
~ .-
. . . , g h
m ' .
m .-
, e t .
- 0,0
- g 100.0 ---
m r % - , ,,- y--e4'l
(' \.,.*
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0.0 8.5 17.0 0.0 8.5 17.0 Eme (SOC) Eme (SOC) l Figure 7 Plant Response to FW Controller Failure (EOC11-2205 mwd /MT to EOC11 with ICF and FMTR)
Page 20
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= l BRUNSWICK 1 24A5376 )
. Reload 10 Rev.O Appendix A l Analysis Conditions
- This is the first reload core for B runswick Unit I which will operate at an uprated power of 105 % (2558 MWt).
l To reflect actual plant parameters accurately, the values shown in Table A-1 were used for this cycle.
1
! Table A-1 l
I l Analysis Value !
Parameter ICF MELLL ICF and MSIVOOS FWTR and ICF l Thermal power, MWt 2558.0 2558.0 2558.0 2558.0 Core flow, Mlb/hr 80.3 62.4 80.3 80.3 Reactor pressure, psia 1060.8 1056.5 1059.5 1060.8 Inlet enthalpy, BTU /lb 530.7 524.6 519.4 530.7 l Non-fuel power fraction 0.037 0.037 0.037 0.037 Steam flow analysis, Mlb/hr 11.09 11.07 9.67 11.09 Dome pressure, psig 1030.0 1030.0 1030.0 1045.0 Turbine pressure, psig 969.0 % 9.3 984.1 941.6 No. of Safety / Relief Valves 9 9 9 11 l Relief mode lowest setpoint, psig i164.0 1164.0 1164.0 1164.0 l l
Recirculation pump power source on-sites on-sites on-sites on-site 5 Turbine control valve mode of operation Partial arc Partial arc Partial arc Partial are I
1 i
I
- 5. Bounds operation wuh ofr-sne power source for reload licensing events for Cycle 11.
Page 25
BRUNSWICK 1 24A5376
, Reload 10 Rev.0 Appendix B Main Steamline isolation Valve Out of Service Reference B-1 provided a basis for operation of Brunswick Steam Electric Plant (BSEP) with one Main Steamline Isolation Valve Out of Service (MSIVOOS)(three steamline operation) and all S/RVs in service.
For this mode of operation in BSEP Unit I throughout Cycle 11, the MCPR limits presented in Swion 11 of this report are bounding and should be applied when operating in the MSIVOOS mode at any time 'aring the cycle.Re peak steamline and peak vessel pmssures for the limiting overpressurization event (MSIV clo-sure with flux scram) were not calculated for the MSIVOOS mode of operation. In this mode of operation it is required that all S/RVs be operational versus the assumed 2 S/RVs OOS for the events evaluated during normal plant operation. Previous cycles analyses have shown that the MSIV closure with flux scram, eva-luated in the MSIVOOS mode, has resulted in the peak vessel pressure being reduced by more than 25 psi, when compared to the same case evaluated with all (four) steamlines operational. I Reference l B-l . Main Steamline isolation Valve OutofServicefor the Brunswick Steam ElectricPlant, EAS-117-0987, GE Nuclear Energy, April 1988.
l 1
l l
Page 26
BRUNSWICK 1 24A5376
, Reload 10 Rev.0 Appendix C Decrease in Core Coolant Temperature Events The Loss of Feedwater licater (LFWH) event and the liPCI inadvertent start-up event are the only cold water l Injection AOOs checked on a cycle-by-cycle basis. A Cycle 11 analysis showed a LFWH ACPR of 0.12.The IIPCI event was shown to be bounded by the LFWH event for Cycle 11.
1 l
i Page 27
BRUNSWICK 1 24A5376
, Reload 10 Rev.0 Appendix D Feedwater Temperature Reduction (FWTR)
Reference D-1 pmvides the basis for operation of the Bmnswick Steam Electric Phnt with FWTR. The MCPR limits presented in Section 11 of this report are bounding and should be applied when operating with FWTR. Previous analysis has shown the FWCF event is most severe at ICF and FWTR.
Reference D-1. Feedwater Temperature Reduction with Maximum Extended Load Line Limit andincreased Core Flow for Brunswick Steam Electric Plant Units 1 arui 2, NEDC-32457P, Revision 1, December 1995.
l Page 28
< BRUNSWICK 1 24A5376
, Reload 10 Rev.0 Appendix E Maximum Extended Operating Domain l Reference E-1 provided a basis for operation of the Brunswick Steam Electric Plant in the Maximum Ex-tended Operating Domain (MEOD). The reload licensing analysis performed for Cycle 11 and documented herein is consistent with and provide the cycle-specific update to the reference E-1 analysis. Application of the GEXI -PLUS correlation to the reload fuel has been confirmed as required in reference E-1. The applica-bility of GE13 was addressed and found acceptable.
Reference E-1. Maximum Extended Operating Domain Analysisfor Brunswick Steam Electric Plant, NEDC-31654P.
GE Nuclear Energy (Proprietary), February 1989.
l i
P Page 29
- - . . - . _ - . - . - . - . . - . - - . . . . . . . ~ . _ . - . . . - - . . - _ - . . . . - . _ - . - .
o e
ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 ;
DOCKET NO. 50-325/ LICENSE NO. DPR-71 TRANSMITTAL OF CORE OPERATING LIMITS REPORT, SUPPLEMENTAL RELOAD LICENSING REPORT, AND LOSS-OF-COOLANT-ACCIDENT ANALYSIS REPORT i
AFFIDAVIT FROM GENERAL ELECTRIC NUCLEAR ENERGY
[-
REGARDING WITHHOLDING FROM PUBLIC DISCLOSURE-IN ACCORDANCE WITH 10 CFR 2.790 l
t i
I 4
i J
i GENuclent Energy GeneralDoctre Company P 0 Bos 780. Wimongton. NC 28402 Affidavit I, Ralph J. Reda, being duly sworn, depase and state as follows:
(1) I am Manager, Fuels and Facility Licensing, General Electric Company ("GE") and have been delegated the function of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in the document, NEDC-31624P, 1 Supplement 1, Revision 3, Loss-of-Coolant Accident Analysis Reportfor BRUNSWICK STEAM ELECTRIC PLANT UNIT 1, Reload 10 Cycle 11, May 1996.
(3) In making this application for withholding of proprietary information of which it is the owner, GE relies upon the exemption from disclosure set forth in the Freedom of Information Act i
("FOIA"), 5 USC Sec. 552(bX4), and the Trade Secrets Act,18 USC Sec.1905, and NRC j regulations 10 CFR 9.17(aX4),2.790(aX4), and 2.790(dXI) for " trade secrets and commercial or financial information obtained from a person and privileged or confidential"(Exemption 4).
The material for which exemption from disclosure is here sought is all " confidential commercial information," and some portions also qualify under the narrower definition of" trade secret,"
within the meanings assigned to those terms for purposes of FOI A Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission. 975F2d871 (DC Cir.1992),
and Public Citizen Health Research Groun v. FDA,704F2d1280 (DC Cir.1983).
(4) Some examples of categories of information which fit into the definition of proprietary information are:
I
- a. Information that discloses a process, method, or apparatus, incbding supporting data and analyses, where prevention ofits use by General Electric's competitors without license from General Electric constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources l or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing of a similar product;
- c. Information which reveals cost or price information, production capacities, budget levels, or commercial strategies of General Electric, its customers, or its suppliers;
- d. Information which reveals aspects of past, present, or future General Electric customer-funded development plans and programs, of potential commercial value to General Electric;
- e. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
Page1
e . .
6*
- .- Attrehm:nt GE Proprietary information The information sought to be withheld is considered to be proprietary for the reasons set l forth in both paragraphs (4)a. and (4)b., above.
l (5) The information sought to be withheld is being submitted to NRC in confidence. The I information is of a sort customarily held in confidence by GE, and is in fact so held. Its initial designation as proprietary information, and the subsequent steps taken to prevent its
)
l unauthorized disclosure, are as set forth in (6) and (7) following. The information sought to be l withheld has, to the best of my knowledge and belief, consistently been held in confidence by GE, no public disclosure has been made, and it is not available in public sources. All disclosures l to third parties including any required transmittals to NRC, have been made, or must be made, l pursuant to regulatory provisions or proprietary agreements which provide for maintenance of
! the information in confidence.
L (6) Initial approval of proprietary treatment of a document is made by the manager of the l originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge. Access to such documents within GE is limited on a "need to know" basis.
l (7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for
- technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GE are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2) is classified as proprietary because it would provide other parties, .4cluding competitors, with information related to detailed results of analytical models, methods and processes, including computer codes, which GE has developed, requested
, NRC approval of, and applied to perform evaluations of the BWR. The development of the evaluation process along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GE asset.
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to j GE's competitive position and foreclose or reduce the availability of profit-making :
opportunities. The fuel design is part of GE's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
, The research, development, engineering, analytical, and NRC review costs comprise a substantial investment of time and money by GE.
The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify, but it clearly is substantial.
GE's competitive advantage will be lost if its competitors are able to use the results of the GE experience to no malize or verify their own process or if they are able to claim an equivalent
- understanding by demonstrating that they can arrive at the same or similar conclusions.
Page 2 t
e . .
s'
- , Attrchm:nt ~ GE Proprietary Information The value of this information to GE would be lost if the information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GE of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing these very valuable analytical tools.
State of North Carolina )
SS County of New llanover )
' Ralph J. Reda, being duly sworn, deposes and says:
That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his knowledge, information, and belief.
Executed at Wilmington, North Carolina, this 20 day of June,1996.
8 Ralph J. Reda General Electric Company l
Subscribed and sworn before me this 20 day of June,1996 oonm
- o~ ,,% .,
! p,,
i -
J.- IM UBL.N g
'\,, N ..s
('/
My commission expires on ,,,,[,;,,ft Notary Public, State of North Carolina Page 3 f
3 o