ML070320406
| ML070320406 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/31/2007 |
| From: | Global Nuclear Fuel |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 0000-0044-1520-SRLR, Rev 0 | |
| Download: ML070320406 (96) | |
Text
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 Fltow.
S- 300.0 -- Relif Valve Flow s Bypass Valve Flow 150.0 200.0 100.0 100.0 50.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 Tune (sec) TMae (sec) vel(incr-REF-SEP-SKRT) 'd
-sn Steam Flow 1Reatvity-brie Steam Flaw 10 A S xdwater Flow Total R iay 0
S0.0
- 0 U
(4
-10
-2.0 3.0 6.0 0.0 3.0 0.0 6.0 T-me (sec) T~M (sec)
Figure 40 Plant Response to Load Rejection w/o Bypass (MOC MELLLA with RPTOOS (HBB))
Page 101
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
-a Neutror FIux(/ 10
-Avg Surface IHeat Flux
-- Core haet Flow
- i. Core hlet Sui3000Iing 150.0 4J 04i*100.0 50.01 a e a a 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Thrm (sec) Tffe (sec) 150.0
-0 10.0 06 M M00.0 M i 50.0
-1.0 0.0 -2.0 0.0 10.0 20.0 30.0 0.0 10.0 20 .0 30.0 Time (sec) Tm-e (sec)
Figure 41 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA with RPTOOS (HBB))
Page 102
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 3W0.0
.0 200.0 100.0 0.0 1 , 0.0 I.-
0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Thm (sec) Time (sec) 150.0 1.0 100.0 0.0 0
- -1.0 50.0 0.0 -2.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) ThIe (mc)
Figure 42 Plant Response to FW Controller Failure (EOC MELLLA with RPTOOS (HBB))
Page 103
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 0.0 3.0 6.0 0.0 3.0 6.0 THne (sec) Timex (sec) 200.0 1.0
, 100.0 r 0.0 0
0.0 9 -1.0
-100.0 -2.0 0.0 3a0 Tm* 3.0(Se) 6.0 0.0 6.0 Time (sec)
Figure 43 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with RPTOOS (HBB))
Page 104
BROWNS FERRY 1 0000-0044-1520-SRLR V VVa U11 An 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Time (sec) Time (sec) 150.0 1.0 4) o 0.0 U
50.0 S-1.0 0.0 -2.0 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Trim (sec) Time (sec)
Figure 44 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with RPTOOS (H1BB))
Page 105
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 300.0 100.0 100.0 0.0 a.i 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 TlxE (Se) Trn (sec) 150.0 sý ýfl 1I PJ 1.0 - - l ... - m~y ater Row s Toda Reactvity 100.0 U
50.0 Cý -1.0 0.0 -2.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Tune (sec)
Figure 45 Plant Response to FW Controller Failure (EOC ICF with RPTOOS (UB))
Page 106
BROWNS FERRY 1 0000-0044-1520-SRLR PAn*rA A D ýv a U.1 A
300.0 200.0 100.0 0.0 0.0 3.0 &0 0.0 ao 6.0 Time (sec) Thne (Sec) 1.0
- 0 S0.0 U
W -1.0 100.0o I
-z0 0.0 3.0 6.0 0.0 3.0 6.0 Tine (sec) Tmve (sec)
Figure 46 Plant Response to Load Rejection w/o Bypass (EOC ICF with RPTOOS (UB))
Page 107
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 2M0.0 125.0 150.0 75.0 C;100.0 25.0 50.0 0.0 -25.0 0.0 10.0 0.0 10.0 20.0 TTmE (sec) Tune (sec) 150.0 U
-. 100.0 C 0
2 0
S U
50.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 47 Plant Response to Inadvertent HPCI /L8 (EOC ICF with RPTOOS (UB))
Page 108
BROWNS FERRY I 0000-0044-1520-SRLR Reload 6 Revision 0 "U
0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Tune (sec) 150.0
- ý II 1 1.o0*
O100.0 -
0.0 0
U 50.0 S-1.0 0.0-0.0 10.0 20.0 0.0 10.0 20.0 Tfne (sec) Tne (sec)
Figure 48 Plant Response to FW Controller Failure (EOC MELLLA with RPTOOS (UB))
Page 109
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 ae-*R0 . . 300.0 6 Relief Vlve Flw
--- Bypass VaWve Flow 150.0 V 200.0 100.0 100.0 0.0 I- M= 0.0 0.0 3.0 6.0 0.0 3.0 6.0 TUne (sec) Tnne (see)
ýe(incht-REF-SEP-SIKRT) Widdeatvy
- se Steam Flow X*- Reactfty 200.0 tine Steam Row 1.0 - Sc Reab.'vity xedater Row Total tVity C
100.0 0 S00.
0 0.0 * -1.0
-2.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (see) Tme (see)
Figure 49 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with RPTOOS (UB))
Page 110
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 125.01
---*- Safet Dome PressValve Raw Ref ValeRow
--- Bpass Valoe Flow
- -- PCI Fkow (% FW)
Rise (psi)
/
"0 75.0 4100.0 25.01 50.0
=*
- M ; L ...... * ..... ..-.*_ L.L..= ,.=,=...=
0.0 -25.0 1 0 .0 10.0 20.0 0.00 10.0 20.0 Tne (sec) T'ffE (sec) 150.0 1.0 100.0 0.0 0
U 50.0 S-1.0
-20 0.0 10.0 20.0 0.0 10.0 20.0 T-ne (ec) Thne (sec)
Figure 50 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with RPTOOS (UB))
Page 111
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 150.0 200.0 010l0.0 50.0 iA 0.0 ..- * ... ,.
0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 T'M (sec) T'U (sec)
X-h-REF-SEP-SKRT) -e- Mid React*
-- Dqoppler Reacfit 150.0 Flow 1.0 -Steam
-- Scram Reactivity ater Row s Totl Reactivity 0.0 U
50.0 04 -1.0 0.0 -2.0 0.0 5.0 10.0 15.0 0.0 5.0 0.0 15.0 T-ne (sec) T-ne (Wc)
Figure 51 Plant Response to FW Controller Failure (MOC ICF & FWTR with RPTOOS (HBB))
Page 112
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
-*- Dome Press Rise (psi)
-*- Safety Vale Row
- Relief Valv Raw 125.0
- Bypass Vave Row
-a- I-PCI Fow (% FW) 150.0
,0 75.0 100.0 25.0 0.0 0.0 10.0 0.0 10.0 20.0 Tu-m (sec) Tmie (sec) 150.0 U
100,0 0 04 20
.5 U
50.0 0.0 100 20.0 0.0 10.0 20.0 TiCe (*ec) Time (sec)
Figure 52 Plant Response to Inadvertent HPCI /L8 (MOC ICF & FWTR with RPTOOS (HBB))
Page 113
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
-a- Done Press Rise (psi)
Safety Valve Row 300.0 -& Relief Vave Raw
-s- Bypass Valve Raw 150.0 o 200.0 100.0 100.0 50.0 0.0 J 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Thme (sec) Tine (sec)
--a- Void Reactivity
- Doppler Reactivity 150.0 1.0 -s- Scram Reactivity
- Tc s- Reactivity oal 100.0 0.0 M " a 9 0
U 50.0 9 -1.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 TUie (sec) Tune (sec)
Figure 53 Plant Response to FW Controller Failure (EOC ICF & FWTR with RPTOOS (HBB))
Page 114
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 150.0 "0
V 14 10D.0 50.0 0.0 10.0 20.0 0.0 10.0 20.0 TITe (sec) Thne (sec)
--a- Void Reactd*ty Doppler Reactivity 0 --. Scram Reactivty U
C 0.0 C
04 2
0 U
U
-1.0
-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Thr (sec)
Figure 54 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with RPTOOS (HBB))
Page 115
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
-- Dome Press
-- Safety Rise (psi)
Valve Flaw 300.0 Relief Valve Row
- Bypass Vave Row 2DO.
100.0 0.0 - 1 1m
- 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Tne (sec) 150.0 1.0
. 100.0 0 0.0 U
S-1.0 0.0 t- -2.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Thme (sec) T'ne (sec)
Figure 55 Plant Response to FW Controller Failure (MOC MELLLA & FWTR with RPTOOS (HBB))
Page 116
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 U
0.0 10.0 0.0 10.0 20.0 T'me (sec) T'mr (sec) 150.0 1.0 100.0 o 0.0 4) 0 U
50.0 S-1.0 0.0 -z0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) TiEm (sec)
Figure 56 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA & FWTR with RPTOOS (HBB))
Page 117
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
-e- Dom* Press Rise (psi)
--- Safety Vale FON Relief Valve
,-Bypass ValveRow Row
. 200.0 100.0 100.0 50.0 0.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tune (sec) Tume (sec) 150.0 1.0 00.0 P 50100.0 U
0.0 50.0 2.0 15.0 0.0 0.0 5.0 10.0 5.0 10.0 15.0 Tm~e (sec) -rum(sec)
Figure 57 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with RPTOOS (HBB))
Page 118
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 2M0.0 125.0 150.0 "0 75.0 X100.0 25.0 50.0 0.0 -25.0 0.0 10.0 20.0 0.0 10.0 20.0 T'm (sec) Tum (sec) 150.0 U
1~X~0 0 0
4.'
E 0
Q a.'
50.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 58 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with RPTOOS (HBB))
Page 119
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 2(0.0
--- Dome Press Rise (psi)
-*-Sft sssss*.Va;eRaw ilet Raw 3Mo.o A Relief Vave RowM/
ilet Subcoling -- Bypass Vale RF 150.0
- 200.0 100.0 100.0 50.0 0.0 0.0 6* 9_~ . I 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) ThtE (Sec) nch-REF-SEP-SKRT) -a- Void Reactivity skmm Row-*0 Doppler Rat 150.0 DSteam Flow 1.0 6--Scran Reaclviy ater Flow s Tota Reactvity 0.0 B1 2
50.0 S-1.0 0.0 -201 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 T-re (sec) Tmr (sec)
Figure 59 Plant Response to FW Controller Failure (EOC ICF & FWTR with RPTOOS (UB))
Page 120
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revisinn 0 200.0
-a- Dome Press Rise (psi)
---s- Safety Valve Raw Relief Valve Raw 125.0
- %-pass NMle RoN HPCI Raw (%FW) 150.0
". 75.0 4 D 2.
S100.0 25.0 0.0 10.0 20.0 0.0 10.0 20.0 Tune (sec) Ttme (sec) 150.0 100.0 4) 0 U
50.0 0.0 "
0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Tume (sec)
Figure 60 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with RPTOOS (UB))
Page 121
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
-*- Dome Press Rise (psi)
- Sa..fetyheFolw let Row 300.0 s Relief Vadve Flow w t s-- Bypass VaIve Ro
. 200.0 100.0 0.0 12 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tuhe (sec) Tffn (sec) nch-REF-SEP-SKRT) -a- Viid Reacth*ity Ekm Rev: . __4_ Dopp React
) Stearn Ro 1.0 a. Scram React*
ater Row -.-- Tota Reactiy "0100.0 CA -1.0
-2.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tune (sec) Tume (sec)
Figure 61 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with RPTOOS (UB))
Page 122
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 125.0 150.0 "7 75.0 S100.0 25.0 0.0 I- -25.0 0.0 10.0 0.0 10.0 20.0 Tme (sec) Thme (Sec) 150.0 1.0
.0.0 0
U S-1.0 0.0 -20 0.0 10.0 20.0 0.0 10.0 20.0 Tune (Sec) Tune (sec)
Figure 62 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with RPTOOS (UB))
Page 123
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 150.0 100.0 100.0 50.0 0.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tihm (sec) Time (sec) 150.0 100.
U I -1.0
-20 0.0 5.0 10.0 15.0 0.0 5.0 10. 0 15.0 Time (sec) Trme (sec)
Figure 63 Plant Response to FW Controller Failure (MOC ICF with TBVOOS (HBB))
Page 124
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 Dome Press a -x-Safety Rise (psi)
Wilve FRON 125.0 ,Relief Valve
---Bypass M-aveFlwRow
-HtPCI Flow (%FW)
, 75.0 25.0 0.0 10.0 20.0 0.0 10.0 20.0 TTine(sec) T-ne (sec)
-*- Lovel(inch.-REF-SEP-SKRT)
-*- Vessell Steean Raw 150.0 e.--Turbine Stearn Fkaw
- s. Feectwatr Flaw S
4.1 S
"0 100.0 0 0..
2 0
44 4) 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 T-em (sec) Ture (sec)
Figure 64 Plant Response to Inadvertent HPCI /L8 (MOC ICF with TBVOOS (HBB))
Page 125
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
-E- Dome Press Rise (psi) 300.01
-* Saety
-*- ValveFlow Relief Valve FRow
-*- Bypass Valve FRow 200.0 100.0 0.01 0.0 t ,I A -.
0.0 5.0 10.0 15.0 0.00 5.0 10.0 15.0 Trme (sec) Time (sec) 150.0 2l -')V--Io I I r-ll
&M 1.0 --- It- cmI*I:
II r lcpcw lty ater Row s Total Reactivity 100.0 00.0 U
50.0 * -1.0 0.0 -20 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tkm (sec) Tfr (sec)
Figure 65 Plant Response to FW Controller Failure (EOC ICF with TBVOOS (HBB))
Page 126
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
- a Dome Press Rise (psi)
- )ESafety av~e Raw 125.0 1 Reief We Fky#
- Byjpass \"vFkm 75.0 sFlFPC ow(% FW 0) 14 25.01
- 1. z71~i~ -
0.0 i -25.0 -
0.0 10.0 20.0 0.0 10.0 20.0 Tfne (sec) Trne (sec)
-a Leve(inch-REF-SEP-SKIRT)
- Vessel Stearn Flow 150.01 -s- Turbine Stearn Flow 1.0
- e. FeedwAte Flow 4)
V 100.0 o 0.0 C
0 50.0 S-1.0 0.0 -2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Tfm (sec)
Figure 66 Plant Response to Inadvertent HPCI /L8 (EOC ICF with TBVOOS (HBB))
Page 127
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 0.0 5.0 i00 15.0 0.0 5.0 10.0 15.0 TIime (sec) T-ne (sec) 0.0
, -1.0
-2.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tine (sec) Tme (sec)
Figure 67 Plant Response to FW Controller Failure (MOC MELLLA with TBVOOS (HBB))
Page 128
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 125.0 150.0 "0 75.0 i*100.0 25.0 50.0 0.0 -25.0 0.0 10.0 20.0 30.0 0.0 10.0 20.0 irne (sec) T'fne (sec) 150.0
-' 100.0 -1.0 U
-2.0 0.0 20.0 30.0 0.0 10.0 20.
0.0 10.0 .0 30.0 Tm-e (W*C) T'un (WC)
Figure 68 Plant Response to Inadvertent HPCI /L8
( MOC MELLLA with TBVOOS (11111))
Page 129
BROWNS FERRY 1 0000-0044-1520-SRLR Rf'1In~d A R AiAinn n Reload A
-*- Dome Press Rise (psi)
-*- Safety Vade Flow
- Relief Valve Fo 300.0 *@-B-pBss Valve Flow 200.0 100.0 NN - _
0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Trun (sec) Tine (sec)
- 0 U
U 9 -1.0
-2.0 0.0 5.0 10.0 15.0 0.0 5.0 10. 0 15.0 Tfre (Sec) T'mn (sec)
Figure 69 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS (HBB))
Page 130
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 2M0.0 125.0
- 75.0 04 25.0
-25.0 0.0 10.0 20.0 30.0 0.0 10.0 20.0 Tme (Sec) T'me (sec) 150.0 1.0 100.0 o 0.0 U
50.0 I -1.0 0.0 -2.0 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Time (sec) T-re (see)
Figure 70 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with TBVOOS (HBB))
Page 131
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
-*- Dome Press Rise (psi)
-*- Safety Valve Flow 300.0
- Relief Valve Faw
-- Bypass Valve Row 150.0 "O 20O.0 100.0 100.0 50.0 0.0 aah 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tume (sec) Time (sec) 150.0 100.0 S0.0 50.0
- -1.0
-2.0 0.0 5.0 10.0 15.0 0.0 5.0 10.'0 15.0 Time (sec) Time (sec)
Figure 71 Plant Response to FW Controller Failure (EOC ICF with TBVOOS (UB))
Page 132
BROWNS FERRY 1 0000-0044-1520-SRLR PInnf A v I -- n
.~A;~
-*- Dome Press Rise (psi)
-*- Safety Valve Flow 125.0 Relief Velve Row Bypass Valve Row
-- HCI Fow (% FW)
" 75.0 25.0
-25.0 0.0 10.0 20.0 0.0 10.0 20.0 TTfE (sec) T'Mx (Sec)
--- Leve(inch-REF-SEP-SKRT)
-*- Vessel Steam Row 150.01 -,-- Turbine Steam Flow Feedwater Flow U
0 0
E U
U 50.0 A
0.0 10.0 20.0 0.0 10.0 20.0 Timn (sec) TUmi (Sec)
Figure 72 Plant Response to Inadvertent HPCI /L8 (EOC ICF with TBVOOS (UB))
Page 133
BROWNS FERRY I 0000-0044-1520-SRLR Reload 6 Revision 0 300.0
" 200.0 100.0 0.0 !- 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Time (Sec) 100.0 0.0 0..5 U
50.0 M -1.0 0.0 -2.01 0.0 5.0 10.0 15.0 0.0 5.0 10. 0 15.0 Time (see) TuE (see)
Figure 73 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS (UB))
Page 134
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 i
-a-- Dome Press Rise (psi)
-- SafetyValve Row
---Relief Valve Flowv 125.0
Bypass MVa Row
-+--FCI Flow (% FV)
- 75.0 25.01
-25.0 L-0.0 10.0 0.0 10.0 20.0 Tmne (sec) Time (Sec)
.--- Level(inch-REF-SEP-SKRT)
-*- Vessel Steam Flow 150.01
- Tuztne Stean Flow 1.0 Feedwater Flow 0.0 50.0 -1.0 0.0 -2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Tfm* (sec)
Figure 74 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with TBVOOS (UB))
Page 135
BROWNS FERRY 1 0000-0044-1520-SRLR D I~~A A; D-ý V D VJLI A 200.0
-a- Dome Press Rise (psi)
-,- Safety
-.-- ValveFlow Relief Valve Raw 300,0 s, Bypass Valve Flow 150.0 2O0.0 M
100.0 100.0 0.0 0.0 p - p 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Time (sec) 150.0 1.0 100.0 0.0
-1.0 50.0 0.0 -20 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sc) Trim (sWc)
Figure 75 Plant Response to FW Controller Failure (MOC ICF & FWTR with TBVOOS (HBB))
Page 136
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
--a Dome Press Rise (psi)
-x- Safety Valve Row 125.0 Relief \Vve Row Bypass Vale Flow HP-.Fcow I (%FW)
.O 75.0 25.0
-25.0 0.0 10.0 20.0 0.0 10.0 20.0 Thne (sec) Trme (sec)
-*- Level(inch-REF-SEP-SKRT)
-*-- Vessel Steam Row 150.0t ,& Turbine Stean Flow
-.-- Feedwater Flow U
100.0 0 50.0 0.0 1-0.0 10.0 20.0 0.0 10.0 20.0 Tlie (Sec) TifE (sec)
Figure 76 Plant Response to Inadvertent HPCI /L8 (MOC ICF & FWTR with TBVOOS (HBB))
Page 137
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 V
0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0
'I"- (sec) T'm- (sec) 150.0 U
100,0 C
2 0
U Cs U
50.0 0.0 L-0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (see) Tmre (sc)
Figure 77 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS (HBB))
Page 138
BROWNS FERRY I 0000-0044-1520-SRLR Reload 6 Revision 0
-a- Dome Press Rise (psi)
-*- Safety Valve ow 125.01 --*--ReliefsVave Byp~ass VaveRawFlow s+ I-PCI Flow (%FW) 150.0 75.01 S100.0 25.0 I 50.0 0.0 - -25.0 0.0 10.0 20.0 0.0 i10o 20.0 Time (sec) Tin- (Sec) 150.0 1.0 V 100.0 o 0.0 50.0 S-1.0 0.0 -2.0 0.0 10.0 20.0 0.0 10.0 20.0 TffnE (sec) Tune (sec)
Figure 78 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with TBVOOS (HBB))
Page 139
BROWNS FERRY I 0000-0044-1520-SRLR
ý U" D- I
- a M-A 200.0 150.0 100.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 T'n, (sec) Time (sec) 150.0 U
100~.0 0 2
0 U
U 50.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tiff (Sec) Thm- (Sec)
Figure 79 Plant Response to FW Controller Failure (MOC MELLLA & FWTR with TBVOOS (HBB))
Page 140
BROWNS FERRY 1 0000-0044-1520-SRLR V~~at D, ; ;
flSVIOaJfUl n
200.0
-a-- Dome Press Rise (psi)
--- Safety Vah Raw 125.0 -- Relief Vae Flow
- BypassVMae Row
-.- I-PCI Fkw (% FW) 150.0
.0 75.0 25.0 50.0
.4 0.0 -25.0 L-0.0 10.0 20.0 0.0 10.0 20.0 Tine (sec) Tirm (sec) 150.0 1.0 o 0.0
-1.0 50.0
-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) ThME (sec)
Figure 80 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA & FWTR with TBVOOS (HBB))
Page 141
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 2M.0 150.0 200.0 "w0 0*9100.0-100.0 50.0 0.0 0.06 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tihn (sec) Time (sec)
,ic.t-REF-SEP-SKRT) -- Void Reactity Steam, Re'; x Doppler Reactity 150.0 SStearn Flow 1.0 .- Scram Reacb*
ater Flow s Total Reacivity 4,
100.0 00.0 U
50.0 1 -1.0 0.0 -20 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15,0 Time (sec) Time (sec)
Figure 81 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS (HBB))
Page 142
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Tune (sec)
- n Leve(incht-RFF-SEP-SKRT)
-*- Vessel Stearn Raow 150.0 -- Turbine Stearn Flow
-- Feedwater Raw 100.0 2
0 L)
,50.0 U.U ~W 0.0 10.0 20.0 0.0 10.0 20.0 Turm (Sec) Tume (Sec)
Figure 82 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS (HBB))
Page 143
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
--a Dome Press Rise (psi)
-x-Safety Valve Flow Relief Valve Row
-s- Bypass Valve Row 150.0 U
4 100.0 -
'V
~200.0 100.0 50.0 2----
0.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tin-M (sec) Tint (sec) nch-REF-SEP-SKRT) -a- Void Reactivity
..- ROW. %-- Doppler Reactivity 150.0 Steam Flow 1.0 -a- Scram Reactivity ater Row - Total Reactivity 5100.0 0.0 50.0
- -1.0 0.0 .... - -- -20 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tine (sec) T-um (sc)
Figure 83 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS (UB))
Page 144
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
-- Domne Press Rise (psi) 125.0 1 '6 RelifVeFow 150.0 "0 75.01 100.0 25.0 50.0 0.0 L- -25.0 0.0 10.0 0.0 10.0 20.0 Trme (sec) TinE (Sec)
--- Level(inch-REF-SEP-SKRT)
-*-- Vessel Steam low 150.0 -t-- Turbine Steam Flow 1.0
-- Feedwater Raw 0100.0 o 0.0 0
ova U
- -1.0 0.0 -20 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Tnme (sec)
Figure 84 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with TBVOOS (UB))
Page 145
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
- Neutr FLux/l10 face Heat FluxD 6---Core k
-- Core Ir --- Bypass Vave Ra Rw300.0 -a-.- m'oule vaive t-lOW 150.0 200.0 100.0 100.0 50.0 2
0.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tnm (sec) T'i (sec) nch-REF-SEP-SKRT) -a- Void Reactivity Slew-R- Doppler Reactivty 150.0 aStean Flow 1.0 - Scram Reactmty
- merRow -o- Tota Reactivity 100.0 04 50.0
-20 0.0 10,0 15.0 0.0 5.0 10.0 15.0 Tfme (Sec) Tme (eeC)
Figure 85 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS (UB))
Page 146
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 150.0 V)
S100.0 50.0 0.0 0.0 10.0 20.0 0.0 10.0 20.0 Tfmt (sec) Tuml (see) 150.0 1.0 100.0 o 0.0 U
50.0 -1.0
-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Titm (see) Time (sec)
Figure 86 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS (UB))
Page 147
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 ZAJ.U 100.0
"*'**D 0.0 T67 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tmlie (sec) d(inch-REF-SEP-SKRT) - d React L~ Steam RawR %
Stear Flow trbine 1.0 KsSteam Flow 0.0
-'- 1% -1.0 1 -20
-100.0, 3.0 6.0 0.0 3.0 0.0 6.0 Trme (sec) T'me (sec)
Figure 87 Plant Response to Load Rejection w/o Bypass (MOC ICF with PLUOOS & RPTOOS (HBB))
Page 148
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
- -Nairon Rux / 10
-* A/g Srfaew Heat Flux
-si Core We Raw 150.0 4100.0 100.0
--"k R 0.0 fm 0.0 3.0 6.0 0.0 3.0 6.0 Tmue (sec) TU'* (sec) e(inch-REF-SEP-SKRT) -.- Reacty ksd Steam Roaw avity bineSteam Rawo 1.0 ranR ty dw-ate FlAN R 0o.0 U
A -1.0
-100.0 1- -2.0 0.0 3.0 6.0 0.0 3.0 6.0 Tfe (sec) Tune (sec)
Figure 88 Plant Response to Load Rejection w/o Bypass (EOC ICF with PLUOOS & RPTOOS (HBB))
Page 149
BROWNS FERRY I 0000-0044-1520-SRLR Reload 6 Revision 0 300.0 100.0
-4 o.0 --
0.0 3.0 6,0 0.0 3.0 6.0 Tme (sec) Tlie (sec) 200.0 1.0 V. 100.0 0.0 1
- -1.0I 0.0 100.0 -J -20 ý-
0.0 3.0 6.0 0.0 6.0 Time (sec) Y'm-w3.0(se)
Figure 89 Plant Response to Load Rejection w/o Bypass (MOC MELLLA with PLUOOS & RPTOOS (HBB))
Page 150
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
-a- Dome Press Rise (psi)
-- Safety Valve Raw 300.0 6Relief Valve Fkow
-*Bypass Valve Row "O200.0 100.0 1 J 0.01 . WA 8 W 0.0 3.0 6.0 0.0 3.0 6.0 Tmie (sec) Time (sec) 200.0 1.0 100.0 0.0 4)
U 0.0 S-1.0
-100.0 -z0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) Tume (sec)
Figure 90 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with PLUOOS & RPTOOS (HBB))
Page 151
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 2M.0 150.0 100.0 0.0 3.0 6.0 0.0 3.0 6.0 Thxe (sec) Tune (see) 1.0 0.0 0 -1.0
-20 0.0 3.0 6.0 0.0 3.0 6.0 Tune (sec) Time (sec)
Figure 91 Plant Response to Load Rejection w/o Bypass (EOC ICF with PLUOOS & RPTOOS (UB))
Page 152
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 2030.0 150.0 4 100.0 50.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 ThmE (sec) Tnme (sec)
C U
"U S
0 U
U 0.0 3.0 6.0 0.0 3.0 6.0 Tm~e (sec) T'nm (sec)
Figure 92 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with PLUOOS & RPTOOS (UB))
Page 153
BROWNS FERRY 1 0000-0044-1520-SRLR RdAIA- A D ýv ; o w" 200.0 We aieF .... 300.0
- Reh*iW eFIlow
- Bypass Vdve Flow
, 00.0 100.0 0.0 3.0 6.0 0.0 3.0 6.0 Tilne (sec) Tfne (sec) 9MQnch-REF-SEP-SKRT) bssel Steam Flow n-200.0 urbine Steam Flow 1.0 "eswater Flow - Reivitv "
C V 100.0 S0.0
-1.0 0.0 -2.0
-100.0 3.0 6.0 0.0 3.0 0.0 6.0 Tune (Sec) Tne (sec)
Figure 93 Plant Response to Load Rejection w/o Bypass (MOC ICF & FWTR with PLUOOS & RPTOOS (IBB))
Page 154
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
-a- Dome Press
--*- Safety Rise (psi)
Valve Flow Relief Valve Flow s Bypass Vave Flaw 150.0 13100.0 100.0 50.0 I/
0.0 0.0 L-0.0 3.0 6.0 0.0 3.0 6.0 Mmne (sec) TyEm (sec) 6, C
U C
0 04 2
0 Cs 4) 0.0 3.0 6.0 0.0 &0 6.0 Time (sec) TynE (sec)
Figure 94 Plant Response to Load Rejection w/o Bypass (EOC ICF & FWTR with PLUOOS & RPTOOS (HBB))
Page 155
BROWNS FERRY I 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 150.0 "AU.U 100.0 100.0 50.0 0.0 0.0 -
0.0 3.0 6.0 0.0 3.0 6.0 Tnre (sec) Tome (sec)
"0 0 U
0.0 3.0 6.0 0.0 3.0 6.0 Tume (sec) Tfne (sec)
Figure 95 Plant Response to Load Rejection w/o Bypass (MOC MELLLA & FWTR with PLUOOS & RPTOOS (HBB))
Page 156
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 -
150.0 100.0 -
100.0 50.0 0.0 0.0 0.0 3.0 6.0 0.0 3.0 6.0 T'mE (sec) T-uE (sec) i-- Lev(incWREF-SEP-SKRT) a--- V\Id 200.0 Vsse
\-
- -Turbine Steam Flow Steam Raw 1.0 X a_*&
SFeedvvater RON T 100.0 S-.00 0
0 U
0.0 i -1.04
-100.0 0.0 3.0 6.0 0.0 3.0 6.0 Time (sec) T'Me (seC)
Figure 96 Plant Response to Load Rejection w/o Bypass (EOC MELLLA & FWTR with PLUOOS & RPTOOS (HBB))
Page 157
BROWNS FERRY 1 0000-0044-1520-SRLR PA1naA A P-.p,1n, 200.0 150.0
- 0O.
l00.0 50.0 0.0 0.0 0.0 3.0 6.0 0.0 ao 6.0 Time (sec) Tfne (sec)
F(igch-REF-SEP-SlaTn -a- d RLacnB (EO Stearn Flow P O ROty tine Steam Flow 1.0 ram ty xkwater Flow 40 U
U 6 100 v~
-20
~
3.0 ~ 6. 1 .030 0.0 6.0 Tune (sec) TffMe (Sec)
Figure 97 Plant Response to Load Rejection w/o Bypass (EOC ICF & FWTR with PLUOOS & RPTOOS (UB))
Page 158
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
. 200.0 100.0 0.0 3.0 6.0 0.0 3.0 6.0 TiMn (sec) Time(sec)
- LeveI(inch-REF-SEP-SKRT) a-- d Reactivi
- Vessel Stean Row --- Reacivity 200.0 - Ttrbine Steam Row 1.0 ramn Reacity
- Feedwater Flow -l Reacti 100.0 0.0 0.0 I* -1.0
-100.0 L -20 0.0 3.0 6.0 0.0 3.0 6.0 Tune (sec) T-rm (sec)
Figure 98 Plant Response to Load Rejection w/o Bypass (EOC MELLLA & FWTR with PLUOOS & RPTOOS (UB))
Page 159
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 2M0.0
.DO.
100.0 100.0 0.0 0.0 10.0 15.0 0.0 5.0 10.0 15.0 Tmfe (sec) Tmie (sec) 150.0 I rpuI Xt 1. 'Ju cmiI I rxoouvfty ate RoFw --o-- Tot* Reactiv*ty 100.0 0.0 .-
04 50.0 S-1.0 0.0 -2.0 0.0 5.0 10.0 15.0 0.0 5.0 10. 0 15.0 T*re (sec) Trne (sec)
Figure 99 Plant Response to FW Controller Failure (MOC ICF with TBVOOS & RPTOOS (HBB))
Page 160
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
-x-- Dome Safety Press Rise (psi)
Valve FRow a- Relief Vaive Row 125.0
-*-- Bypass VWve Fow
-s-- I-PCI Fkow (% FW)
"U 75.0 25.0
- -- 7ýr"T1777-.,; - - ý- -: -. - -ý-ýM=-=-- A ""
0.0 10.0 0.0 10.0 20.0 ThEl (ScC) T'ic (see)
E3-Levd(inch.-REF-SEP-SKRT) x* VAessel Stearn Row 150.0 -s- Turbine Stearn Flow s.- Feedwater Raow
.U10. E 0
0.0 -A-0.0 10.0 20.0 0.0 10.0 20.0 Tffnm (sec) Tnne (sec)
Figure 100 Plant Response to Inadvertent HPCI /L8 (MOC ICF with TBVOOS & RPTOOS (HBB))
Page 161
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
--- Dome Press Rise (psi)
-- Saf Mave R-l ARelif Vve Roaw
-*- Bypass V\3e Row 150.0 V 20.
100.0 50.0 0.0 U.U S 6 :1 +/-
1MA 0.0 5.0 100 15.0 0.0 5.0 10.0 15.0 Tfme (sec) Time (sec) 150.0 vater Row -- Toal Reactivity Fiezir m113
-ow . 1.0 our-cTirr mky-tiv/ly 0.0 50.0 9 -1.0 0.0 - -2.0 0.0 5.0 10.0 15.0 0.0 5.0 10,0 15.0 TiEm (Sec) Time (see)
Figure 101 Plant Response to FW Controller Failure (EOC ICF with TBVOOS & RPTOOS (HBB))
Page 162
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
-a- Dome Press Rise (psi)
-*- Safety Vahe Flow 125.0 Relief Valve Raw Bypass \vae Flow
--- -PCI Flow (% FW) 150.0
-O 75.0 100.0 25.0 50.0 0.0 -25.0 0.0 10.0 0.0 10.0 20.0 Time (sec) T-E (sec) 150.0
'4 C
U C
010.0 C C..
2 0
U (S
U 50.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (sec)
Figure 102 Plant Response to Inadvertent HPCI /L8 (EOC ICF with TBVOOS & RPTOOS (HBB))
Page 163
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
-a- Dome Press Rise (psi)
-*- Safety Valve RFow 6Relief Valve Flow
---Bypass Valve Raw 100.0
^^ q 0.0 a-0.0 5.0 10.0 15.0 0.0 10.0 15.0 T'tme (sec) Tmre (sec) 150.0 C
5*.0 oa 0.
U 50.0 g -1.0 0.0 -20 0.0 5. 0 10.0 15.0 0.0 5.0 10.0 15.0 Trim (se) Tm-e (se)
Figure 103 Plant Response to FW Controller Failure (MOC MELLLA with TBVOOS & RPTOOS (HBB))
Page 164
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 i
-a-- Dome Press Rise (psi)
-*- Safety Vave RFow 125.01 6 Relief Malv
-*---Bypass ValvRow Raw
-- I-PCI FRON (%FW)
I 75.0 U* U ci 25.0
-25.0 0.0 10.0 20.0 0.0 10.0 20.0 Time (8m) Time (see) 0 U
0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Time (Sec)
Figure 104 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA with TBVOOS & RPTOOS (HBB))
Page 165
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 150.0 U
ino 10100.0 50.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tm-xe (sec) TiTfle (see) 150.0 U
100.0 0.0 t0 U
50.0 9 -1.0
-Z0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 TumE (sec) Thme (see)
Figure 105 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS & RPTOOS (HBB))
Page 166
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 20D.0 150.0 V
4 100.0 50.0 0.0 0.0 10.0 0.0 10.0 20.0 Time (sec) T'mn (sec) 150.0 50.0t 0.0 10.0 20.0 0.0 10.0 20.0 Tume (ec) TmTe (sec)
Figure 106 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with TBVOOS & RPTOOS (HBB))
Page 167
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
--- Dome Press Rise (psi)
- Safety Valve Flo SRelief Vave
-s-Bypass ValveRoN Flow 150.0 O 200.0 100.0 100.0 50.0 0.0 - 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Tune (Sec) 150.0 pm't=I I rKuW 1. - ,
%.lic I I I~uNC Iwy oater Row s Totl Reactivity 100.0 S0.0
- -1.0 0.0 -20 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Trun (8ec) T-m- (ec)
Figure 107 Plant Response to FW Controller Failure (EOC ICF with TBVOOS & RPTOOS (UB))
Page 168
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0
-*- Dome Safety Press Rise (psi)
Vahe Flow \
- - Relief Valve Flow 125.0
-- Byps ive Row F a I-PCI Row (% FW) 75.0 1003.0 25.0 1 0.0 10.0 20.0 0.0 10.0 20.0 Tmie (sec) Thme (sec) 9 LevI_(inch-REF-SEP-SKRT)
- Vessel Stearn Row 150.0 s Tutrine Stean Flow 1.0 s Feedwater Flow
. 100.0 0 U
o 01.0 50.0 0.0 -2.0-0.0 10.0 20.0 0.0 10.0 20.0 Tin (Sec) Time (sec)
Figure 108 Plant Response to Inadvertent HPCI /L8 (EOC ICF with TBVOOS & RPTOOS (UB))
Page 169
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 150.0
- 200.0
, 100.0 100.0 50.0 0.0 L- 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tffe (sec) T'ime (sec) 150.0 C 1.0 - ,.Tota
-A , Reactivity
, -vy II r" Flow-100.0
-1.0 50.0
-2.
0.0 10.0 15.0 0.0 5.0 10.0 0.0 5.0 15.0 Tune (Sec) Time (sec)
Figure 109 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS & RPTOOS (UB))
Page 170
BROWNS FERRY I 0000-0044-1520- SRLR Reload 6 Revision 0 2(f0.0 125.0 1 75.O 200.0 50.0 25.0 0.0
-25.0 0.0 10.0 20.0 0.0 10.0 20.0 TfTme (sec) Tnie (sec)
U C
C 2
0 U
0.0 10.0 20.0 0.0 10.0 20.0 TInEm (sec) rinm (sec)
Figure 110 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with TBVOOS & RPTOOS (UB))
Page 171
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Ti*e (sec) 150.0
£4 U
100.0 C 0
0 C-)
ci U
50.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Tume (sec)
Figure 111 Plant Response to FW Controller Failure (MOC ICF & FWTR with TBVOOS & RPTOOS (HBB))
Page 172
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 100.0 0.0 10.0 0.0 10.0 20.0
-rim (sec) Mme (sec) 150.0 4) 0 0.
2 C
44 4) 50.0 0.0 10.0 20.0 0.0 10.0 20.0 Tffe (sec) Tune (8m)
Figure 112 Plant Response to Inadvertent HPCI /L8 (MOC ICF & FWTR with TBVOOS & RPTOOS (HBB))
Page 173
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 150.0 100.0 100.0 0.0 0.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 TnrE (sec) Time (sec)
,v(inch-REF-SEP-SKRT) -e- Vid Reactvity
- - RA-*- Doppler Rectivity 150.0 biýne Steam Flow 1.0 Scram Reactvity edwater Flow s.- Total Reacbvity 100.0 U
01.0
- -1.0 50.0
-201 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 TnnE (sWc) Tune (Wec)
Figure 113 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS & RPTOOS (HBB))
Page 174
BROWNS FERRY I 0000-0044-1520-SRLR Reload 6 Revision 0
-a-- Dome Press Rise (psi)
-x-- Safety alve Raow 125.0 [ Relief Valve Flow
--- Bypass Valve Faw
-- l-PCI Flow (% FW)
- 75.0 100.
25.0
-25.0 L-0.0 10.0 20.0 0.0 10.0 20.0 Tune (sec) Tff w (sec)
- Leve(inch-REF-SEP-SKRT)
-*-- Vessel Stean Flow 150.01
- Turbine Stearn Flow 1.0 s-- Feedwater Flow 100.0 o 0.0 U
-1.0 0.0 0.0 10.0 Tife (sec) 20.0 Jul -2.0 0.0 10.0 Time (sec) 20.0 Figure 114 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with TBVOOS & RPTOOS (HBB))
Page 175
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 300.0 150.0 2DO.
100.0 0.0 0.0 -
0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Tine (sec) Time (sec) 1.0 0.0 U
1 -1.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Thfm (sec) ThmE (see)
Figure 115 Plant Response to FW Controller Failure (MOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB))
Page 176
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 SDome Press Rise (psi)
---Safety Valve Flow 125.0 1 Relief Valve Row s, Bypass I-PCI FlowValve
(%Row FVV) 75.0 25.01 I-
-25.0 I-0.0 10.0 20.0 0.0 10.0 20.0 Tnne (sec) TMe (Sec)
-*-- Levd(inch-REF-SEP-SKRT)
-*-- Vessel Stean Row 150.0 -s- Tudbine Steam Flw 1.0 s- Feedwater Flow o 0.0 50.0 .1.0 0.0 MI -20 0O. 10.0 20.0 0.0 10.0 20.0 T-imr (sec) Tine (sec)
Figure 116 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB))
Page 177
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
-a-- Dome Press Rise (psi)
-*- Safety Valve Row SRelief Vale Raw Bypass Valve Roaw 200.
4100.0 100.0
- r*3..... 0... .
0.0 1 U.0 QU 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 TimE (sec) Trm (sec) 150.0 1.0 100.0 0.0 c -1.0 50.0 0.0 -20 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) TUie (sec)
Figure 117 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB))
Page 178
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 125.0 150.0 75.0
- 100.0o 25.0 50.0 0.0 -25.0-0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 T're (sec) TMIe (see) 150.0 1.0 510.0 o 0.0 U U
50.0 -1.0 0.0 -2.0 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Tiffe (sec) Time (sec)
Figure 118 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB))
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
-*- Dome Press Rise (psi)
- Safety Fow VaveFlow Relie Vave
-- Bypass Valve Flow 150.0 200.0 100.0 50.0 0.0 100.0 0.0 I
0 0.0 5.0 10.0 15.0 0.0 5.0 10.( 15.0 T-ue (sec) Trne (sec) eI(inch-REF-SEP-SKRT) a Void Reactivity
--- Doppler Reactivity 150.0 oineý Stee- Flow 1.0 Scram Reactivity dwater Row s-- Total Reactivity 100.0 .0 15 0.0 E1 5.0 t
0 U
S-1.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 T-nr (sec) TrmE (sec)
Figure 119 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS & RPTOOS (UB))
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BROWNS FERRY I 0000-0044-1520-SRLR Reload 6 Revision 0 I
Dome Press Rise (psi)
Safety ale Roaw 125.0 1 -s Reliefl Vave Flow Bypass Vave Flow
--.- H-CIFkwv (% FW) 75.0
- 100.0 25.01 50.0 0.0 -25.01-01.0 10.0 20.0 0.0 10.0 20.0 Trne (sec) TifE (sec)
--- Le&e(inch-REF-SEP-SKRT)
-*-- Vessel Steam Row 150.0 -*- Turbine Steae Flow 1.0
-o- Feectvater Flow 100.0 o 0.0 3.-82zz * -1.0 0.0 -20 0.0 10.0 20.0 0.0 10.0 20.0 Time (see) Tme (sec)
Figure 120 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with TBVOOS & RPTOOS (UB))
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BROWNS FERRY I 0000-0044-1520-SRLR Reload 6 Revision 0 200.0
-a- Dome Press
--*--Safety Rise (psi)
Valve Flow 300.0 -- Relief aveRow
- Bylpass VWive Row 150.0
- 200.0 100.0 50.0 0.0 0.0 :
0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec) Tmue (Sec) 1 0
4.)
0 0
0 U
(4 4.)
0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 TIITm (sec) Tum (sec)
Figure 121 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS & RPTOOS (UB))
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 125.0
,. 75.0 100.0 25.0
-25.0 0.0 10.0 0.0 10.0 20.0 Tlie (sec) Time (sec) 150.0 1.0 o 0.0 U
50.0 -1.0 0.0 -20 0.0 10.0 20.0 0.0 10.0 20.0 Time (Sec) Time (sec)
Figure 122 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS & RPTOOS (UB))
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 200.0 300.0 150.0 V 20O.0 100.0 100.0 50.0 0.0 0.0 -4 8.
0.0 4.0 0 0.0 4.0 8.0 Time (sec) Tine (sec)
-a-. LeveI(inch-REF-SEP-SKRT)
--- Vessel Stean Flow 200.0 -.a Turbine Stearn Row 1.0
-..-- Feedwater Flow 100.0 S0.0 0
2
- -1.0 0.0 1UU.U I 0.0 4.0 8.0 0.0 4.0 8.0 Tffe (sec) T'f-M (sec)
Figure 123 Plant Response to MSIV Closure (Flux Scram) - ICF (HBB)
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 100.0 430.0 -
0.0 4.0 8&0 0.0 4.0 Tune (see) Tune (sec) 200.0 1.0 V 100.0 S0.0 4-
-1.0 0.0
-20
-100.O0 0.0 4.0 8.0 0.0 4.0 8,0 Tine (sec) Time (sec)
Figure 124 Plant Response to MSIV Closure (Flux Scram) - MELLLA (HBB)
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 Appendix A Analysis Conditions The reactor operating conditions used in the reload licensing analysis for this plant and cycle are presented in Table A-1. The pressure relief and safety valve configuration for this plant are presented in Table A-2. Additionally, the operating flexibility options listed in Section 8 are supported by the reload licensing analysis 14 Table A-1 Reactor Operating Conditions Analysis Value Parameter ICF LCF ICF LCF NFWT NFWT RFWT RFWT Thermal power, MWt 3458.0 3458.0 3458.0 3458.0 Core flow, Mlb/hr 107.6 83.0 107.6 83.0 Reactor pressure (core mid-plane), psia 1066.0 1061.5 1057.7 1053.4 Inlet enthalpy, Btu/lb 526.0 518.2 519.7 510.3 Non-fuel power fraction 0.036 0.036 0.036 0.036 Steam flow, Mlb/hr 14.17 14.14 13.26 13.23 Dome pressure, psig 1035.0 1035.0 1027.4 1027.4 Turbine pressure, psig 988.8 989.0 986.8 986.9 Table A-2 Pressure Relief and Safety Valve Configuration Valve Type Number of Lowest Setpoint Valves (psig)
Safety/Relief Valve 13 1169.1 14The number of valves shown in column 2 of Table A-2 represents the total number Safety/Relief valves configured at the plant. The reload licensing analysis assumed 12 Safety/Relief valves operable to support the SRVOOS flexibility option identified in Section 8.
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 Appendix B Decrease in Core Coolant Temperature Events The Loss-of-Feedwater Heating event was analyzed at 100% rated power using the BWR Simulator Code. The use of this code is permitted in GESTAR II. The transient plots, neutron flux, and heat flux values normally reported in Section 9 are not an output of the BWR Simulator Code; therefore, those items are not included in this document. The OLMCPR result is shown in Section 11.
In addition, the Inadvertent HPCI start-up event was shown to be bounded by the LFWH event in accordance with Determination of Limiting Cold Water Event, NEDC-32538P-A, February 1996. The Inadvertent HPCI with a Turbine Trip results are presented in Sections 9 and 11 and have been confirmed to be bounded by other pressurization events for Browns Ferry Unit 1 Cycle 7.
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 Appendix C Expanded Operating Domain Analyses To provide Browns Ferry Nuclear Plant Unit 1 with operating improvements, expanded operating domain analyses were performed for maximum extended load line limit (MELLL) operation (81% flow),
increased core flow (ICF) operation up to 105% of rated flow, final feedwater temperature reduction (FFWTR) and feedwater heaters out-of-service (FWHOOS) were performed at a temperature of 327.0'F
(-54.7°F at rated power), turbine bypass valves out-of-service (TBVOOS), and recirculation pump trip out-of-service (RPTOOS). In addition, in the event of power load unbalance failure (PLUOOS), limits have also been provided.
Coastdown operation beyond full power operation to 40% power is conservatively bounded by the MCPR operating limits given in Section 11 of this document at the applicable core flow and feedwater temperature conditions in the expanded operating domain (Reference C-1).
Maximum Extended Load Line Limit The operating domain MELLL was established for Browns Ferry Nuclear Plant Unit 1 in Reference C-2.
Increased Core Flow and Final Feedwater Temperature Reduction Operation with ICF throughout the operating cycle and with ICF and FFWTR at the end of the operating cycle was justified for Browns Ferry Nuclear Plant Unit 1 in Reference C-3.
Feedwater Heaters Out-of-Service (FWHOOS)
Operation with FWHOOS (-54.7°F at rated power) throughout the cycle was justified for Browns Ferry Nuclear Plant Unit 1 in Reference C-3. The operating limit MCPR for FWHOOS is bounded by the operating limit for FFWTR (-54.7°F at rated power).
Power Uprate Operation with power uprated to 3952 MWth was justified for Browns Ferry Nuclear Plant Unit 1 in Reference C-3. Operation with power uprated to 3458 MWth was justified for Browns Ferry Nuclear Plant Units 2 & 3 in Reference C-8; this analysis is also applicable to Browns Ferry Nuclear Plant Unit 1.
Turbine Bypass Valve Out-of-Service (TBVOOS)
Operation with TBVOOS was justified for Browns Ferry Nuclear Plant Unit 1 in References C-3, C-5, and C-7.
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 EOC Recirculation Pump Trip Out-of-Service (EOC-RPTOOS)
Operation with the EOC RPTOOS was justified for Browns Ferry Nuclear Plant Unit 1 in Reference C-3, C-5, and C-7.
Turbine Bypass and Recirculation Pump Trip Out-of-Service Operation with the combined Turbine Bypass and Recirculation Pump Trip (RPT) Out-of-Service condition was justified in Reference C-7.
Rod Block Monitor (RBM) Considerations The ARTS Rod Withdrawal Error (RWE) analysis validated that the following MCPR values provide the required margin for full withdrawal of any control rod during Browns Ferry Nuclear Plant Unit 1 Cycle 7:
For Power < 90%: MCPR > 1.70 For Power > 90%: MCPR > 1.40 The reported results below are a maximum of the cycle specific and the generic limit for each setpoint.
The RWE OLMCPR values for the 114% and 117% HTSPs are the same as the generic values calculated in Reference C-2 scaled by the change in the Browns Ferry Nuclear Plant Unit 1 Cycle 7 safety limit.
HTSP Reference C-2 Browns Ferry 1 Cycle 7 Without RBM Filter MCPR Limit (based on 1.07 SL) Rated MCPR Limit (based on a 1.09 SL) 107% 1.20 1.32 111% 1.25 1.32 114% 1.30 1.32 117% 1.35 1.38 Filtered setpoints are specified to be lower than unfiltered setpoints due to the additional lag or delay time associated with filtering. The RWE results shown above for the four HTSPs are unblocked for the Cycle 7 specific calculation at 3952 MWth. Thus the results for the filtered signals would remain the same as the lags or delays in the block associated with the filtered signal makes no difference in the results. The RWE results reported above are those calculated at 3952 MWth and they bound the cycle specific calculations performed for Browns Ferry Unit 1 at 3458 MWth.
ARTS Power and Flow Dependent Limits The ARTS power and flow dependent operating limits for all operating flexibility options are provided in Reference C-6.
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 EOC Recirculation Pump Trip Out-of-Service (EOC-RPTOOS)
Operation with the EOC RPTOOS was justified for Browns Ferry Nuclear Plant Unit 1 in Reference C-3, C-5, and C-7.
Turbine Bypass and Recirculation Pump Trip Out-of-Service Operation with the combined Turbine Bypass and Recirculation Pump Trip (RPT) Out-of-Service condition was justified in Reference C-7.
Rod Block Monitor (RBM) Considerations The ARTS Rod Withdrawal Error (RWE) analysis validated that the following MCPR values provide the required margin for full withdrawal of any control rod during Browns Ferry Nuclear Plant Unit 1 Cycle 7:
For Power < 90%: MCPRŽ 1.70 For Power _>90%: MCPR _ 1.40 The reported results below are a maximum of the cycle specific and the generic limit for each setpoint.
The RWE OLMCPR values for the 114% and 117% HTSPs are the same as the generic values calculated in Reference C-2 scaled by the change in the Browns Ferry Nuclear Plant Unit 1 Cycle 7 safety limit.
HTSP Reference C-2 Browns Ferry 1 Cycle 7 Without RBM Filter MCPR Limit (based on 1.07 SL) Rated MCPR Limit (based on a 1.09 SL) 107% 1.20 1.32 111% 1.25 1.32 114% 1.30 1.32 117% 1.35 1.38 Filtered setpoints are specified to be lower than unfiltered setpoints due to the additional lag or delay time associated with filtering. The RWE results shown above for the four HTSPs are unblocked for the Cycle 7 specific calculation at 3952 MWth. Thus the results for the filtered signals would remain the same as the lags or delays in the block associated with the filtered signal makes no difference in the results. The RWE results reported above are those calculated at 3952 MWth and they bound the cycle specific calculations performed for Browns Ferry Unit 1 at 3458 MWth.
ARTS Power and Flow Dependent Limits The ARTS power and flow dependent operating limits for all operating flexibility options are provided in Reference C-6.
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 The Reference C-6 MCPRp limits are calculated for a SLMCPR of 1.09. The Reference C-6 Kp limits are based on a PLU Power Level of 50% rated power.
The Reference C-6 MCPRf limits are calculated for a SLMCPR of 1.09.
The Reference C-6 LHGRFACp limits are based on a PLU Power Level of 50% rated power.
The Reference C-6 LHGRFACf limits remain unchanged from Reference C-2.
SLO Pump Seizure Operating Limit The cycle-independent OLMCPR calculated for a recirculation pump seizure event when operating in Single Loop Operation (SLO) is 1.51. When adjusted for the off-rated power/flow conditions for SLO (i.e., Kp), this limit corresponds to a rated power/flow OLMCPR of 1.35, assuming SLO SLMCPR <
1.11.
To ensure that the SLO pump seizure analysis is bounded for the current operating cycle, Browns Ferry 1 Cycle 7, the rated OLMCPR must be set > 1.35 when operating in SLO.
References C-I General Electric Standard Application for Reactor Fuel, GESTAR II, NEDC-240 11-P-A-15, September 2005 and GESTAR H U.S. Supplement, NEDC-2401 1-P-A-15-US, September 2005.
C-2 Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Browns Ferry Nuclear Plant Units 1, 2 and 3, NEDC-32433P, April 1995.
C-3 Browns Ferry Unit 1 Safety Analysis Report for Extended Power Uprate, NEDC-33 101P, Revision 0, June 2004.
C-4 Browns Ferry NuclearPlant Units 1, 2, and 3 Single Loop Operation,NEDO-24236, May 1981.
C-5 Safety Analysis for Browns Ferry Nuclear Plant Units 1, 2 and 3 Turbine Bypass and End-of-Cycle RecirculationPump Trip Out-of-Service, NEDC-32774P, August 1997.
C-6 Tennessee Valley Authority Browns Ferry Unit 1 Off-Rated Limits Validation at a Rated Thermal Power of 3458 MWt, GE-NE-0000-0060-4817-RO, January 2007.
C-7 Safety Analysis for Browns Ferry Nuclear Plant Units 1, 2 and 3 Turbine Bypass and End-of-Cycle Recirculation Pump Trip Out-of-Service Combination Mode Out-of-Service, NEDC-32774P, Supplement 1, February 2001.
C-8 Power Uprate Safety Analysis Report for the Browns Ferry Nuclear Plant Units 2&3, NEDC-32751 P, Revision 0, September 1997.
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 Appendix D Thermal Mechanical Compliance A thermal mechanical compliance check is performed for the fast pressurization transients as well as for the loss-of-feedwater heating event and rod withdrawal error to assure that the fuel can operate without violating the thermal mechanical design limits. These limits are established such that reactor operation within these limits provides assurance that the fuel will not exceed any thermal mechanical design or licensing limits during all modes of operation. All thermal mechanical limits are met for Browns Ferry 1 Cycle 7.
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 Appendix E Variable Frequency Drives (VFD) Application To improve the reliability of the recirculation system, Browns Ferry Unit 1 has replaced the recirculation M/G (Motor/Generator) sets with Variable Frequency Drives (VFD). Operation with VFD was modeled in this reload analysis.
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BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 Appendix F List of Acronyms Acronym Description ACPR Delta Critical Power Ratio Ak Delta k-effective 2RPT Two Recirculation Pump Trip ADS Automatic Depressurization System ADSOOS Automatic Depressurization System Out of Service AOO Anticipated Operational Occurrence APRM Average Power Range Monitor ARTS APRM, Rod Block and Technical Specification Improvement Program BOC Beginning of Cycle BSP Backup Stability Protection Btu British thermal unit BWROG Boiling Water Reactor Owners Group COLR Core Operating Limits Report CPR Critical Power Ratio DIVOM Delta CPR over Initial MCPR vs. Oscillation Magnitude DR Decay Ratio DS/RV Dual Mode Safety/Relief Valve ECCS Emergency Core Cooling System ELLLA Extended Load Line Limit Analysis EOC End of Cycle (including all planned cycle extensions)
EOR End of Rated (All Rods Out 100%Power / 100%Flow / NFWT)
ER Exclusion Region FFWTR Final Feedwater Temperature Reduction FMCPR Final MCPR FOM Figure of Merit FWCF Feedwater Controller Failure FWHOOS Feedwater Heaters Out of Service FWTR Feedwater Temperature Reduction GDC General Design Criterion GESTAR General Electric Standard Application for Reactor Fuel GETAB General Electric Thermal Analysis Basis GSF Generic Shape Function HAL Haling Bum HBB Hard Bottom Bum HBOM Hot Bundle Oscillation Magnitude HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line HPCI High Pressure Coolant Injection ICA Interim Corrective Action Page 193
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 Acronym Description ICF Increased Core Flow IMCPR Initial MCPR IVM Initial Validation Matrix Kf Off-rated flow dependent OLMCPR multiplier Kp Off-rated power dependent OLMCPR multiplier L8 Turbine Trip on high water level (Level 8)
LCF Low Core Flow LHGR Linear Heat Generation Rate LHGRFACf Off-rated flow dependent LHGR multiplier LHGRFACp Off-rated power dependent LHGR multiplier LOCA Loss of Coolant Accident LPRM Local Power Range Monitor LRHBP Load Rejection with Half Bypass LRNBP Load Rejection without Bypass LTR Licensing Topical Report MAPFACf Off-rated flow dependent MAPLHGR multiplier MAPFACp Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPRf Off-rated flow dependent OLMCPR MCPRp Off-rated power dependent OLMCPR MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ MELLLA Plus MOC Middle of Cycle MRB Maximal Region Boundaries MSIV Main Steam Isolation Valve MSIVOOS Main Steam Isolation Valve Out of Service MSR Moisture Separator Reheater MSROOS Moisture Separator Reheater Out of Service MTU Metric Ton Uranium MWd Megawatt day MWd/ST Megawatt days per Standard Ton MWd/MT Megawatt days per Metric Ton MWt Megawatt Thermal NBP No Bypass NCL Natural Circulation Line NFWT Normal Feedwater Temperature NOM Nominal Bum NTR Normal Trip Reference OLMCPR Operating Limit MCPR OOS Out of Service OPRM Oscillation Power Range Monitor Pbypass Reactor power level below which the TSV position and the TCV fast closure scrams are bypassed Pdome Peak Dome Pressure Page 194
BROWNS FERRY 1 0000-0044-1520-SRLR Reload 6 Revision 0 Acronym Description Psi Peak Steam Line Pressure Pv Peak Vessel Pressure PCT Peak Clad Temperature PHE Peak Hot Excess PLHGR Peak Linear Heat Generation Rate PLU Power Load Unbalance PLUOOS Power Load Unbalance Out of Service PRFDS Pressure Regulator Failure Downscale PROOS Pressure Regulator Out of Service Q/A Heat Flux RBM Rod Block Monitor RC Reference Cycle RCF Rated Core Flow RFWT Reduced Feedwater Temperature RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS Recirculation Pump Trip Out of Service RV Relief Valve RVM Reload Validation Matrix RWE Rod Withdrawal Error SC Standard Cycle SL Safety Limit SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation SRLR Supplemental Reload Licensing Report S/RV Safety/Relief Valve SRVOOS Safety/Relief Valve(s) Out of Service SS Steady State SSV Spring Safety Valve STU Short Tons (or Standard Tons) of Uranium TBV Turbine Bypass Valve TBVOOS Turbine Bypass Valves Out of Service TCV Turbine Control Valve TCVOOS Turbine Control Valve Out of Service TCVSC Turbine Control Valve Slow Closure TLO Two Loop Operation TRF Trip Reference Function TSIP Technical Specifications Improvement Program TSV Turbine Stop Valve TSVOOS Turbine Stop Valve Out of Service TT Turbine Trip TTHBP Turbine Trip with Half Bypass TTNBP Turbine Trip without Bypass UB Under Bum Page 195