ML20069N899
| ML20069N899 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/31/1994 |
| From: | Goldberg N, Klapproth J GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19304C281 | List: |
| References | |
| 23A7242, 23A7242-R, 23A7242-R00, NUDOCS 9406230254 | |
| Download: ML20069N899 (24) | |
Text
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GE Nuclear Energy O
23A7242 Revision 0 Class I May 1994 0
23A7242, Rev. 0 3
Supplemental Reload Licensing Report for Brunswick Steam Electric Plant Unit 2 Reload 10 Cycle 11 t
3 e
i S
9 y
Approved Approved k[< f' J.F. Klapproth, f anager N.J. Goldberg Fuel Licensing Fuel Project Manager P
$ 62g g g o $
4 P
Brunswick 23A7242
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Reload 10 Rev.0 Important Notice Regarding
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Contents of This Report 4
Please Read Carefully
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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 2. 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 Brunswick Steam Electric Plant Unit 2 and nothing contained in this document shall be construed as changing said contract. The use of this information except as defined by said contract,
)
or for any purpose other than that for which it is inteded, is not authorized; and with re-spect to an such unauthorized use, neither GE nor any of the contributors to this docu-4 l
ment makes any representation or warranty ( expressed or implied) as to the complete-ness, accuracy or usefulness of the information contained in this document or that such use of such information may not infringe privately rights; nor do they assume any respon-
)
sibility for liability or damage of any kind which may result from such use of surh informa-tion.
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,,,n. -, - - -
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1 Brunswick-2 23A7242 i
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Reload 10 Rev.0
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Acknowledgement The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by R.N. Anderson and M.R. Morris. The Supplemental Reload Licensing
)
Report was prepared by R.N. Anderson. This document has been verified by ET. Bolger.
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1 1
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1 1
Page 3
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I Brunswick-2 23A7242 1
Reload 10 Rev.0 i
l The basis for this teport is General Electric Standard Applicationfor Reactor Fuel, NEDE-24011-P-A-10, i
)
February 1991; and the U.S. Supplement, NEDE-240ll-P-A-10-US, March 1991, l.
Plant-unique Items Appendix A: Analysis Conditions Appendix B: Main Steamline Isolation Valve Out of Service Appendix C: Reload Unique Anticipated Operational Occurrence (AOO) Analysis input Appendix D: Feedwater Controller Failure Analysis Appendix E: Maximum Extended Operating Domain l
2.
Reload Fuel Bundles Cycle j
Fuel Type Loaded Number Irradiated:
GE8B-P8DQB 323-1IGL80M-4WR-150-T (GE8x8EB) 8 40 GE8B-P8DQB317-9GL80M-4WR-150-T (GE8x8EB) 8 52 G E9 B-P8 DWB 330-I l GL80M-150-T (G E8 x8NB) 9 44 j
f' GE9B-P8DWB 329-l lGL80M-150-T (GE8 x8NB) 9 124 GE 10-P811XB329L-12GZl-100M-150-T (GE8 x8NB-3) 10 148 Ncx G E 10-P811XB 324-12GL70M-150-T (G E8 x 8N B-3) 11 112
)
G E 10-P8 H X B320-I l GL 100M-150-T (GE8 x 8NB-3) 11 32 GE10-P811XB322-11 GL70M-150-T (GE8x8NB-3) 11 8
Total 560
)
3.
Reference Core Loading Pattern Norninal previous cycle core average exposure at end of cycle:
24027 mwd /MT f
( 21797 mwd /ST) j Minimum previous cycle core average exposure at end of cycle 24027 mwd /MT fmm cold shutdown considerations:
( 21797 mwd /ST)
Assumed reload cycle core average exposure at beginning of 14713 mwd /MT cycle:
( 13348 mwd /ST)
Assumed reload cycle core average exposure at end of cycle:
26013 mwd /MT (23599 mwd /ST) i Reference core loading pattem:
Figure 1 l
l
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i Page 4
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Brunswick-2 23A7242 Reload 10 Rev.0
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4.
Calculated Core Effective Multiplication and Control System Worth - No Voids,20 C
)
Beginning of Cycle, kerrecuve Uncontrolled 1.102 Fully controlled 0.957
)
Strongest control rod out 0.988 R, Maximum increase in cold core reactivity with exposure into cycle, Ak 0.000 5.
Standby Liquid Control System Shutdown Capability
)._
i Boron Shutdown Margin (Ak)
(ppm)
(20 C, Xenon Free) 600 0.036
)
6.
Reload Unique GETAB Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters
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Exposure: BOCil to EOCll-3000 mwd /MT (2722 mwd /ST) with ICF Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWt)
(1000lb/hr)
)
GE8x8NB-3 1.20 1.69 1.40 1.000 7.158 112.1 1.23 GE8x8NB 1.20 1.67 1.40 1.000 7.107 111.3 1.24 GE8x8EB 1.20 1.59 1.40 1.051 6.737 118.3 1.23 Exposure: EOCll-3000 mwd /MT (2722 mwd /ST) to EOC11 with ICF Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR (MWI)
(1000 lb/hr)
GE8x8NB-3 1.20 1.62 1.40 1.000 6.887 113.7 1.29 y
GE8x8NB 1.20 1.62 1.40 1.000 6.860 112.7 1.29 GE8x8EB 1.20 1.53 1.40 1.051 6.508 119.6 1.27 Page 5 3
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Brunswick-2 23A7242
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Reload 10 Rev.0 Exposure: BOCll to EOCll with MSIVOOS and ICF
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Peaking Factors Fuel Bundle Bundle Initial Design Local Radial Axial R-Factor Power Flow MCPR-(MWt)
(1000lb/hr)
GE8x8NB-3 1.20 1.63 1.40 1.000 6.918 113.5 1.28
)
GE8x8NB
.l.20 1.62 1.40 1.000 6.890 112.5 1.28 GE8x8EB 1.20 1.54 1.40 1.051 6.530 119.4 1.27 7.
Selected Margin Improvement Options Recirculation pump trip:
No Thermal power monitor:
Yes Improved scram time:
Yes (ODYN Option B)
)
Measured scram time:
No j
Exposure points analyzed:
2 (EOCll-3000 mwd /MT and EOCll) 8.
Operating Flexibility Options
)
Single-loop operation:
Yes Load line limit:
Yes Extended load line limit:
Yes 3
)
Maximum extended load line limit:
Yes Flow point analyzed:
105.0 %
increased core flow at EOC:
Yes
)-
Increased core flow thmughout cycle:
Yes ARTS Program:
Yes Maximum extended operating domain:
Yes
'Ibrbine bypass system OOS:
No
)
Safety / relief valves OOS:
Yes (credit taken for 9 of 11 valves)
ADS OOS:
Yes(2 valves OOS)
No Main steam isolation valve OOS:
Yes t
Page 6
4 Brunswick-2 23A7242 g
Reload 10 Rev.0 9.
Core-wide AOO Analysis Results O
Methods used: GEMINI; GEX1,-PLUS Exposure range: HOCll to EOCll-3000 mwd /MT (2722 mwd /ST) with ICF Uncorrected ACPR D
Event Flux Q/A GE8x8NB-GE8x8NB GE8x8EB Fig.
(%NBR)
(%NBR) 3 Load Reject w/o Bypass 373 119 0.17 0.17 0.16 2
Exposure range: EOCll-3000 mwd /MT (2722 mwd /ST) to EOC11 with ICF g
Uncorrected ACPR Event Flux Q/A GE8x8NH-GE8x8NB GE8x8EB Fig.
(%NBR)
(%NBR) 3 Load Reject w/o Bypass 423 123 0.22 0.22 0.21 3
D Exposure range: BOC11 to EOC11 with MSIVOOS and ICF Uncorrected ACPR Event Flux Q/A G E8x8NB-GE8x8NB GE8x8EB Fig.
(%NBR)
(%NBR) 3 Load Reject w/o Bypass 378 123 0.21 0.21 0.20 4
- 10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary D
The md withdrawal ermr event in the maximum extended operating domain was originally analyzed in the GE BWR Licensing Repost, Maximum Extended Operating Domain Analysisfor Brunswick Steam Electric Plant, NEDC-31654P, dated February 1989. The MCPR limit for tod withdrawal error is bounded by the operatiny 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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Page 7
Brunswick-2 23A7242
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Reload 10 Rev.0
- 11. Cycle MCPR Values
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l Safety limit:
1.07 l
1 Single loop operation safety limit:1.08
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Non-oressurization events:
Exposure range: HOCll to EOCll GE8x8NB-3 GE8x8NB GE8x8EB l
Fuel Loading Error:
GE10-P811XB324-12GZ-70M-150-T 1.31 GE10-P8HXB329-120Z1-100M-150-T/
1.25 GE10-P811XB322-11GZ-70M-150-T/
GE10-P811XB320-11GZ-100M-150-T LFWII 1.20 1.20 1.20 j
Pressurization events:
Exposure range: BOCll to EOC11-3000 mwd /MT (2722 mwd /ST) with ICF j
Exposure point: EOCll-3000 mwd /MT (2722 mwd /ST)
Option A Option B GE8x8N GE8x8N GE8x8E GE8x8N GE8x8N GE8x8E B-3 B
B B-3 B
B Load Reject w/o Bypass 1.34 1.34 1.33 1.27 1.27 1.26 Exposure range: EOCll-3000 mwd /MT (2722 mwd /ST) to EOCII with ICF Exposure point: EOC11 Option A Option B GE8x8N GE8x8N GE8x8E GE8x8N GE8x8N GE8x8E
)
B-3 B
B B-3 B
B Load Reject w/o Bypass 1.35 1.35 1.33 1.31 1.31 1.29 Exposure range: BOC11 to EOC11 with MSIVOOS and ICF Exposure point: EOCll
/
Option A Option B GE8x8N GE8x8N GE8x8E GE8x8N GE8x8N GE8x8E B-3 B
B B-3 B
B Load Reject w/o Bypass 1.34 1.34 1.32 1.30 1.30 1.28
- 1. Brunswick Steam Electne Plant units 1 and 2 Single Loop Operauon, NEDC-31776P. December 1989, Operating limit MCPR for two loop op:rauon (11.0) bounds the operstmg limit MCPR for smgle loop operanon (SLO): ACPR(SLO) <(ACPR(TLD)-a01). therefore.oper-aung luait MCPR need not be changed for SLO.
i Page 8
Brunswick-2 23A7242
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Reload 10 Rev.0
- 12. Overpressurization Analysis Summary
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Psi Pv Plant Event (psig)
(psig)
Response
MSIV Closure (Flux Scram) 1252 1284 Figure 5
)
2
- 13. Loading Error Results Vaiable water gap misoriented bundle analysis: Yes Misoriented fuel bundle A CPR
)
GE10-P811XB322-11GZ-70M-150-T(GE8X8NB-3) 0.12 G E l O-P8 H X B 320- 1 1 GZ-100M-150-T(G E 8 X 8 N B-3) 0.13 G E 10-P8H X B 324-12GZ-70M-150-T(GE8X 8N B-3) 0.24 GE10-P811XB329-12GZ1-100M-150-T(GE8X8NB-3) 0.18
)
- 14. Control Rod Drop Analysis Results Brunswick Steam Electric Plant Unit 2 is a group notch plant operating in the banked position withdrawal sequence, therefom, the control rod drop accident analysis is not required. NRC approval is documented in
)
NEDE-240l l-P-A-US.
- 15. Stability Analysis Results GE SIL-380 recommendations and GE interim corrective actions have been included in the Brunswick Steam
)
Electric Plant Unit 2 operating procedures. Regions of restricted operation defined in Attachment 1 to NRC Bulletin No. 88-07 Supplement I are applicable to Brunswick 2 Reload 10 Cycle 11.
- 16. Loss-of-Coolant Accident Results
)
LOCA method used: SAFERfsESTR-LOCA
Reference:
Brunswick Steam Electric Plant Units 1 and 2 SAFER /GESTR-LOCA less-of-Coolant Accident Analysis, NEDC-31624P, Rev. 2. July 1990.
d The GE8x8EB LOCA analysis results presented in Sections 5 and 6 of NEDC-31624P conservatively bound the LOCA analysis of the GE8x8NB-3 fuel types. This analysis yielded alicensing basis peak clad tempera-ture of 1537 oF, a peak local oxidation fraction of <0.31 %, and a core-wide metal-water reaction of 0.036%.
The most lirniting and the least limiting M APLIIGRs for the GE8x8NB-3 fuel designs are as follows:
)
- 2. ACPR penahy of 0.02 for the uhed tmsonented bundle has been apphed.
)
Page 9
Brunswick--2 23A7242 3
Reload 10 Rev.0 r
- 16. Loss-of-Coolant Accident Results (cont)
Bundle Type: GE10-P8 tiXB322-11G7-70M-150-T (GE8x8NB-3)
Average Planar Exposure MAPLHGR(kw/ft)
(GWd/ST)
(GWd/MT)
Most Limiting Least Limiting
)
0.00 0.00 10.84 11.92 0.20 0.22 10.88 11.98 1.00 1.10 10.95 12.04 2.00 2.20 11.08 12.14
)
3.00 3.31 11.21 12.25 4.00 4.41 11.35 12.39 5.00 5.51 11.50 12.53 6.00 6.61 11.67 12.68 7.00 7.72 11.92 12.74
)
8.00 8.82 12.26 12.88 9.00 9.92 12.61 13.11 10.00 11.02 12.95 13.23 i
12.50 13.78 13.12 13.27
)
15.00 16.53 12.89 12.95 20.00 22.05 12.29 12.38 25.00 27.56 11.67 11.85 35.00 38.58 10.26 10.47 45.00 49.60 8.78 9.04 50.86 56.06 5.87 6.23 51.71 57.00 5.82
)
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Page 10 y
Brunswick-2 23A7242
)
Reload 10 Rev.0
- 16. Loss-of-Coolant Accident Results (cont)
)
Bundle Type: GE10-P8HXB320-1IGZ-100M-150-T (GE8x8NB-3)
Average Planar Exposure MAPLHGR(kw/ft)
(GWd/ST)
(GWd/MT)
Most Limiting Least Limiting 0.00 0.00 10.81 11.71
]
0.20 0.22 10.87 11.74 l
1.00 1.10 10.97 11.82 l
2.00 2.20 11.10 11.93
)
3.00 3.31 11.24 12.05 4.00 4.41 11.39 12.17 5.00 5.51 11.53 12.30 6.00 6.61 11.68 12.44
)
7.00 7.72 11.84 12.57 8.00 8.82 12.00 12.72 9.00 9.92 12.16 12.86 10.00 11.02 12.33 13.00
)
12.50 13.78 12.52 13.19 15.00 16.53 12.40 12.92 20.00 22.05 11.93 12.28 25.00 27.56 11.44 11.66 35.00 38.58 10.26 10.26
)
45.00 49.60 8.68 8.77 50.49 55.66 5.91 6.05 50.86 56.06 5.87
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Page 11
t Brunswick-2 23A7242
)
Reload 10 Rev.0
- 16. Loss-of-Coolant Accident Results (cont)
)
Bundle Type: GE10-P8HXB324-12GZ-70M-150-T (GE8x8NB-3)
Average Planar Exposure MAPLHGR(kw/ft)
(GWd/ST)
(GWd/MT)
Most Limiting Least Limiting
)
0.00 0.00 10.75 11.79 0.20 0.22 10.78 11.85 1.00 1.10 10.87 11.94 2.00 2.20 11.07 12.08
)
3.(X) 3.31 11.32 12.23
{
4.00 4.41 11.62 12.39 5.00 5.51 11.83 12.56 6.00 6.61 12.02 12.72
)
7.(X) 7.72 12.22 12.91 8.00 8.82 12.44 13.13 9.00 9.92 12.70 13.12 i
10.00 11.02 12.96 13.19 l
)
12.50 13.78 13.17 13.28 15.00 16.53 12.93 12.95 20.00 22.05 12.27 12.42 25.00 27.56 11.62 11.89 35.00 38.58 10.27 10.49
)
45.00 49.60 8.78 9.06 50.66 55.84 5.94 6.26 51.64 56.92 5.78
)
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{
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i Page 12
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o De*nP2 23p,3
@ +5 YY+@
5 W
ll sM M Hs+8s+ M Ms+s8+8s
!+8s+8 M M s+8 M 8+8 8+8 H 8+8 i!
e s+8 M 8+8 E s+8 s+8 H H s+8s+8s+8s
- MMMs+ss+8Es+8HHHHMs+
- Es+ss+sMs+8Es+8MMMMMM ll:M Hs+ss+8 E s+EMar ! M s+s M M l::Ms+8Ms+iEs+8EEMMMEs+s
'::M M Ms+iM X M M M M Ms+ss+8 58+8Ms+8M Hs+sMs+8Ms+8M*
M M M M s+ss+8M M Ms+8H
- H s+ss+ss+ss+ss+s M M M *
"HMEME" a
Ii11IIIIII I 3 $ 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 35 di 43 45 47 di 51 3
Fuel Type A=GE8B-P8DQB323-11GL80M-4WR-1%T E4E9B-P8DWB330-11GL80M-150-T B4E10-P8HXB322-11GL70M-IST F4E9B-PRDWB329-11GL80M-IST r)
C4E10-P8HXB329-12GZ1-100M-1%T G4E10-P8HXB326-11GL100M-IST D=GE8B-P8DQB317-9GL80M-4WR-1WT H4Elo-P8HXB324-12GL70M-1ST l
Figure 1 Reference Core Loading Pattern l
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)
Page 13
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Brunswick-2 23A7242 O
Reload 10 Rev.0 l
Neutron Flux Vessel Press Rise (psi)
- - Ave Surface Heat Flux
- - - - - Safety Valve Flow 150.0 -.--
- Core inlet Flow 300.0 - --- Relwit Valve Flow
--- Bypass Valve Flow D
~
' ' - N h100.0
~
\\
')s g 200.0 s
N s
e m
s*%
C
~
~
~
p 50.0 100.0 l
I I
/
)
0.0 O.0 O.0 3.0 60 0.0 3.0 6.0 Time (sec)
Time (sec)
)
Level (inch-REF-SEP-SKRT) oid Reacavity oppler Reactvity
- - - -. Vessel Steam Flow 200.0 - --- Turbine Steam Flow 1.0 am Reactivity Feedwater Flow Total Reactvity G
m 2
3 y
0.0 V100.0
',g a l *
.' '.., * ~... -....... 3
'\\gA',
e
\\ \\
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n
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N-1.0
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00 o
e C
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1
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l I
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-100.0
- 2.0 0.0 3.0 6.0 0.0 3.0 6.0
]
Time (sec)
Time (sec)
Figure 3 Plant Response to Load Reject w/o Bypass (EOC11-3000 mwd /MT (2722 mwd /ST) to EOC11 with ICF)
Page 15
)
Brunswick-2 23A7242
)
Reload 10 Rev.0
)'
Neutron Flux Vessel Press Rise (psi)
- - - Ave Surface Heat Flux
- - - - Safety Valve Flow l
150.0 - --
Core inlet Flow 300.0 - --- Rehet Valve Flow
--- Bypass Valve Flow
~
-s g100.0
~
,\\ r%
' D, g 200.0 5
C C
}
~
o'
~.,
50.0 100.0
/
I I
?
00 O.0
'1 i
OO 3.0 6.0 0.0 3.0 6.0 Tme (sec)
Time (sec)
Level (incti-REF-SEP-SKRT) oid Re J
oppler Reactivity
- - - - Vessel Steam Flow 200.0 - --
Turbme Steam Flow 1.0
- Scram Reactivity Feedwater Flow Total Reactivity S
e e
3 g
0.0 g1000 g
y y
3...-
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w\\e
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0.0 1 A - - - ~ ~ ~ ~ ~ ~ - - ~ ~ ~ ~. N. -1.0
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-100 0
- 2.0
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0.0 3.0 6.0 0.0 3.0 6.0 Time (sec)
Time (sec) i Figure 4 Plant Response to Load Reject w/o Bypass (BOC11 to EOC11 with MSIVOOS and ICF)
)
)
Page 16.
Brunswick-2 23A7242 O
Reload 10 Rev.0 1
l Neutr>n Flux Vessel Press Rise (psi)
AveSurface Heat Flux
- - - - Safety Valve Flow 150.0 - ---- Core niet Flow 300.0 - --- Relet Valve Flow
--- Bypass Valve Flow 3
__ J,k h
g200.0 g100.0 s'.
E E
N e
g ss%~
c g
]
'7.~ ~. ~
50.0 100.0 I
l 3
I 0.0 1
I 0.0 OO 4.0 8.0 0.0 4.0 8.0 mme (sec)
Bme (sec) l Level (inch-REF-SEP-SKRT)
Void Reacev
- - - - - Vessel Steam Flow
- - - - - Do ler clivity 200.0 Turbine Steam Row 1.0 - - - - Sc R
~ ity v
Feedwater Flow T I vity W
l')
j 3
a0
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m wwo sq.,,....-. h,--~ - - 6
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- 100.0
- 2.0
]
0.0 4.0 8.0 0,0 4.0 8.0 Eme (Sec)
Eme (Sec)
Figure 5 Plant Response to MSIV Closure (Flux Scram) (BOCll to EOC11 with ICF)
J' Page 17 1
1
3 Brunswick-2 23A7242 3
Reload 10 Rev.0 Appendix A D
Analysis Conditions To reflect actual plant parameters accurately, the values shown in Table A-1 were used this cycle.
3 Table A-1 Analysis Value 3
Parameter ICF MSIVOOS Thermal power, MWt 2436.0 2436.0 Core flow, Mlb/hr 80.83 80.83 i
Reactor pressure, psia 1036.0 1036.0 3
Inlet enthalpy, BTU /lb 528.0 528.0 Non-fuel power fraction 0.038 0.038 Steam flow analysis, Mlb/hr 10.48 10.48 Dome pressure, psig 1005.7 1019.8 D
Turbine pressure, psig 950.0 919.3 No.of Safety / Relief Valves 9
11 Relief mode lowest setpoint, psig 1116.0 1116.0 Recirculation pump power source On-sited On-sited 3
Turbine control valve mode of operation Partial are Partial arc L
3.' At increased (105%) core flow.
- 4. Bounds geration with ofr-site power source for reload licensing events for Cycle !!.
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Brunswick-2 23A7242 h,
Reload 10 Rev.O Appendix B
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Main Steamline Isolation Valve Out of Service Reference B-1 provided a basis for operation of Brunswick Steam Electric Plant (BSEP) with one Main
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Steamline Isolation Valve Out of Service (MSIVOOS)(three steamline operation) and all S/RVs in service.
For this mode of operation in BSEP Unit 2 throughout Cycle 11, the EOCll-3000 mwd /MT to EOCll MCPR limits presented in Section 11 of the body of this report are bounding and should be applied when operating in the MSIVOOS mode at any time during the cycle. The peak steam line and peak vessel pressures for the limiting overpressurization event (MSIV closure with flux scram) was not calculated for the MSIVOOS mode of operation because in the MSIVOOS mode it is required that all S/RVs be operational
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versus the assumed 2 S/RVs OOS for events evaluated during normal plant operation. Previous cycles analyses have shown that the MSIV closure with flux scram, evaluated in the MSIVOOS mode, has resulted in the peak vessel pressure being mduced by more than 25 psi, when compared to the same case evaluated l
with all (four) steamlines operational.
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Reference B-1. Main Steamline isolation Valve Out of Servicefor Brunswick Steam Electric Plant, EAS-117-0987,
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GE Nuclear Energy, April 1988.
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Brunswick-2 23A7242
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Reload 10 Rev.0 Appendix C Reload Unique Anticipated Operational Occurence (AOO) Analysis input
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The data previously recorded in Appendix C (input to be used in the analysis of the cold water injection transient) (inadverent startup of HPCI system), has been climinated. The basis of this is the infonnation contained in Reference C-1.
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Reference
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C-1. Determination of Limiting Cold Water Event, March 14,1994 letter fmm J.E Klappmth (GE Nuclear Energy) to USNRC.
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Brunswick-2 23A7242
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Reload 10 Rev.0 Appendix D 3
Feedwater Controller Failure Analysis The Feedwater Controller Failure (FWCF)(maximum demand) AOO is an increase in coolant inventory
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event normally checked on a cycle-by-cycle basis to determine if this AOO could potentially alter the cycle MCPR operating limit. The FWCF AOO is basically a two part event. The first portion is an increase in feedwater flow (to maximum capacity) and the second part is a turbine trip (on high water level) with bypass.
The severity of the FWCF AOO is highly dependent upon the size of the turbine bypass system.
BSEP Unit 2 has a large turbine bypass capacity (88% of rated steam flow) and the FWCF ACPR has always
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been bounded by the load rejection or turbine trip without bypass. The FWCF analysis for Cycle 8 resulted in an Option B ACPR value ofless than 0.08. The limiting AOO for Cycles 9,10 and 11 was the load rejection without bypass with Option B ACPRs of 0.21,0.25 and 0.24, respectively. The cycle-to-cycle variations of the feedwater controller failure event's ACPRs and of the load rejection event's ACPRs are smaller than the rehtively large differences between the FWCF event's and load rejection event's. This trend is not
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affected by the GE8x8NB-3 fuel design. Therefore, this AOO will not be limiting for Cycle 11 and was not analyzed.
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Brunswick-2 23A7242
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Reload 10 Rev.0 Appendix E q
Maximum Extended Operating Domain l
Reference E-1 provided a basis far operation of the Brunswick Steam Electric Plant in the Maxitaum Ex-
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tended Operating Domain (MEOD). The reload licensing analysis performed for Cycle 11 and documented herein is consistent with and pmvide the cycle-specific update to the reference E-1 analysis. Application of the GEXL-PLUS canelation to the reload fuel has been confirmed as requirad in Reference E-1.
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Reference E-1 Matimum Extended Operating Domain Analysisfor Brunswick Steam Electric Plant, NEDC-31654P. GE l
Nuclear Energy (Proprietary), February 1989.
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