ML21361A227
ML21361A227 | |
Person / Time | |
---|---|
Site: | Perry ![]() |
Issue date: | 12/20/2021 |
From: | Energy Harbor Nuclear Corp |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML21361A235 | List:
|
References | |
L-21-287 | |
Download: ML21361A227 (149) | |
Text
{{#Wiki_filter:Q £ c UJ 40 20 100 120 CORE FLOW {% RATED) (Rev. 12 1/03) PERRY NUCLEAR POWER PLANT Typical Design Power/Flow Map Standard Power/ Flow Region Figure 15.0-1
100 f E = (J uJ tr (r (J v, SCRAM WORTH AT 100% = -$37.05 0.43 0 . 93 r.43 t.93 2,43 2.93 3.43 T I M E( S E C . ) S C R A MI N S E R T I O N (Rev. L2 1/03) r'D<\ \ CffiM PERRYNUCLEAR POWERPLANT I \)a/ ,
- {_H Scram Reactivity Characteristics
( REDY) Figure 15.0-2
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tv/l S cram Ti -me C haracteri sti cs Figure 15.0-3
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LJ ct nl (Rev. t2 1/03) t / Y \ I ffi PERRYNUcLEARPoWERPLANT Loss of 100'F Feedwater Heating, A utomati -c FJow C ontro l Fj-gure 15.1-1
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Lu tn tll rF (Rev. L2 1/03) iffiil\ PERRYNUCLEARPOWERPLANT I \-Yl I Loss of 100oF Feedwater Heating, Manual Fl ow C ontrol Figure 15.1-2
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^6a 1fffi\ PERRYNUCLEARPOWERPLANT Feedwater Controll-er Failuret Maximum Demand, With HWL TriPs Figure 15.1-3
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-,on ffib PERRY NUcLEAR PoWERPLANT Loss of C ondenser l facuum at z Inches Per Second Figure tS.Z-j
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@ PERRYNUCLEARPOWERPLANT L o ss o f A u x i l i a r y Power Transformer Figure 15,2-B
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\JOU Loss of AII Grid Connections Figure 15.2-9
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CONTAINMENT (tr"*"'bPERRYNUCLEARPOWERPLANT I / X \ I l\s--4.{
\ryJ RHR Loop C Figure t5.2-I4 (Sheet L of 2)
S/R VALVE CONTAINMENT REACTOF VESSEL
,-rOrr &ffi PERRY NUcLEAR PowERPLANT x--
LPCS Figure l-5.2-14 (Sheet 2 of 2)
GLOB E VALVE EMERGENCY SERVICEWATER EMERGENCY TO SERVICE D IS C H AR GTU E NNEL W A T E RS Y S T E M HEAT EXCHANGER (R e v . t2 1/03) r-:Or^. df'il$bPERRY NUcLEAR PowERPLANr
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RHRLooP B (SuPPression PooI Cooling Mode) Figure 15.2-15 (Sheet 1 of 21
GLOB E VALVE EMERGENCY S E R V I C EW A T E R EMERGENCY TO SERVICE D I S C H A R G ET U N N E L W A T E RS Y S T E M HEAT EXCHANGER (Rev. 12 1/03) trffi PERRY NUCLEAR POWER PLANT RHRLoop A (Suppression PooI Cooling Mode) Figure 15.2-15 (Sheet 2 of 2l
uJ u, ou, GJ C) (J.l 3UnlVUSdht:ll'lood Notss3uddns (Rev. 1,2 L/03]r 11'&\l C[i*}) PERRYNUCLEARPOWERPLANT S M Suppression PooI Temperature During Alternate Shutdown (at 3729 Mwt) Figure L5.2-I1
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fi (J L) tzz I tul! tL>>. TLJ UJ IJ ftJJ I L) u,J (tl lrj dF c\l gB ct lr, ct ct d ro3tuu$ lN3JU3d) (Rev. L2 L/03) f /)a\ \ ffi PERRYNUcLEARPoWERPLANT Fast Closure of Both Main Recirculation VaJves at llt Per Second Figure 15.3-4
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(Rev. L2 1/03) Cffiil5 PERRYNUCLEARPOWERPLANT Seizure of One Recirculation Pump F.igure 15.3-5
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-'an PERRYNUCLEARPOWERPLANT Fast Opening of Both Main Recirculation Loop Valves at 11t Per Second Fiqure 15.4-3
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C?J lo Hrl c. do A o* c, t r? ct ol fre< d rf c{ HF F{ t Fl ia Fl oc (, F{ rt o { { C' !t A d !t Fl o Fa ra (lt Ut Fl F ai 6 lft Fl t\ wt Ctf lfl ;' ttt ttt l.t tr ci - (Vt ttl (\l Gl F{ d Fl FrFI .-a ltt cD tO tO $l lfl (ll (ll rO { Gt lO l*l Ct ?a G{ ltl Ct tg lO F{ Gl c' (,ltrltt Gl +{ C{ C{ tfl A 4 tl Ol g5e (D Ot tt r'{rn a a a a a a a a a a a a " " " t " ' 9t (,\ F old Ol CtNatt :r ? F o ct dt i iri b - c-i,i i r- or ui t'f c{ rl trr 6 co (l dr N (-Q M ! o - m to o I Ft rnr; 6 an o F Fi cD-r N ro cr (Y ?'l N l! tsI g*E ro F F i grr- cr o ico iri o b -{ q! !! c{ ct N trt q g! (rl ql 9! Gf k sr si or cr cr Ft N ct t't t f cl l' rt Gl ct fo ct f" E FI FI (lF{ t(: &2 cr >F{ 4n dFl 4*q te I ro q lt :'::': : i': :,,: qo (h 1 : ":": roI ul?'1 ?1 c: cr Gr @ N(n 6 l.'tl\ Gt cto or !! !q F.o I5l r1 !! ino -r ci iv 6 - ar - or t<i F cl t\ o tn !! N F I q! XDA 6 i In F qt da,E * <c o r\
+ F ra in or6l crr ui ra o dt'l co b rri or vi -i p e o N In o
f\ o (D
!q ct or (n to or !P c g!
or. co c! !9 o! 9 ro i r.r iri oi or trr ci. n iv aY sr ot sr ot N N $l at'$l N d Fr rO (n Gl d rrtl Ft N lo o C) t- ol 6 (D et !t N I q !? q f 99 qro rn d v- - $i Jro cl - ?r n o (o g o ro 10 lo !? ! q $ r.lC ro qr d ctl tt $f Ul { ro
,( trl r- fl 6ra.o F{ ch frf t o Cf ij o ct 61 61 m c' ol cn crl r<E ; a4 F o O O -l *r i ; ; - i -r rr 7. ?. c{ N sl xt ( oo. O Q G, Gt F{ Fl d a a a Fl Fl 7a Fa Fl F{ d Fl t{ "
Fl rl t
?' F{ F c' d "r
C} O rO'an { tV $l Fl A Or O F rO l'l rr trl (\l rt ln rt G.t N cr t Or @ F (\l Sl Gl $l (\l $l .< FlFa ;l ?a r{ d Fl d F{ (Rev. t2 t/03) trffi PERRY NUcLEAR POWER PLANT _ v _ Critical Rod Pattern for Mi spl aced B undl e A cci dent Figure 15.4-4
- 1. SCENARIOI EVALUATION COiDENSER ENVIRONMENT ENVIRONMENT
- 2. scEl{ARro2 EVAUTAnON OFFGASTREATMENT COT{DENSER SYSTETII DECAYOF NOBI.E CIASESA10 ffiTElmON oF lolrll.lE (Rev, tz 1/03)
&fib PERRY NUcLEAR PowERPI-ANT -\/- \].ATJ Leakage P ath Model for R od DroP Accident Figure 15.4-5
PIJ}TT COORDIt{ATE I2 610 l4 t8 22 26 46 50 54 58 lil I I il! I rr--+--i----!-- I I I -!-u--L---
'---+---f:i I
ri! iil l--i--i-- lil 5,--j- --l I 47 ---l {3-39 35 31 27 23 l9 15-I I ll -F I I I 7---f---j-- ffi- --J---
--{----
l--l-I 3 -r-*---r I I I I Ii I I (Rev. L2 1/03) trffi N--6 PERRYNUCLEARPOWERPLANT
-'H R od P attern for R W EA nal ysi s 14 Core Geometry (Rated Power Case)
Figure 15.4-6
J tr, r,LN'E tna)E lrJ(L f > -F-(03lUHJCI1f,l33U3dl o vr td trJ 2 roflHu s ll{3tu:ld) llev. 12 1/03) t 1 ^ \ I ffiM PERRYNUCLEARPOWERPLANT
\-JQ(r Inadvertent Startup of HPCS Figure 15.5-1
UJ g IJJ' IJJ o z> F v7 ei UJ 5>
= FZ co Iv, CE I
l-.- E o 22 si coo F!o ilJ
\j J tJJ IJJ z 4 ,2
- ) Ut o
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FY 3 (^F o z< UJ uJ (9 tl.
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z IJJ
= =
LlJ 3 J z UJ o v) E n l.l-tl, P ()(J v tr G; F b UJ 6 E uJ tr 3 tJ-(Rev. tZ 1/03)
/-lOn dffi*\ PERRYNUCLEAR POWERPLANT w
Steam Flow SchemaEic For Steam Break OuEside Containment' Figure 15,5-1
U
-T r-tr (D < O-l < O-T U.T g1 UO 1-1tr t-t-tr Ltr C ;- ^' - .( {D E J 0 0
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= ! -I FJ d .l- 0, cl- r-tr o o o CI C
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= o- OJ; C (n a l la t- (, ! .\
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l =0' o cl- <-l l _o .i o* 3 ctr lJ o - T5 0 LE > l 1l rn (D+ qL d a C) lo a -t cF J, (n a
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r Rz. O Zt- 3 qc) m v f =D C-) = \- -{ o nT ,39 -o l rn .l'
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9a z.
FLOW .-+ CONTAINMENT Cfffi\ PERRYNUCLEARPOWERPLANT v Leakage Path for Feedwater Line B reak Outsi de C ontai nment Figure 15.6-3
N U C L E A RS A F E T Y NUCLEAF SAFETY OPEFIA'IONAL O E S I G NC R I T E R I A CRITEFIA ANTICIPAT O OPFATIONAL TRANSI NTS 8WR OPERATIN STATES IOENTIFICATION OF SAFC,TY ACTIONS FULES FOR EVENT ANALYSIS REEULTS(EACHSTATE} IOENTIFICATION OF SYSTEMSANO LIMITS ESSENTIAL FOR ACHIEVING SAFETY ACTIONS IEACH STATEI IOENTIFICATION OF INTRASYSTEM ACTIONS WFIICH MUST 8E FEOUIRO OR RFSTFICTEO IEACH EYSTEMI IOENTIFICAYION OF MINIMUM SYSTEM HAFDWAFIE CONOI'IONS TO ACCOMPLISH ACTIONS IEACH SYSTEMI T O E N T IF I C A T I O N O F H A R O W A R E C O N D I T I O N S
'O SATISFY fIEOUNOANCY REQUIREMENTS ACH SYSTEM (OPEBATIONAL NUCLEAR S ^ F E T Y F E O U I R E M E N T S ,L I M I T I N G CONOITIONS FOR OPERATION}
IOENTIFY SURVEILLANCE TEST FFEOUENCIES AVAI LAEILITY C O N SI D E R A T I O N S IOENTIFY ALLOWABLE FEPAIR TIMS I ^*o^, toi-. t^---;l WHEN SYSTEM TNOPEFAELE ILIMIlING I orenarrornr-REoutRE' I CONOIIION FOR OPERATION} ; M E N T S N o r s a r t s F t E D: L r - r + - - d SIMPLIFICATION r--- I SYSTM.LEVEL SYS'EM.LEVE L I SYSTEM.LVEL OUAL ITATIV E OUALITATIVE OUALITAIIVE I PLANT SAFETV PLANT DESIGN BASIS SYSTEM DESIGN EASIS I CONFIRMATION CONFIRMATION (Rev. 12 1/03) PERRYNUCLEARPOWERPLANT Block Diagram Used to Derive Nuclear S afety Operati onal R equi remen t , System Level QuaLitative Design B asi -s C onfi rmati on Audits and Technica] Specifications Figure l-5A.2-1
z z z 9 o o F () F F (J U u,, F LUJ F U.l UJJ F r.u I.IJ J FUJ tr 5,rr UJ F q) h U) o> EW oo> zEu oo> E IEUJ dsE Z uJ tr-z o>o UJ llJ n' -: l- Ftr-UJ {i, fi l;>9; = EuJ Efi o{li V) k= o@* O EO } , {H ; iFL r EH j ztt Y z z o z O o gi l - -u J , , , 3 F z tr F tr F >>7 t! F t- utJ O UJ C) t! ) HoF; 27 F!nu-cc 22t JO FuJ F F uJ cc po) o o CIo tnE:o LDCClrr z e=< aftzQ tu UJ UJ f , ; tJJ
==eH F J J
-l u.ri o- L o z e O-J EE[5 t- o, ;i tu u, -) rF
=z is LIJ lY t! .r OrJ 6 5 ;o Qflg -ft-uJ
[l z< =& ?tr 9oo> hHrs
=l.U 6> (/) uJ ou Eq sd c lll otr z z z z o o tr tr c" tr ,FHE*
F (J- bc.l iJ (J \t I,IJ J IJJ J tUJ uJ - : E FuJ IJJ Ftu l- r u < o> (r F o> o> o> cuJ cc uJ 0: uJ tr JuJU (J' < r - r l u a t r o-J o-J E<Eftr
-lF <?, tr3:5P 6H Frr <= E3H:E IEagtt IT fr3 bH 5uJ l-H z z z o
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z z z 2 z z zo o o o o o ovt F F F F t! F L) UJ uJ F (J O UJ
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f r u 1r r.lJ IJJ F F- r' F F F o t-Z F I r!J ccJ Et (rJ Ooul
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EL g1 o> o-o> 1g LUJ o- uJ I> cL uJ E> HHi Iils I> F zu Eul Ft! F r,! FUJ c\t J G'J z rf,J Fil3 z ( f ) J lI)J uJ rF uJ JF
- 4. ?.
uJ 1fr rU)Z AE 6; 26t (L k= 3= trpo lrDtru (Rev. 12 1/03) EHi-tro ilo EH EH PERRYNUCLEARPOWERPLANT z5E gob LHT Pos s i b L e I n c o n s i s t e n c i e s in Ehe Selection of Nuclear SafeLy Operat ional Requirem.ents Figure 1-5A.2-2
i9, NUMBER OFEVENT EVENT E V E N TT I T L E STATESIN WHICH STATES
@, THISPROTECT]ON S E O U E N CIES APPLICABLE D ]F F E H E N T P L A N TC O N D I T I O N D IF F E R E N TP L A NC O N D I T I O N INDICATES THAT SYSTEMS O AND F S H A R EA S A P A I RT H E R E O U I R E M E N T T O M E E TT H ES l N G L EF A I L U R EC R I T E R I O N PERSONNEL (MANUALI ACTION REOUIRED FOR SYSTEMW SYSTEM MUSTITSELF M E E TT H ES I N G L EF A I L U R E CRITERION I N D I C A T ETSH A TO N EO R M O R EO F T H E K E Y P R O C E SPSA R A M E T E RM SU S T B E L I M I T E DT O S A T I S F YN U C L E A R S A F E T YO P E R A T I O N ACLR I T E R IA E A C HC O N N E C T EPDR O T E C T I OSNE O U E N CIES FORJUSTONESAFETYACTION (Rev. 12 I/03]'
ffiffi M PERRY NUcLEAR PoWERPLANT r{X Format for Protection Sequence Diagrams Figure L5A.4-1
F R O N TL I N E SAFETYSYSTEM x SAFETYSYSTEM A U X I L I A H YA D I A G R A MI N D I C A T E S T H A TA U X I L I A R I E S A , 8 . A N DC A R E ESSENTIAL TO THE O P E R A T I OO NF SAFETYSYSTEM T H E F R O N TL I N E A U X I L I A R YB SAFETYSYSTEMX. N OC H R O N O L O G Y O R O R D E BO F A C T I O NI S I M P L I E D SAFETYSYSTEM A U X I L I A R YC PERRYNUCLEARPOWERPLANT Format for S afety S ystem A uxi l i ary D i agrams Figure 15A.4-2
2ut siIi
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Cflffi\ PERRYNUCLEARPOWERPLANT wo Format for C ommonal i tY of A uxi l i ary D i agrams Fi gure l -5A . 4 -3
;t:
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( R e v . L2 L/ 03) ffiM l\lrF#t PERRY NUcLEAR PoWERPLANT X..P Safety System AuxiLiaries Figure 15A.5-1
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at
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r
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^6.^. /Fi\ .ffi*'M PERRYNUCLEARPOWERPLANT I l S afety A cti on S equences for Normal Operation in State A.
Figure 15A.6-3
uJ' tr
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,?
l'l trsf L
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Ao 6 o uuJ o trF E Pb 8i I E UJ
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aufi t!Zf,F kt r CI ;) F=J YrF ur 3?i
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I
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Q ' A J fgHs (Rev. T2 1_/03)
-4\n CffiN\ PERRYNUCLEARPOWERPLANT r{x Safety Action Sequences for Normal- Operation in State B.
Figure 15A.6-4
dsr 5"?i ii; : u g B ( , F HE!:d ) sHi rHF HgsEE s < ( i 33id 2 s5:? r( a cEccAl ! 9YJJ I ?= J ??qq B'trE HE f J =: tG pi ir F J
-o 6>
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= @ ?H 3oJ< "E H H :? <v14 g>
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<l Bs 3E N F 5 ;<
u icE 3a2 =d. 3Fi E x wz 3 g fi=Ed Y J 2H :gHF EEE d:U tr> tf;E6 z 3w oo lE
+(9 ?fi F :
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(,>:r 9<u: 3!8i *Z; E U> 6;?Y E3ig O>o cF:z fiHE (Rev. 12 L/03) r,rOrr r r -Al I d6*15 PERRYNUCLEARPOWERPLANT rjcl.J Safety Action Sequences for Normal Operation in State C. Figure 15A.6-5
o :- ri A :r e-
; "g:;! !> E *
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;iFi i.le-(R e v . I2 1 / 0 3) r /-(\ ) &ffi PERRYNUCLEARPOWERPLANT --/- \ \-x-l ,,
SafetY Action Seguences for Normal OPeration in State D' Figure 15A.6-6
{.-EY,F,ryTr-^-\ MANUAL OR INADVERTENT SCRAM REACTOR PROTECTION SYSTEM SIF C O N T R O LR O D D R I V ES Y S T E M slF SCRAM nan trffi PERRY NUcLEAR PowERPLANT
._r(X P rotecti on S equence for Manual or Inadvertent S cram Figure 15A.6-7
S E R V I C EA t F SYSTEM STATES S T A T E SA , B STATESC, D PLANNED OPERATION S C R A MS I G N A L H I G HP R E S S U R E W H E N3 M A I N REACTOF L I F T SV A L V E P F E S S UR E STEAM LINES PROTECTION TRANSFERRING RELIEF C L O S E D> 1 0 % SYSTEM H E A TT O S U P . SYSTEM P R E S S I OPNO O L IN S E R T INCIDENT CONTROL CONTROL ROO DETECTION S T A R TH P C S ,R C I C , PRESSURE ROOS DRIVESYSTEM O N W A T E RL E V E L 2 R E L IE F CIRCUITRY M A I N T A I N l , v A T E RL E V E L CORE COOLING (Rev. 12 1/03)
,ffi) PERRY NUcLEAR PowERPLANT tts#T P rotect.i ve S equence for Loss of P Iant Instrument or S ervi ce Air SYstem Figure 15A.6-8
EVENT9 INADVERTENT START.UP HPCSPUMP STATESA, 8. C AND D STATESB, D STATESB, D STATES ArC FEEDWATER REGULATOR PRESSURE CONTROLLER PLANNED FAILUFE OPERATION FAILURE MAXIMUM DEMAND PLANNED SEE PLANNED SEE OPERATION E V E N TN O . 2 3 OPERATION EVENT NO.22 (Rev. 12 1/03) (ffi pERRyNUSLEARpOwER PLANT l \-v/ l Protective Sequence for Inadvertent S tartup of H P C S Pum Ps Figure 15A.6-9
E V E N TI O STARTUPOF IDLE RECIRCULATION PUMPS
\ STATESA, B. C, D j STATESA AND B STATE D STATESB AND D POWERl0-60% POWER5.10%
ee 3 rr IRM o \PRM to tr HIGH n {IGH UJ 3 tr, :LUX o FLUX llj c SIGNAL 3 ;IGNAL V o G EQ lo rLANl\trU TL'T OPERATION OPERATION NEUTRON NEUTRON MC) N I T O R I N G MONITORING SYSTEM SYSTEM slF F REACTOB SCRAMSIGNALON PROTECTION N E U T B O NM O N I T O R I N G SYSTEM SYSTEMTFIP STF CONTROLROD INSEFTCONTROLRODS DRIVESYSTEM sfF
/\
SCRAM ( R e v. L Z l-l03 )
\/
rDflI
.fl-'-'M PERRYNUCLEARPOWERPLANT Protective Sequence for Inadvertent Startup of ldle R eci rcul ati on Loop P umP Figure 15A.6-10
RECIRCULATION LOOP F L O WC O N T R O LFAILURE M A X I M U MD E M A N D STATESC AND D STATED, MODE S W I T C HI N R U N , STATEC POWEROPEHATION STATED (MODESWITCHNOT IN RUN} P L A N N E DO P E R A T l O N NEUTRON H I G HN E U T R O N FLUX MONITORING ( A P F M }S I G N A LT O SYSTEM RPS SCRAMSIGNAL REACTOR ON NEUTRON PROTECTION MONITORING SYSTEM SYSTEMTRIP CONTROL R O DD R I V E I N S E R TC O N T R O L FODS SYSTEM (Rev. 12 1/03) t /-L\ l CffiM PERRYNUCLEARPOWERPLANT P rotecti ve S equence for R eci rcul ati on Loop Fl ow C ont r o] Failure Maximum Demand Figure 15A. 6-l-1
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E V E N TI 3 R E C I R C U L A T I O NL O O P P U M PT R I P ON OR EOTH S T A T E SC A N O D O N E P U M PT R I P STATE C STATE O TWO ONE PUMP TRIP P U M PT R I P PLANNEO OPERATION O N EP U M P T R I P PRESSURE HEATTO RELIEF SUPPRESSION SYSTEM POOL CONTAINMENT ANO REACTOR REACTOR VESSEL PROTECTION ISOLATION SYSTEM CONTROL SYSTEM MAIN STEAM INCIDENT CONTROLROD START HFCS. RCIC, LINEISOLATlON DRIVE SYSTEM DETCTION ON WATER LEVEL 2 VALVES CIFCUITRY REACTOR MAINTAIN VESSEL WATER LEVEL ISOLATION (Rev. 12 1/03) O6"'}DPERRYNUCLEARPOWERPLANT { " r \ l l \\1 / ' R eci rcul ati on Loop P ump Tri p one or both Figure 15A.6-13
EVENT14 ISOLATION OF ALL MA!N STEAM LINES STATES C, D STATEC STATED H I G HP R E S S U R E REACTOR S C R A MS I G N A LW H E N PRESSURE L I F T SV A L V E PROTECTION 3 MAIN STEAM R E LEI F TRANSFERRING SYSTEM > 10% L I N E SC L O S E D SYSTEM HEATTO SUP. P R E S S I OPNO O L PRESSURE R E LEI F C O N T R O LR O D D R I V ES Y S T E M INCIDENT S T A R TH F C S ,R C I C , DETECTION O N W A T E RL E V E L 2 CIRCUITRY MATNTAINW A T E RL E V E L INITIAL CORE COOLING (Rev, 12 1/03) Cfl*'6 PERRYNUCLEARPOWERPLANT Protective Sequence for fsolation of All Main Steam Lines Figure 15A.6-L4 (Sheet 1 of 2)
E V E N T1 4 ISOLATIONOF ONE MAIN STEAMLINE STATESC, AND D LESSTHAN GREATERTHAN 90%POWER 90%PowER CONTINUE PLANNED NEUTBON HIGHNEUTRON MONITORING OPERATION F L U XS I G N A L SYSTEM SCRAM SIGNAL REACTOR ON NEUTRON PROTECTION MONITORING SYSTEM SYSTEM TRIP INSERT CONTROLROD CONTROLRODS DRIVESYSTEM (Rev. 12 1/03) (T'""D PERRYNUCLEARPOWERPLANT Protective Sequence for Isolation of One Mai n S team Li ne Figure 15A.6-14 (Sheet 2 of 2l
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-'an df"i$b PERRY NUcLEAR PowERPLANr tryJ P rotecti ve S equences for Inadvertent OPening of a SafetY/
Relief Valve Figure L5A.6-15
E V E N T1 6 CONTROLROD WITHDFAWALERROR START.UP AND REFUELING OPERATIONSTATESA AND B 3 tr, o o o T G STATEB I N T E R M E D I A TR EA N G E l- o F tr o l.- z o o E o tu o z z o o (t PLANNED UJ HIGH a NEUTRON NEUTRON OPERATION tL MONITORING o FLUX SYSTEM SIGNAL o
=
l! tr SCRAM SIGNAL BEACTOR REACTOR ON
,.REFUEL" PNOTECTION NEUTRON PROTECTION SYSTEM SYSTEM MONITORING SYSTEM TRIP C O N T R O LR O D CONTROLROD DBIVESYSTEM DRIVESYSTEM R O DB L O C K (Rev. L2 1/03) ffiM Fra-/,zt PERRYNUCLEARPOWERPLANT P rotecti ve S equence for C ontrol Rod W i thdraw al E rror for S tartuP and Refueling Operations Figure 15A.6-15
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E V E N T1 9 RHRS-SHUTDOWN COOLING I N C R E A S ECDO O L I N G STATESA, B, C. AND D PLANNEDOPERATION P L A N N E DO P E R A T I O N t /)<\ l CffiN\ PERRYNUCLEARPOWERPLANT RHRS S hutdow n C ool i ng Fai l ure Increased Cooling Figure, 15A.6-19
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E V E N T2 1 LOSSOF A FEEDWATER HEATER STATED R E C I R C U L A T I OFNL O WI N R E C I R C U L A T I OFNL O WI N AUTO PLANNEDOPERATION H I G HF L U X S C R A MS I G N A L ( T H E R M A L P O W E RM O N T T O R } S C R A MS I G N A L BEACTOR ON NEUTRON PROTECTION MONITORING SYSTEM S Y S T E MT R I P CONTROL R O DD R I V E I N S E R TC O N T R O LR O D S SYSTEM (Rev. 12 l _ / 0 3) (ffi pERRyNUcLEAR pOwERpLANT r{ts Protective Sequence for Loss of a Feedwater Heater Figure 15A.6'21
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/i'an ,ffi Y.b\ LX PERRYNUCLEAR POWERPLANT I \_Y/ J v
ProEect.ive Sequences for Feedwater Controller Failure Maximum Demand Figure 1-5A'.6-22
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EVENT24 FIRSTPRESIIUFEREGULATOR FAILURE- CLOSED STATESC AND D SECONDPRESSURE REGULATOH STARTHPCS,RCIC PRIMARY ON LOWWATEB CONTAII.IMENT LE V E L AND REACTOR VESSELISOLATION CONTFOLSYSTEM MAINTAIN MAIN STEAMLINE CORE ISOLATIONVALVES COOLING PLANNED OPERATIOT{ INITIAL CORE COOLING RHRS - supPREsSf ON POOL i,tODE
'COOLINc SUPPRESSION POOL TEMPERATURE LIMIT STAFT DEPFESSURIZATION MANUAL REOUIRED VALVES FV FORCOITITFOLLED DEP OPRATION MAINTAIN WATER IN REACTORVESSEL T
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EVENT32 I N A D V E R T E NLTO A D I N GA N D O P E R A T I O-N F U E LA S S E M B L Y I N I M P R O P EPRO S I T I O N STATESA. B, C, D PLANNED OPERATION ffi-M PERRYNUCLEAR POWERPLANT
- v Protective Sequence for Inadvertent Loadi ng and Operation of FueI A ssembl Y i n fmproP er P osi ti on Figure 15A.6-32
EVENT 33 FECIRCULATION LOOPPUMP SEIZURE STATEO ONLY INCIDENT SNSES HIGH I N C IO E N T SENSES PHESSURE DETECTION REACTOR VESSEL DETECTION LOWWATER RE L I E F CIRCUITFY W A T RL E V E L CIRCUITFY LEVEL SYSTEM PRESSURE RELIEF REACTOR MAIN STEAM LINE PROTECTION ISOLATION VALVE SYSTEM CONTROL R O OO R I V E SYSTEM MANUAL RV ACTUATION (Rev. 12 1/03) f /)< \ I ffi PERRYNUcLEARPOWERPLANT P rotecti ve S eguence fo r Recirculation Loop PumPSeizure Figure 15A.6-33
EVENT 3{ RECIRCULATION LOOP P U M PS H A F TB R E A K STATED ONLY INCIDENT S E N S EH SIGH I NCIDENT DETECTION REACTOFVESSEL OETECTION CIRCUITBY WATERLEVEL CIRCUITRY REACTOR MAIN STEAM LINE PROTECTION ISOLATION VALVE SYSTEM CONTAINMENT ISOLATION (Rev. L2 1/03) Cffi".$ PERRYNUCLEARPOWERPLANT
\12(l_J Protective Sequence for R eci rcul ati on Loop P um p Shaft Break Figure 15A.6-34
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E V E N Td 2 AUGMENTED OFF-GAS TREATMENTSYSTEMFAILURE STATESA, B, C, AND D STATESA, B STATESC, O PLANNED S E EO T H E R OPERATION LOSSOF MANUAL MAIN CONDENSER OPERATION CONDENSER VACUUM ACTION H I G HP R E S S U R E EVENT26 ACTIONS OFF.GAS SYSTEM ISOLATION (Rev. t2 1/03) rr'on ffi*'"Y1PERRYNUCLEARPOWERPLANT
\JclU P rotecti ve S equences A ugmen t ed Offgas Treatment S ystem Fai l ur e Figure 15A. 6-44
EVENr 43
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- 10. 15.
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- 10. 15.
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^Or\ .Vffi PERRYNUCLEARPOWERPLANT Feedwater Controller Failure 3" 129 Mvi l t C ore P ow er 100* FIow 25ooF R ated FW T Figure 15D-6a (Sheet 2 of 4)
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-a>,-\ &f$b PERRY NUcLEAR PowERPLANT Feedwater Controller Failure 3729 MWt Core Power 100t FLow 25ooF R ated rw r Figure 15D-6a (Sheet 3 of 4)
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NEUTRON PERKFU 6. rSEC) I LEVELII F-SEP.SKINT 2r.rR LEVEL( INCHESI NN L I INCHESI TTTEH-(PCTI hr I lPcTl q. TI}tE IS E CI (Rev. 12 1./03') ^,o^ C(ffi\ PERRYNUCLEARPOWERPLANT t\Y/, v - Generator Load Rejection w /A B l pass 3729 MW t C ore P ower L05t Core Flow Figure 15E.3-L (Sheet I of 2)
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6. rSECr V E L I I H-NEF-SEP-5KIRT R sEh 9 LEVEL( I NCHES) R SEt" D LEVEL( INCI.IES} TFETI I TPCTJ - 1 0 0 .L
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TIHE ISECI (Rev. L2 L/03\ PERRYNUCLEARPOWERPLANT Cffi"'"T) Generator Load Rejection W /O B ypass 3729 MW t C ore P ower 73.62 Flow Figure 158.3-2 (Sheet I of 2)
I VEssEL S R I S E ( P S I ) 2 STHLINE B E sR I S EI P s I } TY VE FLOl'l(o) L0t4 [o) V E FLO }I[ o) FL0I.ItPCT)
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T I H E rSECf I V O I DN E f ; C T I V I T T 2 O O P P L ERRE N C T I V I T Y 2. TI},IE rSEC) (Rev. L2 1/03) PERRYNUCLEARPOWERPLANT Generator Load Rejection W l A B ypass 3729 MW t C ore P o wer 73,6t Flow Figure 15E.3-2 (Sheet 2 of 2)
I LE V E L(I -SEP-sKIRT 2HR LE VEL ( I NCHESI (INCHESI
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.N -a PERRYNU6LEARPOryERPLANT \-)-(J Feedw ater C ontrol l -er Fai l ure 3729 MWt Core Power 1058 Flow Figure l-58.3-3 (Sheet 1 of 2)
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- 10. 15.
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,V"ffi, PERRY NUCLEAR POWER PLANT LjA{J
_v-Feedwater Controller Failure 3729 MW t C ore P ow er f05t Flow Figure 158.3-3 (Sheet 2 of 2)
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- 10. 15.
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- 10. t5.
TI}IE ISEC) (Rev. tZ L/03) Cffi PERRYNUCLEAR POWERPLANT l / A I I Feedw ater C ontrol l er Fai l ure 3' 129 MW t C ore P ow er 73.6t Fl- ow Figure 15E.3-4 (Sheet L of 2)
r vE55 E L P 5 R I S E( P s I ) 2 5Tl.l L INE 5 R I S E( P s I I 3 TURB INE sUB IBTU/LBI VE FTOH(PCTI FLoH(PCT)
- 10. 15.
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( R e v. 1 2 L/03) ffiM PERRYNUCLEARPOWERPLANT Feedw ater C ontrol l er Fai -l ur e 3129 MWt Core Power 73.6t FIow Figure 15E.3-4 (Sheet 2 of 2\
5 VEssELS q. TIr'rE rsEcr I LEVE L(I -sEP-5KIRT 2 ll B SEN LEVEL(INCHES) N R 5EN VEL( I NCFI ES) H (PCT) I (PCT) {. TIt'tEtSECt (Rev. 12 l-l03) PERRYNUCLEARPOWERPLANT t [ A l ffiM rli5/J Generator Load Rejection w/O Bypass 104.2t Power 105t Flow 250oF FWT F i g u r e 1 5 8. 1 1 - l " ( S h e e t L o f 2 l
T VESSEL 5 N I S E ( P S I) 2 5TT,I LIN E 5 R I S EI P S I ) SHFETY V E FLO , .(I o) V E FL O l. (l o) VE FLOi^l(o) FLoH(PCT)
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I NEUTRON 2 PERKF CENTENTEHP
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- 10. 15.
TI}IE rSECl (Rev. L2 1/03) n'On 1fffi PERRYNUCLEARPOWERPLANT
-v-Feedwater Controller Failure 104,2* Power l-05t FIow 2500F FWT Figure 15E.LL-z (Sheet L of 2)
\JESSEL E SR I S E( P 5 I)
R I S E( P 5 I ) S T}1LIN E P B E S Tllrmruruet vE FL0l.l IPCTI FLoHtPcTI I vo]mffidrtvtrr gmtrili{ivit+ a/r,(inrLEnrl:li TI yl TY F. F -1. L) CE lrJ E
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( R e v. L Z t/03) ffi PERRYNUCLEAR POWERPLANT
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Feedwater Controller Failure 704,22 Power 105t Fl-ow 2500F FWT Figure 158.11-2 (Sheet 2 of 2)
I NEUTBON UX 2 PERKF CENTER TEHP 5 VEsSEL 5 a trJ 100. CT (tr lt E' AL) 50. ctr lrJ o-u. TII,IE I LE V E L(I H-REF-5EP-sK I RT 2HR t} LEVEL ( INCI-IEs) NRSE LEVEL{ INCHES) {. T I I 4 EI S E C ) ( R e v. t 2 L/ 0 3 )
@ PERRYNUGLEARPOWERPLANT Generator Load Rejection w/o B l p a s s 1 0 4 . 2 2 P o w e r 1 0 8 . 7
- F L o w 3?OOF FWT Figure 15E.11-3 (Sheet 1 of 2)
I VEssEL P S R IS E ( P S )I 2 STHLINE 5 R I S EI P S I ) 3 S FFE TY FL0H (ol 5 BYPRSS V V E FL0H ( o) 6 TURBsTE FLoH ( PCT) u, 6. TII4Et S E C ) V O I DN E OOPPLER T} L' c lrJ E 2, TI},IEtSEC) ( R e v . T2 1 / 0 3) PowERPI-ANT ribf,-\ 6t'tb PERRY NUcLEAR t_D(-r v Generator Load Rejection W/O BYPass 1'04,2* Power 1 0 8 . ? t F I o w 3 7 0 o FF W T Figure 15E.11-3 (Sheet 2 of 2)
CENTERTEHP RT FLUX 6. rSEC) EVEL(I BT N E F-5EP- 5KI R 5EN LEVEL( I NCHES) R SEN ( I NCHES) LowrPcT) I (PCT) -100.
- 0. u. 6.
TII,IE( s E C ) ( R e v. . 1 2 1/03)
#}b PERRYNUCLEAR POWERPLANT -\./-
M Generator Load Rejection W/O BYPass 104-2? Power 110t Flow 320oF FWT Figure 158.1.1-4 (Sheet 1 of 2)
I VEssEL 2 5 T } 4L I N E ol L V EF L 0 t l ( c l FLol.lrPcTl TIVITY RCTIVITY TIVITT U} L' c! trJ E 2. TII,IE( 5 E C ) (Rev. L2 1/03) ffffi PERRYNUCLEARPOWERPLANT Generator Load Rejectlon W/O Bypass 104.2t Power 110t Flow 320oF FWT Figure 15E.11-4 (Sheet 2 of 2)
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- 10. 15.
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- 10. 15.
TI},1ErSEC ) (R ev . 1,2 1 / 0 3 ) d;$b PERRYNUCLEARPOWERPLANT r /><\ I r{,_y Feedw ater C ontrol l er Fai l -ure t04.22 Power L08t FJ-ow 3700r F.wr Figure L5E.1L-5 (Sheet I of 2)
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- 10. 15.
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- 10. t5.
T I M E(sEc r LEVE L(I -R E F.5EP- SKIRT l.l n SEN LEVELIINCHES) R LE V EILI N; HEs} to. 15. TII,IEISECI ( R e v. L 2 r/03) d6$5 PERRY NUcLEAR PowERPLANr
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- 10. 15.
TIHE [SEC) (Rev. 12 1/03) n'On ffi PERRYNUCLEARPOWERPLANT v Feedw ater C ontrol l er Fai -l ure L04.2t Power 110t Flow 3 2 O O FF W T Figure 15E.1L-6 (Sheet 2 of 2)
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^6^ #fib PERRYNUCLEAR POWERPLANT Generator Load Rejection W/O BYPass 104.2t Power 74.8t FIow 370oFFWT Figure 158.11-? (Sheet 1 of 2)
1 VESSEL P ES RISE (PSI) 2 STM LINE PRES RISE IPS1) 3 5RFETY V LVE FLOW t>>) LVT70-200. 100. 0.
- 4. 6.
TIME (SEC) 1 VOID RERC TIVITT 2 DOPPLER F ERCTIVITT 3 SCRRMREf CTIV1TT a
- 2. 3.
TIME ISEC) (Rev. 12 1/03) PERRY NUCLEAR POWER PLANT Generator Load Rejection W/O Bypass 104.2% Power 74.8% Flow 370°F FWT Figure 15E.11-7 (Sheet 2 of 2)
NEUTRON LIX PERKF CENTEBTEHP RVE SURF E HERTFLUX 6 lrJ 100. Cr Ctr L o 2 .-il \Il vv' 6 cc trJ g
- g. 6.
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T I } 4 E( S E C } (Rev. 12 l/03]r
'\
r n!a\ ff'ffi PERRYNUCLEARPOWERPLANT Generator Load Rejection W/O Bypass L04.2* Power 73.7t FLow 320oF FWT Figure L5E.1L-8 (Sheet 1 of 2l
I V E S S E L s n l S E ( P S)i 2 s T ML I N E NEsRI SE IPSII SRFETY VEFL0i.l(ol V E F L O h( o l vE FL0l,,l. (o) FLOH(P C TI rl. TIt'lE(sECl V O I DN E R d T ] V I T Y DOPPLER RENCTIVITT S C R RN E H : T I V I T Y J> L.' cf UJ (tr 2. TlttE I S E C ] (Rev. LZ l/03) l /><\ I (ffi-"6 PERRYNUCLEARPOWERPLANT N U
\jOU Generator Load Rejection W/O Blpass 1,04.22 Power '13.7\
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- 10. 15.
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- 10. 15.
TII4Er S E C ) (R e v . L 2 1/03) ffi PERRY NUcLEAR PoWERPLANT X-ry Feedwater Controller Failure 104.2t Power 74.88 Flow 370" F FW T Figure 158.11-9 (Sheet I of 2)
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- P o w e r 74 . 8 t F I o w 3 7 O O FF W T Figure 15E.11-9 (Sheet 2 of 2)
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- 10. 15, TIt'lEtSEC)
L(I -5EP-5KI RT 5EN D L E V E(LI N C H E S } L E V E(LI N C H E S } 10. TI I,IE rSEC) (Rev. t2 I/03) r /><\ l ff"',b PERRYNUCLEARPoWERPLANT r.)cry Feedwater Controller Failure lA4.2Z Power 73.7t Flow 3 2 O O FF W T Figure L5E.11-10 (Sheet L of 2)
I V E S S E L 5 N I S E( P s I) 2 5TI.,ILINE 5 R I S E ( P 5 II TUR 5 R I S E( P S ] } SUB(BTU/LB) VE FLOI,I (PCT I FLor.rI PcT)
- 10. 15.
TI I.4EI S E C ) ,yl' CJ CE u.J 0c 10. TI I,,IE( s E C l (Rev. 12 1/03) ffi PERRYNUCLEARPOWERPLANT
\JO{J Feedwater Controller FaiLure L04,22 Power 73.7t Flow 3 2 O O FF W T Figure 158.11-10 (Sheet 2 of 2)
l{. = Total Core FIow t { ; - A c t l v e L o o PF l o w t l i = I n a c t i v e L o o PF l o w (R e v . t2 t/03) tr'ffi PERRY NUCLEAR POWER PLANT t \></ ,
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(Rev, L2 1/03) n'art tr-D PERRYNUCLEAR POWERPLANT w P eak D ome P ressure V ersus Initial Power Level, Turbi ne Tri p at E OE C Figure 15f.3-1
a lr, t00. CE cc t! t AIJ 50. Ctr lrJ o-il F-SEP-sI(I RT P ITI0N (ol 5 FI.ICF.IIFXDEI.IR},I/ HI.ILTRIPS (Rev, 12 l/03)
@ PERRYNUCLEARPOWERPLANT Feedwater ControlLer Failure Maximum Demand S i ngl e Loop Operati ons a
Figure 15F.3-2 (Sheet 1 of 2)
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BON TEI.lP E lrj 100. cr Itr l.t. E F 2 u J\,' Lt I E, l4J 5
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TI}IE rsEcl I L E V E L ( I H-REF-sEP-5KIBT 2 F C v t P I T I 0 NI o l 100. 0. TIH E IS E C I (Rev. 12 L/03) 1f"ffi PERRYNUcLEARPOWERPLANT v Generator Load Rejection, w /O B l pass S i ngl e LooP Operation Figrure 15F.3-3 (Sheet 1 of 2)
I VESSEL R I S E( P s I 2 ST}I LINE RISE IPSII (ol ol VE FL0l'l (ol FLfH (PCTI tl. 6. TII'IE (sECr v0l0 RE TIVITY DOPPLER C T I V I T Y IVITY t-(J G t^J Itr 2. TII,IE rsEcr (Rev. LZ L/03) CqA"il\PERRYNUCLEARPOWERPLANT L ^ / Generator Load Rejectiont W/O B l P ass S i ngl e Loop Operati on Figure 15F.3-3 (Sheet 2 of 2)}}