ML20127C048
| ML20127C048 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/16/1991 |
| From: | Beckner W Office of Nuclear Reactor Regulation |
| To: | Chlenjak J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20126H006 | List: |
| References | |
| FOIA-92-267 NUDOCS 9109200206 | |
| Download: ML20127C048 (40) | |
Text
{{#Wiki_filter:. of a < t; f 5, g "['DochbtNos.J50413; and 50-414 MEMORANDUM FORi~ Jack Chlenjak,--Chief Operations Program Engineering Branch Division of Reactor Safety Region 11 FROM: William D. Beckner, Chief Risk Applications Branch Division of-Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation
SUBJECT:
CATAWBA GENERIC RISK INSIGHTS FOR SHUTDOWN RISK INSPfCTION On the basis of your recent request, we are providing you with the enclosed inspection guidance for.an outage team inspection. The inspection items'were: selected on the basis of the PWR Generic PRA insights study and available-shutdown risk study results. As you are aware, regulatory requirements in this area are limited and the. inspection scope is beyond licensing require-ments in many areas. Consequently, it is recommended that the inspection be limited to a fact. finding audit rather than a conventional team inspection activity. The enclosure is divided into four parts: 1. Pre-inspection discussion items 2. A brief summary of two-recent events .3. A brief summary of shutdown risk studies 4. Audit / inspection scope + We welcome an" comments from you and are looking forward to interacting with. -4 you and o . members in order to enhance the inspection process. o$h$$$ojjg Original signed by: 9fo ,f William D. Beckner, Chief p 4 Q\\h Risk Applications Branch f Division of Radiation Protection: M and Emergency Preparedness Office of Nuclear Reactor Regulation- ' Enc 4 owe. As stated DISTRIBUTION p 'FRussell, 12G18 SEbneter, RII J p , Qq,,EJh .FCongel, 10E2 _AGibson, RII. .MIh g , pf; WBeckner, 10E4 KCampe Elmbro, 9Al JChung y MCullingford, 12G18_ Decket Files 9 g*L / BGrimes, 9A2_ RAB-r/f GHolahan, 8E2 RAB Chron yf2 3 DFC.
- RAB:DREP:NRR
- SC:RA :DREP
.. :.... 1u)g......:..............:.............'::............ 2BC:RAB:D ((g NAME
- JChung:b
- KCam
- WBeckner
......:....f........:.............:..............:..............:..............:..f. a.... DATE 309// /
- 09////91 09//$/91 D
z RECORD COPY-Document Name: PRA TEAM INSP DRAFT jgfgr
3 + n-3.t i, .e (., 6 t~. -September 16, 1 w1 'y Docket Nos. 50-413 i and 50 414 MEMORANCUM FOR: Jack Chienjak, Chief Operations Program Engineering Branch Division of Reactor Safety Region 11 1 FROM: William D. Beckner, Chief Risk Applications Branch Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation
SUBJECT:
CATAWBA GENERIC RISK INSIGHTS FOR SHUTDOWN RISK INSPECTION On the basis of your recent request, we are providing you with the enclosed inspection guidance for an outage team inspection. The inspection items were selected on the basis of the PWR Generfc PRA insights study and available shutdown risk study results. As you are aware, regulatory requirements in-this area are limited and tM inspection scope is beyond licensing require'- ments in many areas. Consequently, it is recommended that the inspection be limited to a f act. finding audit rather than a conventional team inspection activity. The enclosure is divided into four parts: 1. Pre-inspection discussion items 2. A brief summary of two recent events 3. A brief summary of shutdown risk studies 4. Audit / inspection scope We welcome any comments from you and are looking forward to interacting with you and your team members in order to enhance the inspection process. Original signed by: William D. Beckner, Chief Risk Applications Branch Division of Radiation Protection and Emergency Preparedncss Office of Nuclear Reactor Regulation
Enclosures:
As stated DISTRIBUTION WRussell, 12G18 SEbneter, Rll FCongel, 10E2 AGibson, Rll WBeckner, 10E4 KCampe Elmbro, 9Al JChung HCullingford, 12G18 Docket Files l BGrimes, 9A2 RAB r/f-l_ GHolahan, 8E2 RAB Chron .. :..... &Jg iBC:RAB:D OFC
- RAB:DREP:NRR
- SC:RA :DREP NAME _:JChungsbw
- KCam s
- WBeckner
......:....h........:.............:..............:..............:..............:............ DATE :09// /
- 09////91
- 09//$/91 0FFICIAL RECORD COPY _
Document Name: PRA TEAM INSP DRAFT
n -- 5<' ( _G,.- ERE-INSPECTION DISCUSSION ITEMS WITH LICENSEE o IPE AND PRA INSIGHTS ' Progress of IPE/PRA study and applicability, if [ available, to S/D conditions.- Identification of risk during transitional (heatup and cooldown) operations, shutdown, and outage. o AWARENESS OF RECENT CONCERN ABOUT-SHUTDOWN RISK GENERIC LETTER 88-17 i Recent events Shutdown risk study: Seabrook, Zion and French PRAs NUMARC Initiatives -o ANY SPECIFIC CRITERIA FOR SAFE CONFIGURATION " ENHANCED" CONFIGURATION _(CONSERVATISM) " MINIMUM" CONFIGURATION Normal and Emergency POWER SUPPLY and other SUPPORT SYSTEMS: TS VERSUS-ADMINISTRATIVE CONTROLS o VOLUNTARY ENTRY INTO LCO PRIOR TO SHUTDOWN-1: l Any TS requirements: MANAGEMENT PHILOSOPHY LCO MAINTENANCE. PHILOSOPHY JCO PRACTICE L-o IDENTIFICATION OF IMPORTANT EVOLUTIONSLOF OPERATION-DURING-SHUTDOWN AND OUTAGE Identification-of'IMPORTANT systemsland trains during each-EVOLUTION of_ operations (eg..-Mid-Loopj)_ Requirements, including'TS ~ Administrative commitments beyond TS'and license. conditions i: - o OUTAGE MANAGEMENT 1. -PHILOSOPHY-(eg. Mind set that S/Dils-low risk) PLANNING' IMPLEMENTATION: ORGANIZATIONAL INTERFACE yg q >W--- -,e wa u
,a (w CATAWBA RISK-BASED INSPECTION OUTAGE MANAfd2iENT AND SHUTDOWN RISK Prepared by Risk Applications Branch, DREP, NRR I.
SUMMARY
OF EVENTS A. LOSS OF RESIDUAL HEAT REMOVAL SYSTEM, Diablo Canyon, Unit 2, April 10, 1987, NUREG-1269 Generic Letter No. 88-17, October 17, 1988 : LOSS OF RHR P'JMP OPERATION DURING MID-LOOP OPERATION o Unexpected drainage of the RCS leading to fully developed vortexing and subsequent loss of RHR RHR pump, followed by recovery delay for approximately 1.5 hour. o Anomalies of Reactor Vessel level instrumentation o containment Integrity: Equipment Hatch removed; Steam Generators Manways removed; Nozzle Dams o Thermocouples decoupled for removal of the reactor vessel head o Procedural deficiencies on RCS draindown and mid-loop operation ; Abnormal procedure not included mid-loop operation ; procedural adherance o Planning and Coordination of work activities: control of Outage Activities ; work coordination during the event in the control; room ; lack of training. B. VOGTLE UNITS 1 AND 2, LOSS OF OFFSITE POWER WHILE IN MID-LOOP (UNIT 1) AND REACTOR TRIP (UNIT 2), MARCH 20, 1990 o No TS requirements nor backup power supply.Two of the four safety bus power supplies were on maintenance during the mid-loop operation: planning problem. o Station staff has no effective control over a fuel or lubricant truck in the switchyard. o Diesel Generators Reliability: Significant large number of failures occured on Calcon jacket water temperature trip sensors.
.I C
- s' II.
SUMMARY
OF SHUTDOWN RISK PRA A. ZION NUCLEAR PLANT RESIDUAL HEAT REMOVAL SYSTEM PRA a. OPERATIONAL EVOLUTION FOR SHUTDOWN 1. Plant shutdown y 2. Draining for Refueling or Maintenance 3. Filling for Refueling ( 4. Draining cavity after Refueling 5. Refilling the RCS-after Refueling or Maintenance 6. Cold Startup b. TYPES OF OUTAGES 1. Refueling Outages: 1,2,3,4,5 and 6 2. Drained Maintenance Outage: 1,2,5 and 6 3. Maintenance Outage with RCS Full: 1 and 6 c. INITIATING EVENTS 1. LOCA 2. Loss of Cooling Accident (LC) 3. Cold Overpressurization Accident -l B. SEABROOK STATION PROBABILISTIC SAFETY ASSESSMENT AND SHUTDOWN / REFUELING OUTAGE RISK INSIGHTS a. Shutdown risk may.be comparable to at-power risk b. Shutdown risk can be significantly reduced with low cost modifications and administrative controls, c. Dominant risks:
- 1. Loss of RHR at reduced inventory
- 2. Loss of Coolant Accident d.
Numerical results less important than for power . operation studies: 1. Greater uncertainty because of the importance of operator actions 2. Large variability in risk due to changes in RCS configuration
( e t ~ Risk important configuration during_ Refueling e. Outage 1. Risk is high when RCS inventory is reduced to vessel flange before and after refueling 2. Important maintenance activities are identified 3. No significant risk conditions are identified for spent fuel due to large water inventory and lesser susceptability of pool to external events C. PROBABILISTIC SAFETY STUDY OF REACTOR UNIT 3 IN THE PALUEL NUCLEAR POWER CENTRE (1300 MWei a. The annual core damage frequencyis 10E-5 per reactor year, of which 6.1E-6 (56.5%) and 4.7E-6 per(43.5%) reactor year are contributed by the states during shutdown and at power / hot shutdown period respectively. b. Core-Damage Frequency by Shutdown Operational Modes (as percent to total shutdown CD frequency): OPERATIONAL MODE % CDF POWER / HOT STANDBY / HOT SHUTDOWN 43.5 RHR SYSTEM CONNECTED ON SHUTDOWN 5.5 PRIMARY SHSTEM FULL / VENTED; RHR 19.5 PRIMARY SYSTEM OPEN; RHR 31.5 _.ma.h-~ _-_m______--___.____________.__________________-_____________._.______._____.-_m- _________-__m Aw
~ >, O
- .. n *,:
?"k q C. Initiating Events 1 SHUTDOWN RISK-INITIATING EVENTS PER REACTOR YEAR ~ LOCA 513E-6 l ATWS; PRIMARY SYSTEM TRANSIENT 6.7E, SECONDARY LINE BREAK; WATER / STEAM-5.7E-9 STEAM GENERATOR TUBE BREAKS- - 1'. 2 E09 LOSS-OF FEEDWATER 1.0E TOTAL LOSS OF HEAT SINK-3.3E-8 LOSS-OF EMERGENCY DISTRIBUTION SYS. 4. 7 E-8 -- TOTAL 6.1E (LOSS OF RHR NOT INCLUDED) -III. AUDIT / INSPECTION ACTIVITIES A. Administrative-control and outage management B. Outage Performance Indicators C. Identification'ofLoperational evolutions:and. l potential risks l: D.
- = Operational' evolution versus plant-system configuration-L E.
- Operational evolution versus(electrical-l::
distribution-system y -F. Operational evolution versus adequacy:and j-availability of. plant ~ instrumentation
- G.
IdentificationLof: Critical Path Items:itesting, R . surveillance, Inservice,:and maintenance i. H.- ' Personnel training, procedures,. requirements (e.g.,a L. TS).andJcommitment IJ ,,n
-M . ~.. - 4, A. ADMINISTRATIVE CONTROLS AND OUTAGE MANAGEMENT 1. Administrative control program for outage management o Administrative control procedures established o outage management program established o outage goals Safety and ALARA goals Configuration control and criteria Modifications Regulatory requirements Milestones and timing Project scoping Budget o organization and task responsibility o Interfacing between various organizations 2. Planning o Planning input Lessons learned Method of determining activity priority Regulatory and safety concerns o Outage scope. Operational Evolutions Cold shutdown and cold stratup Draining Mid-loop operation Refueling Draining cavity after refueling Refilling RCS o Outage scope: Critical Path Items Refueling Steam Generator work (PWR) Turbine overhaul IST/ maintenance / testing / surveillance Modifications o support Training Equipment, procedures, materials, etc. Services, contractors, communications, etc. o Readiness: Operations Training, mock-ups Procedures: mid-loop operation, alarm responses, emergency, communications Tagging, administrative controls Configuration controls: backup / redundancy / power Work requests, system alignments Interfaces with various organization o Readiness: Outage Tracking of milestones 50.59 packages Service, contracting, procurements
^ t' 7-(Readiness: Outage, continued) Preventive maintenance and calibration Job controls (tagging etc.) Work priority / duration / resources ALARA review Temporary procedures and special plant conditions TS changes or relief Record management: storage, QA, classification Contingency plant for high risk activities Risk analyses and applications 3. Scheduling o Details and paper trails o Document controls and interfaces o Prerequisites o Activity coordination o Review and approval 4. Outage activity and control o ANSI /ANS 3.2 guidance o Testing / surveillance requirements and results o Progress monitoring mechanism and controls 5. Outage Program Evaluation PRE-OUTAGE o Accurate schedule input and adequacy o Timely release of revisions o Current information included o Milestones and engineering supports o Equipment preventive manitenances o Materials, equipment, installation adequate o Management concurrence adequate distribution of schedule o Appropriate training received OUTAGE o Schedule revisions issued timely o Updating and implementation of' work progress o Priority changes and resources appropriate o Reviews timely o corrective works prompt o Management awarness of plant status I l
. ; : :. n a ;. m - t' POST-OUTAGE o Documentation and review complete o Lessons learned documented and reviewed o open items reviewed and closed B. PERPORMANCE INDICATORS DURING OUTAGE 1. Management actions and reactions 2. Variation of outage schedule duration 3. Unfinished works: changes in scope and rationales 4. Adequacy of 50.59 packages 5. Adequacy (or changes) of resource allocation 3 6. Rework and rotests 7. Lack of materials and documentation 8. Conflicts and inadequacy of interfacings 9. Closecuts 10. Staffing and planning 11. Contamination and radiation exposure 12. Personnel safety records 13. Total planned versus actual labor hours 14. Lack or adequacy training 15. Equipment availability 16. Nonconformance reports C. OPERATIONAL EVOLUTIONS AND POTENTIAL RISK 1. Identification of operational evlolutions by; o Outage purpose: Maintenance, refueling, others o Nuclear Instrumentaion o Core heat removal o Reactor vessel water inventory l
y f ^ '(operational evolutions continued) o Fresh and spent fuel manupulations o Electrical system and power supply o containment integrity o RCS status o Availability of instrumentation, interlocks, Safety systems 2. Transitional operations o Appendix G curve recalibration and relief valve setpoints o Cold shutdown. cold startup procedural adequacy o Adequacy of training o Adequacy of system / electrical power backup / redundancy 3. Residual Heat Removal System Operations o Low Pressure Injection mode o Low Pressure Core Spray o Shutdown mode o Recirculation / condensing mode o Vulnerability: Interlock, suction MOV, discharge, heat exchanger, service water, manual operation D. OPERATIONAL EVOLUTION AND PLANT SYSTEM CONFIGURATION 1. Configuration Management and Control Criteria o Risk-level,-accumulated risk o Public health risk (PRA Level III) o Core damage frequency (PRA Level I, IPE) o Control function unavailability-o System unavailability o component unavailability o Human reliabilityL 2. Operational evolution and minimum system configuration o " minimum" versus " enhanced" versus plant practice o Identification of backup, redundant train, system, and component: risk importnt system / component / human action o Mid-loop operation and basic event identification (fixed versus non-fixed nozzle dams, vent path) o Refueling operation and basic event identification (Indian Point 2 event) o Abnormal / emergency operating procedures o_ Training o LCO-maintenance during shutdown /startup operation
~ ( u,, (2... system configuration continued) o Potential risk: LOCA, primary system transients, water / steam line breaks, loss of RHR, loss of power o Accident mitigation: Forced feeding, feed / bleed, boiling, containment isolation, RCS inventory recovery E. OPERATIONAL EVOLUTION AND ELECTRICAL SYSTEM 1. Identification of electrical distribution system alignment during the shutdown operational evolutions 2. Regulatory / licensing requirements on electrical power system : minimum requirements 3. Plant practice versus minimum / enhanced power system: 1 EDG, 1 offsite, 1 battery, 1 AC, 1 DC bus-buses from inverter 4. Variation of the electrical distribution system during different evolutions of shutdown operation 5. Availability of " protected train" for shutdown operation and S/U transformer 6. Availability of automatic electrical controls: ie., load sequencers, undervoltage relays 7. Availability of manual controls B. Off-normal alignment during shutdown operations: backfeed, procedure; analyses of off-normal lineup 9. Maintenance activity: " protected" power division 10. Provisions for Station-Blackout l F. SHUTDOWN OPERATIONS AND INSTRUMENTATION 1 L 1.. Identification of all.available intruments during various evolutions of shutdown operation 2. Identification of necessary indicators and l instrumentation dt ring each shutdown operational evolution 3. Interlocks and associated instrumentation
- i-(F. Instrumentation continued) 4.
Identification of temporary instruments and their adequacies (i.e., procedures) 5. Calibration records: "As Found" versus "As Left" 6. Redundancy of indicators and instrumentation 7. Availability of power source G. IDENTIFICATION OF CRITICAL PATH ITEMS 1. Steam Generator Works o Planning and procedures o Nozzle dams o 50.59 modification package o System lineup and operations o Potential risks and risk assessment o Radiological aspects 2. Turbine overhaul 3. Wish list /PRA and critical path items i 4. Refueling 5. Testing /IST/ Surveillance o Appendix J tests o Post maintenance testings o TS Refueling. tests ~ o IST requirements o Re-start tests : control rods / friction tests, etc. o Calibration of instrumentation (inclusive of logic tests) 6. Contractors,_ bench tests, in-place tests, off-site-tests H. TRAININ
G. PROCEDURE
S. REOUIREMENTS. GOOD PRACTICE 1. Availability of shutdown event simulation, mock-ups, training programs 2. Availability of shutdown operating procedures 3. Training on shutdown accidents or events: awareness,_ mind-set
~ (.. F' ( H. Training, etc. continued) 4. Availability of AOP, EOP, and training proram, Hitigation operations 5. Availability of administrative procedures which may exceed the requirements; good practices IV. AUDIT / INSPECTION DOCUMENTATION A. Document facts ( not opinion ) D. Do not speculate or niike recommendations C. Clarify requirements versus commitments versus good practices D. No consultation ~ E. Findings must be supported by documentation and facts F. Mission is fact findings
4 ,1 c 6 4 - r First Refueling Outage Review j l r Relative Risk vs Time After Shutdown and RCS Inventory l i i j l i L l* i l' *.
- 4,:
f REACTOR CAVITY. FUEL OFFLOAD .e %, g. ' M,
- tv.
- Q
- fi'l ,.
'C > \\ ,l g . gg e,. 7 -4 t 9 s.,
- i. ; ['.j -
f { 7((2, ?-I. 5 m
- ",3
[
- :p:%.=L i'): -
~ 3, g. ...f ,.r 3;p:
- 7.fi y$'nk;; >:'),$ f h ' ~. *
.g a ? O '-'E?L y9 t - 1 I RC5 kwentory ' _G - h u,- y s: n n ', A ", f.<j'g og :p,, 9., .. ;(, ,O <r-Re{ative RI3K 13 4-
- 3. <,,, z.
u. ,;}t_ a- .sf ;? ,r:7-tt. 't bf> .4' l
- Q, sG; RANCE
'. ;s e -q l 'l-s'? PRZR' PRZR. L. FLANCE
- A':
\\ O 4 8 12 16 20 24 28 32 36 40 44 48 52 56 60 t l t Days After Shutdown l l New Hampshire Yankee i 1
h l STEAM [s0 ~ l ~ CENERATOR NOT _\\
- = : Quxt:::::::::
AcconULATOR l3 COMMECTIO l \\ / ar = l L "E ntAcron n cgy o c,RC t ca?5gER {E REACT VESSEL l t
r RN REACTOR COOLANT SYSTEM.. l s,eAn t-3 days ~ \\ ((h3. CENERATOR f gpg i
p......._.._.._.._
7 ACCUMULATOR CONNECTION i 1 t l l. j , n i b, NOT [ 'COLO "3 '"f j O O-a f e i q.. ljk (11 f HEIR ll I. 1 l } MOT i p i ' 'l l' [ LEC REACTOR j COOLAMT i, l l1T CORE ) PUMP p CROSSOVER PIPE 4 t 1 4 c { " LOOP SEAL" e l r s 1 l l REACTOR id l f J 'lf. VESSEL 1 i l-c l l'
NN REACTOR COOLANT SYS T Eti-r i sTEnn t-3 days + 15 minutes ~ i CENERATOR i . / Loss of RHR I r r ( = :: =::=:=.- -- u.. _.. __.. _.... - l T L' ACCunotaTOR CONNECTION p jlm l' i ) NOT i f COLD LEC l O O ~
- ~
j 2 ' p (ggg i HOT LEC REACTOR C00LawT l PUne CORE l CROSSOVER PIPE g j -Loor SEAL" i i REACT i VESSEL i i i t i i [ 9 i
1 1 4 t t, 1 I @N Yj w % :.. e o d, s +l. #wh ^ t w[ b. V - 'e'P84 6= [w_
- z. ?> ~.
s4+ ~.~ t a t J, = ta w >.;17 f 947
- .s-s,,,-
'g .# t. s w w... r.. n. :. 3: .v.. e- . s-n v.%r w o n m.g.y,,a..w; a%w. s y ym n<w m,,=,,=,,=..c.,'. 9' ~ w. 4 ~ ^' e, . % 2t .d = ' .u .- J f. m,, e +.. 4, 4 ,..e n. Wi,W,m s , ~,.., 9-t + 6 1,.(n-a w- ~:.0 d . Ag, u 4 u p =_ - - Ap : aa fe.rmeme. y. un o g,',, - o r j c-e 3 r' m.,,,,,,,,,, E 7 fD.'". , O-O t ."="'c
- ,""* 4O
.N L 9 ~ m 0"," ! ~ ' [ a====' ,m m, w./s oc M b 3e [3, s; +c. - - 1., ,y. y '. p. p 'g..t. sg
- g*-
.p'* m'. 2 ,y w v j C 3 ~ eetstse ' ' ~ a:rneue
- W-Q,. y 7 4.!
j ,i n '; me= a + ,, - p,' 3.y,. , _ _ _._ sc= m y ~. ms y Cg 3.@4.L7 f g,eits e*ve M:t acnemas*on i .m 'a w e,
- m. arremmamen
~ y 3m< - : x e : >
- e..
4 e sxy.. n, ~m ,.w. J
- 4. 7 p ;
m .~
- ; b~.w*
'w j Aae%D:t % H. R d.m ~p = M m. g s c a 7
- m. O m
w ~.y ' t ?-Q. i w s. ' n. :,
====== g-O. g ~5.. m.3; : b -m, _.
- A '.
>y
== 4 .. 4 w.,' g%g j ; e j + 4
- 7%p a u en
=
g '.4 %*'9 %3gp .f g. .w=, e.. o =.. h. m.
- 4.,
~ w w J e v v-. t i p.a,r g e j wa*<:nn&"w%f 3 ';; l ?, d :Y Q, '", a ., Q,.. s.,.. r.- n. c%.cs x my, y, . : i f,., - L hn.WG kp:1. +. 4 r 4s n m.f ;, 'm o ,. j
- y
- p p%.y!!. > j p:f:p (.J'> M t{g-pa pyny,e..
q, w ,t
- c j A g-A FA6 rg;' QE,..];g A
A Dryg gqq" t j .m A >g,y., y aca'se {--e ac.'se cutsaswa.' ' i '7 7 .X U' g ; j - s s ~ 4
- m.,.p
- ;. ~ ^s~ e 6 -w.-.g@ .___a-c. , J. et. c '.jy:j, c' 'le ; ; c%Jl @y, +er=..;'. .s e, -
======== tes i y.fp =s uneam-p.v
===(, et. ~- [ w -e e ,.1 N 'N-1 tussescuum a y,h. a a N ~ l l su ,h fW. ,- j yn' '- [ ?D ...d P. ff l &gn 1 p p : e c @di@Q T lu n.p <W ; ~ d% iC v!S D-j."."," 4O J f, ^ .,O-. '. = = ( .e =e %n M.N.s L.s, - E ,_ms n s ~ -n .+.c +. > t e { &* %pY .s l kgC f 'r.. ~ y s-4 ), a 4 p.s d :M,..u;.v' 4 in 4, 5.#. 8 g m,".vj.. '[
- w y '
- :(. 1 ~~ ] w n m p n ; w N_ : J+ ..n v
- m. ;
o.c- ,- rw ..r.; w,m n 7 m ,=m,.,...imiep t m ,, G,7 x g'Q ^, -xov + a& 'fp z. .. =, - q ;.f% + e.. [ t 1 gg g;;. ' g~ 7. L emanmeseem l n: - p. ,-c e. t< y. -m-,-. .f. ,) ,J., i ,l w),. f. :_. ^ j jt '. Nrp
- 4.,,,,, ?
y _g - 4,,, .a p;.. - umeew > w.':.f.. s y o o c,r m.m u ec w. 7 e te... c s u ,} be ^ ^ i " ' ""'" M*, j t l 3 x ^&, a i f .t i Figure 3.1-3. Catawba Unit 1 Flesctor Coolant System Showing Component Locations
- j tif.I I
9 i-. e. -p 3+--
,' I ) ~ c .P. G RG R E D B B A A B D A A B A MA / / / / / / EO C Q Q Q C C C Q C C L A A A A A A A A A A yr E a C m R N U O m OI u STA M M M M M M M S RC R R R R R R R EO G G G G G G G a WLW W W W W W W ta O _ S S S S S S S D P U A B A A B A m E e G t A ~ s T y L 0 0 0 0 0 0 0 0 0 0 Ss O 0 0 0 0 0 0 0 0 0 0 V 6 6 6 6 6 6 6 6 6 6 t t n ne E an C l o o R p U oCm O S N N N N N N N N N N O W W W W W W W W W W rC R O O O O O O O O O O o E t N N N N N N N N N N cd W K K K K K K K K K K ae O N N N N N N N N N N et P U U U U U U U U U U Rce l 2e S N O r I 1 o T f A a C b O L W C C C C C C C C C C 0 a R R R R R R R R F R 1 taC .PE MP O Y V V V V V V 1 1 C T O V O V O V V O O V O M N M N M N R M M N M 3 e D lb I aT T L N E EN SS O P 0 8 A A B B E 8 A 1 2 3 4 5 6 V B A 6 7 M 1 2 3 3 3 3 3 3 3 3 S O C C C C C C C C H H H H R R R R R R R R R R R lll;!i i !Illl f .( lff r l1 ifIil Wi
- .. g!
j! 3 r ! r;i! ti! r! t!! 11 11 r!! e e i i t i i t f,,.,. f,,.x ~~ f o f C + 0 't g. g g! I-g g V t i i eo Of.i @h I E o e il oka k 6!' Y !e tir j t i3 _a
- n sie -
o]:l g a I s ( l} r, 5g ll n f r .- 3 rp -1 E Slarj g 4][sr j f y j ,I un w i i r ges i gas g 2 E a:
- ~
k l "l3 3 f's f I i D L L 5 -th' t$3 2 U 9, - f, 3l 2,. ][. < ." ][4- ~f i ,.(.5p.g ,,. (.5,.,; e e
- 1 Ogf y, e
oE,!o) ^ y-y e 7 l l g, a. g i
- [R_
fJ-I C g-e,l, ai 1 D,.; .c 5, u el 3 I ..j I OEI' OK j )- Oli OK i i og e s t.- i i ll.g m { lM ~ l .LJrTI 28 12/88
Table 3.3-1. Catawba 1 & 2 Emergency Core Coo!Ing System Data Summary ~ for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. TYPE LOCATION LOAD GRP. RH-1368 MOV SiPMRMB UNKNOWN 600 BMCCRM560 AC/B HH-1848 MOV MPENRM543 UNKNOWN '600 AMCCRM577 AC/A RH-185A MOV MPENRM543 UNKNOWN 600 AMCCRM577 AC/A RH-28A MOV HXRMA UNKNOWN 600 AMCCRM577 ACIA RH42A MOV HXRMA UNKNOWN 600 AC/A RH-658 MOV HXRMB UNKNOWN 600 ACIB RH-P1A MDP RHRPMRMA BUS 1 ETA 4160 ASWGRM AC/A RH-P1B MDP RHRPMRMB BUS 1ETB 4160 BSWGRM AC/B SI-1008 MOV SIPMRMB UNKNOWN 600 BMCCRM560 AC/B SI-103A MOV SIPMRMA UNKNOWN 600 AMCCRM577 AC/A SI-118A MOV SIPMRMA UNKNOWN 600 AMCCRM577 AC/A g* SI-121 A MOV MPENRM543 UNKNOWN 600 AMCCRM577. AC/A SI-135B MOV SIPMRMB UNKNOWN 600 BMCCRM560 AC/B SI-150B MOV SIPMRMB UNKNOWN 600 BMCCRM560 AC/B SI-1528 MOV MPENRM543 UNKNOWN 600 BMCCRM560 AC/B SI-162A MOV MPENRM543 UNKNOWN 600 AMCCRM577 ACIA SI-P1A MDP SIPMRMA BUS 1 ETA 4160 ASWGRM ACIA SI-P1B MDP SIPMRMB BUS 1ETB 4160 Bd6 AC/B SI-RWST TK RWST 03 ....m
~ Table 3.5-1. Listing of Components ControIIed by Auxiliary Shutdown Panels i Aumaliary Shutdown Auxihery Shutdown Auxihery Feedwater Pump Panel 1A Penel 18 Pump Turtdne Control Penel SDPNLRMA SDPNLRMB AFWTCPRM AFW Purry 1A StartStop AFW Purry 18 Start /Stop AFW TD Pump Start /Stop AFW Suedon Vahres AFW Suction Vahres AFW Sucilon Vahres 11A 98 7A 15A 180 A2 (Hotw,3r} 250A 3100 A4 (Upper Surge Tank) [ AS (C$T) AFW Dedierge Vahes AFW Dscharge Vanes AFW TD Dscharge Vanes 62A 468 540 58A 420 GGB 60 40 50A 56 44 38A NSW Pump 1A NSW Ptym 1B NSW Stypfy Vahre Cer*1 fugal Charging Purry 1 A Centri'ugal Charging Pump 1B 116A CCW Pump 1 A CCW Purg 1B 85B CCW Pump 2A CCW Purm 28 Deem Gen Atmos Steam Dump S@ Cat W e, Doric Ack! Transfer Purm 1A Doric Add Transfer Purm 1B SV19 CVCS Vahres CVCS Vafves 13 1A 1228 7 2A 1238 1 13A 1248 Steem Gen Atmos Steam Durg Trans Swind 37A 1250 Train A Autoh Oscharge Valve As gn Reset i 186A 2368 Train D Auto-S: art Dscharge Vahre AEgn Reset 172A 2?4 238A 309 - i 148 l. 34 r 309 CCW Vahes CCW Yahres 1A 28 3A 188 50A 538 51A 2280 230A 54B Pressurtzer PORY Valvo 03A Pressurizer PORV Vafvs 320 Pressurtzer Block Vahre 34A Pressurizer Dock Vahre 310 M. Pressurizer Hesters Pressurtzer Heaters E Desm Generator lealetion Vanes Steam Genera'or Isolation Vahres 1SM7 1SM1 j 1SMS 1SM3 r -
E i e Er a 58 ! ~I [ il t l I E ]1 8 a ri. ,1 = a = 2 p = - - m ..i Ii e e ii Ib ! ';I k 8 i i 3 E ]i i i L 5 = . J l' 'i 'g IrH. = = "l. =lli ~ I [i$ 0-8 n s* ..j l- [ =t E
- -t-g
-= 2 n v s 5i i w e n l '"~ --o---o-I Q l ~ l
== 5 l 7@ [ I ~1 g n C R 8 g = I ! 3 i. !l! v n C 'P-- _Ie ! !l~ l l -4 = = = i 5 n 3= i i k = o n 2 a I 3 g g 8 t -g. I n_~ e I J it = + I { 4 f -= = I = r; e [ g I t e e, 3-E -il [ l'! = L = ll I&! -i l = 4 4 42 12/88
r.c ur. m,.re <r <r j O t's Em I Y catTaI I e r9 e n ir m m n = = _ = =. _. ... = = ===m..=t t ira oc ne u a n eno y 3:13 fft.aC .co y am;S st.ps .00 T RIS ffUtA 1B iB U U 1F 8 m m m itsie etIng St wie m I -a I t. w rvac a, ~ ir u II tr 1r it o o ir ip"-- it ja .:e um. cc n,c .a:n== .,x,1.. .x.. acn-= cc.-m a -= u,-- I n ie n e . g gggr y .cc 7 are.<tr n o ---is n i, =- =.- MW 98TF71Otut D SO flea? rom la piacas Me tisE e SERFET CMeIIE ALK78FD at asrvtysE Tasr. km e Figure 3.6-1. Catawba 14160 and 600 VAC Electric Power Distribution System (Sheet 2 of 3 Train A) e e
.- p' = ,,.s, 'n u o Il i t m carts irm iim i .l tl .u. ,.. euc.ay -coo,,n. l "i 1r le is m m ir 2' i I ..cne. - - - .o. m- -- -- wn m -,w. l: t . TTW l i. l! 1 e ai n, n* e. It il ll 1: 4, A II II 11 ll 11 11 Il 11 If 1 ,,os ,,os
=
==u ,o. .,a tm, ~ n anDC Mwwe 11 Il ll ll ll ~ Il Il il Il 11 1[ IB ~ sec't_ spurasaties ogwywo sefut sonst gruncufMD 8Euesetsut amF.rrise.mmt e.so ftent sput e rsos egv asqE "DC 'N SGJuuN CassM a OstOaf msevM Test M.. m
- =
~ Figure 3.6-1. Catawba 14160 and 600 VAC Electric Power Distribution System (Sheet 3 of 3, Train B) e e O -49 s-- ~n mmy. w. n
d 8 9 g ~ O '8 g$ i I e w I A5 G k i ' P [ c - l i i - i
- --. Q a
ru e !!= I,. 1 a ! I g [g I d Y. - 3 }. ~ c ~ lij t-E 1 e iO
- i e
f i T E o + 8 2 g K I O i L I g 1: l--- [ i E lll
- je 3 -H i-*
e e m a_._ V.. c E o
- t ll=!
a g l-a- o s - -e-I g 1; j g e a 9 ll em E e e t D g p I i l T t, = [ I I -o-+-+ 1 y i l e a. g l o I l p l l'f,,,-*--*:{-- -l i _f' i W D l_,_ f{ e io l { 8 f. I _m 3 s l I 8 6
- t-f.
e -. t ' -g jr I _ g . [_... -+ t.. w en : n ~ 1 I E l
- 2.,{.~.
4 1 g n 1 ~ (,. g Y s 7-Q .s T .t . kj ~ ^ g_ ! ~L' f)f ..a cJ gi s ib 4 5 . a 33 1 o._ ! 9-ri _e. 8 g g-g 21 e l 1 i i ! c 8 = I p-I ns 1388
1 ==== l b i--l I r6 me m. s.v. o l.. 2 l 3 .....c g em tw. m um l . - x. m ~.: m m n ^ ., S " - - m m = = ;','J.,,, m e ;r=,,,,, oft 4 t I 4 tog osrw [ iv 6 n, - u o, n . ie e l l l ..e.,,<. t.c ,t. A ~ .4 ;
- 1
~ u e n a s e 4 n, - in t l I I i c.cc...,, i ~. 1-t .u.. m. m. m. ,t .t. ,1 - h 4P ir g tl-m e, 4 .It, it /, IB-** II 8 11 O O 11 ll tr see it.m isoc n.=c
x n.
.acnom wx *t.= wx n on
==
x '=
=x m .ix = t 4 4 A 6 I i..... . I .. u..,,, T O $37. g m. tM F m.C, sasses.,. %d .C -n e l . o. a n .cc.. .ce n.. =cnom -re n -re,e ocyt o so,te.T m es mw cue _, (per oreto n s== =a==vrwo--= we s.e, i arv wi ,y SG 8141 C.fe 8W E K38E D.7. peg (usF tes + 3 -m s. g m..~ i i i .s.c-3 Figure 3.G-2. Catawba 14160 and 600 VAC Electric Power Distribution System Showing Component Locations (Sheet 2 of 3, Train A) i m m
- +
e*
- - i
,.,[, . ~ ii4 sno i m<. t a c o 1 L i$ 1 t s ne i, n w. o ,.l m.- I p m m Co c i& 1 5' ,,l o 5 = g w i 1 n i s a i = w = 1 =.. 1 1 =. o m._ .m h = e eu S I 4i i9 s rt s vi m
- r. t s m
s m 4 ns mru nY e at t s e e n o ty y iC sun S t 4, a. epf s n n,? aaU. . Da u) M o E T s i 0 p m3 t t ,f bB . P E = wC s i e r t O.s n l.i sMt si t i aT*r t ia woy Dr ss p. T . s. S ,p e. r r i. ,I i$ s. m. of .a e ~ w3 ~ i y _.. Po c i. o. c3 o I I i t r s t e c s m ce o i$ eh a g l S E( i 1 I I i C A -1 V ,r 0 0 ,z i 6 d o l d + o 16 n a e j 0 c 6 o 1 I l 1 4 = 1 [ a i 1 r o c g a = s a B I 5 w b a . %mxss.f m.3,. - s v w m' j e = ll s i l x, o(m_.wy;i+m 7Q.:7 as. a . yI <,.= 1-t R . ;; ~ ?, .F a j..
- +
u b. y += i;1 1 C 9 . c n)ag.. : p y.e 'yL,
- m
= C y u a t as 2 , s
- [v
s j r. 8 sa-< i. >,wgm.%yy1 ,.g 3 1e, ,l e cT..- 1.- r A o,.e-s
- j..
u 7,.,. ca*. g . -4p r ~ , s.3, i F .p6c 3n J 1 aw .,;:,j; i. k
J., a A AA = M A, A m m &M AAas a,a4_a4wam m.- wmesm _a wam_ r_h_* imAWa.W--da_e h -hap.m---wm*44A- _RM.e- ' h w,J ,<W4-Ae r6 6,1..a 4, 3-.M,,a4hte 4 _,a.--- M ,L 5 I ,i b i i s~ p g g = m s ~ v e = = = B e lylt 8 t 6 ~- E y = g i I' y g -=- = m p g e I s S 5 ssl* i n EW Y e ~ = u g IrW E h s r - m-H s = g g! : T l i = V -0 S 1 E v - = = S y a,; s I S 'l VTs [l E ! I e t I a [ { i [5 vi _u =
- s. 4_
o r n_ $ Ag M E > l V y a E v e i + 3 j + s 5 h_ fl } r H gu j = +- o !El in 4 r -a E y = l I" 5 m I U = = 5 6 g e gt n = s 1 -i f l*a g a 8 I I! 0 w !I l ! 5 ~* b f Q g i g 4 a[g l!. M _5 r 1 = = = g V 8 8 E. nig s III 1 I W ~~~ 18: lIe I E s s!- y-r!! I s tim-E e = = - - ,.=_.- - -,_-_._ _.. - _,
e e m.mee + m~ *. - g gM_' M 0 0 E sW W (Q' D O I ii y af R lgI_r1ll} . 8 i b W I 3 h, E I s E W l h e d ._m t G v, E s -e = a a E W R 'xg. m I f- -e-E lP I 7-g- 8 ', - - - -s . 5, y e, u) w, s 11 W. C s [ Sr 1 js s _O J ! V)On V . ;j 3 = -r V r
- Sa*f s
- bIw, se r
m 8 [ ~ 4 I ~ 6
- - " ~
lr y y g p g r e y V B-y i B o ,v: a, j h hk .g C ~ Be t l L a w' c E ) f b
- b I
E h / E.- ,T n a 3 ~ g!. l' _~ $ P U$ l f y E }y ' il E $5 1 l v y -c v c w OO. g -*-6-_I ..p-e k ~*-
- k II 30 7
i F 3 gw j oi? Ub* m c. e a$ = 3 Sa 4 1 s m.c I N u) V v-g ..g. W le : y; N g3 .o s 4 a n
- -., (..
a. .+ 5 .m ~. -.,, g p i g- . k. 5 j. ,ej% a g ~ h . g +,. , y w h; 'J. - db ] ~e f 3 y {i - W Q g "y_ }.. O y l-:.m;.- I 1 a ..;4 s g s + - $ Rh;. 3 6 j.'4 ' ~ ~ 'r-yn s x-p3
- g.w
- I y
u. g -Q' _$. 6-g. s
- 5. f '. y
.?: x, y \\i r, y _ % n: r) s .=t t p 1 S@ u-= k ,;q s '3 (( 90 0-5 '3 <f-3'L i 3 ,.7 ' N/s: \\l 7""" 4 W 'i 6.' [15 l t h 8 5
- ' t" i
f h \\ l v_ O g 5};; . L ' 3.-J lgW "[ .cy ,,O: E mx JP' t n. 0 e y w" 7,, ;- MW U -, ~g< * * .c gs.p %.u,m,. m' G i s s e %v i .. r;,, c. _g AJ.' ,6 J. s J 4. g ":, e geG s s
- c 3
5 ..5}%(,, yih 8, -{( J [,j i,M s,' w g-, --.,m +. , u. 49 12/88
,..na~--.-a.u ....n. .u-sa.w..~n.u- .,>.as-nu.-ra=a~.-~.s~--... ,n.---~m.au--.a ..--s.+,.n.-- at ...,-n-n.. u 4 4 4 4 4 lj,1 = b yL a!lal-bl -l i v l i! { 18 l = = n = = = m l.8 E Eo! .l E ye g o. E w i E s a ) C 0 h n-l l l m@1 i m 65.s H3 v. an > g.-- y- - g
- 8
[ 8 i. a-g o 3 l8 !gt l bg --g N l ty w h 8 6 I* 3l1 55-g I E = s 4 4 _4 + ,,y,_ ..-n..-+ w " ' ' * ' ' ' ' * '~ ' ~ ~ ~ ~ ' ~ ~ ~ ' '
S L2 e e e.:. am .r t-x. . a a
- n eg e
g g '.. i ' ^ o -e 8 { U g, j m, % w,. , ~ ,.e c c _o n, ~ i,.. ,-a i"- n.7 <.. w ., -.,m s h'! g ' gh 0gs3 g . g < > p[ +. ,7 7 19 - - - l '7 t.d j y. 8 4 _._., J B 8. .s cH, v a s x n ,= = D[ ~ t, m =
- 2 N-E 3.
g o a ,v l y-in ', 0' g y ] J,s 4 p ..K >b) o ~, - > y 1 x p t m 4 w cu. E l F _c t,.. g e . S h. W ;% ti, I; E, s, m e 4 [ u 3 y-g g _e n. u g n s ~ "' cc 4 o g; 5 M D o x- ~.,. . j. o u .c E r.' 1, %gogg-p 1 c -<g _[ g C a yx x L e s-d-l l = + x c ~:,, :. : w n x L r $ ;a i,b h! ~ '., y p } $4 4 0 e 4 o y ' s-+ .V> ;; o 4 w O '.. - ' g od p; X / v .. n g s; w, .c _ [:. n.. +- i s 4 + s w s 7.,=" n,=2,# -. ,j" b g a = ki, ' m L e ,~.n. w . c, n ,, h,,:[, y,ng;$,hh ,g, w p. +g. y yyy
- g y
e [.k ~ h-( U [ k .- ' f-ijg e ( xbm:y 3 p ay n ..c MgWngs%pggy; :pgg@pga WfMd 15 wsw m n??,, Q g3Q (.* m -r%y 'q/7A @pr a4; .WW;ga 4 g o ma- [w. ; : .u m u i ky: ,j;y-V-f QR;;j Q.5 : l Q _7.... %;ik. (f y R ' f (' r. o i M mm:woma ;, a a.x 3-pW, y~hw J;n % v qwn nw
- w{,qq_w;e
- r? ?
w sa m .o. wm m s O nP".f M'lv W ~*- me .a -.#' 6;, g.bg;p.
- -J ee O g.
.ww. /4.QS"g r L . a -t J g' i ^ x W n w k M. .M..
- 4%. g w
~ :. &n",/e, e t 0,. 7 n + ,a .w ,4y m;w ~e am.- w>: < $ 4 .~ +u n m* -n - f ,N, A:+ 4 3g C+4:M
- m' Aa r m'. '. n*
e - 1g* ~ v r+
- n w
u W~; y.. }w i --- -g ~T ' m -eQQ 'lQ;,g} ^*,, Q t t 'V + ;y _ ~ %;*y y ~ JW, aMR M, MMsfM@W n &,r' T T[ - g V j is- , ( +- y w; w - m, w e V 6,3 py $ y1 % M w~;pgwpwtp y s,o ': m i n g w %, m tq w n * % m p p, 3 ;M..w +.,e,+,,., y ,.g* x, 4 g eIt:p ga<. ~ 3. ;? - w~p mmx ye. .u, y t r. ;;.c.e ;, + 3. 4. e g 4. s 9. s. gp> w3 gv #,. 4 s m y-op. y-a: 1 ( y c. -f y
- e q,
<c.n <.<,.a s .-.r s r m dm-- + 4 51 p D/88--
4- -4 6 g,A4. e e h e m., a 5 -ge4Wese
- e. gate.e 4 4 eue w k,hjui
= g,,,,,,,,,,,,,,,,,,,,,,, i = E l l l E N -< l i I 5.- n o E8 v l M a-y e v 0-I l 5-a h l m l r c e Eg / w .l!.' I 3 m D t e s h-m y Elll ,E 3 E I ln o 5l [ >-j,g-] il .a v o x g / y A ., o +- ll=e,lg.u-<l-j i y ~~ l ? =>! l1 5 8* l l ~ 3 n 2 a a 5 ld_ ,l 5 0 a53-Elgs . l u1 + e =y ksa ~jl / - f gI l g g [Lgj g-t. a a l .t .c e l-alltiin!! l!j gg !!'gl l
- 1. -
l
- g, j
.p ~. <,,,,,,,,,,,,,,,,,,,,,,e c 52 m
r ~ Table 3.6-1. Catawba 1 & 2 Electric Power System Data Summary f for Selected Components (Continued) { COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG. LOCATION LOAD _GRP TYPE TRANIETXE TRAN ASWGHM BUS 1 ETA 4160 ASWGRV AC/A TRANIETXF TRAN BSWGRM DUS1ETB 4160 BSWGRM AC/B \\ e k o 9 a La
-~ e<, L TABLE 3.6 2. LISTING OF ELECTRICAL SOURCES AND LOADS AT CATAWBA 1 & 2 POWE R VOL1 AGE E ME RG POWER LOUME LOAD LOAD COMP COMPONE hi SOURCE LOAD GRP LOCATCH SYSTEM COMPONENT ID TYPE LOCATON BAT TIE B A 126 EcsA BATRMA EP BUS 1ECA BUS DCSWGAM BATT1 EBB 126 DC/B BATRMB EP BUSIEDS BUS DCSWGRM BATTIEBC 126 DOC BATRMC EP BUSIEDC BUS DCSWGRM BAT 11EBD 126 DQD BATRMD EP BUS 1EDD BUS DCSWGRM BUS 1ELAA 600 AC/A ASWGRM EC MCCIEMAA AUX AMCC AM677 BUS 1ELAB 600 AC/B dSWGRI EP MCC1E MAB AUA BMOC RM660 BUS 1E LxC 600 AC/A AS M kM EP MCCIEWu Aux AMOCRM$77 BUS 1E LAD 600 AC/B M WdRM EP MCC1 EMAJ AUX BMCCRM%Q BUSIETA 4160 AC/A ASWGRM AF W AFW P1A MDP AF WPMRM BUS 1 ETA 4160 AC/A EWGRM CCW CC W-P1 A MDP $60AB BustETA 4160 AC/A ASWGRM CCW CCWP2A MDP 660AB BUS 1 ETA 4160 AC/A A5eCRM CVCS CV P1A MDP CHPMRMA BUS 1EIA itFs AC/A ASWGRM ECCS RH.P1A MDP RHAPMAMA E S1 ETA 4160 AC/A ASWGRM ECCS sip 1A MDP $$ MAMA BUSIEI A 4160 AC/A ASWGRM EP 1RANIETXA TRAN ASWGAM BUS 1E T A 4160 AC/A ASWGAM EP TRAN1E T AC TRAN ASWGRM BUSIETA 4160 AC/A ASWGRM EP TRANIETxE TRAN ASWGRM BUS 1 ETA 4160 AC/A ASWGAM SW NSW.PI A MDP NSWA BUS 1ETB 4160 AC/B EiSWGRM AF W AF W-PI B MDP AF WPMAM BUS 1ETB 4160 AC/B BSWGRM CCW CcW P1B MDP 660AB BUSIETB 4160 A C/B BSWGRM CCW CCW P2B MDP 660AB BUS 1ETB 4160 AC/B BSWGRM CVCS CV PIB MDP CHPMAMB BUSIETB 4160 AC/B BSWORM ECCS RH PIB MDP RHAPMAMB BUS 1ETB 4160 AC/B BSWGRM ECCS SbP1B MDP StPMRMB ^ BUS 1ETB 4160 AC/B BSWGRM EP TRANIE TAB TRAN BSWGRM BUS 1ETB 4160 AC/B BSWGRM EP TRAN tETAD TRAN BSWGRM BUS 1ETB 4160 AC/B BSWGRM EP TRANIETAF TRAN BSWGRM BUS 1ETB 4160 AC/B BSWGRM SW NSW P1B MDP NSWB DG1A 4160 AC/A ASWGRM EP BUSIETA BUS ASWGRM DG1B 4160 AC/B BSWGRM EP BUSIETB BUS BSWGRM MCCIE MXA 600 DC/A AMCCRM577 EP BC1ECA BC DCSWGRM b 55 12/88
l ,~ T ADLE 3.6 2. LISTlHO OF ELECTRICAL SOURCES AND LOADS AT CATAWBA 1 & 2 (CONTINUED) POW E R VO$T AG E EMERG POWE R LoukCE LOAD LOAD COVP COMPON E NT SOURCE LCADCAP LOCATON SYSTEM COMPONENT M TYPE LCCATCN MCC1EMxb 600 DC/D BMMCRM577 EP BC1 ECD BC DC5WGRM KCIEWG 600 AC/A WCAG 6W NSW43A MOV 677AB KCIEmi 600 DO'C AMCCRM577 EP BC1ECC BC DC4WGNA MCC1 E MAJ 600 DC/B BMCCRM577 EP BC1ECB BC DC&WG4M WCIEWO 600 AC/A NSWA 6W NSW 2&A MOV NSWA MCC1E WR 400 AC/B NSWB SW N$W44B MOV NSWB K C1LMAG 600 65F 6bF AF W AFW 174 LOV AFWPMRM KC1SWG 600 6SF $5F AF W AFW 175 MOV AFWPMRM KC)$mG 600 6$F $$F AF W AF W 178 MOV p's MCC2E W H 600 AC/B K C2AH $W NSW46B MOV 677AB r. T RAN1 E T AE 600 AC/A ASWG4M EP Bus 1ELAA Bus ASWGRM TRANIE TxE 600 AC/A ASWGRM EP TU$1 ele C Dv5 ASWGRM 1MN1ET AF 600 AC/B B5WakM EP BUS 1ELXB BUS bSWGRM ^ 1MNIET AF 600 AC/B b5WGRM EP BUS 1 E LXD BUS BSWGRM UNNNOWN 600 AC/A ASWGRM AF W AF W 116A ACV AFWPMRM UNNNOWN 600 AC/A AMCCRM577 AF W AF W.15A MOV AF WPMRM UNNNOWN 600 AC/B BMCCAM560 AF W AFW 16B MOV AF WPMRM UNNNOWN 600 AC/A ASWG4M AFW AF W 250A MOV AF WP MRM UNNNOW N 600 AC/B BSWGRM AF W AF W 310B MOV AFWFMRM UNNNOWN 600 AC/B DSWGRM AFW AF W.42B MOV ODH UNNNOWN 600 AC/B BMCCRM560 AFW AFW 46B ACV Di UNKNOWN 600 AC/A AMCCRM577 AFW AFW40A MOV D1 UNNNOWN 600 AC/B bMCCRM560 AFW AF W44 B ACV D1 UNNNOWN 600 AC/A AMCCRM577 AFW AF W4&A MOV Di UNNNOWN 600 AC/A ASWGRM AFW AF W-62A MOV CQi UNNNOWN 600 AC/B BMCCRM560 AFW AFW 8bB MOV AFWPMRM UNNNOWN 600 AC/A AMCCRM577 CCW CCW 66A MOV 677AB UNNNOWN 600 AC/B BMCCRM560 CCW CCW41B MOV 677AB ~ UNNNOWN 600 ACiB BMCCRM560 CVCS CV.10B MOV MPEN RM543 UNKNOWN 600 AC/A AMCCRM577 CVCS CV 19 A MOV MP ENRM543 UNNNOWN 600 AC/A AMCCRM577 CVCS U 252B MOV SiPMAMB i w f. 8
__--___-________56 12/88
) } i o, TABLE 3.6 2. LISTlHO OF ELECTRICAL SOURCES AND LOADS AT CATAWBA 1 & 2 (CONTlHUED) POWLA VOLT AG E EMER3 POWER SOURCE LOAD LOAD COMP COMPON E N1 DOURCE LOAD GRP LOCATION SYSTEM COMPONE NT ID TYPE LOCATION UNNNOWN 600 AC/B BMCCRM560 CYCh CV 2038 LOV &IPMRMS C UNANOWN 600 3C/8 BMCCRM!.40 ECCS RH 1368 64V GiPMRMB UNKNOWN 600 AC/A AMCCRMS77 ECCS RH 1649 LOV MPENRMS43 UNOOWN 600 AC/A AMCCRub77 ECCS RH 186A iMV MPENRMS43 UNNNOWN 600 AC/A AMCCRM577 ECCS hH.26A MOV HARMA UNNNOWN 600 AC/A ECCS RH42A MOV RNRMA UNNNOWN 600 AC/B ECCS RH 468 MOV Kr.RMB UNNNOWN 600 AC/B BMCCRM560 ECCS ShiOOB MOV SiPMRMB UNNNOWN 600 AC/A AMCCRM577 ECCS Si103A MOV $4PMRMA UNNNOWN 600 AC/A AMCCRM577 ECCS Sb116A MOV SIPMRMA UNKNOWN 600 AC/A AMCCRMS77 LCCS Sh121A MOV MPENRMS43 UNNNOWN 600 AC/B II.tCCRM560 ECCS $613SB MOV $4PMRMB UNNNOWN 600 AC/D BMCCRM560 ECCS SL160B MOV SIPMRMB UNNNOW N 600 AC/B BMCCRM560 ECCS $1162B MOV MPENRMS43 UNNNOWN 600 AC/A AMCCRM&77 ECCS Sh162A MOV MPENRM$43 UNNNOWN 600 AC/B BSWGRM RCS RC418 MOV RC UNNNOWN 60b AC/B RCS RC42B NV M UNNNOWN 600 AC/A ASWGRM RCS RC43A MOV RC UNNNOWN 600 AC/A RCS RC44A NV M UNNNOWN 600 AC/B LCWGRM ES AC.35B MOV M UNNNOWN 600 AC/B RCS RC468 NV RC UNNNOWN 600 AC/A ASWGRM RCS RH 1B LOV M UNANOWN 600 AC/A ASWGRM RCS RH 2A ACV E L NNNOWN 600 AC/B BSWGRM RCS RH460 NV RC. UNNNOWN 600 AC/A ASWGRM RCS RH47A ~. MOV M UNMOWN 600 AC/A AMCCRM577 SW DW 144A MOV 677AB UNNNOWN 600 AC/B BMCCRM577 SW NSW 225B MOV 677AB UNKNOWN 600 AC/A TW NSW 232A MOV DGA ~ ~ ~ " ~ UNNNOWN 600 AC/A AMCCRM577 SW NSW 28?A ACV 6T7AB UNNNOWN 600 AC/B 3W E W 2928 ACV DGB UN%NOWN 600 AC/B BMCCAM577 SW NSW4478 MOV 5??AB e, 6 2 51 12/88
j il L ErIl (( Is I M- . s I3 _ _ __Se-MO _j_ g i 1 I s l 4 XX I Y ]:]:> E I T= 3 i r y ei .I .I 65 ~I ~i h (( ', t [l e y g gg 8 8 a i 11 la j i -l, II I jI 4 I 8 1,! 1 _Ig ig l n
- =
1 [ j J,! i 8 03 1 g a s o i 1 Da oyl 1 ! e I n-1 i l 3 c t .I t + E Oli SX: D{j O{( O+ Oh'l DJi s{r g l 1 I l l I i k P P P M ll l N I, i i-Ses $1s-Its $1 f a E) E3 ' [i] 1GJ t i O!{f .OX{ ,OF OX {. 5 to fi:- T1: _.fi;9 'I= j ,c I I [ rt 5 .o g l
- ()g 1[ Ji g
g,A i g ^: y
- 5
,c> l g ~ .l l s f .e-
- 5.'
e: c4 l ^ ^ = i, u ^ i, e ( E c O]:a' . O][t g c ( S 11 = -}}