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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CONTAINMENT (tr"*"'bPERRYNUCLEARPOWERPLANT I / X \ I l\s--4.{
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S/R VALVE CONTAINMENT REACTOF VESSEL
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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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-'an PERRYNUCLEARPOWERPLANT Fast Opening of Both Main Recirculation Loop Valves at 11t Per Second Fiqure 15.4-3
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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
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- 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
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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
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\-JQ(r Inadvertent Startup of HPCS Figure 15.5-1
UJ g IJJ' IJJ o z> F v7 ei UJ 5>
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Steam Flow SchemaEic For Steam Break OuEside Containment' Figure 15,5-1
U
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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
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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
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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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Figure 15A.6-3
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-4\n CffiN\ PERRYNUCLEARPOWERPLANT r{x Safety Action Sequences for Normal- Operation in State B.
Figure 15A.6-4
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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 )
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.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
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,.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 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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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
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E V E N T{ I GASEOUS RADWASTE SYSTEMLEAK ORFAILURE STATESA, B, C, D STATESA. B STATESC, D MANUAL OPERATOR MAIN CONDENSER ACTION LOW VACUUM OFF.GAS SYSTEM ISOLATION PLANNED OPERATION SEE L O S SO F C O N D E N S E R VACUUM E V E N T2 6 ( R e v. 1 2 1/03 ) Ifffi, PERRYNUCLEARPOWERPLANT Protective Sequences for Gaseous Radwaste SYstem Leak or Failure Figure 15A' 6-39
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
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EVENr 43
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- 10. 15.
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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)
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- 10. 15.
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- 10. 15.
TI}IE rSECl (Rev. L2 1/03) n'On 1fffi PERRYNUCLEARPOWERPLANT
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@ 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)
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- 10. 15.
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- 10. 15.
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- 4. 6.
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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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- 10. 15, TIt'lEtSEC)
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- 10. 15.
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\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)
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@ 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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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)}}