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[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23110A2402023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Table of Contents ML23173A0132023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 12, Structures and Shielding, Sections 1 Thru 4 - Redacted ML23110A2462023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, PEA Chapter 00, Cover Page and General Table of Contents ML23110A2472023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix E, Table of Contents ML23110A2372023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary, Table of Contents ML23110A2422023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Control and Instrumentation, Table of Contents ML23110A2592023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix N, Peach Bottom Site Meteorology ML23110A2392023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix D, Table of Contents ML23110A2532023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations, Sections 1 Thru 8 ML23110A2202023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Exhibit IV, Vessel Fabrication and Assembly ML23173A0552023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix E, Station Atmospheric Release Limit Calculations - Redacted ML23110A2232023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix G, Plant Nuclear Safety Operational Analysis ML23173A0402023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Control and Instrumentation - Redacted ML23173A0382023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix M Containment Report - Redacted ML23172A2812023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix C, Figures - Redacted ML23173A0582023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 10, Figures - Redacted ML23110A2312023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 11, Table of Contents ML23110A2602023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 3, Figures ML23173A0162023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 5, Figures - Redacted Rev1 ML23173A0172023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Sections 10 Thru 23 - Redacted ML23172A2802023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 9, Figures - Redacted ML23110A2652023-04-10010 April 2023 Submittal of Revision 29 to Updated Final Safety Analysis Report and Rev. 24 to Fire Protection Program ML23173A0452023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 9, Table of Contents - Redacted ML23172A2752023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix a, Table of Contents - Redacted ML23173A0332023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 2, Site - Redacted ML23172A2622023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 7, Figures - Redacted ML23173A0482023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 12, Table of Contents - Redacted ML23110A2562023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary ML23110A2322023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix P, Environmental Technical Specifications ML23173A0232023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 12, Figures - Redacted ML23110A2242023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Exhibit Vi.B Unit 3, Deleted ML23110A2612023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix O, Table of Contents ML23173A0592023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix J, Identification-Resolution of AEC-ACRS and Staff Concerns - Redacted ML23173A0492023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix a, Figures - Redacted ML23110A2512023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, PEA Chapter 6, Figures ML23173A0572023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix C, Structural Design Criteria - Redacted ML23173A0562023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 10, Auxiliary Systems, Sections 1 Thru 24 - Redacted ML23173A0292023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 8, Figures - Redacted ML23173A0432023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 8, Electrical Power Systems - Redacted ML23172A2842023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix C, Table of Contents - Redacted ML23173A0372023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix a, Pressure Integrity of Piping and Equipment Pressure Parts - Redacted ML23110A2482023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix K, Exhibit III, Summary Stress Report ML23110A2452023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix H, Table of Contents ML23110A2502023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 8, Table of Contents ML23110A2292023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 10, Table of Contents ML23110A2572023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 5, Containment ML23110A2212023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 1, Figures ML23110A2282023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix F, Interaction of Units 2 and 3 ML23110A2412023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Appendix Q, Figure ML23110A2622023-04-10010 April 2023 9 to Updated Final Safety Analysis Report, Chapter 13, Table of Contents 2023-04-10
[Table view] |
Text
0.020 , . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
ROD DROP ACCIDENT MAXIMUM CONTROL ROD WORTH WITH SINGLE OPERATOR ERROR FOR VARIOUS OPERATING STATES AT BEGINNING OF LIFE WITH ROD SEQUENCE CONTROL SYSTEM 0.015 ROD SELECTION ERROR
- r
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o o
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It
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ROD WITHDRAWAL ERROR 0.005 o
~ ~ ~ I! ~ ~ 1eci 0 20 40 60 80 100 o 0 0 0 ci AVERAGE MODERATOR DENSITY 19m/eel CORE AVERAGE POWER (%1 PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT ROD DROP ACCIDENT MAXIMUM CONTROL ROD WORTH WITH SINGLE OPERATOR ERROR AT BOL WITH RSCS FIGURE J.4.1
0.020 , . . . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ , ,
ROD DROP ACCIDENT MAXIMUM CONTROL ROD WORTH WITH SINGLE OPERATOR ERROR FOR VARIOUS OPERATING STATES AT THE MOST REACTIVE POINT IN CORE LIFE 16600 MWd/TI WITH ROD SEQUENCE CONTROL SYSTEM 0.015 J:
~
lr o
~
- ROD SELECTION ERROR 8
lr 0.010
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ROO WITHDRAWAL ERROR 0.005 50% ROD DENSITY o~ ....._ ....._ .... ..........................._ ....._...._....._ ......................_ ..........._ ....._ ...
20 40 60 80 100 AVERAGE MODERATOR DENSITY Igm/eel CORE AVERAGE POWER (%)
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT ROD DROP ACCIDENT MAXIMUM CONTROL ROD WORTH WITH SINGLE OPERATOR ERROR AT MOST REACTIVE POINT IN CORE LIFE (6500 MWd/T) WITH RSCS FIGURE J.4.2
)
TY'tII' J\A.L-OU'l' 0"
JULL-'"
'WIT'"
'NNE::
RIC COMPANY PHILADELPHIA ELEC~ POWER STATION OTTOM ATOMI PEACH B UNITS 2 AND 3 S REPORT UPDATED FINAL SAFETY ANALYSI I
~I CK DIAGRAM OF SCHEMATIC BLO EXPOSURE F~~5~~
RE RSCS MWd/T
)
FIGURE J.4.3a
)
POSITION LIGHT PROBE 185 ROO POSITIONS - ISOLATOR ~ TYP OF
& ALARM STATUS 185 RPI CAB f
CORE DISPLAY EE 4 ROO DISPLAY BYPASS SWITCH LIGHTS 185/4 APPROXIMATELY I
185 WIRES -
SELECT RELAY 1--_-41 t I~ --~ Al MODULES I I TO
.-_-11 1~ A2
.-;~
MANUAL ~CRD I I CONTROL
. - - - 11 I~ Bl
--.;;..;~
SYS 1 1 B2 PHILADELPHIA ELECTRIC COMPANY
. - - - 11I IIt--------..;;;.;~
L------j---t: C
~t_------..-.--4------ .. PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT ROO SELECT PANEL RSCS BLOCK DIAGRAM FOR CORE EXPOSURE <6500 MWd/T FIGURE J.4.3b
)
A'lMM r"OI'
~l.*our Ir....... * ...
SWI""
~
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I I
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TRIC COMPANY PHILADELPHIA ELEC C POWER STATION I
I OTTOMATOMI I I I
I I
I PEACH B UNITS 2 AND 3 S REPORT I I UPDATED FINAL SAFETY ANALYSI
~~..".,."
~I AI """A~~l.D K DIAGRAM OF SCHEMATIC BLOORC EXPOSURE s
C FOR C E RS >6500 MWd/T FIGURE J.4.4a
)
POSITION 185 ROD POSITIONS LIGHT PROBE
& ALARM STATUS ISOLATOR -- TYP OF 185 RPI CAB BYPASS SWITCH CORE DISPLAY 4 ROD .Ir ,.
DISPLAY 4 Power Permissive Signal LOGIC-RSC LIGHTS 185/4 APPROXIMATELY - ...._..,..._...:-~--Power Alarm Signal SEQUENCE
,. WITHDRAWALI INSERTION SELECT 185 WIRES SELECT RELAY ~_~I t I~ Al .....
MODULES I I TO A2 MANUAL ~CRD
~_~I I~ ---- --t I I CONTROL
~_~I I~ Bl
.....;;.~
SYS I I t---~I I~ B2
--:;.~ PHILADELPHIA ELECTRIC COMPANY I r PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT I
ROD SELECT PANEL RSCS BLOCK DIAGRAM FOR CORE EXPOSURE >6500 MWd/T FIGURE J.4.4b
) CQ'ITIDL roo SroCK L~ coas READY FOR DROP
,...--..------------------0....-------------.
CONTR:>L ROD IS SnJCK U NEAR FULL OR FULL CQ\1TROL ROD SEPARATED Flu.1 OO'ITR:>L G),ITROL ROD DRIVE t.lJVE
ABNORMALLY R:>D DRIVE 1...--~--.ilI~I~----1 c::IFUE~*~L~a~iA.~'1~N~EL- RJEL afAN:-JEL A LOOSE OB- II'lI:cn~N-=:ITR:>~L-~R:>]D,...
.----....0"'""""'----1 INtAR Q)~TROL NEAR COATIllL JECT Ei~TERS BEC(}.fES r ROD \'b\RPS ROD SHIFTS QIA.'OO:L A.~D DISfORTED U..WETECfED
~ ~ LOCATIU~ BLOCKS IT FAILURE 10 IMECHAi~ICAL OPEAAl'OR OPERATOR QJUPLE illN1IDL FAILURE L-J IGNORES A.fY CamlL"fED IROD m mTVE lHE DRIVE SYMPTCM OF WITI1DRAWAL Q..r------I UN<XXJPLING 1 TESf FAILSt-1 I--;:;;;::::~::I;:_ _o CONTROL ROD NEVER muPLED LL'1E l.w..fU,~CfIQ\j COLLETT FL-JGERS CN+1ED IN DRIFT ALAA\1 :>1af OPERATTVE I
WITH CONTROL EXTRACfIo.~ IEXTRACTION OF (lIT J.1()S [}N I~---~ l RODOOVE OF M CUT bUT OF SEQUENCE POSITIo.~ L~DI -'IOPERATOR FAILS' OPERA11JR CATJR ERRD.i- 1m TEST FOR IG.'iORES ~
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MOCHA.ileAL 1
MEOiANICAL OF S~UE:~CE Co.'1TIDL ROD
~ONTROL ROD DRIVE loURING STAR1'UP 0---------.,
~~RA~L ~:::.~ FI:'JGERS1 ":S- KE~-WE:. . .ID-L.- _-:"- - - -'-~ -~-Ip-J~-~'iF~J; I ~~Q~.~;F DRIVE AT 1
FAILURE OF TIfE CO~TROL POWER WI1HDRAWAL (X)LLETT Ron SIGNAL PISfOI'J S /SPUD Q
EOU,Q,-
PRESENT STUCK
- {EED PROPER SIG'JAL IDl) STUCK IN DECDUPLE POSITIO.J BINT LOCKI~G PLUG
~=--_--Io 1 r------~
J ALL SIX SPUD THREJ\IYS O:J Ill~DEX 'lUBE COUPLING -rnm'l{OL ROD ATTAaIM5~T
~1"rrOlES .Jar RECEIVED FINGERS CCUPLLJG BREAKS SOCKET VELOCITY OPERA1OR ron WOImI J IJ W&MG BY REED BREAK SPUD DISE'J- BREAKS LIMITER WELDS FAIL SELECfS A'J MWIMIZER LOCATIO.~ SWITaIES GAGED CASTL'JG FAIU:; CUT OF SEQ. PERMITS EX-
~8~
I CD.HroL roD TRALIIm OF SELECfED CO,'J'TRi:1L roo ron CONHOL SEQUEN-CER SYSTEM PERMITS EXTRACTI 1::1>1 OF REED ~"WITaI REED SWITOi REED 5WIT(}f I SELECfED CONfROL RlR POSITIOiJ FOR RED LIGHf FOR OVER- I ROD I
LOCKL~G mUPLLJG I
SPUD L~DICATIo.~ OF LOCATIO-J 48 FAILS CWSED uN WCATIm 48 FAILS CLOSED TRAVEL FAILS OPE>1 BA,\lD BREAKS SPUD U'JSCREWS I TIiREAffi STRIPPED o Means all inputs must be present for the result to take place.
Means only one of the inputs nust be present for the resurt. to take place.
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT FAULT TREE MODEL OF A CONTROL ROD STUCK IN CORE READY FOR A DROP FIGURE J.4.5
)
ROD STUCK VE.S ROD DROPS Y£S COL.O ST~RTUP \(~~
(8 )( IO-I!5) ~ ( I. 0 )~. l 10*9 .1'10- 5
) \NO HOT STARTUP "e.§ @
l ~O 18 (8" 10- ) ( 7 " 3 lO*. Vl:~ ~
( .114 >\NO PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT REACTOR STATES USED IN THE ANALYSIS OF THE CONTROL ROD DROP ACCIDENT FIGURE J.4.6
- IlOD IlOllI'II ftUlCIft til MIl DIOP IICUIl TDIl (lie)
PlAIt
)U~ call. .
1lO. It, PUlL 'IllS 15'"'
PAILIII ,I0Il 0' 0CC1IUDCI*
(1.42111110. 31)
(1.UllxlO* 36)
)415 call.. 1200 (7 ..lIalO:~~)
(7.111110 )
>425 call... 1150 n , 5I1alO:~~)
(1.5111110 )
)425 call... 1460 (4.93xll(~~)
(4.931110 )
375 call1lll 1075 (3.241l10:~:)
(3.24.10 )
425 c.l/"" 1435 350 call... 1035
..25 c.l/llll 11115 (.395xlO:~:)
(.3951110 )
350 c.l/... 730 (2.5.. tO::~)
(2.5"10 )
400 call... 800 265 c.l/... 440 (1I."10:~:)
(11."10 )
750 (2.5RIl1O::~)
~1ih~
310 call...
(2.511xlO )
270 call. . 410 (1.71l10:~~)
(1.71110 )
(.655) (.915) 225 call.. 375 160 call..
ItO c.lI... 100 135 e.l/... (0)
(.726)
(0) 115 call,,", (2.4xlO:~~)
(7.4xl0 )
-::r~:::":~.::~:: ~'=-=~:~~~l"\;~':~*l.laer 1Ia1, aM r...wr ......r R.fera to 'ro.....Ult' witll PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT PROBABILITY ANALYSIS OF CONTROL ROD DROP ACCIDENT FIGURE J.4.7
PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 UPDATED FINAL SAFETY ANALYSIS REPORT OFF-SITE EFFECT OF ROD DROP ACCIDENT FIGURE J.4.8