ML070320406

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0000-0044-1520-SRLR, Revision 0, Supplemental Reload Licensing Report for Browns Ferry, Unit 1, Reload 6 Cycle 7, Figures 40 Through 124
ML070320406
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
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)
v • d • e


Text

BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 100.0 50.0 0.0 0.0 S- Fltow. 300.0 -- Relif Valve Flow s Bypass Valve Flow 200.0 100.0 3.0 6.0 0.0 3.0 Tune (sec) TMae (sec)vel(incr-REF-SEP-SKRT)

'd-sn Steam Flow 1Reatvity-brie Steam Flaw 10 A S xdwater Flow Total R ia y 0 S0.0-10-2.0 3.0 6.0 0.0 3.0 T-me (sec) T~M (sec)Figure 40 Plant Response to Load Rejection w/o Bypass (MOC MELLLA with RPTOOS (HBB))6.0*0 U (4 0.0 6.0 Page 101 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 04-a Neutror FIux(/ 10-Avg Surface IHeat Flux--Core haet Flow i. Core hlet Sui3000Iing a e a a 4J 50.01 0.0 10.0 20.0 Thrm (sec)30.0 0.0 10.0 20.0 30.0 Tffe (sec)150.0-0 10.0 50.0 06 M M M00.0 i-1.0-2.0 20.0 30.0 0.0 10.0 20 Time (sec) Tm-e (sec)Figure 41 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA with RPTOOS (HBB))0.0 0.0 10.0.0 30.0 Page 102 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 3W0.0.0 200.0 100.0 0.0 1 , 0.0 5.0 10.0 15.0 Thm (sec)150.0 100.0 50.0 0.0 I.-0.0 1.0 0.0 0-1.0 5.0 10.0 15.0 Time (sec)0.0-2.0 0.0 5.0 10.0 15.0 Time (sec)0.0 5.0 10.0 15.0 ThIe (mc)Figure 42 Plant Response to FW Controller Failure (EOC MELLLA with RPTOOS (HBB))Page 103 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 0.0 3.0 6.0 0.0 3.0 6.0 THne (sec) Timex (sec)200.0 , 100.0 0.0 1.0 r 0.0 0 9 -1.0-100.0-2.0 0.0 3a0 Time (sec)6.0 0.0 3.0(Se)6.0 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 A n V V a U11 0.0 10.0 20.0 30.0 0.0 10.0 20.0 30.0 Time (sec) Time (sec)150.0 50.0 1.0 4)o 0.0 U S-1.0 0.0 0.0-2.0 10.0 20.0 30.0 Trim (sec)0.0 10.0 20.0 30.0 Time (sec)Figure 44 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with RPTOOS (H1BB))Page 105 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 300.0 100.0 100.0 0.0 a.i 0.0 0.0 5.0 10.0 15.0 TlxE (Se)5.0 10.0 15.0 Trn (sec)150.0 100.0 50.0 sý ýfl 1I PJ 1.0 -l -... -m~y ater Row s Toda Reactvity U Cý -1.0-2.0 10.0 15.0 0.0 5.0 10.Time (sec) Tune (sec)Figure 45 Plant Response to FW Controller Failure (EOC ICF with RPTOOS (UB))0.0 0.0 5.0 0 15.0 Page 106 BROWNS FERRY 1A 0000-0044-1520-SRLR D Aýv a U.1 300.0 200.0 100.0 0.0 0.0 3.0 Time (sec)&0 0.0 ao Thne (Sec)6.0 1.0 S0.0 W -1.0*0 U 100.0o 0.0 I-z0 3.0 6.0 0.0 3.0 Tine (sec) Tmve (sec)Figure 46 Plant Response to Load Rejection w/o Bypass (EOC ICF with RPTOOS (UB))6.0 Page 107 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 2M0.0 150.0 C;100.0 50.0 0.0 125.0 75.0 25.0-25.0 0.0 10.0 0.0 10.0 20.0 Tune (sec)TTmE (sec)150.0-. 100.0 50.0 U C 0 2 0 S U 0.0 10.0 Time (sec)20.0 0.0 10.0 20.0 Time (sec)Figure 47 Plant Response to Inadvertent HPCI /L8 (EOC ICF with RPTOOS (UB))Page 108 BROWNS FERRY I Reload 6 0000-0044-1520-SRLR Revision 0"U 0.0 10.0 20.0 Time (sec)0.0 10.0 20.0 Tune (sec)150.0 O100.0 -50.0 0.0-0.0; ý II 1 1 0.0 0 U S-1.0 10.0 20.0 0.0 10.0 Tfne (sec) Tne (sec)Figure 48 Plant Response to FW Controller Failure (EOC MELLLA with RPTOOS (UB))20.0 Page 109 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 100.0 0.0 I-0.0 200.0 100.0 0 0.0 ae- ..300.0 6 Relief Vlve Flw--- Bypass VaWve Flow V 200.0 100.0 M= 0.0 3.0 6.0 0.0 3.0 TUne (sec) Tnne (see)ýe(incht-REF-SEP-SIKRT)

Widdeatvy;se Steam Flow X*- Reactfty tine Steam Row 1.0 -Sc Reab.'vity xedater Row Total tVity C S00.0-1.0-2.0 3.0 6.0 0.0 3.0 Time (see) Tme (see)Figure 49 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with RPTOOS (UB))6.0 0.0 6.0 Page 110 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0-Dome Press Rise (psi)--*- Safet Valve Raw Ref ValeRow /--- Bpass Valoe Flow* -- PCI Fkow (% FW)125.01 4100.0 50.0 0.0 0 150.0 100.0 50.0"0 75.0 25.01M ; L ...... ..... ..-.L.L..= ,.=,=...=-25.0 1 0.0.0 10.0 20.0 Tne (sec)0 10.0 20.0 T'ffE (sec)1.0 0.0 0 U S-1.0-20 0.0 10.0 20.0 T-ne (ec)0.0 10.0 20.0 Thne (sec)Figure 50 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with RPTOOS (UB))Page 111 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 150.0 010l0.0 50.0 0.0 0.0 150.0 5.0 200.0 iA 0.0 ..-... ,.10.0 15.0 0.0 5.0 T'M (sec) T'U (sec)X-h-REF-SEP-SKRT) -e- Mid React*-- Dqoppler Reacfit-Steam Flow 1.0 -- Scram Reactivity ater Row s Totl Reactivity 0.0 U 04 -1.0-2.0 10.0 15.0 0.0 5.0 T-ne (sec) T-ne (Wc)Figure 51 Plant Response to FW Controller Failure (MOC ICF & FWTR with RPTOOS (HBB))10.0 15.0 50.0 0.0 0.0 5.0 0.0 15.0 Page 112 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 100.0 125.0 ,0 75.0 25.0-*- Dome Press Rise (psi)-*- Safety Vale Row*Relief Valv Raw* Bypass Vave Row-a- I-PCI Fow (% FW)0.0 0.0 10.0 0.0 10.0 Tmie (sec)20.0 Tu-m (sec)150.0 100,0 50.0 U 0 04 2 0.5 U 0.0 100 20.0 TiCe 0.0 10.0 20.0 Time (sec)Figure 52 Plant Response to Inadvertent HPCI /L8 (MOC ICF & FWTR with RPTOOS (HBB))Page 113 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 100.0 50.0 0.0-a- Done Press Rise (psi)Safety Valve Row-& Relief Vave Raw-s- Bypass Valve Raw 300.0 o 200.0 100.0 J 0.0 15.0 0.0 0.0 5.0 10.0 Thme (sec)5.0 10.0 Tine (sec)15.0 150.0 1.0 0.0 0 U 9 -1.0 100.0 50.0 M " a 9--a- Void Reactivity

  • Doppler Reactivity-s- Scram Reactivity

-s- Tc oal Reactivity 0.0 5.0 10.0 15.0 0.0 5.0 TUie (sec) Tune (sec)Figure 53 Plant Response to FW Controller Failure (EOC ICF & FWTR with RPTOOS (HBB))10.0 15.0 Page 114 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 10D.0 50.0 V"0 14 0.0 10.0 20.0 TITe (sec)0.0 10.0 20.0 Thne (sec)U C C 04 2 0 U U--a- Void Reactd*ty Doppler Reactivity

--.0 Scram Reactivty 0.0-1.0-2.0 0.0 10.0 20.0 Time (sec)0.0 10.0 20.0 Thr (sec)Figure 54 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with RPTOOS (HBB))Page 115 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0-- Dome Press Rise (psi)--Safety Valve Flaw Relief Valve Row-Bypass Vave Row 300.0 2DO.100.0 0.0-1 1m *0.0 5.0 10.0 Time (sec)150.0.100.0 15.0 0.0 1.0 0 0.0 U S-1.0 5.0 10.0 Tne (sec)15.0 0.0 t-0.0-2.0 5.0 10.0 15.0 0.0 5.0 Thme (sec) T'ne (sec)Figure 55 Plant Response to FW Controller Failure (MOC MELLLA & FWTR with RPTOOS (HBB))10.0 15.0 Page 116 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 U 0.0 10.0 0.0 10.0 20.0 T'mr (sec)T'me (sec)150.0 100.0 4)50.0 1.0 o 0.0 0 U S-1.0 0.0-z0 0.0 10.0 20.0 Time (sec)0.0 10.0 20.0 TiEm (sec)Figure 56 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA & FWTR with RPTOOS (HBB))Page 117 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0-e- Press Rise (psi)--- Safety Vale FON--- Relief Valve Row-,-Bypass Valve Row 100.0 50.0 0.0 0 150.0 50100.0 50.0.0 5.0 10.0 Tune (sec).200.0 100.0 0.0 15.0 0.0 1.0 00.0 P U 0.0 2.0 15.0 0.0 5.0 10.0 Tume (sec)15.0 0.0 5.0 10.0 Tm~e (sec)5.0 10.0-rum (sec)15.0 Figure 57 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with RPTOOS (HBB))Page 118 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 2M0.0 150.0 X100.0 50.0 0.0 125.0"0 75.0 25.0-25.0 0.0 10.0 20.0 T'm (sec)0.0 10.0 20.0 Tum (sec)150.0 1~X~0 4.'U 0 0 E 0 Q a.'50.0 0.0 10.0 20.0 Time (sec)0.0 10.0 20.0 Time (sec)Figure 58 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with RPTOOS (HBB))Page 119 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 2(0.0 150.0 100.0 50.0 0.0--- Dome Press Rise (psi)-*-Sft 0.0 5.0 150.0 50.0 ilet Raw 3Mo.o A Relief Vave Row ilet Subcoling

-- Bypass Vale RF200.0 100.0 0.0 9_~10.0 15.0 0.0 5.0 Time (sec) ThtE (Sec)nch-REF-SEP-SKRT) -a- Void Reactivity skmm Row-*0 Doppler Rat D Steam Flow 1.0 6--Scran Reaclviy ater Flow s Tota Reactvity 0.0 B1 2 S-1.0-201 10.0 15.0 0.0 5.0 T-re (sec) Tmr (sec)Figure 59 Plant Response to FW Controller Failure (EOC ICF & FWTR with RPTOOS (UB)).I 10.0 15.0 M/0.0 0.0 5.0 10.0 15.0 Page 120 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revisinn 0 200.0 150.0 4 D S100.0 125.0". 75.0 2.25.0-a- Dome Press Rise (psi)-- Safety Valve Raw-s- Relief Valve Raw-%-pass NMl e Ro N HPCI Raw (% FW)0.0 10.0 20.0 Tune (sec)0.0 10.0 Ttme (sec)20.0 150.0 100.0 50.0 4)0 U 0.0 " 0.0 10.0 20.0 Time (sec)0.0 10.0 20.0 Tume (sec)Figure 60 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with RPTOOS (UB))Page 121 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0-*- Dome Press Rise (psi)* Sa..fetyheFolw 0.0 5.0 let Row 300.0 s Relief Vadve Flow t s-- Bypass VaIve Ro.200.0 100.0 0.0 12 10.0 15.0 0.0 5.0 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 CA -1.0-2.0 10.0 15.0 0.0 5.0 Tune (sec) Tume (sec)Figure 61 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with RPTOOS (UB))10.0 w 15.0"0100.0 0.0 5.0 10.0 15.0 Page 122 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 S100.0 125.0"7 75.0 25.0-25.0 0.0 I-0.0 10.0 0.0 10.0 20.0 Thme (Sec)Tme (sec)150.0 1.0.0.0 0 U S-1.0 0.0-20 0.0 10.0 20.0 Tune (Sec)0.0 10.0 20.0 Tune (sec)Figure 62 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with RPTOOS (UB))Page 123 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 150.0 100.0 50.0 0.0 100.0 0.0 0.0 5.0 10.0 15.0 Tihm (sec)0.0 5.0 10.0 15.0 Time (sec)150.0 100.U I -1.0-20 10.0 15.0 0.0 5.0 10.Time (sec) Trme (sec)Figure 63 Plant Response to FW Controller Failure (MOC ICF with TBVOOS (HBB))0.0 5.0 0 15.0 Page 124 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 125.0 , 75.0 25.0 a Dome Press Rise (psi)-x-Safety Wilve FRON ,Relief Valve Flw---Bypass M-ave Row-H tPCI Flow (% FW)0.0 10.0 20.0 TTine (sec)0.0 10.0 T-ne (sec)20.0 150.0"0 100.0-*- Lovel(inch.-REF-SEP-SKRT)

-*- Vessell Steean Raw e.-- Turbine Stearn Fkaw s. Feectwatr Flaw S 4.1 S 0 0..2 0 44 4)50.0 0.0 0.0 10.0 20.0 T-em (sec)0.0 10.0 20.0 Ture (sec)Figure 64 Plant Response to Inadvertent HPCI /L8 (MOC ICF with TBVOOS (HBB))Page 125 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0-E- Dome Press Rise (psi)-*- Saety Valve FRow-* Relief Valve Flow-*- Bypass Valve FRow 300.01 200.0 100.0 0.01 0.0 5.0 10.0 15.0 Trme (sec)0.0 t 0.0 A -.,I 0 5.0 10.0 15.0 Time (sec)150.0 100.0 50.0 2l -')V--Io I I r-ll &M 1.0 ---It- I I r lcpcw lty ater Row s Total Reactivity 00.0 U-1.0-20 10.0 15.0 0.0 5.0 10.Tkm (sec) Tfr (sec)Figure 65 Plant Response to FW Controller Failure (EOC ICF with TBVOOS (HBB))0.0 0.0 5.0 0 15.0 Page 126 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 125.0 1 75.0 0)14*a Dome Press Rise (psi)*)E Safety av~e Raw Reief We Fky#*Byjpass \"vFkm s FPC Flow(% FW 25.01-1. z71~i~ -0.0 i 0.0 10.0 20.0 Tfne (sec)-25.0 -0.0 10.0 20.0 Trne (sec)150.01 V 100.0 50.0 0.0-a Leve(inch-REF-SEP-SKIRT)

  • Vessel Stearn Flow-s- Turbine Stearn Flow e. FeedwAte Flow 1.0 4)o 0.0 C 0 S-1.0-2.0 0.0 10.0 20.0 0.0 10.0 20.0 Tfm (sec)Time (sec)Figure 66 Plant Response to Inadvertent HPCI /L8 (EOC ICF with TBVOOS (HBB))Page 127 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR 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 10.0 15.0 0.0 5.0 10.Tine (sec) Tme (sec)Figure 67 Plant Response to FW Controller Failure (MOC MELLLA with TBVOOS (HBB))0.0 5.0 0 15.0 Page 128 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 50.0 0.0 125.0"0 75.0 25.0-25.0 0.0 10.0 20.0 30.0 irne (sec)0.0 10.0 20.0 T'fne (sec)150.0-' 100.0 U-1.0-2.0 20.0 30.0 0.0 10.0 20.Tm-e (W*C) T'un (WC)Figure 68 Plant Response to Inadvertent HPCI /L8 ( MOC MELLLA with TBVOOS (11111))0.0 0.0 10.0.0 30.0 Page 129 BROWNS FERRY 1 Rf'1In~d A 0000-0044-1520-SRLR R AiAinn n Reload A-*- Dome Press Rise (psi)-*- Safety Vade Flow*Relief Valve Fo*@-B-pBss Valve Flow 300.0 200.0 100.0 NN -_0.0 5.0 10.0 15.0 Trun (sec)0.0 5.0 10.0 15.0 Tine (sec)*0 U U 9 -1.0-2.0 10.0 15.0 0.0 5.0 10.Tfre (Sec) T'mn (sec)Figure 69 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS (HBB))0.0 5.0 0 15.0 Page 130 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 2M0.0 125.0* 75.0 04 25.0-25.0 0.0 10.0 20.0 30.0 Tme (Sec)0.0 10.0 20.0 T'me (sec)150.0 100.0 50.0 1.0 o 0.0 U I -1.0 0.0-2.0 0.0 10.0 20.0 Time (sec)30.0 0.0 10.0 20.0 T-re (see)30.0 Figure 70 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with TBVOOS (HBB))Page 131 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 150.0 100.0 50.0 0.0 300.0"O 20O.0 100.0-*- Dome Press Rise (psi)-*- Safety Valve Flow* Relief Valve Faw-- Bypass Valve Row aah 0.0 0.0 5.0 10.0 15.0 Tume (sec)5.0 10.0 15.0 Time (sec)150.0 100.0 50.0 S0.0-1.0-2.0 10.0 15.0 0.0 5.0 10.'Time (sec) Time (sec)Figure 71 Plant Response to FW Controller Failure (EOC ICF with TBVOOS (UB))0.0 5.0 0 15.0 Page 132 BROWNS FERRY 1 PInnf A 0000-0044-1520-SRLR v .~A;~ n I --125.0" 75.0 25.0-25.0-*- Dome Press Rise (psi)-*- Safety Valve Flow Relief Velve Row Bypass Valve Row-- HCI Fow (% FW)0.0 10.0 20.0 TTfE (sec)0.0 10.0 20.0 T'Mx (Sec)150.01--- Leve(inch-REF-SEP-SKRT)

-*- Vessel Steam Row-,-- Turbine Steam Flow Feedwater Flow 50.0 U 0 E 0 U U A 0.0 10.0 20.0 Timn (sec)0.0 10.0 20.0 TUmi (Sec)Figure 72 Plant Response to Inadvertent HPCI /L8 (EOC ICF with TBVOOS (UB))Page 133 BROWNS FERRY I Reload 6 0000-0044-1520-SRLR Revision 0 300.0" 200.0 100.0 0.0 0.0 !-0.0 5.0 10.0 15.0 Time (sec)0.0 5.0 10.0 15.0 Time (Sec)100.0 50.0 0.0 0..5 U M -1.0-2.01 10.0 15.0 0.0 5.0 10.Time (see) TuE (see)Figure 73 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS (UB))0.0 0.0 5.0 0 15.0 Page 134 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 i 125.0* 75.0-a-- Dome Press Rise (psi)-- SafetyValve Row---Relief Valve Flowv---- Bypass MVa Row-+--FCI Flow (% FV)25.01-25.0 L-0.0 0.0 10.0 Tmne (sec)10.0 Time (Sec)20.0 150.01 50.0 0.0.--- Level(inch-REF-SEP-SKRT)

-*- Vessel Steam Flow* Tuztne Stean Flow Feedwater Flow 1.0 0.0* -1.0-2.0 0.0 10.0 20.0 0.0 Time (sec)10.0 20.0(sec)Figure 74 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with TBVOOS (UB))Page 135 BROWNS FERRY 1 D I ~~A A;0000-0044-1520-SRLR D-ý A V D VJLI 200.0 150.0 100.0-a- Dome Press Rise (psi)-.-- Safety Valve Raw-,- Relief Valve Flow s, Bypass Valve Flow 300,0 M 2O0.0 100.0 0.0 0.0 p -p 0.0 5.0 10.0 Time (sec)15.0 0.0 5.0 10.0 15.0 Time (sec)150.0 100.0 50.0 1.0 0.0-1.0 0.0-20 0.0 5.0 10.0 15.0 0.0 5.0 Time (sc) Trim (sWc)Figure 75 Plant Response to FW Controller Failure (MOC ICF & FWTR with TBVOOS (HBB))10.0 15.0 Page 136 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 125.0.O 75.0 25.0-25.0--a Dome Press Rise (psi)-x- Safety Valve Row Relief \Vve Row Bypass Vale Flow HP-. I Fcow (% FW)0.0 10.0 20.0 Thne (sec)0.0 10.0 20.0 Trme (sec)150.0t 100.0 50.0-*- Level(inch-REF-SEP-SKRT)

-*-- Vessel Steam Row ,& Turbine Stean Flow-.-- Feedwater Flow U 0 0.0 1-0.0 10.0 20.0 0.0 10.0 20.0 TifE (sec)Tlie (Sec)Figure 76 Plant Response to Inadvertent HPCI /L8 (MOC ICF & FWTR with TBVOOS (HBB))Page 137 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 V 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0'I"- (sec)T'm- (sec)150.0 100,0 50.0 U C 2 0 U Cs U 0.0 L-0.0 5.0 10.0 15.0 0.0 Time (see)5.0 10.0 Tmre (sc)15.0 Figure 77 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS (HBB))Page 138 BROWNS FERRY I Reload 6 0000-0044-1520-SRLR Revision 0 125.01 150.0 S100.0 50.0 75.01-a- Dome Press Rise (psi)-*- Safety Valve ow Relief sVave Raw--*-- Byp~ass Vave Flow s+ I-PCI Flow (% FW)25.0 I 0.0 -0.0-25.0 10.0 20.0 Time (sec)0.0 i10o 20.0 Tin- (Sec)150.0 V 100.0 50.0 1.0 o 0.0-S-1.0 0.0-2.0 0.0 10.0 20.0 TffnE (sec)0.0 10.0 20.0 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 D- ; Aý U" I a M-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)150.0 100~.0 U 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 D , ; ; n V~~at flSVIOaJfUl 200.0 150.0 50.0 0.0 125.0.0 75.0 25.0-a-- Dome Press Rise (psi)--- Safety Vah Raw-- Relief Vae Flow-4-- Bypass VMae Row-.- I-PCI Fkw (% FW).4-25.0 L-0.0 0.0 10.0 20.0 Tine (sec)10.0 20.0 Tirm (sec)150.0 50.0 1.0 o 0.0-1.0-2.0 0.0 10.0 20.0 Time (sec)0.0 10.0 20.0 ThME (sec)Figure 80 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA & FWTR with TBVOOS (HBB))Page 141 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 2M.0 150.0"w09100.0-50.0 0.0 0.0 150.0 100.0 50.0 5.0 200.0 100.0 0.06 10.0 15.0 0.0 5.0 Tihn (sec) Time (sec),ic.t-REF-SEP-SKRT)

-- Void Reactity Steam, Re'; x Doppler Reactity SStearn Flow 1.0 .- Scram Reacb*ater Flow s Total Reacivity 4, 0 0.0 U 1 -1.0-20 10.0 15.0 0.0 5.0 Time (sec) Time (sec)Figure 81 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS (HBB))10.0 15.0 0.0 0.0 5.0 10.0 15,0 Page 142 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 0.0 10.0 20.0 0.0 10.0 20.0 Time (sec) Tune (sec)150.0 100.0 ,50.0*n Leve(incht-RFF-SEP-SKRT)

-*- Vessel Stearn Raow--Turbine Stearn Flow--Feedwater Raw 2 0 L)U.U ~W 0.0 10.0 Turm (Sec)20.0 0.0 10.0 20.0 Tume (Sec)Figure 82 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS (HBB))Page 143 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 U 4 100.0 -50.0 0.0 0.0 150.0 5100.0 50.0--a Dome Press Rise (psi)-x-Safety Valve Flow Relief Valve Row-s- Bypass Valve Row 5.0~200.0'V 100.0 0.0 10.0 15.0 0.0 5.0 Tin-M (sec) Tint (sec)nch-REF-SEP-SKRT) -a- Void Reactivity

..- ROW. %-- Doppler Reactivity Steam Flow 1.0 -a- Scram Reactivity ater Row -Total Reactivity 0.0-1.0.... --- -20 10.0 15.0 0.0 5.0 Tine (sec) T-um (sc)Figure 83 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS (UB)).-2----10.0 15.0 0.0 0.0 5.0 10.0 15.0 Page 144 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 150.0 100.0 50.0--Domne Press Rise (psi)'6 RelifVeFow 125.0 1"0 75.01 25.0-25.0 0.0 L-0.0 10.0 0.0 10.0 TinE (Sec)20.0 Trme (sec)150.0 0100.0--- Level(inch-REF-SEP-SKRT)

-*-- Vessel Steam low-t-- Turbine Steam Flow-- Feedwater Raw ova 1.0 o 0.0 0 U-1.0 0.0-20 0.0 10.0 20.0 0.0 Time (sec)10.0 20.0 Tnme (sec)Figure 84 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with TBVOOS (UB))Page 145 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 100.0 50.0 0.0-Neutr 6--- Core k-- Core Ir FL ux/l10 face Heat FluxD 2 0.0 5.0 150.0 Rw300.0 -a-.- m'oule vaive t-lOW--- Bypass Vave Ra 20 0.0 100.0 0.0 10.0 15.0 0.0 5.0 Tnm (sec) T'i (sec)nch-REF-SEP-SKRT) -a- Void Reactivity Slew-R- Doppler Reactivty a Stean Flow 1.0 -Scram Reactmty#merRow -o- Tota Reactivity

-20 10,0 15.0 0.0 5.0 Tfme (Sec) Tme (eeC)Figure 85 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS (UB))10.0 15.0 100.0 04 50.0 0.0 10.0 15.0 Page 146 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 S100.0 50.0 0.0 V)0.0 10.0 20.0 Tfmt (sec)0.0 10.0 20.0 Tuml (see)150.0 100.0 50.0 1.0 o 0.0 U-1.0-2.0 0.0 10.0 Titm (see)20.0 0.0 10.0 20.0 Time (sec)Figure 86 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS (UB))Page 147 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 0.0 ZAJ.U 100.00.0 T67 3.0 6.0 0.0 3.0 Time (sec) Tmlie (sec)d(inch-REF-SEP-SKRT)

-d React L~ Steam RawR %trbine Stear Flow 1.0 KsSteam Flow 0.0-'- 1% -1.0 1 -20 3.0 6.0 0.0 3.0 Trme (sec) T'me (sec)Figure 87 Plant Response to Load Rejection w/o Bypass (MOC ICF with PLUOOS & RPTOOS (HBB))6.0-100.0, 0.0 6.0 Page 148 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 150.0 4100.0* -Nairon Rux / 10-* A/g Srfaew Heat Flux-si Core We Raw--"k 0.0 100.0 R 0.0 fm 3.0 6.0 0.0 3.0 Tmue (sec) (sec)e(inch-REF-SEP-SKRT)

-.- Reacty ksd Steam Roaw avity bineSteam Rawo 1.0 ranR ty dw-ate FlAN R 0o.0 A -1.0-2.0 3.0 6.0 0.0 3.0 Tfe (sec) Tune (sec)Figure 88 Plant Response to Load Rejection w/o Bypass (EOC ICF with PLUOOS & RPTOOS (HBB))6.0 U-100.0 1-0.0 6.0 Page 149 BROWNS FERRY I Reload 6 0000-0044-1520-SRLR Revision 0 300.0 100.0-4 o.0 --0.0 3.0 6,0 0.0 3.0 Tme (sec) Tlie (sec)6.0 200.0 V. 100.0 0.0 1.0 0.0 1-1.0I 100.0-J -20 ý-6.0 0.0 0.0 3.0 Time (sec)3.0 Y'm-w (se)6.0 Figure 89 Plant Response to Load Rejection w/o Bypass (MOC MELLLA with PLUOOS & RPTOOS (HBB))Page 150 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 300.0"O200.0-a- Dome Press Rise (psi)-- Safety Valve Raw 6Relief Valve Fkow-*Bypass Valve Row 100.0 1 J 0.01 6.0 0.0.W A 8 W 0.0 3.0 Tmie (sec)3.0 Time (sec)6.0 200.0 100.0 1.0 0.0 U S-1.0 4)0.0-100.0-z0 0.0 3.0 6.0 0.0 3.0 Time (sec) Tume (sec)Figure 90 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with PLUOOS & RPTOOS (HBB))6.0 Page 151 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 2M.0 150.0 100.0 0.0 3.0 6.0 0.0 3.0 Thxe (sec) Tune (see)6.0 1.0 0.0 0 -1.0-20 0.0 3.0 Tune (sec)6.0 0.0 3.0 Time (sec)6.0 Figure 91 Plant Response to Load Rejection w/o Bypass (EOC ICF with PLUOOS & RPTOOS (UB))Page 152 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 2030.0 150.0 4 100.0 50.0 0.0 0.0 3.0 6.0 0.0 3.0 ThmE (sec) Tnme (sec)6.0"U C U S 0 U U 0.0 3.0 6.0 0.0 3.0 Tm~e (sec) T'nm (sec)6.0 Figure 92 Plant Response to Load Rejection w/o Bypass (EOC MELLLA with PLUOOS & RPTOOS (UB))Page 153 BROWNS FERRY 1 RdAIA- A 0000-0044-1520-SRLR D ;ýv o w" 200.0 0.0 200.0 V 100.0 0.0 We aie F .... 300.0 eFIlow-Bypass Vdve Flow , 00.0 100.0 3.0 6.0 0.0 3.0 Tilne (sec) Tfne (sec)9MQnch-REF-SEP-SKRT) bssel Steam Flow n-urbine Steam Flow 1.0"eswater Flow -Reivitv " C S0.0-1.0-2.0 3.0 6.0 0.0 3.0 Tune (Sec) Tne (sec)Figure 93 Plant Response to Load Rejection w/o Bypass (MOC ICF & FWTR with PLUOOS & RPTOOS (IBB))6.0-100.0 0.0 6.0 Page 154 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 13100.0 50.0 0.0-a- Dome Press Rise (psi)--*- Safety Valve Flow Relief Valve Flow s Bypass Vave Flaw 100.0 I/0.0 L-0.0 0.0 3.0 Mmne (sec)6.0 3.0 6.0 TyEm (sec)6, C U C 0 04 2 0 Cs 4)0.0 3.0 Time (sec)6.0 0.0&0 6.0 TynE (sec)Figure 94 Plant Response to Load Rejection w/o Bypass (EOC ICF & FWTR with PLUOOS & RPTOOS (HBB))Page 155 BROWNS FERRY I Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 100.0 50.0 0.0"AU.U 100.0 0.0 -6.0 0.0 0.0 3.0 Tnre (sec)3.0 Tome (sec)6.0"0 0 U 0.0 3.0 6.0 0.0 3.0 Tume (sec) Tfne (sec)6.0 Figure 95 Plant Response to Load Rejection w/o Bypass (MOC MELLLA & FWTR with PLUOOS & RPTOOS (HBB))Page 156 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 -150.0 100.0 -50.0 0.0 0.0 200.0 100.0 0.0 100.0 0.0 3.0 6.0 0.0 3.0 T'mE (sec) T-uE (sec)i-- Lev(incWREF-SEP-SKRT) a--- V\Id\- Vsse Steam Flow X* -Turbine Steam Raw 1.0 SFeedvvater RON T S-.00 0 0 U i -1.04 3.0 6.0 0.0 3.0 Time (sec) T'Me (seC)Figure 96 Plant Response to Load Rejection w/o Bypass (EOC MELLLA & FWTR with PLUOOS & RPTOOS (HBB))6.0-100.0 0.0 6.0 Page 157 BROWNS FERRY 1 PA1naA A 0000-0044-1520-SRLR P-. p,1n, 200.0 150.0 l00.0 50.0 0.0 0.0*0O.0.0 U 3.0 6.0 0.0 ao Time (sec) Tfne (sec)F(igch-REF-SEP-SlaTn -a- d RLacn B (EO Stearn Flow P O ROty tine Steam Flow 1.0 ram ty xkwater Flow 40 U v~ 6 100-20 3.0 ~ ~ 6. 1 .030 Tune (sec) TffMe (Sec)Figure 97 Plant Response to Load Rejection w/o Bypass (EOC ICF & FWTR with PLUOOS & RPTOOS (UB))6.0 0.0 6.0 Page 158 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 0.0 200.0 100.0 0.0-100.0 L 0.0.200.0 100.0 3.0 6.0 0.0 3.0 TiMn (sec) Time (sec)-LeveI(inch-REF-SEP-SKRT) a-- d Reactivi-Vessel Stean Row --- Reacivity-Ttrbine Steam Row 1.0 ramn Reacity-Feedwater Flow -l Reacti 0.0-1.0-20 3.0 6.0 0.0 3.0 Tune (sec) T-rm (sec)Figure 98 Plant Response to Load Rejection w/o Bypass (EOC MELLLA & FWTR with PLUOOS & RPTOOS (UB))6.0 6.0 Page 159 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 2M0.0 100.0.DO.100.0 0.0 0.0 10.0 Tmfe (sec)15.0 0.0 5.0 10.0 15.0 Tmie (sec)150.0 100.0 50.0 Xt I I rpu 1. 'Ju cmi I I rxoouvfty ate RoFw --o-- Reactiv*ty 0.0 .-04 S-1.0-2.0 10.0 15.0 0.0 5.0 10.(sec) Trne (sec)Figure 99 Plant Response to FW Controller Failure (MOC ICF with TBVOOS & RPTOOS (HBB))0.0 0.0 5.0 0 15.0 Page 160 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 125.0--- Dome Press Rise (psi)-x-- Safety Valve FRow a- Relief Vaive Row-*-- Bypass VWve Fow-s-- I-PCI Fkow (% FW)"U 75.0 25.0---7ýr"T1777-.,;

--ý --: -. --ý -ý M=-=-- A "" 0.0 10.0 ThEl (ScC)0.0 10.0 T'ic (see)20.0 150.0.U10.E3- Levd(inch.-REF-SEP-SKRT) x* VAessel Stearn Row-s- Turbine Stearn Flow s.- Feedwater Raow E 0 0.0-A-0.0 10.0 Tffnm (sec)20.0 0.0 10.0 20.0 Tnne (sec)Figure 100 Plant Response to Inadvertent HPCI /L8 (MOC ICF with TBVOOS & RPTOOS (HBB))Page 161 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0--- Dome Press Rise (psi)-- Saf Mave R-l ARelif Vve Roaw-*- Bypass V\3e Row 150.0 V 100.0 50.0 0.0 20.U.U 6 1 S 1MA : +/-0.0 5.0 100 15.0 Tfme (sec)0.0 5.0 10.0 15.0 Time (sec)150.0 50.0 0.0 -0.0 Fiezir m113 -ow .1.0 our-cTirr mky-tiv/ly vater Row -- Toal Reactivity 0.0 9 -1.0-2.0 10.0 15.0 0.0 5.0 10,0 TiEm (Sec) Time (see)Figure 101 Plant Response to FW Controller Failure (EOC ICF with TBVOOS & RPTOOS (HBB))5.0 15.0 Page 162 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 100.0 50.0 0.0 125.0-O 75.0 25.0-25.0-a- Dome Press Rise (psi)-*- Safety Vahe Flow Relief Valve Raw Bypass \vae Flow--- -PCI Flow (% FW)0.0 10.0 0.0 10.0 20.0 Time (sec)T-E (sec)150.0 010.0 50.0'4 C U C C C..2 0 U (S U 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 Reload 6 0000-0044-1520-SRLR Revision 0 100.0-a- Dome Press Rise (psi)-*- Safety Valve RFow 6Relief Valve Flow---Bypass Valve Raw^^ q 0.0 5.0 10.0 15.0 T'tme (sec)0.0 a-0.0 10.0 Tmre (sec)15.0 150.0 50.0 C oa 0.U g -1.0-20 0 10.0 15.0 0.0 5.0 10.0 Trim (se) Tm-e (se)Figure 103 Plant Response to FW Controller Failure (MOC MELLLA with TBVOOS & RPTOOS (HBB))0.0 0.0 5.15.0 Page 164 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 i 125.01-a-- Dome Press Rise (psi)-*- Safety Vave RFow 6 Relief Malv Row-*---Bypass Valv Raw-- I-PCI FRON (% FW)IU ci 75.0 25.0-25.0 0.0 10.0 20.0 Time (8m)0.0 10.0 Time (see)20.0 0 U 0.0 10.0 20.0 Time (sec)0.0 10.0 20.0 Time (Sec)Figure 104 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA with TBVOOS & RPTOOS (HBB))Page 165 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 ino 10 100.0 50.0 0.0 U 0.0 5.0 10.0 15.0 Tm-xe (sec)0.0 5.0 10.0 15.0 TiTf le (see)150.0 100.0 50.0 U 0.0 t 0 U 9 -1.0-Z0 10.0 15.0 0.0 5.0 10.0 TumE (sec) Thme (see)Figure 105 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS & RPTOOS (HBB))0.0 5.0 15.0 Page 166 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 20D.0 150.0 V 4 100.0 50.0 0.0 0.0 10.0 0.0 10.0 20.0 T'mn (sec)Time (sec)150.0 50.0t 0.0 10.0 20.0 Tume (ec)0.0 10.0 20.0 TmTe (sec)Figure 106 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with TBVOOS & RPTOOS (HBB))Page 167 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 100.0 50.0--- Dome Press Rise (psi)* Safety Valve Flo SRelief Vave RoN-s-Bypass Valve Flow O 200.0 100.0 0.0 -0.0 0.0 0.0 5.0 10.0 15.0 Time (sec)5.0 10.0 15.0 Tune (Sec)150.0 100.0 pm't=I I rKuW 1. -, %.lic I I I~uNC Iwy oater Row s Totl Reactivity S0.0-1.0-20 10.0 15.0 0.0 5.0 10.0 Trun (8ec) T-m- (ec)Figure 107 Plant Response to FW Controller Failure (EOC ICF with TBVOOS & RPTOOS (UB))0.0 0.0 5.0 15.0 Page 168 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0--- Dome Press Rise (psi) \-*- Safety Vahe Flow*- Relief Valve Flow-- Byps ive Row F a I-PCI Row (% FW)125.0 75.0 1003.0 25.0 1 0.0 10.0 20.0 Tmie (sec)0.0 10.0 Thme (sec)20.0 150.0.100.0 50.0 0.0 9 LevI_ (inch-REF-SEP-SKRT)

  • Vessel Stearn Row s Tutrine Stean Flow s Feedwater Flow 1.0 U 0 o* 01.0-2.0-0.0 0.0 10.0 20.0 10.0 20.0 Time (sec)Tin (Sec)Figure 108 Plant Response to Inadvertent HPCI /L8 (EOC ICF with TBVOOS & RPTOOS (UB))Page 169 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 , 100.0 50.0* 200.0 100.0 0.0 L-0.0 0.0 5.0 10.0 15.0 Tffe (sec)0.0 5.0 10.0 15.0 T'ime (sec)150.0 100.0 50.0 C I I 1.0 --A ,. , , -vy r" Flow- Tota Reactivity

-1.0-2.10.0 15.0 0.0 5.0 10.0 Tune (Sec) Time (sec)Figure 109 Plant Response to FW Controller Failure (EOC MELLLA with TBVOOS & RPTOOS (UB))0.0 0.0 5.0 15.0 Page 170 BROWNS FERRY I Reload 6 0000-0044-1520-SRLR Revision 0 2(f0.0 200.0 50.0 0.0 125.0 1 75.O 25.0-25.0 0.0 10.0 20.0 TfTme (sec)0.0 10.0 20.0 Tnie (sec)U C C 2 0 U 0.0 10.0 TInEm (sec)20.0 0.0 10.0 rinm (sec)20.0 Figure 110 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA with TBVOOS & RPTOOS (UB))Page 171 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 15.0 Time (sec)(sec)150.0 100.0 50.0£4 U C 0 0 C-)ci U 0.0 5.0 10.0 Time (sec)15.0 0.0 5.0 10.0 Tume (sec)15.0 Figure 111 Plant Response to FW Controller Failure (MOC ICF & FWTR with TBVOOS & RPTOOS (HBB))Page 172 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 100.0 0.0 10.0 0.0 10.0 Mme (sec)20.0-rim (sec)150.0 50.0 4)0 0.2 C 44 4)0.0 10.0 20.0 Tffe (sec)0.0 10.0 20.0 Tune (8m)Figure 112 Plant Response to Inadvertent HPCI /L8 (MOC ICF & FWTR with TBVOOS & RPTOOS (HBB))Page 173 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 100.0 0.0 0.0 150.0 100.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 TnrE (sec) Time (sec),v(inch-REF-SEP-SKRT) -e- Vid Reactvity--RA-*- Doppler Rectivity biýne Steam Flow 1.0 Scram Reactvity edwater Flow s.- Total Reacbvity U 01.0-1.0-201 5.0 10.0 15.0 0.0 5.0 10.0 TnnE (sWc) Tune (Wec)Figure 113 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS & RPTOOS (HBB))15.0 100.0 50.0 0.0 15.0 Page 174 BROWNS FERRY I Reload 6 0000-0044-1520-SRLR Revision 0 125.0 [100.* 75.0 25.0-a-- Dome Press Rise (psi)-x-- Safety alve Raow Relief Valve Flow--- Bypass Valve Faw-- l-PCI Flow (% FW)-25.0 L-0.0 0.0 10.0 20.0 Tune (sec)10.0 Tff w (sec)20.0 150.01 100.0* Leve(inch-REF-SEP-SKRT)

-*-- Vessel Stean Flow* Turbine Stearn Flow s-- Feedwater Flow 1.0 o 0.0 U-1.0 Jul 0.0-2.0 0.0 10.0 20.0 0.0 Tife (sec)10.0 20.0 Time (sec)Figure 114 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with TBVOOS & RPTOOS (HBB))Page 175 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 0.0 0.0 5.0 10.0 Tine (sec)300.0 2DO.100.0 0.0 -15.0 0.0 1.0 0.0 U 1 -1.0 15.0 0.0 5.0 10.0 Time (sec)15.0 0.0 5.0 10.0 Thfm (sec)5.0 10.0 ThmE (see)15.0 Figure 115 Plant Response to FW Controller Failure (MOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB))Page 176 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 125.0 1 SDome Press Rise (psi)---Safety Valve Flow Relief Valve Row Bypass Valve Row s, I-PCI Flow (% FVV)75.0 25.01 I--25.0 I-0.0 0.0 10.0 20.0 Tnne (sec)10.0 20.0 TMe (Sec)150.0-*-- Levd(inch-REF-SEP-SKRT)

-*-- Vessel Stean Row-s- Tudbine Steam Flw s- Feedwater Flow 1.0 o 0.0.1.0 50.0 0.0 MI-20 0O.10.0 T-imr (sec)20.0 0.0 10.0 Tine (sec)20.0 Figure 116 Plant Response to Inadvertent HPCI /L8 (MOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB))Page 177 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 4100.0 200.-a-- Dome Press Rise (psi)-*- Safety Valve Row SRelief Vale Raw Bypass Valve Roaw-3..... 0... .100.0 0.0 1 0.0 5.0 10.0 15.0 U.0 QU 0.0 5.0 10.0 Trm (sec)15.0 TimE (sec)150.0 100.0 50.0 1.0 0.0 c -1.0 0.0-20 0.0 5.0 10.0 Time (sec)15.0 0.0 5.0 10.0 TUie (sec)15.0 Figure 117 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB))Page 178 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0100.0o 50.0 0.0 0.0 150.0 510.0 50.0 10.0 20.0 T'r e (sec)125.0 75.0 25.0-25.0-30.0 0.0 1.0 o 0.0 U U-1.0-2.0 30.0 0.0 10.0 20.0 TMIe (see)30.0 0.0 0.0 10.0 20.0 Tiffe (sec)10.0 20.0 Time (sec)30.0 Figure 118 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS & RPTOOS (HBB))Page 179 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 100.0 50.0 0.0-*- Dome Press Rise (psi)-Safety Vave Fow Relie Vave Flow--Bypass Valve Flow 0.0 150.0 200.0 100.0 0.0 5.0 10.0 15.0 0.0 5.0 10.(T-ue (sec) Trne (sec)eI(inch-REF-SEP-SKRT) a Void Reactivity

--- Doppler Reactivity oineý Stee- Flow 1.0 Scram Reactivity dwater Row s-- Total Reactivity 5.0 .0 15 0.0 E1 t 0 U S-1.0 5.0 10.0 15.0 0.0 5.0 10.0 T-nr (sec) TrmE (sec)Figure 119 Plant Response to FW Controller Failure (EOC ICF & FWTR with TBVOOS & RPTOOS (UB))I 0 15.0 100.0 0.0 15.0 Page 180 BROWNS FERRY I Reload 6 0000-0044-1520-SRLR Revision 0 I 125.0 1-100.0 50.0 0.0 0 150.0 100.0 75.0 Dome Press Rise (psi)Safety ale Roaw-s Reliefl Vave Flow Bypass Vave Flow--.- H-CIFkwv (% FW)25.01-25.01-0.0 1.0 10.0 20.0 Trne (sec)10.0 TifE (sec)20.0--- Le&e(inch-REF-SEP-SKRT)

-*-- Vessel Steam Row-*- Turbine Steae Flow-o- Feectvater Flow 3.-8 2zz 1.0 o 0.0-1.0 0.0-20 0.0 10.0 20.0 0.0 Time (see)10.0 20.0 Tme (sec)Figure 120 Plant Response to Inadvertent HPCI /L8 (EOC ICF & FWTR with TBVOOS & RPTOOS (UB))Page 181 BROWNS FERRY I Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0-a- Dome Press Rise (psi)--*-- Safety Valve Flow-- Relief aveRow* Bylpass VWive Row 300.0* 200.0 100.0 50.0 0.0 0.0 : 0.0 5.0 10.0 Time (sec)15.0 0.0 5.0 10.0 Tmue (Sec)0 4.)0 0 0 U (4 4.)15.0 1 15.0 0.0 5.0 10.0 15.0 0.0 5.0 10.0 TIITm (sec)Tum (sec)Figure 121 Plant Response to FW Controller Failure (EOC MELLLA & FWTR with TBVOOS & RPTOOS (UB))Page 182 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 100.0 125.0 ,. 75.0 25.0-25.0 0.0 10.0 Tlie (sec)0.0 10.0 20.0 Time (sec)150.0 1.0 o 0.0 U-1.0 50.0 0.0-20 0.0 10.0 20.0 Time (Sec)0.0 10.0 20.0 Time (sec)Figure 122 Plant Response to Inadvertent HPCI /L8 (EOC MELLLA & FWTR with TBVOOS & RPTOOS (UB))Page 183 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 200.0 150.0 100.0 50.0 0.0 8.0.0 4.0 Time (sec)300.0 V 20O.0 100.0 0.0 -4 0 0.0 1.0 S0.0 0 2-1.0 4.0 8.0 Tine (sec)200.0 100.0 0.0-a-. LeveI(inch-REF-SEP-SKRT)

--- Vessel Stean Flow-.a Turbine Stearn Row-..-- Feedwater Flow 1UU.U I 0.0 4.0 Tffe (sec)8.0 0.0 4.0 T'f-M (sec)8.0 Figure 123 Plant Response to MSIV Closure (Flux Scram) -ICF (HBB)Page 184 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR Revision 0 0.0 4.0 Tune (see)200.0 100.0 430.0 -8&0 0.0 1.0 S0.0-1.0-20 8.0 0.0 4.0 Tune (sec)V 100.0 4-0.0-100.O0 0.0 4.0 Tine (sec)4.0 Time (sec)8,0 Figure 124 Plant Response to MSIV Closure (Flux Scram) -MELLLA (HBB)Page 185 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR 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 14 licensing analysis 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 14 The 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.Page 186 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.Page 187 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.Page 188 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR 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.Page 189 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR 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.Page 189 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 Nuclear Plant 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 Recirculation Pump 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.Page 190 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.Page 191 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR 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.Page 192 BROWNS FERRY 1 Reload 6 0000-0044-1520-SRLR 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 Reload 6 0000-0044-1520-SRLR 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 Reload 6 0000-0044-1520-SRLR 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

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