ML20134E336
| ML20134E336 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/03/1997 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20134E313 | List: |
| References | |
| NUDOCS 9702060167 | |
| Download: ML20134E336 (493) | |
Text
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urrestan} 3 \ DEFINED TEIBts of this section appear in capitalized type bold, A/ are applicable throughout these Technical Specificationsg a.), A. ,, l ([$esyseirealAcNosskbc M* h , 6 ACT10Il s be that part of a Specification which prescribesg p ures >ee -- under designated condi_tigns.m _
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AZIlt mlAL POWER TILT A T, pg 0 4 . Ihgenerated AZIMimlAL POWER TILT shall be the maximum ifference between the power in any core quadrant (upper or lower and the average r of all quadrants in that half (upper or lower) of the core divided the average of all quadrants in that.halLlupper or lowerts core. .2 T, - max} !< .< > - L1 l ' C11AlglEL CALIBRATIO11 f.9 y OM.)@cTannelA CilA181EL CALIBRATICII shall be the adjustment, as necessary, of the output such that it responds with the necessary range and accuracy to known values of the par er which the hannel sonitors. The L N mATIOli shall __ encompass ti F eha TKc1Fgthh safis alaser ansrrar me -- shal' include the CIIAIDIEL rum.sa . CalA10lEL CALIbRATICII may rformed by any series of sequential, l overlapping or total channel steps such that the entire channel is calibrated. W QSe yponeds, Cuc h e- s Seniors, t*larW,cld loyh [,< y) +,;p fu neJ,orst rcepcive al f> pee fom 4 hc ,pw a ,g/te .,1 j, G fa ,,c.LM, De OlA ANit CMIURaitou CALVERT CLIFFS - UNIT 2 1-1 Amendment No. 149 A3 GliN(p l ion o[ ins $ra m ed c lM nne(,5 w;)h y e ys b. a.cD n,a << s.1<+ m,r -su p ,as ,,, ,_,i,u, _,, sc, ,, _,3 casa ./ 19.<c norm a I ca I, b(dre , J de re me. in im /
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1 e co' h C a b b ^ l* 0 i l O l oaf A 1.s etnutn0Ns i I CRAlglEL CRECK
@ A CHAlglEL CNECK shall be the qualitative assessment of channel i OA. behavior during operation by observation. This determination s l include, where possible arison of the channel indication a status with other indications r status derived from independent ins at channels measuring the same parameter.
CalAlelEL FUllCTIONAL TEST dCb l h A CNAllREL FialCTIONAL TEST shall b
@ (s M o M M d s AIthe i ection of a simulated signal into the hg Thannel as closeincluding,alam
_ SPERABILITY to the nsor trip as practicable to verifyh. n iI#'Us 'l' 6 La functions. ca r ver LI a /or r Y ,0! Y (CONTAIgENTI RITY Q@% The means(.HANNiA af a. .rerics fkNC YloMAl. YiS of pr foi i c hanne / r +rpr s ery n4rer I, c so H,af a i
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- 1. CONT INT TY sha exist when: d"/'#a r dt ' ' # 4' 1 .1 All trati ired to e closed duri ccident j Cap e of being c1 ed by an OPERAB Containment I" " r l'*4 #1 d "'*'
Au tic Isolati Valve System.
- b. losed by man valves, blind an es, or de ivated 40 fxele 6/ *"'. f., jinu /hc j, ,
automatic y es secured in t ir c osed pos ions, i except for alves that are n under admi strative fa r c /,w (cl a re control pe mitted by 5 cification 3.6 .1. g
- 1. . All equi nt hatches are osed and seal .
.8.3 Each rlock is in c ance with the utrements f l Spe ication 3.6.1.3 1.8.d containment 1 age rates are thin the 1 its of pecification 3 .1.2 and 1.8 The sealing chanism associ ed with eac penetrat n (e.g.,wel . bellows or Og ings) is OP LE.
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! fc0g dnaar/ erad d _ [allhheway/rfloffromt reacfrcof C0ff ALTERATION *l 7 4- D fu.el,souaes h CORE ALTERATION shall be movementb4nie612(1In3of any component within the reactor or reachVNy vesse1~with the vessel head removed c o , fro / and fuel in the vessel. Suspension of C0tt ALTERATI shall not preclude completion of movement of a component to a safe sart n position. , c0RE OPERATING LINITS RE @ ThegE1PE is the unit specific document that
@ provides cyce specmc parameter limits for the current reload cycle.
, These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 6.5. Plant operation within these l limits is addressed in individual Spec ications. j DOSE E0UIVALENT I-131 ! DOSE EQUIVALENT I-131 shall be that concentration of I-131 j i
@t/3pc and isotopgram)ic mixture which alone would produce theofsame I-131.1-132.1-133, thyroid dose as the quantity I 134 an present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID.14844. " Calculation of Distance !
Factors for Power and Test Reactor Sites.' l E - AVERAGE DI5 INTEGRATION ENERGY 4
@ I shall be the average (weighted in proportion to the concentration
! of sum each radionuclide of the average betainand thegasma reactor coolant energies per atdisintegration the time of samp(ling)in MEV) for of the isotopes, other than iodines. with half lives greater than 15 minutes. . .; making up at least 9M of the total non-iodine activity in the coolt.nt. . 4 ENGINEERED SAFETY FEATURE RESPONSE T M h @fnTerval The ENGINEttED SAFETY FEATURE RESPONSE TM shall be that time from when the monitored parameter exceeds its ESF actuation , setpoint at the channel sensor untti the ESF equipment is capable of performing its safety function (i.e. the valves travel to their required positions, pissp discharge pressures reach their required values etc.). g/f Times shall include diesel generator starting and sequence loading delays where applicable. 6 ihe res,conce -f o'mc rnay be mensserecIby G ng .re o tes . 5 .sj ue.,lio$' over k po% f 9, or 40$<l SN fr .To 4h*f 4ke e else resja:x re fr%c is,-
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m enw e <ls i tX[ VERT CLIFFS - UNIT 2 1-3 Amendment No. 193 i Q Qn-,) L* M ino % : ya ue co,,M m eJ /edyc nde, L<> i c nc, u ,ea., + 2b il b O* Wl* O
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1 M DEFINITIONS RE00fkCY NotATIOW ( i 1e rv T . h5E0lISRADWA$TETREATMENTSY[rEN
- 1. A EDUS ASTE THE SYST is any stem des ned and i talled to red e radi etive aseous ffluent by colle ing Pri ' ry oolant ystem fgases rom t Prima Syst nd provi ing for lay ,
holdup or the urpose of redu ing th total r ioactivi prior rel se Qo th enviro nt _ j QDEWTIFIE0lLEAKAGE IDENTIFIED LEAKAGE shall be: #'
#}d d "_ P /'
h$. Leakage (except Congsntun u'ausj@)(McJeteddtadD, such as pump seal or valve packing leaks tha", are captured, and conducted to a sump or collecting tank, or M.D l (pg. Leakage into the containment atmosphere from sources that are
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both specifically located and known either not to interfere with C f)1 the operation of Leakage Detection Systems or not to be PRESSURE //pr ( 4 BOUNDARY LEAKAGE. or fjou prog /Py , g Reactor Coolant System leakage through a steam generator to the Secondary System. r k'#f T t8 (j yo CGNrifftd MEMBE!($) 0F PUBLIC T lIA "#I
- 1. MEMBE 5)0FT PUBLIC s 11 inclu all pers s who are n cupation ly asso ated with he plant This cat ory does so inc1 e
- loyee of the u lity, it contracto or vend s. Also ex uded om ,f
, this ca gory are rsons enter t site to rvice equi to o make d iveries.
- hFF5I7f DOSE CAL (UtATIONI4ANUAL (00dMh
- 1. The OFF TE DOSE LCULATI MANUAL (00CM)sh I contai the i hodology nd par ers used n the e culation f offsit doses a i r sulting f radio tive gas us and iquid eff ents,i the cale ation ./I f gaseous nd liqui effluen monitor g alam nd trip tpoints, nd in the condu of the adiologi 1 Envi ntal nitoring rogram. he ODCM shall al contal the radi ctive e luent co trols, r iological j
, enviro ntal mon toring a ivities and dese iptions the inf tionj
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CALVERT CLIFFS - UNIT 2 1-4 Amendment No. 194
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- 1. DEFINITIONS I 7
! that uld neluded the Annu Radiolog al Enviro ntal Oper ng
- Re and toactive fluent ease Repo , required y Specifi ion i ,//
j (6
.2 and .6.3, re ctively. )
OPERABLE - OPERABILITY
@ haveOPERABIA system, subsystem, n it is train, amponent c6MOe of perfoming or device its specified ' shall be OPERABLE j function (s). M TcVin thia tieffiiiMon mn ne tJef assumerion MMd *'9 ./
4 necessary attendant' instrumentation, controls, nomal #JMpemeroency j electrical power sources, cooling or seal water, lubritTtion or other e i required auxiliary equipment that are required for the system, subsystem, i i . train, component or cevice to perfom its function (s) are also capable of i 3 perfoming their related support function s . l l Sele Sfece'Ne e , (psenrigmAt)noot I
@. MENE shall correspond to any one inclusive combination
, oT tore reactivity condition, power level and average reactor coolant temperaturekspecified in Table 1.h *y [ M M '}.[,p y ! j . g . (cl reactor verre I hu d [dhe N ODES j PNYSICS TESTS - fa ble 8 3 PHYSICS TESTS shall be those tests perfomed to measure the , i
@damental fun nuclear characteristics instrumentation f.nd@ described in Chap of the reactor core 13.0 of the FSAR,truauthorized A/ and i under the provisions of 10 CFR 50.59, o othenvise approvecFby the Consnission.
i; d) f (PerW-fijY1EAKAGE l hY PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam' generator 'j j tube leakage) through a non-isolable fault in a Reactor Coolant System j component body, pipe wall or vessel wall.
- PURGI[G \ .
i 1 4 PURG or PU is t control d proces of dis ing a or as l A q - rom a co finemen to main in tempe ture, h dity, entrat n /-liI l other o rating ndition in such manner at repla nt at or s is - requi to pur y the c finement 1 1 CALVERT CLIFFS - UNIT 2 1-5 Amendment No. 194 1 O i j [#7# .C .fll
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- 1. DEFINITIONS RATED THERMAL POWER TP f
j A,l 7 TAT 6THERN&fase_ hall be a total reactor core heat transfer rate o the~ reactor coolant of 2700 Wt. l
~
REACTOR SYSTEN E TIME
~1.26- The REACTOR SYST INE shall be the time interval from l
- when the monitore parameter exceeds its trip setpoint at the channel '/g i sensor until electrical power is interrupted to the CEA drive mechanism.4 . ,
l 3EPORTABLE/EV [ resf[unsw (( h'Nredimj fMjJ,M*y se l'im, bc
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,g ! red / 6 y hal any/f those/conditidhs spedified in) l l g, ,p 8 D j
'"" ($N""*"=tIQshall
~ ~~ @ AbeED the instantaneous amount of reactivity by ch the rescur is suberitical or would be subcritical from its present
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- condition assuming all full length control element assemblies (shutdown and k th 8 rIrM b
- regulating) are fully inserted except for the single assembly of highest g ingeg,,g,,,]
j reactivity worth which is assumed to be fully withdrawn. f g ,.j ,.f g l 1 cte s sa 19 h drea.=0 ! "5ITfB00M6ARh faret5/uct GiA /6 J I he e he , ,4 l &lly l Aq .
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l'nSc<lef Uht f'* ' i in ' I wa e,( .S hrse (fo9s ra</ l SOURC$CNEt _ Q 4erm led En Im NC C '*'" ' } 1. A RC CNECkshall he essee of cha el l pons the phannel sori!ua[tativea
/kposedt sour f in sed) Oc IdA ~
= dio tivi y.g - f,$ t i STAGGERED TEST BASIS 1 h A STAGGERED TEST SASIS shall consist of:
- fa. tes sched e for[systMs, s syst , tr ns nests obtgined or ther spec led te i desi sted _div ing t
. int al i to(IFtquaK suotntervals) d n t t. beg g b . 4 CALVERT CLIFFS - UNIT 2 f 1-6 Amendment No. 194 l gg, -l Y)C k) $*JJCf!
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} l INSERT NEW STAGGERED TEST BASIS DEFINmON f 4 A STAGGERED TEST BASIS shall consist of the testing ofone of the systems, subsystems, channels, or other designated com,ments during the interval ==iAM by the l Surveillance Frequency, so that all systems, subsystems, ch=~ls, or other designated } e-- ;-:= - are tested during n Surveillance Frequency intervals, where n is the total number of systans, subsystems, channels, or other designated w-..; = = in the
- associated function.
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ecih&=liC# l*O l O : 1 DEFINITIONS THERMAL POWER
,1 @ THERMAL POWER shall be the total reactor core heat transfer rate to l the reactor coolant.
MTA/INTEGb7 ebb 1ALIEAKING CTOR-h! he ed h0TA[PLANARMADIAL PEAdNG FACTOR 4 F!, 4 Th OTAL P RADIA NG F OR i he maxi rat e l l eak t verage r densi f the divi fuel in o he 1 planes.
, (unrod d horizo IUNI1IENTI/IhLEAKAGE esceg/ PCP r-/ /co&#)
UNIDENTIFIED LEArAGE(Ma)(gh11 leakage which is not IDENTIFIED l GE(or4vnpivLyr LEARAEEJ rUNREdRICTED AR 1 6 An cess t which ESTRI EO AREA hall be ny area.a or beyond th '5!TE not co trolled the lice ee for purp es of ARY h ' protect n of 1 ividual from ex sure to r istion and adioact e f ; materi s, or y area ithin th SITE BOU ARY used fo reside ial ! quart s or fo indust tal, c rcial, i titutional, and/or creati nal u ses. i bIldTIONEXNAU[TTREATMEldSYSTEM '
- 1. A VENTI ION T TREA SYSTEM is ny system des gned a l 1 stalled to educe gas us radici ine or rad active mater in articulate orm in of vents by ssing vent ation or ven exhaus gases brough ch coal ads rs and/o HEPA filt for the pu se of ving iodines particul es from t gaseous e aust stream f or to e [
release o the en ronment. ch a syst is not consi red to ave any ' effect n noble s affluen . Enginee Safety Fea re (ESF) Atmospheric Clean System are not to idered to VENTILATION UST T TMENT compon ts. ($YST CALVERT CLIFFS - UNIT 2 1-7 Amendment No. 194 O e,,esa
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' 1 DEFINITIONS
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1 8 Y nfi NG is t contro11 process t to me tain temp ature, p ssure, h idity, f dische {ng air orgas fromfa replac entrati or l ['$ ther o rating ondition. n such a nner th air as is not p ided or required ring V NG. Vent, used in tem n . does not i ly a V ING'proce s_. j
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O 1 DEFIN m 0NS j TABLE 1.16(Pa9e Mj h g lieoEs w..e REACTIVITY AVERAGE LANT l 3 91 CONDITION. K TEMPERATURE l
- 1. POWER OPERATION g 0.99 >R h j 2. STARTUP g 0.99 gR @
- 3. NOT STAISBY < 0.99 $b g 300*F
- 4. NOT $NUTDOWI < 0.99 % @' 300*F > T, > 200*F 3
- 5. COLD $NUTDOWN < 0.99 $h 1 200*F
- 6. REFUELI gg /VA gh O
/Y DExcluding decay heat. (
h Reactor vessel head unbolted @MydMd{uel in the vesseh qJef,%9/on CALVERT CLIFFS - UNIT 2 1-9 Amendment No. 149 O V page t o J II
. - - . -. . _ - . . . -. . ~ - _ - . - _ _ - . _ _ _ - . - . . . - - -
C(ihi(Ye*O*t l*O ll .i lO i
- 1. DEFIN m 0NS retr 24 FRE00 MBTATION
=rm m .
l i At est once per 12 hours l l D least once per 24 hou . W At least once per 7 . M , At least once per 1 days. 0 At least onc r 92 days. f At least a per 6 months. V j 4 R At 1 t once per 18 months. ' S/U P or to each reactor ST . P. Completed prior to e release. l Not applicable. 1m=L At i.ast onc per u ntas. l urup j w j i
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- Spec.hcaG 2.0 l i
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- 9. l 2.0 SAFETY LIMIT 5 h !NI O 1A d 5YST s 5ET R ' O i 2.1 SAFETY LIMIT $'
i REACTOR CORE 7, f, j The combination of THERNAL POWER, pressurizer pressure, and highest rating loop cold leg coolant temperature shall not exceed the limits in Figure 2.1-1. h l l l (s . In MODES .2. a -.1 2., pm A /*ra- ' l 2. l.I'2 APPLICABILITY: MODES 1and] he. f <a * (444') Eh* $ A# W j M: - 3, I.I is wa te ka,s r%rc re mp ua-r e e . sI)
.2.2.l @ fee 0 ting r the old I def emperat the nd nati the hest /
has exca0d
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l e aporon te pres iter pre re li in ROT ETANDBY w' thin j 1 hour. _
, _ _ _ _ , _ ~
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i f. b e NRC Opera ns Center shal notified by t ephone as soo as ossible and n all cases wi n one hour.
- c. The Vice sident-Nuclea nergy and the o site review f tion l
j shall otified withi 4 hours. 4/ i ! . A Saf y Limit Viola on Report shall prepared and beltted to i th onnission, th offsite review ction and the ce President N lear Energy wi in 14 days of e violation. m REACTOR' COOLANT SYSTEM RESSURE; Q , l,7, 2.1.2 4 Th e Reactor Coolant System pressure shall not exceed 2750 psia. APPLICABILITY:hES1,2,3,4andM 2.2.z m mo (rt n 2 a in u. a @) MODES 1 and 2
- a. hengr the Ba(ctor Cadfant Sdem nrendre handeeeded aff0 psiD l 2 2.'l I he en*0T sTANoir wisn the neactor Cociant System pressure witnin ts - <
limit within 1 hour. Ib. T NRC Operatio Center shall e notified by elephone as soon s ssible and i 11 cases with one hour. l 1 ic. The Vice P dent-Nuclear ergy and the fsite review fu tion I
} shall be ified within hours. .
- f. A Safe Limit Violati Report ena11 prepared and bmitted to !
the C ission, the o site roiew f ction and the ce President ! Nuc ar Energy with 14 day, of t violation. J CALVERT CLIFFS - UNIT 2 2-1 Amendment No. 193 b w o
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i Spec 8cdc>- 2.0 l (sid 2.0 SAFETY LIMITSMDf!M_dGJkTYAf5TEnHtTT34fns) N0 DES 3, 4 and 5 fMeNhe ReadCoolaMystem nedInure M avesa#2750 Ma> [ reduce the Reactor Coolant System pressure to within its limit within 5 minutes. Th NRC Operati ns Center shall be n ified by lephone as con as } l [b. sible and all cas within on hour. -
- c. The Vice P ident-Nu ear Energ and the o site revi function [,/
shall be n ified wi in 24 ho . A Safety imit Vio tion Re shall prepared d submit d to i the C ission, t offsite view fun ion and e Vice P sident { Nucle Energy w hin 14 da s of the olation. j l i i CALVERT CLIFFS - UNIT 2 2-2 Amendment No.193 l O 2 a , p,
ecofrab'o 2.0 iO 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS f i e i e e ij 2 I -
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' REACTOR CORE THERMAL MARGIN SAFETY LIMIT CALVERT CLIFFS - UNIT 2 2-3 Amendment No. 193 l O
V fage 3 of 7
..- .- . _ ..... -.. - .. ..~.... -.- - -.____._ _ -.-. - _ _=__ _- -
l SpecscAu- 20 1 4
- O SAFETY LIMITS AND LIMITING SAFETY SYSTEN SETTINES 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SETPOINTS
. ,2.2.1 The reactor protective instrumentation setpoints shall be set I j ' consistent with the Trip Setpoint values shown in Table 2.2-1. ! I l APPLICABILITY: As shown for each channel in Table 3.3-1. . ] }MIlDE: With a reactor protective instrumentation setpoint less . conservative than the value shown in the Allowable Values colian of j Table 2.2-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1.1 until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with gTrip Setpoint value.
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\ ge $peafic., he>, 3.3 J, R PS lQ 1 Im J~ a' ed ** ^ i i j . f a e l l s CALVERT CLIFFS - UNIT 2 2-4 knendment No.193 l JO i p, v s ,
fgdec ife, J.T.l a O i : }, P { 2.0 SAFETYLIMITSAWMMITINGSAFETYSYSTEMSETTIN$$ 2.2 LINITING SAFE SYSTEM SETTINGS ^ ! REACTOR TRIP S NTS i l t 2.2.1 The cto protective instrumentatto setpoints shall be se consistent Trip Setpoint values l th t in Table 2.2-1. APPLIC LITY: As shown for each cha 1 in Table 3.3-1. i i Ellg![: With a reactor protectiv nstrumentation setpot less l conservative than the value sh in the Allowable Valu column of ; Table 2.2-1, declare the chan inoperable and apply applicable ACTION statement requirement of S fication 3.3.1.1 unti the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with u the Trip Setpoint value, j l l l O . l CALVERT CLIFFS - UNIT 2 2-4 Amendment No. 193 l
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- ~ TABLE 2.2- E ty g
. REACTOR PROTECTIVE INSTRMUITATIM TRIP SETP0Illi LDtITS ,
"t ALLOMBLE VALUES O,
m FUNCTIONAL UNIT TRIP SETPO!Ili Q t 3 1. Manual Reactor Trip Not Applfcable Not Appiicable .
- 510% above TRUBEL POWER, with a 510% above THEMAL POWER, and
- 2. Power Level - High -
=!
E minimum setpoint of 30% of RATEB a minimum setpoint of 30% of U TREEMid. POWER, and a maximum of BATED THENgu. POWER and a e ! maximuut of $ 107.0% of RATER S ! m 5101.0% of RATED TREEMAL POWER. , THEMAL POWER. I > 95 > 95 A 3. Reactor Coolant Flow - Low 'I 71ow)ofdesignreactorcoolant Tiow) of design reactor coolant ,
- 4. Pressurizer Pressure - High 3 2400 psfa 5 2400 psia
- 5. Containment Pressure - High 3 4 psig 5 4 psig :
m 3
- 6. t 685 psfa t 685 psia agGeneratorPressure-
- 7. Steam Generator Water Level - 310 inches below top of feed 310 inches below top of feed y Low ring ring , ;
~
a a it ' a . g ! I
.I .Mh0h d,
Rg [ A m
.a q-n % .y g
- n s +t e 3 k Iby e
C
? s 7 :
N 6W 3 '
- t-s :v Ih k 9
e . 1
O O O m g TABLE . h
-e REACTOR PROTECTIVE INSTRIN4ENTATION TRIP SETPOINT LIMITS TRIP SEiPOINT ALLOWABLE VALUES 8 (FUNCFf0Nf/ WNITl Q (1. iianca1Xctorfrio ,
Not ApplIcab }NotAppiicable g
- 2. Power Level - High 510% abo THERMAL , wi % a 5 10% above THERMAL POWER, and 5 t E minimum etpoint of 3 of RATED a minimum setpoint of 30% of d !
4 THE POWER. and a ximum of RATED TREIBIAL POWER and a g l m 51 .0% of RATED RMAL POWER. maximum of 5107.0% of RATED o THERMAL POWER. p
- 3. Reactor Coolant Flow - Low > 95 reactor coolant >9 of design reactor coolant l l Tiow) of dest T1 ,, y =
- 4. Pressurizer Pressure - High $ 2400 psi 5 2400 psia h
m 5. Containment Pressure - High 5 4 pst S 4 psig
- 6. Ste Generator Pressure - ~> 685 sia ^> 685 psis I La e M
- 7. Steam Generator Water Level - 2 10 inches bel top of feed 210 inches below top of feed g Lo. e, rin,
} b
= ;
E i k= LAM i n ! ~2 E i -g 3 3> v
~ .
g"z: f^ l I v
O o O m g TABLE 2.2-1 (Continued) o i G ar_arTOR PESTECTIVE INSTEEMENTATION TRIP SETPOIllT LDtITS g g w - TRIP stTre m Panamanig yntges g E rencnount.enIT Trip setpoint adjusted to not 3 8. Axial flux offset M Trip setpoint adjusted to not exceed the limits pmided in exceed the limits p m ided in i the COLR the COLR , g m M 9. Thermal Mergin/ Lou Pressure
" Trip setpoint adjusted to not Trip setpoint adjusted to be
- a. Four Reactor Coolant Pumps not less than the larger of Operating exceed the limits provided in the COLR (1) 1875 psia, or (2) the limits provided in the COLR $
5 135 psid 5 135 pstd
- b. SteamGeneratorPrgsure Difference - High N
IRA IIA
- 4. 10. Loss of Load "
$ 2.6 decades per minute
- 11. Rate of Change of pouer - High M S 2.6 decades per minute 1
i. t [ i Mn Q N, T~b a s b- N: 1 d s a$e %n CN
- $ I' sS if 3 b
I y c
? I bQ % s
' i-N 9
t g TABLE (Continued) ro i G REACTOR PROTECTIVE Ill5TRipqENTATION TRIP SETPOINT LIMITS g
-' y FUNCTIONAL UNIT d) IIPSEdOINT ALLOM4BLE VALUES G 8. Axial (ffGQRset) Tri setpoint adjus to not1 Trip setpoint edjusted to not g !
. 3 -- e eed the limits vided in exceed the limits provided in g E
%,0nte4.b-N,=,k)
, m COLR the COLR -
m 4 9. Therwei Margin / Low ssure W / g
- a. Four Reactor Coo t Pumps I Trip setpoi adjusted to not Trip setpoint adjusted _to be Operating exceed th 1 sits provided in notlessthanthfea g of. h
.I the COLR (Ilynsis asiaar f27the w limits provided in the COLR d
- b. Steam Generator sure 5 13 psid 5 135 psid Difference - High y
- k
$ 10. Loss of Load NA NA h
- 11. Rate of Change of Power - High per minute 5 2.6 decades per minute -
{S2.6 deca e Ot. ') = *
?
E us 7a % = Y h_ a , t>
- 9 ;
~
. - - - - . . . . . . - . . - - . - . _ _ - . . - . . - _ . - . . _ _ - _ - _ - . - . . - . . - . _ - - . ~ . _ .
.I ' Spec. k be 2.o ) O - 5 ! 1 2.0 SAFETY LIMITS AND LIMITING 5AFETY SYSTEM SETTINGS
*~--~w _
; TABLE 2.2-1 (Continued)
. TAILE NOTATION 3
i 4 i See Specification 3.2.5, 'ON8 Parameters.' for the design reactor coolant flow. IN Trip may be bypassed below 10% OF RATED THERMAL POWER bypass shall j be automaticany removed when THERNAL POWER is t 10% of RATED
- THERMAL POWER.
} (2) Trip any be manually bypassed below 785 psiat bypass shall be
- automatically removed at or above 785 psia. .
(3} Trip may be bypassed below 15% of RATED THERMAL POWER; bypass shall
; be automatically removed when THERMAL POWER is 115% of RATED THERMAL j POWER.
(d) Trip may be bypassed below 10% and above 12% of RATED THERMAL
- POWEL i
!O T i See Oscwao J 6k y es &
- n. I, RPs Ink",ed W l Syc;[,csho-l .
I l i i 4 i CALVERT CLIFFS - UNIT 2 2-7 Amendment No. 193 l a
- O i
pyc 7.I 7
5t ' A
- b ' 5'3'I O
2.0 SAFETY LIMITS AND LIMITING 5AFETY SYSTEM SETTINGS b -D (Continued)' h TABLE Il0TATION S g g tion 3.2.5, arameters." for thepen reacg , Trip may be b asscd below 10% OF RATD THERMAL POWER bypass shall be automatica y removM when THERMAL POWER is 110% of RATD THERMAL POWER. Coal +/t A (c) W# Trip may be manually bypassed below 785 psia; bypass shall be automatically removed at or above 785 psia. Trip may be b assed below 15% of RATED THERMAL POWER; bypass shall be automaticahy removed when THERMAL POWER is t 15% of RATED THERMAL POWER. feds it (,) Trip may be bypassed below 10% and above 12% of RATED THERMAL POWER. foeiaett, Q g 19 4,,,17 .ge unk in M 00E l > tS% g (4,,Je CHANNEL cAEut .17 eff o ic 4. W.-de Rea p e) %.~. u... . ,, s . ,4 CALVERT CLIFF 5 - UNIT 2 2-7 Amendment No. 193 l O
\
1 hVctIsr Mon 3. N
..-:=-==_~~~ -_
- 7. O LiMiTWG cc2NDtTioN ro R OPERAT8oN (LCc) APPLICAGI
= -_ _ - _ _ - _ - -
_ _ = _ _ _- i
.sg4.--AppueettWP- 4 P' ev'al *J i Lc o '5. c. 2 o nd L.C o 5 . o. *7 A2 Compliance with the Limiting Conditt 3.0.hdeceeding
^6 specifications ing isforthe Operation contained in required SpraATra ".' MODES or_
7 4
**c a+ " *iana anecified '"-~'2 -=-=1_Mt;upon failure to sees sne *
- jP,g .S " g,c o miting Conditions for Operation, the associated ACTIgli reautrements shal j be me C "T.O.$ ..J "$.O.6 4
CO T3.,0.2 W =,11a th a pecific n shal 1st the pequi, _ . 9 A* I A .'2 i- r Ope a ist ut l f** S
, ad t wi a the itt ified inte 1s.f~ii sne ueTYT' s
H3n' 4. i i 'for Operation is restored =-- = rior to expiration of the specified requir e. t me[W3 _ad? >,.~n 5 4 *@
fP'i'9? r intervaly completion of j ACTION requirements is not '
O' N ad E E " '" " ' I
=
~3h a Limitins_ condition for Opr.gis --
within not one met. burW q.= so.ii: a ... ;.YN= iniiTat R tF unit p in a MDDE in wh ~ specificatto T*NO ** * * * ** *' '"*d* 's*d ** "'u Actio l does not apply by placing it, as applicable, in: , si a * + p*=v ad 4 .* , i 7 - s p: J .. ,,4 .J by Ac f l
- 1. At lesst HOT STAlWBY within : X hours
- 2. At least BOT 38UTBetEl within rs, and
-' Acooy A.4 3. At least COLD SEU190lAl within[__'-";;_- _
rs..' .-pi,4.., ,, A h
#""'i* nihere corrective meatures are camoleted that reit o # N' n under the '
"~ '* h * [' h. i i ACTION requiremen.tse t ou ta en RUN wun w t c o 7. o .~5 i+ i s fieu u s inun asu rom t ge_g *4 8 "tw?#
O *^ 1 i ition Ooerati eji ins to se requ nus are c _ t. ting ..s y g_ , i ed lh thrTylitTVtausi spec 1TfEitionu to nf.'3b.3,
. w . -.J,s (NSPRT ,_3.$.4 Entry 1[0ptRATICEAL NODE or other specified condition shal'f6 ,,, I LCO no ra mades sne the L in ng m r ratt - -
--7 3 0.4 ons e ined he w,4 A; 4Q l
._1 , Thi tston Insii not pMVHilisu DP ?! ,,g b ,g A 4.a j na us tred to comply with ACTIGIl requirement nts are stated in the 4 tcat Except ons to the
"**3 j 4-* ]
, ,, ,,,g h 3.
To shenas nope e um . stem. ause i emergency
- r. . componem r sevice r sourc : inoper date
- P * * ** 1 ' * - " "
- e. M o n E .c *
- 1 1
p le ause nomal r source inoperable t may 5 J eeJ A a cons er for t rpose of sfying t ut s of Y .p..S. 4-% e PW c. L. i.4y etc'a tele Li no Cond ion for fon prov I (1) its 4r , t.,,r. d corresponding nomal or emergency power source is orgsA8LE: and (2) al l of ,. 4 .F A . .e te w..m-+ a +a r L auhevatants). trainfs).
= tis) and devi tefs = = - =
L Oko5[Su (NSERT Lco 3.o.$ ,,,,7, ,, *, S
- 4. . . . ,
L0 06 l L. . "), b d 'S cu5s -- *I cks. -s Pe
< . . . . , .a. o w T. F. I cALVERT CLIFFS - UPIT 2 3/4 0 1 Amendment No. 149 AC. 5 ** "' S C.h-** +/k O
, , .n
!O ? INSERT LCO 3.0.4 i LCO 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1,2,3, and 4. [.I 4 1 INSERT LCO 3.0.5 l Equipment removed from service or declared inoperable to comply with ACTIONS may j be returned to service under administrative control solely to perform testing required to
- demonstrate its OPERABILITY, the OPERABILITY of other equipment, or variables to
/j be within limits. This is an exception to LCO 3.0.2 for the system retumed to service
! under administrative control to perform the testing required to demonstrate
)
j OPERABILITY. INSERT LCO 3.0.5 ! When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to L . CO 3.0.2 for the supported system. In this event, i additional evaluations and limitations may be required in accordance with Specification 5.5.15, " Safety Function Determination Program (SFDP)." If a loss of safety function is i {*q j determined to exist by this program, the appropriate Conditions and Required Actions of j the LCO in which the loss of safety function exists are required to be entered. ! When a support system's Required Action directs a supported system to be declared j inoperable or directs entry into Conditions and Required Actions for a supported system,
- the applicable Conditions and Required Actions shall be entered in accordance with LCO l 3.0.2.
.t !O QW
- L
1O INSERT LCO 3.0.7 l Special test exception (STE) LCOs in each applicable LCO section allow specified Technical Specifications (TS) requirements to be changed to permit performance of 'g special tests and operations. Unless otherwise specified, all other TS requirements remain
- unchanged. Compliance with STE LCOs is optional. When an STE LCO is desired to be l met but is not met, the ACTIONS of the STE LCO shall be met. When an STE LCO is I
not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with the other applicable Speci6 cations. O l O p p .a
- - . - ~. - - . - _ - . _ - _ . _ . - - _ - - _ . _ _ _ _ _
i j 5puk k 39.I ( lO.
'3/4.0 APPLICABILITY 7
& Sp A,b 3. o
" ' #" " 'd ' A##
i N NE CO MITIM FM OPEM TIM l 5.0.1 Compliance with the Limiting conamons ror operation contained in 1 1 the succeeding specifications is required during the OPERATIOEL MODES or
- other conditions specified thereing except that upon failure to meet the j *
,, Limiting Conditions for Operation, the associated ACTION requirements shall be met.
I B.0.2 Noncompliance with a specification shall exist ahen the requirements ! of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition l for Operation is restored prior to expiration of the specified time ! intervals, completion of the ACTION requirements is not required. l 3.0.3 When a Limiting Condition for Operation is not met, except as ! provided in the associated ACTION mquirements, within one hour ACTION l shall be initiated to place the unit in a MODE in which the specification i does not apply by placing it. as applicable. int i 1. At least NOT STANDSY within the next 6 hours, a 2. At least NOT SNUTDOW within the following 6 hours, and ! ! 3. At least COLD SINmeAl within the subsequent 24 hours.
, dhere corrective measures are completed that permit operation under the LCTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the O
s Limiting Condition for Operation. Exceptions to these requirements are stated in the individual specifications. 3.0.4 Entry into an SPERATIONAL N00E or other specified condition shall l mot be made unless the conditions of the Limiting Condition for Operation ! are met without reliance on provisions contained in the ACTIM j requirements. This provision shall not prevent passage through OPERATIONAL l MDDES as required to comply with ACTIM requirements. Exceptions to these ! requirements are stated in the individual specifications. 3.0.5 When a system, subsystem. train, component or device is determined to be inoperable solely because its emergency power source is inoperable. , or solely because its nomal power source is inoperable. It may be ' considered OPERABLE for the purpose of satisfying the **a"ir===ah of its y . toolicable Limitino condition far namention. nrovidedd (1) its A(p
% corresponding normal or emergency p(ower source is OPERABLE; and (2) all ofits red
, 2, g
i CALVERT CLIFFS - UNIT 2 3/4 0-1 Amendment No. 149 O pp 3 J I2-
1
- 5e . p.U .., 3. g -
i 1 j b O ' st43-arrmamrTr i
)
i ' are , or 11 e satisfy the requ' raments of this specification.
- Un1 s both conditi (1) and (2) are s sfied within 2 hou ACTICII 1 he initiated place the unit i a IIDDE in which the ppI1 cable ;
j initi Conditi for Operation t apply by placi t, as j appli le. in: ,. L, , ] l 1. A cast BOT STAlW0Y thin the next 5 . , . 2. least BOT SN within the fell 6 hours, and + i At least COLS within the s uent 24 hours. l l This pacification is applicable in IIODES E er L J IbJsEit 3.o.I 5 _ ._, u
% h.0.1 Surveillance or other co utrements shall be applicable during the OPERATIONAL ions specified for individual Limiting Conditions for
=- = - - -
Operation unles W S E RT 519-themise stated in an individual Surveillance __Raouirement _1 o,7 5R Each Surveillance Requirement shall be rfomed within the
= --
.- nied time interval with a maximum allowab extension not to exceed 2Ipercent of the specified surveillance interval g "[ ~ '* Qg ,
4.0. allure to em a Surveillance Requirement within the all ps .n c os ped *e"6ar su 111ance inte al defined Specificati 4.0.2. shall onstitut e r- 3 e .. w , c d espliance the OPERAB requi s for a Limi ng Conditi p, , y # w , fim, j for Operati The time 11 ts of the requirene are appli / at the ti it is identif that a Su 11ance Requi nt has no *
- f' ' g.g perfo . However, t time of app cability may delayed fo up to c.- J " m *I 24 .to pemit t completion o the surveill e when the awabl g, f,,b . cy out time limits the ACTIO11 utrements a less than hours.
1 e111ance Reg
==n+. -
ts do no have to be pe ormed on i rable ** t'a &- - -
.0 Entry into an SPERATICIIAL IIDDE or other s ified condition shall g y g g q7 no i, se made unless the surveillance Requirement (Wassociated with the Limiting Condition for Operation have been perfomed within the stated surveillance interval or as otherwise specified. This provision shall not S R^=-- 3.0.'3
^
prevent passage through or to OPERATIONAL IIDDES as required to comply with y* ACTIO11 requirements.
- v. -
IsR T.o. + u .a v v.~w c., % y ma s er e h r- s p < .T;,d c a~J b A "" [@MoOE pLc.4.h+y-n
- ~ - _ _ - _ _ -
MoOES . i33 . . J 4,f - -- _ ~ - - _ _. CALVERT CLIFF 5 - Ull!T 2 3/4 0-2 Amendment No. 14g O 4 .F 6 p$e
. - - . - - . . . _ . - ~ . - . . . --. . . . _ - - -
i $p,. S. c .A io 4 3.$6 l INSERT SR 3.0.1 {O Failure to meet a Suiveillance, whether such failure is experienced during the performance j of the Surveillance or between performances of the Surveillance, shall be failure to meet ,~/ 2 the LCO. Failure to perfbrm a Surveillance within the specified Frequency shall be failure j to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. 4 l INSERT SR 3.0.2 i For Frequencies specified as "once," the above interval extension does not apply. l If a Completion Time requires periodic performance on a "once per..." basis, the above Frequency extension applies to each performance aAer the initial perfonnance. [h t l Exceptions to this Specification are stated in the individual Specifications. i 4 INSERT SR 3.0.3 Ifit is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from j the time of discovery, up to 24 hours or up to the limit of the specified Frequency,
- whichever is less. This delay period is permitted to allow performance of the Surveillance. [,3 i
i If the Surveillance is not performed within the delay period, the LCO must immediately be j declared not met, and the applicable Condition (s) must be entered. 1
- When the Surveillance is performed within the delay period and the Surveillance is not i met, the LCO must immediately be declared not met, and the applicable Condition (s) must
{ be entered. O l l P e O i
$~p ac 8 .e 4. b 3 . %
. 4/4*-PPtreenm
- 0.5 Surveillance Requirements for inservice inspection and testing of j ASME Code Class 1. 2, and 3 components shall be applicable as follows
- a. Inservice inspection of ASME Code Class 1. 2. and 3 components and 4
inservice testing of ASME Code Class 1. 2 and 3 pumps and valves - shall be perfomed in accordance with SectIon II of the ASME Boiler and Pressure Vessel Code and applicable Mdenda as required by , 10 CFR 50, Section 50.55a(g), except where specific written relief has been Section granted by)the 50.55a(a)(6 (1). Commission pursuant to 10 CFR 50,
- b. Surveillance intervals specified in Section XI of the ASME Boiler and l l
Pressure Vetsel Code and appitcable Mdenda for the inservice , inspection and testing activities required the ASME Boiler and , Pressure Vessel Code and applicable Mdenda hall be applicable as follows in these Technical Specifications: i ASME Boiler and Pressure Vessel Required frequencies for Code and appitcable Mdenda perfoming inservice , 4 teminology for inservice inspection and testing l i insnection and testino actbf Qgi Agtivities I 1 lieekly At least once per 7 days Monthly At least once per 31 days t O Quarterly or every 3 months Semi-annually or every 6 months Every 9 months At least once per 92 days At least once per 184 *_ys At least once per 276 days Yearly or annually At least once per 366 days
- c. The provisions of Specification 4.0.2 are applicable to the above i
, required frequencies for perfoming inservice inspection and testing activities. ! d. - Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
- e. Nothing in the ASME Boiler and Pressure Vessel Code shall be
- construed to supersede the requirements of any Technical Specification.
l 1
$rc Cis cu u .o % of G.ys G ., e Spee . F. e rA .e s 5. 0
%4 a. .A ra+.w e C*~4**h~
1 i i CALVERT CLIFFS - UNIT 2 3/4 0-3 Amendment No. 149 O a Gt f C
-. .,------------ -- -- ~ - --
yfQ }.;^} ~ i hs ub r. T. 9 . . M7 c- I af* I i O m s-:-rs g :::.: = = = = - e~7_ n 2 -~Tn,n e~r:um3gLi \ c n= .. ;-u y .' O.".5 *:r :'":-.:: ": i -+= * *' N ASME Code Class 1. 2. a;nd 3 componentgst!' _,f :_2L i:r inservice
- ':"n:' .:;;;Ms ;d testing f*yyM'e of r, k/;d/,
i ' a. Inservice inspecti f ASME Code Class 1. 2. and 3 esponents a I" # # '" inservice testi f ASME Code Class 1. 2. and s and valves I c-["/c#b / ! shall be perf in accordance with Section of and Pressu essel Code and applicable Add a as required by ASME Boile .F.,//,*,j l l 10 CFR ction 50.55a(g). except who pecific written relief 1 has oranted the Commission pu nt to 10 CFR 50 j L _m_ eet n 15.ssa fa)( ) f t ) _ _ f,2/ [ L.. .. : ( '- N b n Section of the_ASME Soiler and
. s&_t -.n--
m - andn., .. .L.Addenda
.. m
. = __ .a v. m .
! b.Ppessure Vessel ....Code apolicable,
~
l
= k=M^ss? f __ '
folloM "- : "1f.ppi6 1.
- o. "f:" ";:::":__;,j-hili E:55Eijj a's
= _
. q l ASME Boiler and Pressure Vessel Required frequencies for
\
j Code and applicable Addenda perfoming inservice teminology for inservice inspection and testing j inspection and testino activities activities Weekly Monthly Quarterly or every 3 months At least once per 7 days At least once per 31 days [. ll At least once per g2 days 1 Semi-annually or every 6 months At least once per 184 days Every g months At least once per 276 days
- -Ypar e,r ,angua11y east,ance,per-466-daysw
- d o.-
p s7f -'ycup= 2 2. . ' e r**+ casee Pv 73 o Sans fpp'11cabTeSoMhe1t we
- b'l required fre R 3.0 activities. quencies for perfoming._. rvice inspection and testing l
h rfomanfe of the aboyW' inservice spection and hall win _ addition 4o other_ s fled Surveilla te nD activi Requirements j @}. u Nothing in the ASME Boiler and Pressure Vessel Code shall be \ construed to supersede the requirements of any Technical Specification. l l
/
r y p e w o n J s w .?. o. 2 e < p & i u ~ me a,a w - f i i i CALVERT CLIFFS - UNIT 2 3/4 0 3 Amendment No. 149 !O Page/6 4 D
.. = .-
hp ec .C, ca v.e 3. I . I i O 1 V I {, g -9/4* REACTIVITY CONTROL $YSTDt3
- 3. l . I L't.:.: 4MAff9N-ttMmt0c SRUTDOWN MARGIN - T, ,
LIMITING CONDITION FOR OPERATION Svhh4 The SNUTDOW MARGIN shall be within the limit provided in the om. 1 APPLICABILITY: h b 3 and 4. l Acrocr/ 4 : With the SNitTDOWN MARGIN outside the limit orovided in the COLR. l i need ately initia stic sa4vuon or egg o ttnus MatioWn i 3 =- -Nk" -- =no 1 len un il the required $NUTDOWN MARGIN is, restored. l l 4
$URVEILUUICE REQUIREMENTS
' D . 7.1. 1 i.i.i.id The $NUTDOW MARGIN shall be detersined to be within the limit provided in the COLR:
- a. With ne hour after dete n of an inoperable s)andat
- O I t once per 12 hour j required $N ereafter while the C s) is I noperable. If the operable CEA is untrip le. the above GIN shall be increase y an amount at 1 3 tequal to the hdrawn worth of the untr pable CEA(s)
.~ When MODES 1 or 2 wit z 4.v. .. ' m vu6 per 12 hpors l by erifyin that CEA p withdrawal is hin the Trarprfen '
sertion L mits of ecification 3.1. .f i 1 J a
! f ISpecjpVfest Ex on 3.1h CALVERT CLIFFS - UNIT 2 3/4 1 1 Amendment No. 163 i O 1 . s +
n.
l 1 2
$p-c .fi-.a ..s 7.t.'2. l l
lO 1 3.I $f4* REACTIY!TY CMTROL SYSTDt3 b
- T. l . 'l he et vi+y .t -.
- - . = = T ., m
, ,,, , ,;,, g,;p A.
] LIMITIIIG C0llDITI0lt FOR OPERATICII 6u 9
- t. <
o,a.. 4 a
#4 r ( X A w/gjI v.w s v, . I .2 MI 'h i" 22 ^J ~ ~i" *i'*II h I;l'I'~' ;l I bi; r'-' '- d ; ;I w /
APPLICABILITY: MODES 1. GC ~ I the ' -- _ ~ _ si suius inc. unu rivvine the l y e and con borati > 40 pm 00 p c
- act oh:tio or moutwata na+<1 m o< Tem mine.
ummers in, , l b @tRT A w D h l SURVEILLANCE REQUIREMEllTS - T.44.1.1 The Shumoun nnusan shall be determined to be within the limi vided in the COLR:
- a. Within one hour after detection of an inoperable CEA(s) and at O I least once per 12 hours thereafter while the CEA(s) is inoperable. If the inoperable CEA is untrippable, the above required 518UTp0WN MARGIN shall be increased by an amount at least l
equal to the withdrawn worth of the untrippable CEA(s).
- b. When in MODES 1 or 2 with 4 21.0, at least once per 12 hours l by verifying that CEA group withdrawai is within the Transient f a==etLos Limits of Specification 3.1.3.6.
l 4 J.s m..- . r e t. . y 3 f '$p ,. f. , 4. .. ~4.1.1. 3L. fido,. M3%" [ee $ Test ption346.1.) CALVERT CLIFFS . UNIT 2 3/4 1-1 Amendment No. 163 O ey u3
$ pee.L ++n 5.t."2.
l INSERT ACTION A & B l CONDITION REQUIRED ACTION COMPLETION TIME A. Corereactivitybalance A.1 Re-evaluate core design 7 days not within limit. and safety analysis and determine that the reactor core is acceptable for continued operation. AND A.2 Establish appropriate 7 days operating restrictions and SRs.
~
l B. Required Actions and B.1 Be in MODE 2. 6 hours i Associated Completion i Time not met. p.,y 2 .F 3
$q, e e .F. < .4 . ., 3. \ . I i
l
- O 3/4.1 REACTIVITY C0llTROL SYSTDts SURVEILIAllCE REQUIRDtDITS (Continued) i c. When E 2 with .0. within 4 hours for to achiev p$ l 4 or criticality ifying that t icted critic '
i sition is within limits of Specif ion 3.1.3.8 - L.i nitial operati l . Prior bove H units i FUWER after each el loading, by sideration of ctorsof(e) w the CEA groups the Transient In ion Limits of cification 3.1 .6. -
*I*I gl When in IIDDES 3 or 4. at least once per 24 hourjs y considerat ng Ts66m na 7
gT Ine foll 1
- 1. Rea r' Coolant System boron centration, l
- 2. C position. 4*7 '
! 3. actor Coolant System av ge temperature. , ! 4 Fuel burnup based on gro therinal energy ge . ton, ' 4
. Xenon concentration. , )
j J. Samarium concentrat . j ) f4.1.1.1.2 The overall core reactivity paisnce shall oe conipared to ) ] predicted values to demonstrate agreement within i1.0% Ak/k at least once}
, per 31 Effective Full Power Days (EFPD). This comparison shall consider at a
least those factors stated in Specification 4.1.1.1.1.e. above. The 4 d predicted reactivity values shall be adjusted (norina112ed) to correspond to l l the actual core conditions prior to exceeding a fuel burnup of 60 Effective; Q11 Power Days after each fuel loading. f i 1
$er ds s es s s e o ,
*V c % ">
F.e (y,A,.+.- 3.i.E,
*2 p . . % w , + 7 E" I*-ce
- i
- 1 CALVERT CLIFFS - UNIT 2 3/4 1-2 Amen 6nent lio. 163 O
r, 2.n
$ pre Fm +. 4 3. l . 2 f,, J . . ., w .. 3 F c L. v <, i C. , <$ p , . . c . , ., + . o , 3. t . t .1, 9*O 3/4.1 REACTIVITY CONTROL SYSTDt3
'SOM - T.S SURVIIt1AllCE REQUIREMENTS (Continued) ,
c.~ unen in MODE 2 with K,,, < 1.0. within 4 hours prior to achieving )
' reactor criticality by verifying that the predicted critical CEA position is within the limits of Specification 3.1.3.6.
- d. Prior to initial operation above 5% RATED THEIBIAL POWER after each fuel loading, by consideration of the factors of (e) below, with the CEA groups at the Transient Insertion Limits of Specification 3.1.3.6.
d [r ~[ r pg ,, , g e. When in MODES 3 or 4. at least once per 24 hours by consideration of the following factors: nog ,
# 4 *'" el 1. Reactor' Coolant System boron concentration. !
l . 4,3 . d 2. CEA position.
- 3. Reactor Calant System average temperature.
- 4. Fuel burnup based on gross thermal energy generation.
5. (6. Xenon Samariumconcentration, concentration. an [d S Rs. ) . 7 1 4,:.:.22 redictedThe over:11 values core reactivity to demonstrate agreement balance within +shali r 31 Effective Full Power Days (EFPD).fThis comparison s 1.0%_A red to be cgk/k at least once constnef'ac Q
- t. 4 ,
est 3.best factoftettled in 50ec1Mcation M1.1.1.e. v C he redicted reactivity values shall be adjusted (normalized) to correspond to
, the actual core conditions prior to exceeding a fuel burnup of 60 Effective Q M'2. 5 ull Power Days after each fuel loading.
N OTT _~ w ~ U Q
'#c N.<e: ~ - ~ y o r g, j _ ,._
M y r ey.r ed o f-4. e 60 ( F F PD r-+ ,, e . t. Co,t o d .g 4 7X[ ' ~ ---- - ---- ) _ l CALVERT CLIFFS - UNIT 2 3/4 1-2 Amendment No. 163 7, u 5
. _ _>_.. m . _ _ _ . . _ _ . . . _ . _ . _ . _ . _ _ _ _ _ _ _ _ . . . . _ _ _ _ _ . _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ _ _
hecbeat.e4 3. I . l i !O l l 3.) -5/4,4. REACTIVITY CONTROL SYSTDt$ i j 3/4...- BORATION CONTROL A. T. t . L 6OMM l saurung ra J ~ i LIMITING CO WITION FOR OPERATION l LC.o "5.1 1 l;. .;.2 The $NUTDOW IIARGIN shall be within
- limit nrovided in the -
1 or fn -b ra w ha be 5 88 f i APPLICABILITY:-INDE 5.
- ACIlE
DON A a. With the $ NUT 90W NARGIN outside the limit provided in the COLR, l -
]
immediately initiate and continue boration a+ w o songf te A( l
"= m e noi s. . ... .. ...ivaienpiintil the required 5NUTBGM I au is restored.
i . Wit pressurizer rained to < 90 i has and all sourc of'
-borated water 88 gps, immediat suspend all ope ions nvolving posit reactivity the while the NARGIN i is increased compensate for t additional sou of non-
- i j
borated wat (to588 7 or reduce the s es of non-bora water j l i j suRvr!LLanct Rteu!RosNrs 5 M .l.\.) ! 4.4 4.i.4 The SEUT30W MARGIN shall be detemined to be within the limit i ) provided in the COLR: 1 i _._ Within
. hour after detection an inoperable CEA(s) nd a least e per 12 hours there er while the CEA(s) is Jino able. If the inopera CEA is untrip ble, above -
{ 1 red $5UT90W MARGIN 11 be increased an at at less ual to the withdrawn rth of the untrippa e (s) h At least once ser 24 hoguy sideratin of the fo owis$ 7 actors i f'
- 1. ctor Coolant Syst ron concentration, j 'LA.
CEA position, y f CALVERT CLIFFS - UNIT 2 3/4 1-3 Amendment No. 163 O n m
pa c Mi r %+ie T.l.1 I l l 3/4.1 REACTIVITY C MTROL SYSTEMS SURVEILLANCE REQUIREMDITS (Cestinued)
/3. Rea r t.colant system evera temperature, i 4. F burnup based on gross real energy gener ton 4,
- 5. enon concentration, an f L
Samarium concentratio f 1.1.2.2 With pressurizer drained to < inches determine-
- a. W1 n one hour and every 12
]
l urs thereafter that the lov in j Reactor Coolant System above the bottom of the ho og nozzles, and
- b. Within one hour and ery 12 hours thereafter tha he sources ei non-borated water 5 88 gym or the S MTD0lAt GIN has been !
increased to e nsate for the additional no rated water j sources. 1 O CALVERT CLIFFS - UNIT 2 3/4 1 4 Amendment No.163 l O V py 4- # 4-
CS 3.1. l .3 i )
,k 3 1 REACTIVITY CONTROL SYSTDt$
3/4.1. B0 RATION CONTROL l oron Dilution j l LturT ss Comeriz a optaAnon , 3.1.1.3 The flow rate o actor coolant through the actor Coolant i System shall be > 3000 ppm never a reduction in ctor Coolant System j boron concentretTon is beino de. APPLICABILITY: All N00ES. Ellg With the flow rate of react cool t through the Reactor Coolant l operations involving a reduction System
- 3000 ppa immediately suspend in boren concentration of the Reactor C nt System.
SURVEILLANCE REQUIRDIDITS 4.1.1.3 The flow rate of actor coolant through the Re tor Coolant System shall be deterni d to be 1 3000 sps within one hou rior to the *i start of and at least ce per hour during a reduction in t Reactor O , Coolant System boro oncentration by either
- a. Verif .g at least one reactor coolant pump is in operat , or j
- b. V fying that at least one low pressure safety injection is n operation and supplying g 3000 spe through the Reactor Coo t l System.
CALVERT CLIFFS - UNIT 2 3/4 1 5 Amendment No. 163 l O pey IEl
l l 4 c . . r. . + ., s. i . 3 ; i i I
- O i
i
- 3/4.1 REACTIVITY CM TROL SYST M 5 l N#- *i
- 3. l . 3 Moderator Temperature Coefficient- -
{ LIMITI N CO WITI M FOR OPERATION L.C O i 5. I , 3
- 1.1."- The moderator temperature coefficient (MTC) shall be:
l a. Within the limits provided in the COLR, and i
- b. Less positive than the Ilmit line of Figure beh4-t.
D 1.5-Q l l h j 1 APPLICABILITY: NDDES 1 and 2 O " ' 1( _ l_ i
$113: With the moderator temperature coefficient outside any one of the ,
! above limits, be in at least BOT STAMBY within 6 hours. I 1 1 SURVEILLANCE REQUIREMENS
.1 The MTC shelfe deteminec to ithin its limits l(4.1.
c motory measu ;s. E C measured ues shall be est sted]l 1,, /\ , g O /or compensated permit direct c ison with the a inits.2 i
~
)
I I
/See gal T/ Exce3H6n 4doj CALVERT CLIFF 3 - UNIT 2 3/4 1-6 Amendment No. 163 O
e, i .o
_. _. . . . . . _ . - - . - . . _ _ . ~ . . . .- . ..
$ peeSe enti on 3.13 :
I O 3/4.1 REACTIVITY CONTROL SYSTDt3 j 4
- e d
CNI?c '16-012D-
=
8 1 l l t a R E
~
8 l lN - l o - 8 g I B 3 g IlIl llll - I I I I l I
! 5 5 5 5 5 5 5 W/#p01).IDtTI3Dt EAUJSOd FIRYuCFTIY D*N3 ~$
FIGURE 3.2.: ' _ l
% ALL0tlABLE P05fTIVE NTC LIMIT fe9 4 rW 4 CALVERT CLIFFS - UNIT 2 3/4 1-7 Amendment No. 163 O
7, 2.r s
5 9 5J, e 3t3 i i i /3 I V l l 3/4.1 REACTIVITY CONTROL SYSTDt3 ,
$URVEILIAllCE REQUIRDIDITS (Continued)
. .;.,.I The MTC shall be determined at the following frequencies and THElBEL POWER conditions during each fuel cycle:
CTA T.).3 ,1 % Prior to initial operation above 5% of RATED TutlpEL POWER, after 3 each fuel loading. SR T ,t,3,- b. At any L POWE ve 90% of ED THE R. hin F.,e 7 EFPD er init ly reachin equilib condi at or l r . .g ,,, .' y .jgtve of RAT TNENIAL after eac fuel to ing. i N 'I31 raa5on o s . ' r.'. ,. . _., .- l i 3 OI engec4 r d e l care 4 , , ,, p h LA Gi c.7 e ie C. 4.w (3 U 7 EFPO or Er*O __e te c,..u; sy.zo. 4o @
- - - - __ gy ~
G lu I. Thu Scuve,'llece & n ol rep.< :n ,1 & 5I? T.l.1I y e< fxmej p ,, . , 4, e , .+,,, ,, f, ,,,gg , ,, , , o IA/dec { '
' r <= s e n er u-L'.r.
- 2. 5 Oc b1T( f , j., ,- l h tv.ptc ed
- Jht C ot R Iin,4 wir - er/< <p.>l. 4. i w & a .. . {
C tj tI C , 50 ~]./.3 2 Wy ba' /ffsU
- N+lcl0Jn
-lu Crcerc n% I ll1c m inl W m mms 4 Occc.<.u- f r, o<
ot {loLk ,lle baran &n c r> lre"l ids as/ Ok<2 L MTC 4
* (KcerJ 4ha l0Lrr _firs,o), _ _
t_}ra.y-fc lcd _-{O CALVERT CLIFFS - UNIT 2 3/4 1-8 Amendment No. 163 l U l pa$e 3 of 3
-. - - . . . .. .-. - --- .~ . . -_ . _ _ . .
& TS 7. I. I.E i
W [ W VGD TO $ECmo*J 3,4 A c, g 4,2 i 4.1 REACTIVITY CONTROL SYSTEMS 3/4,1.1 B0 RATION CONTROL 2 Minimum Tannerature For Criticalite i LIMITING C0 m ITION FOR OPERATION 3.1.1.5 The Reactor Coolant System lowest operating loop temperature (T.,,) j shall be 3 515'F when the reactor is critical. 3 APPLICABILITY: NDDES 1 and 2 with 4 21.0. l ACTION: With a Reactor Coolant System operating loop temperature (T i
< $15'F, restore T.,, to within its limit within 15 minutes or be in E) i STANDBY within the next 15 minutes.
1 l l $URVEILLANCE REQUIREMENTS 4.1.1.5 The Reactor Coolant System temperature (T.,,) shall be detemined i to be 1515'F:
- a. Within 15 minutes prior to achieving reactor criticality, and j b. At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T.,, is less than 525'F.
3 J 1 i i i
- I CALVERT CLIFF 3 - UNIT 2 3/41-9 Amendment No. 163 O
a p3e le i
i F s e.. . i . r u .. , 3. 4 . 2. (
- O A.t A. I
! RE TOR c. cola NT
- 3. k l
4/4rt REACTIVITY CONTROL SYSTDt3 1 4l' ! ! !!"J.T un ivn i mn. i QCS A' Minimum Temperature For Criticality 3.9.2 LIMITING CONDITIM FOR OPERATION )
- LCO
- .;.1.; The Reactor Coolant System lowest operating loop temperature (T ,,)
+ T. 4. ~2. shall be 1515'F when the reactor is critical. 2 APPLICABILITY: MODES 1 and 2 with 4 it 1.0. l AC. Tlc h) A ACTION: With a Reactor Coolant System operating loop temperature (T
< 515'F.ithin Mit- :the'lwx:
T ritht: it! ' trit ;O.;i. : ;;i=t= r be in nutes.
.) l MoOE '2 m .% l A4
\derc < t.o 1 l
4
$URVEI1DRcf mairvauDtENTS 6k ,
u4.1.1.5 The Reactor Coolant System temperature (T ,) shall be determined - l 4 ~3 4 2 I
. .. to be 1 515'F: I f -- . . U.: . 1; .; . te. ,,. ; m te eih;e.;i., ... J , 6riti6.iiii,..4-
% At least once per 30 minutes t- th: 7;;;;;- i; ;riti =1 n d th; A,3
- "-
- t;r Oeel;r,t Oylte ? , it !Mi t'.r ";T. j
- - ~ - - . -. ,
AM SR hjoTE: Gly r e ., . < d n 4o b P O ' ~M !
= ^- s--
RCS T mL .s2s*f . l oo ps,
- - - - _- M. t
. Ada: Y ' - - ., }} oks . ,, Om t y e q ui? #E 4o %e g o, Ca + 'r4
@ em '1~a h 526' I; is ae' RC S 1..p s ~ -
- ~
I 1
\/"S y NC$ 'I. i, p. b. uop 1 sis
- F l
i CALVERT CLIFFS - UNIT 2 3/4 1-9 Amendment No. 163 4 s
)
e, d 1
l CT5 ~5. ( . 2. I ]
.\
/4.1 ptACTIVITY CONTROL SYSTDt$
3/+ 1.2 BORAT10N.3YSTDIS Flow Paths - Shutdown j LDtITINE ITION FOR OPERATION l 3.1.2.1 As a inimum, one of the following boron injection fl paths and one associated t tracing circuit shall be OPERABLE:
- a. A flow th from the boric acid storage tank via ither a boric 1 acid pump r a gravity feed connection and che ng pump to the 5 Reactor ant System if only the boric acid orage tank in
' Specificati 3.1.2.7a is SPERABLE. or
- b. The flow path rom the refueling water tan vja either a charging or a high ssure safety injection to the Reactor l oc ant System i only the refueling wat tank in Specification 3.1. 7b is SPERABLE. l I
APPLICABILITY: MODES 5 and 6.
- With none of the above ow paths RABLE, suspend all operations nyo ving CORE ALTERATI0lts or post ive rea tvity changes until at least ,
one injection path is restored to O RAB status. l O SURVEILLANCE REQUIRDetNTS 4.1.2.1 At least one of the abov required ow paths shall be demonstrated OPERABLE:
- a. At least once per 7 ays by verifying at the temperature of the heat traced portio of the flow path is ove the temperature limit line shown Figure 3.1.2-1 when a ow path from the concentrated bort acid tanks is used.
- b. At least once r 31 days by verifying that a h valve (manual.
power-operate ,or automatic) in the flow path t at is not locked, sealed, or o twise secured in position, is in s correct position. At 3 'F and less, the required OPERABLE HPSI pump shall be in ull-to ock and will not start automatically. At 301'F and less. HP use wl11 be conducted in accordance with Technical pecification 3.4.g.3. CA ERT CLIFFS - UNIT 2 3/4 1-10 Amendmet.t No. 178 O
,, a,
._.___ _ -._ _ _ . _ _ . . _ - _.__ _ _ _ . . _ _ _ _ . _ . _ _ ~. _ _ . _ _ _ . . _ . .
CT$ ~5.l.2,2, 4 4 iO i R.t 3/4. REACTIVITY CNTROL SYSTDi$
- 3/4.1. B0 RATION SYSTDtS Flow Paths - Doeratine LIMITING C05 ON F9R OPERATI M i 3.1.2.2 At least we of the following three boron injecti flow paths and
- one associated heat tracing circuit shall be OPERABLE
4
- a. Two flow pa s from the boric acid storage ks required to be OPERABLE pu ant to Specifications 3.1.2. and 3.1.2.9 via either a Doric cid pump or a gravity f connection, and a j charging pump t the Reactor Coolant 5 es, and
- b. The flow path f the refueling wate tank via a charging pop
! to the Reactor Coo nt System. j APPLICABILITY: NODES 1, 2, 3 4. l Aflign: With only one of the a e requ boron injection flow paths to j the Reactor Coolant System GPERAB , ore at least two boron injection
- flow paths to the Reactor Coolant s to OPERABLE status within 72 hours
- or be in at least NOT STANDBY and bo ted to a SNUTBOW MARGIN equivalent i to at least that required by Specif c ton 3.1.1.1 at 200*F within the next l 4 6 hours; restore at least two f1 pat to OPERABLE status within the next i
7 days or be in COLD $5UTD0lAl wi in t next 30 hours.
$URVEILLANCE REIlUIREMENTS 4.1.2.2 At least two o the above required flow ths shall be demonstrated OPERABLE:
- a. At least ce per 7 days by verifying that he temperature of the heat tra d portion of the flow path from t concentrated boric acid ta s is above the temperature limit 11 shown on Figure .1.2-1.
- b. At est once per 31 days by verifying that each Ive (manual, r-operated or automatic) in the flow not locked, s led, or otherwise secured in position, is path in that its treet sition.
CALVERT CLIFFS - UNIT 2 3/4 1-11 Amendment No. 163 O n or 2
<T5 7. t . 2 . 2 1
- 1 f~
R.\ / 3 REACTIVITY CMT40L," M
- SURVEIL EQUltDWITS (Continued)
; c. At least one REFUELINE INT y verifying on a SIAS test j signal that:
(1)eachautomatic e in t path actuates to its correct position. (2) ric acid pump starts. i i l O CALVERT CLIFFS - UNIT 2 3/4 1-12 Amendment No. 163 l O 73, 2 .a
l c_T 5 3.t.2.3 l i i O O j 3 REACTIVITY CONTROL ST5TDi$ l 3/4.1.2 B0 RATION SYSTDIS
- arnina pian - Shutdown LDt! TING COMITION SPERATION 3.1.l.3 At least one che pump or one high pres re safety injection l pump in the boron injection path required OP LE pursuant to specification 3.1.2.1 shall be LE and cap e of being powered from an SPERABLE emergency bus.
APPLICABILITY ' ISDES 5 and 6. ,
- With no charging pump or pressu safety injection p op
' Lt. suspend all operations volving CORE ERAT 10fts or positive l reactivity changes until at I t one of the requi pumps is restored to l OPERABLE status. SURVE!LLANCE RDIDITS l
- 4.1.2.3 additional Surveillance Requirements other than those requ i by Spe ication 4.0.5.
l J 4 ( i l
~
i . At 301*F and less, utred OPERABLE HPSI pump sha pull-to-lock and will not start a __ N11y. At nd less. HPSI pump use will be conducted in accord Technical Specification 3.4.g.3. CALVER - UNIT 2 3/41-13 Amendment No. 178 4 !O p 3e !Jl
.. . . . . . _ . - - ._ .. _ _ _ _ - - _ .- ~ _ _ . . .
G.T 5 3. t . 2 . 4-1 l 4.1 SEACTIVITY CONTROL SYSTDt$ 3/4. BORATION SYSTDt3 Charcino Pumos - Doeratino LIMITING C ON FOR OPERATI M 3.1.2.4 At less two charging pumps shall be OPERABLE.* APPLICABILITY: 1. 2. 3 and 4. With only on charging pump OPERABLE restort at least
- c arg ng pumps to OPE LE status within 72 hours or be in at I st NOT STANDBY and borated to a UTDOW NARGIN equivalent to at less that required by Specification .1.1.1 at 200*F within the next 6 rs; restore at least two charging pump to OPERABLE status within the n t 7 days or be in COLD $ NUT 90W within the ext 30 hours.
SURVEILLANCE REQUIREMENTS 4.1.2.4 At least two charging pumps hall be d nstrated SPEAABLE: , s. At least once per REFUELING I ERVAL y verifying that each ( charging pump starts automatic ly Injection Actuation Test Signal. n receipt of a Safety
- b. No additional Surveillance Req nts other than those required by Specification 4.0.5.
i a ve 80% RATED THElpWLL POWER the two OPERABLE charging pumps shall have independent power supplies. LVERT CLIFFS - W IT 2 3/4 1-14 Amendment No. 163 i
!O pf i .e i
i cts 3 t .2. 5 i ! !O
- a. t !
1 l 3/4. REACTIVITY CMTROL SYSTDt3 3/4.1.2 B0 RATION SYSTEMS d ric Acid Pumos - Shutdown ) LIMITING CONDITIM 0PERATIM 3.1.2.5 At least one bor cid pump shall be ERABLE and capable of , being powered from an OPERAB emergency bus only the flow path through the boric acid pump in Specific ion 3.1.2 a above, is OPERABLE. j APPLICABILITY: HOSES 5 and 6. 1 i ACIlm: With no boric acid pump L as required to complete the flow i path of Specification 3.1.2.1a. spend al perations involving CORE ALTERATIONS or positive react 1 ty changes u 1 at least one beric acid i pump is restored to OPERAB tetus. l
\
SURVEILLANCE RE 5 4.1.2.5 No dditional Surveillance Requinments other than thos utred i by Specif ation 4.0.5. l J O N 1 1 J l 1 4
; CALVERT CLIFFS - UNIT 2 3/4 1-15 Amendment No.163 l O
I
. . . . . . - . - . . . . - . - - - - . - . . - - - - - . _ . - . - . - - - - . ~ . - - - -
) i CTS 3.t.7.6 b.) 3 .1 RFACTIVITY C01tTt0L SYSTDi$ 3/4. 30 RATION SYSTDt$ Boric Acid Pians - Onoratino j
\
i LIltITING ION Fet GPERATION f 3.1.2.6 l i a. The boric id pump (s) in the boron inj ion flow path (s) , required to erERABLE pursuant to 5 ification 3.1.2.2.a shall i be SPERA8LE a capable of being from an GPERABLE ! emergency bus. j .. I When in IIDDE 1 > 80% of RA TN POWER i
- 6. The boric acid pump (s) in boron injection flow path (s)
{ required to be OPERABLE rsu t to Specification 3.1.2.8.a shall a be OPERA 8LE and capabl of bei powered from an SPERABLE emergency bus. { i APPLICABILITY: IEIDES 1, 2 and 4. ! I i With one beric cid pump required for the von injection flow i i AGIN!): pathis pursuant to ei r Specification 3.1.2.2.a o 3.1.2.8.a inoperable.
- restore the boric ac pump to SPERABLE status within hours or be in at j least NOT STAISBY thin tne next 6 hours and borated t SNUTDOlel ll4R$1N equivalent to at east that required by Specification 3.1. 1 at 200*F
- l
! restore the abo requiredboricacidpump(s)toSPERABLEs tus within the
- next 7 days o be in COLD Si1WTBelAl within the next 30 hours.
l - SURV E REQUIRDIDITS i
.2.6 No additional Surveillance Requirements other than those requi j y Specifications 4.0.5 and 4.1.2.2.
/
t l 4 i i 1 { CALVERT CLIFF 5 - UNIT 2 3/4 1-16 Amendment No.163
;O py I oF i 1
! l i ,1 l cT5 3. l .2. 7 j i 3/4. REACTIYITY_ CONTROL _IYSTEM5 3/4.1.2 30 RAT 10N SYSTDi$ Berated Water Sources - Shutdown LIMITING CO W ON FOR OPERATION i 3.1.2.7 As a sin , one of the following borated water s rces shall be SPERABLE: j
- a. One boric a d storace tank and one associat at tracing l circuit with he tank contents in accordance th Figure 3.1.2-1.
- b. The refueling er tank withe j 1. A minimum cent ined borated water vo of 9.044 gallons,
- 2. A minimum solutt temperature of 5'F, and
! 3. A minimum boron tration o . 1 '
- a? 2300 ppe in HDDE and
- bJ the boron concente ion imit of Technical Specification 3.9.1 E 5.
- RELICABILITY
- ful0E5 5 and 6.
i - l : With no borated water sou es LE. suspend all operations i nv6 ving CORE ALTERATIONS or pos ive reacti ity changes untti at least j one borated water source is rest to OPERAB status. i SURVEILLANCE REQU!tENENTS i 4.1.2.7 The above requ d borated water source shall demonstrated SPERABLE: j
- a. At least e per 7 days by:
l
- 1. Ver ying the boron concentration of the water.
- 2. rifying the contained borated water volume of the ta . and 3 Verifying the boric acid storage tank solution temperatu when it is the source of borated water.
At least once per 24 hours by verifying the RWT temperature when it is the source of borated water and the outside air temperature is < 35'F. CALVERT CLIFF 5 - UNIT 2 3/4 1-17 Amendment No.179 O py ( . F 2.
i i f C.T 5 3. I . ~2. 7 t t I 4 k.l !, /4.1 REACTIVITY CONTt0L SYSTDIS 4 i i 170
- 1..:M:elis iiss.T::.i en . =t ,hrisb2 r: m.t i:.er .mL5.e=_i:..:a
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- FN' 7.y - --r= J --!:.: T-r r= . +i + ; FM .-.r e '.asu .x,;n my g.l 8 7 8 9 10 11 STORED BORIC ACID CONCDITRATION (m)
FIGURE 3.1.2-1 0115I188180RIC ACIS STORAGE Taint VOLIBIE Als TDIPERATURE AS A FullCTIOli 0F STORED B0RIC ACID C0llCENTRATIO11 LVERT CLIFFS - UNIT 2 3/4 1-18 Amendment 10o.163 l J ey 2 .e 1
]
4 i C 7~3 3.l 2 ) MovEO To SECTicN 3.5 AG 3.5.2 2/4.1 REACT!YITY CONTROL SYSTDt3 3/4.1.2 BORAT10N SYSTDtS j Charcino Pump ECCS Subsystem f LIMITIM COMITIM FOR OPERATION i 3.1.2.8 As a minimum, the following equipment shall be OPERABLE: I
- a. Boric Acid Storage Tank 22 and its associated heat tracing circuit shall be OPERABLE per Specification 3.1.2.9.a and the i 4 boron injection flow path via Boric Acid Pug 22 from Boric Acid I Storage Tank 22 shall be OPERABLE per Specification 3.1.2.2.a and f Specification 3.1.2.6. l l AND.
, One of the following: 4
- b. The boron injection flow path from Boric Acid Storage Tank 22 via *
; a gravity feed connection shall be OPERABLE per !
Specification 3.1.2.2.a. or. ! Soric Acid Storage Tank 21 and its associated heat tracing circuit shall be OPERABLE per Specification 3.1.2.9.a and the boron injection flow path from Boric Acid Storage Tank 21 via a O gravity feed connection shall be OPERABLE per Specification 3.1.2.2.a. APPLICABILITY: IWDE 1 > 80% of RATED TIERNAL POWER. ACI1gg: With only one of the required combinations of borated water sources and flow paths OPERABLE. restore two required combinations of borated water sources and flow paths to OPERABLE status within 72 hours or reduce power to less than 80% of RATED THERMAL POWER within the next , 6 hours and comply with Specifications 3.1.2.2. 3.1.2.6. and 3.1.2.g as applicable, m CALVERT CLIFFS - WIT 2 3/4 1-19 Amendment No. 163 l O n i .c 2
Sp ,c .c. ,s . ,, T.5.2 O o 1 x n _w e m _s n < ~ s9
- 5. 5 .
3, s. g . :/:.:.: -enA,+m-smas Qoe yn..,3 _ _ , - - - - Q LCo L - "" ' W h 3.3.2 --0.;.2.? ffYminimum the following equipmen shall be OPERABLE: *
- a. Boric Aci Storage Tank 22 and i associated heat tracing circuit 11 be OPERABLE per % cification 3.1.2.9.a a he boron ection flow path via ric Acid Pump 22 from ic Acid Stora Tank 22 shall be LE per Specification 3. 2.2.a and 5 Ication 3.1.2.6.
AND, of the following:
. The boron injection ow path from Boric Acid 5 rage Tank 22 via j a gravity feed c ction shall be OPERABLE 5pecification 3. 2.2.a. or, Boric Acid 5to ge Tank 21 and its associa heat tracing circuit shall 3.1.2.9.a and t O
OPERABLE per Specificat boron injec on flow path from Boric Ac Storage Tank 21 aa ravity f connection shall be GP per tpecifica on 3.1.2.2.a. APPL 4tAttttTjh NBDE 1 > 80% of RATB TREMAL POWER. pog ' With only of the requi combinations of rated water s and flow s SPERABLE, ore two requi ombinati s of ted water s es and flow s to OPERABLE s us within or duce power t ess than 80% RATED TWERNAL R within the J
,p'hoursand Iy with Spec cations 3.1.2.2 .1.2.6, and 3 .2.9 js a
Qp11 cable ,
=-
o-s r.a . 4. v g.. c.. c.q , g CALVERT CLIFFS - UNIT 2 3/41-19 Amendment No. 163 l O m s .r 6
[ ff S. l Io h j l
- 4 j MOVED To SBcTeow 5, 5 AS 3, 5, 7 l I
l i -
/4.1 REACTIVITY CONTROL SYSTDt3 SURVEILLANCE REQUIRDestis
}
4.1.2.8 No additional Surveillance Requirements other than those required a by Specifications 4.0.5. 4.1.2.2 and 4.1.2.9. 1 (. J f 1 4 s
- 1 i
) 2
\
l !O i 1 j i i 1 CALVERT CLIFTS - tillIT 2 3/4 1-20 Amendment No. 163 l O ey 2.v 2
hec. f. , , 4 .. % l. T. "2. O l l svavtrumcr asettomrrs _ , l C4.1f.8 by/ SpecMadditiog 1Fcations Surveillas/. a.eu1 f.0.541.2.2. and 4d4Min a+hmesian thoseAnutedd)
- A. ,
inst s,T sR Note k%s p.s.r 6 C su. . . a . . ,, a R, 7. 5.2. 4 v -. 5: 7 < c. c w c L. . $. 3 r~p -AA< , d,wr locas , f low .f 1 37 1 v.c4 ;, { T s o .., P, .3,. A' O CALVERT CLIFFS - UNIT 2 3/4 1-20 Amendment No. 163 l O p S, 6 .r 6
- crs 5, s. 2, p .
1 i 1 1
.\
6 j /4.1 REACTIVITY CONTROL SYSTDt5 3/4. 2 BORATION SYSTDt5 Berated Water Sources - Operatino i LIMITIM Com M FOR OPERATION 3.1.2.9 At Isast of the following three borated ster sources shall be OPERABLE:
- a. Two boric acid oragetank(s)and associated heat tracing circutt per tank th the contents the tanks in accordance with Figure 3.1.2- nd the boron centration limited to 5 8%,
and
- b. The refueling water tank
- 1. A minimum contained at water volume of 400.000 gallons,
- 2. A boron concentrat of betwe 2300 and 2700 ppe,
- 3. A minimum solu on temperature of , and
- 4. A maximum ution temperature of 100*F IEIDE 1.
APPLICABILITY: ful0E5 , 2, 3 and 4. O E1191: With on1 one borated water source OPERABLE, restore a least two borated water s rces to OPERASLE status within 72 hours or be in t least M T STANDBY w in the next 6 hours and borated to a $ NUT 90lAl MARGI equivalent at least that required by Specification 3.1.1.1 at 200' l restore a east two borated water sources to OPERABLE status within the next 7 ys or be in COLD 58UTDelAl within the next 30 hours. CALVERT CLIFFS - UNIT 2 3/4 1-21 Amendment lio. 163 O ge t .F 1
... .- . .- _ - - _ -. ._.- .- _ _ - _ _ _ - . . - ... _ _ - _. - ~.._ - - ~ . - .
4 CTS 3. \ . "2. , 9 i
/4.1 REACTIVITY C0lfTt0L SYSTDt3 AURV E REQUIRDIDITS 4.1.2.9 At two borated water sources shall be strated SPERA8LE:
- s. At least r 7 days by:
1 Verifying the cone atton in each water source.
- 2. Verifying the co ned ted water volume in each water source, and
~
- 3. Verif the boric acid storage tank tion temperature.
- b. At st once per 24 hours by verifying the Infi t ature when ,
outside air temperature is < 40*F. O CALVERT CLIFFS - UNIT 2 3/4 1-22 Amendment No. 163 l O Pat, u2
l Te,.. r. , a... T . i . +- lO I l 3.l 4ft;t REACTIVITY CONTROL SYSTDt3 3, t , & -;/0.;.; rfr_: J.R= l CEA
- h. _-
trurTras c0 m m en pea OptRATIN 3**M
- 1.3.! The CEA Motion Inhibit and allkowngreguTsti$XEAs shall be OPERABLE with each CEA of a given gewup posnionea vunin i.5 inches (indicated position) of all other CEAs in its group.
APPLICABILITY: NODES 1 and [ I sum: .
'. ad +?+,
7 N k With one or more CEAs (regulating or shutdown) inoperable due to ( being untrippable, be in at least NT STAMBY within 6 hours. M'
- 4 6 / ( With the CEA Motion Inhibit inoperable, within 6 hours either:
<*c T/+ g.24\,
p, , g, f EL?.i L Restore the CEA Motion Inhibit to OPERABLE status, or
, / 11 1. Fully withdraw all CEAs in groups 3 and 4 and withdraw the e N CEAs in group 5 to less than 54 insertion, or f
An i o*J o f 19 c,a . , , m 3. Be in at least BOT STANDSY. f
. With one regulating CEA inoperable due to causes other than 3 addressed by ACTICII a above, and inserted beyond the Long Tem I l$teady State Insertion 1.inits but within its above specified alignment requirements, operation in MODES 1 and 2 may continue
'f
$or14up daystoper7 calendar says per year.occurrence f with a total accumulated time of) 1
. With EA treguisung unu w - ; inoperso sue to ca et than addressed by 2011 a above, but thin its above s cified alignment utrements and ett fully withdra ,
ithin the Long Te steady State Inser n Limits if in V Laroun 5. operati in M DES I and 2 continue.
-N0 k ~~ ~ '
f,eh*p Wq ain a gd'ogy l% r., L . . ., s . . - 5p , , F. , 4 . ., e r cL..m-s T. f.k " p,g,4 t gk CEA. < - s , , 4, . , t . ~ . 4 ., " 3 Y )' n,- Wf$dw* lbput
J ,1 f/G 5pesh(F TestJat'EptientK10.2Alf3.E44 Q
f'- CALVERT CLIFF 5 . UNIT 2 3/4 1 23 Amendment llo,163 O l p.y ( F5
. i
l l $ ye & <.A.e, s. t . C l lO T j 3/4.1 MACTIVITY CONTROL $1 M 3/4.1.3 NOVABLE CONTRot AS$DSLIES. j CEA Position l 1 LIMITINE CSSITION F98 SptRATION
- I f 3.1.3.1 The CEA Motion Inhibit and all shutdown and regulating CEAs shall
- - be OPERABLE with each CEA of a given group positioned within 7.5 inches j (indicated position) of all other CEAs in its group. .
j APPLICABILITY: INDES 1* and 2*. i EllGE8 2
- a. With one or more CEAs (regulating or shutdown) inoperable due to
! being untrippable, be in at least NOT STANDBY within 6 hours. j b. With the CEA Notion Inhibit inoperable, within 6 hours eithers
- 1. Restore the CEA Motion Inhibit to OPERABLE status, or a
Fully withdraw all CEAs in groups 3 and 4 and withdraw the 2. CEAs in group 5 to less than 5% insertion, or Q_ Be in at least SOT STAISOY. l [.'With regulating CEA i ble due to causes et than f add ed by ACTION a abow and inserted beyond t Long Ters - 5t dy State Insertion Li ts but within its abov specified g, s , gnment requirements peration in NODES 1 a may continue for up to 7 days per currence with a total cumulated time ( 5 14 days per cal er year.
- d. With one CEA treguienng or snutoown) inoperable due to causes'
- other than addressed by ACTION a above, but within its above y specified alignment requirements and either fully 'rithdrawn or within the Long Tern Steady State Insertion Limit *, if in CEA
- . group 5 operation in NODES 1 and 2 may continue, i
l } $,e de s, . ..m .F <% = s* > (,t ag , c . f. c.,4. - 3. l .
- "dA A t . 3., _ , a ' '
i j h See special Test Exceptions 3.10.2 and 3.10.4.) CALVERT CLIFFS - UNIT 2 3/4 1 23 Amendment No. 163 j
- O 4
3e+ 7 9c
i i 4
$p-cAc*+ien T, t , t 4
LIMITIM COMITIN FOR SPERATIM (Cestimmed) N k *,, other DAs es A With CEA in one its CEA group(regulating by less thanor15shutdown inc . sisaligned ration in from1 ba
*h .s / r d **.*
- and 2 may continue, provided that the misa igned CEA is restored 4i Ab to within its specified alignment requirements within one hour.
otherwise implement Action g.
- f. WithoneCEA(regulatingorshutdown)misalignedfromanyother Ac,mg 4 CEA in its group by 15 inches or more, operation in NgDES 1 and 2 2g may continue, provided that the misa11gned CEA is tored to within its soecified alignment requirements within s1me
- c. 4.. .. . uniowance setermined by 5 ivii w ,_ _;. e sriestion monitor system or. if full core powe distribution .
mont ins system time Iowance is unava able the all le ti shall be that p vided in the COLR therwIseimpi t ion g. If the LR allowable time used, the p isalignet. P value used to etermine the all le time to re go the CEA - sfm11bethe1 est measurement t en within 5 da prior to t CEA misali nt. If no measu nts were tak ithin 5 da . trier to misalignment./Temectately 1mplement Action g.
- cti O
I 1. L.* b CM gh.. F. pl*t .1.L..e L3 n.- c rs , Ac kaa , . A bea ]
+= n.In p.av CALVERT CLIFFS - UNIT 2 3/4 1-24 Amendment No. 163 O
, s. 2 ., s
1
%-eVle 6 4 ~$ . I , +
l 3 l0 b F5'$ j c* 2b i 3/4.1 REACTIVITY CONTROL SYST MS i: .l. k b PId8 LIMITING COMITION FOR OPERATIM (Castissed) h, , h,. 43 K With one CEA (regulating or s down) not within its specified alignment requirements at t conclusion of the time allemence h inmediately start to implement
- permitted by Actions e, f
- the following actions
- g. If the TN level orier to the mise 11 t was T
- M tOtJ 7 greater an of BATO ThEMAL , 13 p0MER 11 1 L. 2 be ced to ess than the gre er of:
1 A. I i M.5 50% of TG TBEMAL l ! L b) 75% f the TEEMAL 1evel prior to the misaliennent) R.Jx TCD. r {ter exceeding the time allowance pemitted by '[ - P
- 2. If the T5 level prior to misalignment was
! TREMAL p0WER. mai n TREMAL p0MER no 1 < 50% of I1ehert the value neier to t misali-l be one hou r estaD11sning the appropriate TBEMAL p0WER as required above, 1 eithers l M..t o*J 4,7 [~% Restore the CEA to within its specified alignment (, requirements, or ! 2. the CEA indberable. nzaer ceclar na,4ne s.uu ! b1_a/ POWER ersunnen may continue "or up to 7 days per ACn oN occurrence with a total accumula ed time of < 14 days per A,- alandar year provided that/El ; ; hous efts m - g* dem < -- reniam . i,,,,.. of sne CEAs in the troup 1 with the inoperable CEA are aligned to within 7.5 inches of i the inoperable CEA whiles Fa) maintaint allowable CEA seg e and CEA groit l insert inits located in the LRs for a regulati i C nd with the TBEMAL level restricted uan Soecification 3.1.3.6 inn subseeuent on. or A,3 f ^maint ing the remainde of the CEAs ing shutdown i f kJ wi wn to at least inches. ,
<ee 4.s s m... . F eL m. ,
F,r v < h+ ..- 3. L . f --d s.i6 w.,u - c a i s. 4.., t.. . w <> i !
- b
- l a+.es. cFA I m e.&.. L . . q
CALVERT CLIFFS - WIT 2 3/4 1-25 Amendment No. 163 i lO r Y T O 'a( l - - - . __. _ - _ - . . _ _ - -
{ Sp ec . G e g-t,,, '5. t .F i lO 4 3/4.1 MACTIVITY CONTROL SYSTDt$ LIMITING Co W ITION FOR OPERATION (Continued) ['s. With one CEA ( lating or shutdown) not within its a cified K alignment requ raments at the conclusion of the time aNowance l the following actions: permitted by Actions e, f or h 1emediately start to impleme
- 1. If the TNERNAL POWER level prior to the misalignment was greater than 50% of RATED TREEMAL POWER. THERMAL POWER shall be reduced to less than the greater of:
a) 50% of RATED THEWIAL POWER b) 75% of the THERMAL POWER level prior to the misalignment , within one hour after exceeding the time allowance pemitted by Actions e f or h.
- 2. If the TNERNAL POWER level prior to the misalignment was
- 50% of RATED THERMAL POWER. maintain TNERMAL POWER no j Eigher than the value prior to the misalignment.
If negative reactivity insertion is required to reduce THERNAL POWER, boration shall be used. Within one hour after . estabitshing the appropriate THERMAL POWER as required above, either:
- 1. Restore the CEA to within its specified alignment requirements, or
- 2. Declare the p inoperable. After declarine the CEA Moccurrence with_a total accumulaned time of < 14 days perinoperablearvdE Actig 4 dar yearJrovided that with' n one haur ar".er declart EA inoperable /The remainder of the CEAs En the w th sne inopersole CEA are aligned to within 7.5 inc s of the inoperable CEA while:
Ymaintaining the allowable CEA secuence and CEA group7 insertion limits located in the COLR; for a regulating CEA and with the TNERNAL POWER level restricted pursuant to specification 3.1.3.6 during subsequent operation, or , b) maintaining the remainder of the CEAs in a shutdown group withdrawn to at least 129 inches. J I*'r dw c .<. s i % .F c.% g. g F=e se #. e -t e .e 3. l .
'cea Ai y -_
CALVERT CLIFFS - UNIT 2 3/4 1-25 Amendment No. 163 O
, .m n
l Sp a .N +.o% '3, t . (, t j i !O 4
-8/4.4-4fMHHP'4ieN5hb4485 ENS-l Ig'. WithoneCEA( lating or shutdown) not within its a cified
, alignment requ resents at the conclusion of the time a owance i pemitted by Actions e, f ,r n tunedtately start to implement the following actions:
- 1. If the THERNAL POWER level prior to the misalignment was e
greater than 50% of RATS TRERNAL POWER. THERMAL POWER shall j' be reduced to less than the greater of a) 50% of RATED TWElgiAL POWER j b) 75% of the THElpiAL POWER level prior to the misalignment . ! within one hour after exceeding the time allowance permitted by Actions e, f or h. , L. If the TWERMAL POWER level prior to the misalignment was
< 50% of RATD TNFRNAL POWER, maintain TNERNAL POWER no Eigher than the value prior to the misalignment.
If negative reactivity insertion is re.;c-d to reduce THERMAL ! POWER, boration shall be used. Wit',in one hw.ir sfter j establishing the appropriate THERFAL POWER a required above, either: 1 1. Restore the CEA to within its s'>ect',ted alignment j requirements,or M. 2
- 2. Declare the CEA inoperab1_e. After declarine the CEA
- i- ;;d';. ertuuvu y continuefor up to 7 cayf per
- currence w a total a 4 lated timro f < 14 daysyfr calendar we provide
- hin one hour after acciari I t C r G ina w ahTBf 1 -erd er ^ ih CMa in 5 yrvdp j with the' inoperable are ali to within inches o thpeperable C 11e:
l I y ini.161i in siiewspie 6t.n sequence and CEA group i insertionlimits located in the COLRs for a regulating l CEA. and with the THERNAL POWER level restricted pursuant to $pecification 3.3.3.6 during subsequent operation, or b) maintaining the remainder of the CEAs in a shutdown group withdrawn to at least 12g inches. j t (,, 4 u m,.* S c'a 5- s / F.r Q.G. 4,.-.
~4.1. t"G A
] I .,+.. , L.. . + i 4 CALVERT CLIFFS - UNIT 2 3/4 1-25 Amendment No. 163
. O
- 1 th ! O
1 h,, . f, c. 5, o ~5.t. + i !O I i 1 l 4 3/4.1 REACTIVITY C00mt0L SYSTD15 ! LIllITIM COMITIM FOR OPERATIM (Contissed) gW'" A
- h. With than one CEA ( ulating or shut misaligned and otherCIAinits];
eac isaligned CEA is t in 15 inches of i ) mcan 4,p,4 ,
/
g p (indicated pos ir specified al on)restorethemi Itened CEAs to wit n nt requinments thin one hour, et s . immediately dec1 the misaligned C inoperable and i
- </ % '
If y one CEA (Mgula orshutdown) ement (Action misaligned 1. a and of one hou . implement Action g era AC tioQ D K da r r - +6.- e 77 - _ . _-_ withmorethanoneCEAdrogulatingorshutdown)misalignedand any one or more of the misaligned CEAs is 15 inches (indicated j sition) or more fmm any other CEA in its group, be in at least , STANSY within 6 hours._ _ i (seO 6 l %g r _fe lle m .iy c.EA -
~ev* m v-
.c
> r. s .s{.S a -
p =- O bervi44 / SURVEILLANCE REQUIRENDITS _f = _=
*4*I 0.:.0.1.; The position of e EA shall be detemined to be within h7.5 inches (indicated ooson) of all other CEAs in its group at least._
bAcuoy
'" ' * * *
- 9 lonce per 12 hou surin time in5=rveis . .. sne swvission circui
~
g g* l nd/or ctA notion it are knoperable, then verify the individual C O % 3. \ . 4.4. sitions,at les_
.3.:."
by inserting E e per 4 hours. er cgg CEA not fully inserted shall be determined to be OPERABLE 92 at least 7.5 inches at least once peria osys.fror s 6 Ming sne 6ta L.4
..biiis 6tA nas an p rabl k(no,~e... sitionindicatioeannel,tbtest.17t alterna indication system 1 pulse nter or voltage d iding network) will used to monitor positi . If a direct po tionindication(ful out reed switch or Itage divi ng network) canno restored within t minutes from the 43 e ncement of CEA ton, or CEA withdrama exceeds the survel ance esting insertion b = 7.5 inches, the pos ton of the CEA sha be assumed lohavebeen>1 nches from its group the connencement CEA metian >)
% 3.1. 4.3 .i.;;.i.;; T once per tion Inhibit shall.be demonstrated OPERA 8LE at least
,als rb. .y a func si seus wni6n visiv. so.6 .n si uit 4h1 CEA group erlap and sequ ng requirements o Specif ation 3.3.3.6 that the ci t also prevents a EA from being A.
mis gned from all her CEAs in i roup by more than .5 inches [ icated positi .f had -
& CEW dev '% gg 4
- gh.i+- !s ophtu.t!.
,' {
Aa: @ 4.s 9( pos4,*.% ,a...,__ .-l-c.. o r y e ca w .4er *b.
, R s4_
e) i '* *M S CALVERT CLIFFS - UNIT 2 3/4 1-26 Amendment flo.163 l O ! py+35
g~ x,e., 1.<. 5 [ i i !O i l . 3/4.1 REACTIVITY ColffROL SYSTDt3 LIMITING COMITION FOR OPERATION (Coettneed) MTl CN A \ With more than one CEA (regulating or shutdown) misaligned and each misaligned CEA is within 15 inches of any other CEA in its group (indicated position) restore the **C 1 " 1A3 to within their specified alignment requirementsGr th'n one tour otherwise L* 1emediate1Ldeclare the mina11- " cEAs ' Enrable and implement Action 1J If only one CEA (regulating or shutdown) remains 11saligned at the end of one hour, implement Action g.
- 1. LWith more than one CEA (regulating or shutdown) 1-aa^rablasor AcTeoN B with more than one CEA treyussung or snu5 gown) misaHgned and any one or more of the misaligned CEAs is 15 inches (indicated hion) or more from any other CEA in its grAou_n at leasD L.
m a wunin = - - - SURVEILLAlK: CEttRRDebiT5
.1.3.1.1 The position of each CIA thall be detemined to be within
.5 inches (indicated positi" *- CEAs in its group at least]
once per 12 hours exe.ept . . '3 when the Deviation Circuit and/or CEA Motion Ir.hibit %n verify the individual CEA positions at least once pt., 4.1.3.1.2 Each CEA not full) . .erted shall be determined to be OPERABLE l by inserting it at least 7.5 inches at least once per 31 days. For the purposes of performing the CEA operability test, if the CEA has an inoperable position indication channel, the alternate indication system (pulse counter position. or voltage If a direct positiondividing indicationnetwork)(will full out reedbe usedor switch tovoltap monitor t dividing network) cannot be restored within ten minutes from the commencement of CEA motion, or CEA withdrawal exceeds the surveillance testing insertion by > 7.5 inches, the position of the CEA shall be ass to have been > 15 inches from its group at the commencement of CEA motion. 4.1.3.1.3 The CEA Motion Inhibit shall be demonstrated OptRABLE at least once per 31 days by a functional test which veriffes that the circuit . maintains the CEA group overlap and sequencing requirements of Specification 3.1.3.6 and that the circuit also prevents any CEA from being misaligned from all other CEAs in its group by more than 7.5 inches Qndicatedposition). , , S ee J.sc w.m ,9 ch3,3 fee $ p,,h,*,,, o., y, g ,g -
"C E A Al.p.., t "
CALVERT CLIFFS - UNIT 2 3/4126 Amendment No. 163 l O py + .9 +
cT5 3.1.l.3 } ! /4.1 SEACTIVITY CNTROL SYSTDi$ l 3/4 .3 MDVABLE CONTROL A55DBLIES position Indicator Channels ! LDt! TINE ITION POR OptRATION 3.1.3.3 At les two of the following th-ee CEA po tion indicator channels shall GPERABLE for each shutdown and ulating CEA:
- a. CEA volta divider reed switch positi indicator channel, capable o temining the absolute position within i i 1.75 inches j
- b. CEA ' Full Out" o " Full In* reed itch position indicator channel, only if t CEA is full withdrawn or fully inserted, as verified by actuati of the ap icable position indicators and
- c. CEA pulse counting pos ton i icator channel.
APPLICABILITY: IWDES 1 and 2. AGIl0E:
- a. With a maxima of one EA per g having its voltage divider reed switch position ndicator cha 1 or its pulse counting O position indicator annel inoperab andtheCEA(s)withthe inoperable positi indicator channel artially inserted, either:
- 1. Within 6 a) Rest the inoperable position ind ter channel to GP LE status, or b) in at least NT STAMBY. or c Reduce TNERNAL POWER to 5 70% of RATED TN POWER: if stive reactivity insertion is required to ce TN p0WER, boration shall be used. Operatio at or below this reduced TBEMAL POWER level may conti provided that within the next 4 hours either:
- 1) The CEA group (s) with the inoperable position indicator is fully withdrawn while maintaining CALVERT CLIFF 5 - Ultli 2 3/4 1-27 Amendment No. 163 O
gy t or 3
<!. T S 3. l . 3, 3 1
O O 3/4.1 REACTIVITY C0llTROL SYSTDt3 l l l LI TIIIG C0m!T3001 FOR OPERATIO11 (Continued) 4 l the withdrawal sequence nquired by Specification 3.1.3.5 and when this CEA g reaches its fully withdrawn position. t Full I Dut" limit of the CEA with the inoperab position indicator is actuated and verifies th CEA to be fully withdrawn. Subsequent to ful withdrawing this CEA group (s), the THElstAL level may be returned to a level consistent w h all other j 11 cable specifications and ration may j c tinue per Specification 3. 3.3 aboves or
- 2) The with the perable position indicat group is ful(s)ly inse , and subsequently maintai fully insert . while maintaining the withdrawal vence a THERMAL POWER level 4 required by ciff ion 3.1.3.6 and when this CEA group maches : 11y inserted position, the Full In" Ilmit the CEA with the inoperable indicator is ac e and verifies this CEA to be fully insert . Su equent operation shall be within the 1 its of cification 3.1.3.6. and may
, continue Specificat n 31.3.3 above. ~ or.
- 2. If the fallu existed before entry in MODE 2 or occurs prior to an all CEAs out' configuration theCEAgroup(s) with ino ble position indicator channe st be moved to the "Ful t'gositionandverifiedtobe 11y withdrawn via a
- 11 Out indicator. These actions t be completed withi 10 hours of entry into N00E 2 and prior o exceeding 704 f RATED THERMAL POWER. The provisions of l 5 cification 3.0.4 are not applicable. Once thes actions completed, operation may continue per Specification 3.1.3.3 above.
- b. ith more than one CEA per group having its CEA pulse counti position indicator channel and either (1) the ' Full Out' or
- u In' position indicator, or (2) the voltane divider position indicator channel inoperable, operation In IIODES 1 and
/
t
; CALVERT CLIFFS - UllIT 2 3/4 1 28 Amendment No.163 O
n u3
CTS d T. l . ~3. 3 1 S .\ i ! /4.1 ptACTIVITY CONTROL SYSTDIS j TING CO WITI M FOR OPERAT!aN (Contiamed) j 2 may continue for up to 24 hours provided that for the facted j EAs. either: f 1. The CEA volta r reed switch position i cator
- nnels are , or j -
- 2. The
' " Full Out" or " Full In" reed swit position indic or channels are OptRABLE. with t CEA fully withdrawn i or full inserted as verified by act ton of the applicable J position icator. i 1 SWVEILtANCE REQUIRDIDITS x 4.1.3.3.1 Each required CEA positi indication channel shall be i determined to be OptRABLE by date ni CEA positions as follows at least once per 12 hours, by:
- a. Verifying the CEA 1se counting ition indicator channels and
- the CEA voltage vider reed switch sition indicator channels agree within 4 inches, or 1 -
J
- b. Verifyi CEA pulse counting position ndicator channels and I
the CEA 11 Out" or " Full In' reed switch sition indicator j channel agree within 4.5 inches, or ! c. Ver ing the CEA voltage divider twed switch po ion indicator c nels and the CEA ' Full Out' or " Full In" reed tch position ! icator channels agree within 4.5 inches. 4 4.1.3. . During time intervals when the deviation circuit is 1 able, the ve verification of required CEA position indicator channels s 1 be ma at least once per 4 hours. c n l E
- CALVERT CLIFFS - WIT 2 3/41-29 Amendment No. 163 l 1
l0
., - - , r- -
$pec[r=4-s 3=I k O
f~3/4.1 REACTIVITY CONTROL SYSTDt3 3/4.1.3 DOVABLE CONTROL ASSEMBLIES CEA Dron Time LDt! TING CONDITIO11 FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) CEA drop time, from a fully withdrawn position, shall be 3.1 seconds from when the electrical power is interrupted to the C rive mechanism until the CEA reaches its 90 percent insertion position with:
- a. T.,, t 515'F. and
- b. All reactor coolant peups operating.
APPLICABILITY: MODES 1 and 2. AGIIn: with the drop time of any full length CEA determined to exceed the above limit, restore the CEA drop time to within the above limit prior to ) ('y r..dtna en isnnr i e _a, SURVEILtJUICE REQUIREMENTS _ N 3' I * *6 4.1 ? 4 The CEA drop time of full length CEAs shall Le demonstrated through measurement prior to reactor criticality: ' y For all CEAs following each removal of the reactor vessel head, fb. For specifically affected individual CEAs following any maintenance on or modification to the CEA drive system which ' could affect the drop time of those specific CEAs, and tc. At le6st once per REFUELING INTERVAL. i (" di s c o.. ... ,F ch. 3,g
$ 0 *ef..=4. o a; g ,3, 4, "C E A Q , p T , ,.
- CALVERT CLIFFS - UNIT 2 3/4 1-30 Amendment No. 163 a
p.Sc 5 .F 5
3 CTS 5. I . 3. 4-1 O a.1 1,
- 3/4.1 REACTIVITY C0llTROL SYSTDt3 i
3 .3 90VABLE CONTROL A55DSLIES 1 l CEA Bron Time
- LDlITIIIB C01BITICII OPERATICII
! 3.1.3.4 The individual fu engt hutdownandcontrol)CEAdroptime, I i from a fully withdrawn positt all be 1 3.1 seconds from when the electrical power is interrup to CEA drive mechanism untti the CEA i reaches its 90 percent i ion post withs i j a. T.,, 3 515* and
~
- b. All ctor coolant pumps operating.
l APPL 1 CAB : 98DE5 1 and 2. ! : With the drop time of any full length CEA determined to exc the i ve limit. restore the CEA drop time to within the above limit prior t 1 i proceeding to 9100E 1 or 2.
/
I jO ---- 61.3.4 The CEA drop time of full length CEAs shall be demonstrated
- through measurement prior to reactor criticality
- )
Q For all CEAs following each removal of the reactor vessel head, j 4 specifically aTTectec individu s following any j aatntenance on or modiff he CEA drive system i could affect me of those specific CEAs, i
- e east once per REFUELIIIG IllTERVAL. j 1
l1 T J. u . . ... e a ,,, i F., (p . r, .. +, _ 3. i , t+, 3 -, l CEA At.y - s
- e l CALVERT CLIFF 5 - Ull!T 2 3/4 1-30 Amendment No. 163 i
l
i j 67c ifi 4.,s 7. l . 5 i i O
~3. I W REACTIVITY CONTROL SYSTDt3
- 3. t . $ efett !!tt!dM-f9EEMiggGE-
, Shutdown CEA Insertion Limit l l LIMITING CONDITION FOR OPERATION .
"O 'b l . O :.;.0.; All shutdown CEAs shall be withdrawn to at least 129.0 inches.
APPLICABILITY: N0 DES 1 and 2 m, _ .g. l Ar.TioW$ ACTION: With one or more shutdown CEA s) withdrawn.Axcept Top A,t3, 4 c veillance testing pursuant no 50ec1"icarian s.i 1.1.7 i Ina
.0' nchesAnsiderthe CEA:s isa'igne el
/ GoeotT' catwn 3.1.34. Actio , f. h ory,yand issne ste.
as app
]
Appl . . .s. i .4 wq - l NS ERT -h A 4 d. 4 A' 7, L. L.7 3 J SURVEILLANCE REQUIREMENTS
+:tt 5 Each shutdown CEA shall be detemined to be withdrawn to at least Sq 3* g
- 5- l 129.0 inches:
minutes for to with wel of any sinre[ sting CargroWithi during a approach to reactor criti ity, and
- b. At least once per 12 hours theree44ec.
l i l l i i s 3pn i s'. 'e.1 L;;FlieT.3.l0.2. CALVERT CLIFFS - UNIT 2 3/4 1-31 Amendment No. 163 l l O 1 y i .c +
Seef.c h 3.1. 5~~ l INSERT ACTIONS A,B,C i CONDITION REQUIRED ACTION COMPLETION TIME l' A. One shutdown CEA A.1 Verify the accumulated Once within 4 hours withdrawn 2121.5 times the Shutdown CEAs j inches and < 129 have been withdrawn /@2 inches. 2121.5 inches and < 129 l inches. 24 hours thereafter l I l B. One shutdown CEA B.1 Restore shutdown CEA(s) 2 hours withdrawn 2121.5 to within limit. i inches and < 129 inches for > 7 days per occurrence or > 14 days per 365 days. M One shutdown CEA withdrawn < 121.5 inches. M Two or more shutdown CEAs not within limits. C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion 4 Time not met. O er +
.- - -. - - . . - - . _ . _ _ . _ . - .. - - _ . ~ . . . . . _ _ _ _ = . _ _ . -
$ pre M r.4,'en 3.l.6 l 3.l 9/4,4 SEACTIVITY C0llTROL SYSTDi$
3, t , ( 0/4.1.; Re AZ CCL ".*SL".* Reculatino CEA Insertion Limits _ _ _ --_- w -
- p. ,E, 'J eh.d. 4 .a s -<4 ' = a l'a M (@O' L) ;
i LIMITIns conoIT!cu FOR OPERATION -i _ _r = ' d +d '-* '#"% * *d LCO "3.1 6 -;.;.O.4M regulating CEAsequence and to the insertio!roups shall be limited to tl . limits provided in the COLRJ[ regulating CEAs ' re constere; to se runy wunerswn .f.... wunerswn to at least i 29.0 inche n ctA inswruen ew6 ... nu wnv ivr= 36 vy u ste L A .1. seruon um and the Transient ion Limiti, rest cted tot
- a. < hours per 24 hour terval, .
b < 5 Effective Full r Days per 30 E ective Full Power ey
- Tnterval,and
- c. 5 14 Effective ull Power Days pe calendar year.
APPLICABILITY: N00ES1and2ktM l . , EIIM: - I M'T TON A a. With the ulating CEA groups inserted beyond the Transient , nnerY on mitt /Except for avr,wiii ns. 6c m ng pursuant tC
- ineci+ cation 4.1.3.1.2/vitnin two nours enner: -
l AffilteI't y
- y g g, p 1. Restore the regulating CEA groups to within the limits, or
- 2. Reduce TMERNAL POWER to less than or equal to that fraction of RATED TNERNAL POWER which is allowed by the CEA group
- position using the limits provided in the COLR. l
- b. With the regulating CEA groups inserted between the Long Tern Steady State Insertion Limits and the Transient Insertion Limits for intervata. E4 hours oer 2L,hpur interyg AC1 ton B dfier'ations s crsuant to M Trevisions of 4 ON c.--and-e of Specification 3.1.3.1. operation may proceed prov1oea :
1. The COLR short Tem are not StaedyorState Insertion Limits provided in the] exceeded, l 2. Any subsequent increase in THEMIAL POWER is restricted to j hhs 3Q g 5% of RATED TREAMAL MIWEP per hour. 5-. +r I [ WSpecial Tset'TxceptionM2 and)(16.4] CALVERT CLIFFS - UNIT 2 3/4 1-32 Amendment No. 163 j b v p,$c I oF b
f l 5 73 , 9,, +,. , 3.1. (, 4 !O 4 i 3/4.1 REACTIVITY CONTROL SYSTDIS { LIMITI116 C01SITION FOR SPERATION (Continued) i
- c. With the regulating CEA stoups inserted between the Long Ters Steady State Insertion Lleits and the Transient Insertion Limits AC*tio N C for intervals > FPD ner 30 EFPD_ interval or > 14 MD ner M NEE" M iU" 8'.!.'"*r E M I M M either:
i 1. Restore the regulating groups to within the Long Ters Steady j State Insertion Limits within two hours, or ,2 f 2. Se in at least Bef STAlWBY within 6 hours. p, , , n =- __ SURVEILLAllCE REQUIRDIENTS C'
- _ ' j_
SR L t.4.1 3 ".i.2.- The position of each regulatt group s ell be deteral be within the Transient Insertion Limi at least once per 12 hou excep ActtoN o curing neu inwrv is . .. we ruk .;. . O' ..'. . .. i. 4raoi rify the individual CEA oositionsdt least once ser 4 tou The faccumulated times during wnten sne ulating CEA groups are inserted M l l . 6.1 beyond the Steady State Insertion Li O I s but within the Transient Insertion dimits shall be determined at least once per 24 hours. f AJ4 - G R 3.1. 6. 3 V,...C'r POn L ai. -. or<m+I Tl e 4 oPemAste %s _= -
~
n .. ,....i.~. :. - . , . . . , ,. .
- 1. - p .. C. . ~ , J .s , .aay t., A u
- 7. . . .
eede '2. _ f- - CALVERT CLIFFS - Ull!T
- 3/4 1-33 Amendment llo.163 l m 2 .v +
i
. c c. s Fv.A . c s 3*A=\
1 - !O ! .3. 2 4/44 PQWER DISTRIBUTIM LIMITS 4/4 del LINEAR HEAT RATE *! y 7,l LIMITIus C0m! TIM FOR OPERATIM M 2* \ -44,1 The linear heat rate shall not exceed the limits provided in the
- COLR. _ _ - ,
j APPLICABILITY: MODE 1. exc.o r e s
' _M_-_'_e- - d 'd
(* 4
- With the linear heat rate exc Ngithe'lieffs'Provided in the
, as indicated by four or more coincident incore channels or by t
- outside of the power dependent control limits provided in i
Ac4 - : AXIAL SEAPL f 1 A m th. cotR.r.1 nI inut [ heat ha M to unt. ithig.3he1p1ts and pherivjeetion s. puce 9-iu;.ary c L] i g Restore hour, or the linear heat rate to within its limits within one c
^*#' '
! & 8e in at least(IST-9fAISJS )within the next 6 hours. l
-a j SURVEILIAllCE REQUIRDWITS f2.)(1 Thg4rovisions'of SpectP(cation 4/4 are MIt aDeWeahC
%NW -4rt:ht The linear heat rate shall befe 'ned i t
~
thy 40ntTMUDsly.morittoria m cart ib yt its__11pttsK i Excore Detector Monitoring System'~or With the n System.
;h either the tector Monitoring (Q. LA 2j
) ^9 O 4.2.1.3 Excore Detector Monitorina System - The Excore Det ., 14 crt g Systemmaybeusedformonitoringthecorepowerdistributigy: Monitoring
- 4 "a . Ve ying at least e per 12 hours that the CEAs arefrithdrawn l l i and maintai t or beyond the Long Tem SteadyEste ; .-
j L Insertion Lisi f Specification 3J.3.6. - ,A.5 3' *\- Verifying at least once per 31 days that the AXIAL SNAPE INEX a.lem CL. setpoints are adjusted to within the limits provided in the 4 f ( _% SupWfe111aM.2.hh l CALVERT CLIFFS - UNIT 2 3/42-1 Amendment No. 163 i
, O y i a3
_ .__ . . _ _ .,. _ ...... __ . _ .. ~ . _ ._ _ ._ . _... _ . _ _ _ __. _ . _ _ _ _ _ . _ . _ . _ _ . _ . _ _ - Tye . F. r 4. , , 5. 2 , ( 4 i
~
3/4.'2 PindR DISTRIBUTION LIMITS SURVEILLANCE REQUIRDIDITS (Centlemed) .f Pc [Ver ying at least once 31 days that the SEAPE INDEX3 - ntained within the its provided in the C0 . where l~ 00 percent of the a able power is the allowable (L. N A' j fraction of RATED PgWER as detemi by the 4 limi
- provided in the .
SR 3.2.13 4
- Q 3,7, t,4 __ Incore Detector Monitorine System - The Incore Detector Monitoring may be used for monitoring the core power distribution by verifying.
I4ON I t t the incore detector Local Power Density alarms: qq '", 2, g A/ Are adjusted to satisfy the requirements of the core power distribution map which shall be updated at least once per 31 days l of accumulated operation in MODE 1. eA .7 ? I .k @ Have rate limit theirprovided alam setpoint adjusted in the COLR whentot brotect the linear uncertainty factorsheat provided in the COLR are appropriately included in the setting of l these alarms. O l l l CALVERT CLIFFS - UNIT 2 3/4 2-2 Amendment No. 168 O y 1.o
_ _ . . .________m _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ . . _ . _ _ _ _ . _ _ . _ . _ . _ _ _ _ . ! hy c . Q.4, o % '3. 2 . \ }' 5,, J., ... , ., 5: c u
- 3. N N q r, . c -
I 2.2* O. u p T- ,, 3 I . 3/4.'2 POWpt DISTRIBUTION LDtIT3 - l 3/4.2.2 TpTAL PLAftAR RADIAL PEAKIM FACTOR - FL i i LDt! TING EONDITION FOR OPERATION i ! 3.2.2.1 The calculated value of F,shall be within the limit provided in
- the COLR. - [
APPLicABILfTY: 'lWDE 1*. g With FJ,outside the limit pmvfded in the COLR. within 6 hours
- a. Withdraw and maintain the CEAs at or beyond the Long Tem steady. ;
State Insertion Limits of Specification 3.1.3.6 and reduce ' THE4 MAL POWER as follows: f
- 1. Reduce THERMAL FJWER to bring the combination of THERMAL
- PCWER and F,within the limits provided in the COLR. or T 2. Reduce TNERNAL POWER to less than or equal to the limit ,
established by the full core power distribution monitoring j l y9 system as a functio =r of Pg or i
- b. Be in at least NOT STAWBY.
u ! g i SURVEILLANCE REQUIREMENTS
- L:. :
.$, &b >
4.2.2.1.1 The provisions of Specification 4.0.4 are not applicable. N V [.[ 4.2.2.1.2 F, shall be detemined to be within its limit at the following intervals:
"~
O I L a. Prior to ration above 70 percent of RATED THERMAL POWER after each' fuel ading..
- b. At least once per 31 days of accumulated operation in NODE 1. and
, fc. Within four hours if the AIDemlAL POWER TILT (T) is outside'the) q- limit provided in Specification 3.2.4. f At least once per 3 days of accumulated operation in NODE 1 when
%k monitoring linear heat rate using the Excore Detector Monitoring -
System per su el11ance 4.2.1.3. g yg 7g ,& ~TIEufe Ot4 j 1 i $")/o7., 7 k+Us* *6e *) ud 4"j$"") LHR ~ / See Special Test Exc t1 3 10.2. p CALVERT CLIFFS - Ult!T '2 3/42-3 Amendment No.168 O e . ., s.e s
q ,. . w. < . , T. 2. 2 i 4 O i . g7 -4/4h POWER DISTRIBUTION LIMITS 4/4d:t TOTAL PLANAR RADIAL PEAK! M FACTOR - FI,,
- 5. '2. 2 Limma c0mma r0R wtRAna l
l D 3. 1 2 4.t 34 The calculated value of F,shall be within the limit provissed in the COLR. - APPLICABILITY: 'INIDE k Actica 4 : With F, outside ,[tha .,w ,18-itarevidad cru m_ we. w a haurs e :
. LT 4 _f we +k.
_e _.
,4 .
)
Q. ,, 4 6 7. Wit and ntain the C at or beyond he Long Te Steady. Insert Limits of cification 3 .3.6 and ce as follows:
- 1. Re e THERMAL to bring t combinati f TN 6 A and P,wi n the limits rovided in .e COLR. o (4I '
2 Reduce TN POWER to le than or al to the mit j
, establis by the full e power d ribution nitoringj system a a function of g or j , r, m
- b. Se in at least Geff*AleBY. (], L- J/
6 ko.o ~" r s [~' b Ac7 t o u Q l
$URVEILLANet REQUIREMENTS l appligh
~
6.2M1 Theyrtfvisions%ecificaM.O.4 a 4.2.2.1.2 P, shall be detemined to be within its limit at the following 3 ntervals: gs+
, a. Prior to o ration above 70 percent of RATED THERMAL POWER after
( ' qf', ,),' each fuel oading,
, i b. At least once per 31 days of accumulated operation in MODE 1.@ l
_s [d.F2 c. Within four hoursinifSpecification limit provided the A111emlAL 3.2.4.P1WER - TILT (T) is outside th]e vF g 1 i At least once per 3 days of accumulated operation in MODE 1 when ]
% ! c;
. ld monitoring linear heat rate using the Excore Detector Monitoring System per Surveillance 4.2.1.3.f J f;yj .CcL.,,,p\ '
<<< J.,c ...
; G, fr,. . . r. , 4. . , ,t. 2. i , /
{f "LuQ* / 4 h Sppfal Tag Excep(on f0.T' CALVERT CLIFFS - UNIT 2 3/4 2 3 Amendment No. 168 O p,e I oI 2
f, Tp . . .' f . .. + - 3. ~2 .4-l 5,, Jm , n .,- . F cL . ..,, s ! " I f. , 6p,. A b. 5. 1.7 ," Toki PL,-. , L 4. ( P,. w g C., o . t l 4.'2 POWER DISTRIBUTI N . LIMITS 3/4.2.2 TOTAL PLANAR RADIAL PEAKIM FACTOR - FI,. ! LIMITI M CO M ITION FOR OPERATI M i j 3.2.2.2 The calculated value of F, shall be within the limit provided in the COLA. l ! APPLICABILITY: 'MDDE 1*. l g: With P,outside the limit provided in the COLR. within 6 hours 1 -
. s. Withdraw and maintain the CEAs at or beyond the Long Tem Steady i State Insertion Limits of Specification 3.1.3.6 and reduce !
TutRMAL POWER as follows: i
- 1. Reduce TIERMAL POWER to bring the combination of THERMAL POWER and P,within the limits provided in the COLR, or '
- 2. Reduce TNERNAL POWER to less than or equal to the limit established by the full core power distribution monitoring system as a function of Pg or
- b. Be in at least NOT STANDBY.
~
O SURVEILLANCE REQUIRDIENTS . 4.2.2.1.1 The pavisions of Specification 4.0.4 are not applicable. I 4.2.2.1.2 P, shall be detemined to be within its limit at the following l intervals:
"'a. Prior to yoading, ration above 70 percent of RATED THERMAL POWER after each fuel
- b. At land =ct - Edays of accumulated operation in MODE 1. and A( tict4 A k Within four hours if the A2tMTRAL POWER TILT (T) is outside the
\ limit ymyided in Specification 3.2.4.
- d. At least once per 3 days of accumulated operation in MDDE 1 when monitoring linear heat rate using the Excore Detector Monitoring -
System per Surveillance 4.2.1.3. See Special Test Exception 3.10.2. -
~
CALVERT CLIFFS - UNIT 2 3/4 2 3 Amendment No. 168 O n2n -
$7,, x . 4 . a 5.2.2 O .
4/4d-fgg131ERHEHRHdgHt- - SURVEILLANCE REQUIRDIDifs (Continued) ,) 5~R. T.7.~2, l 4.2.2.1.3 F shall be detemined each time a calculation is required by using the in, core detectors to obtain a power distribution map with all CEAs ) ,i NOTE at or above the Long Tem steady state Insertion Limit. This detemination '\- shall be limited to core planes between 1M and SM of full sort height -- inclusive and shall exclude regions influenced by grid effai:ts. l l O V l l
.,e S .
I l CALVERT CLIFFS - UNIT 2 3/4 2-4 Amendment No. 168 l l
~
lO I
")- F2 p $4
l (per.G, 4. , I,'2,3 O~
- 3. 2 37t:t POWER DISTRIBUTIM LIMITS
- 3. 2 . '3 s/4*a- TOTAL INTEGRATED RADIAL PEAKING FACTOR - F1 LIMITING C MDITIM FOR OPERATI M k O ** 2 3 3.2.3 The calculated value of P, shall be within the limits pmvided in the COLR. l APPLICABILITY: MODEb ,
l ge With : r P, outside the limits provided in the COLR within 6 hours 3 7 ___ ____ 3 ACT5oN E, _ ( h Be in at lesst = ..._ - .Por d _ f. q-_., 6{.
. Withdraw and nfalE~the CEA's aTWhieyEdTh'e Gng Tem Meady) ~ l State Inter on Limits of Specification 3. .6 and reduce 1 THERMAL ER as follows:
- 1. duce THERMAL POWER to bring combination of THERMAL 1 POWER and P within the limi maintain th,e peripheral ax rovided in the COLR. and s ape index within the D g-inits provided in the CD '~
axial flux offset contro or
)
.2. Reduce THERNAL POWER o less than or equal to t init i
[N established by the ull core power distributio __ nitarina) ' d system as a fun on of P, e.[e R [ ~* > : , ( ; _ ,,. _ . !
-- --- l i
$URVEILLANCE REQUIREMENTS P
4 (4.2,3d ThMvisioneYf SpeMation 4 Mare hplicatie) h, 74 3.?,3,1 -4'15.t- P, shall be determined to be within its limit at the following intervals:
- a. Prior to operation above 70 percent of RATED THERMAL POWER after
' [' "e each fuel loading.
.y .a
- b. At least once per 31 days of accumulated operation in MODE 1. and l
'r ,, E Within four hours 1T Ene AZIMUTHAL POWER TILT (T) is outside thje w11mit given in Specification 3.2.47-(ce J. s u 4 5.. .P CL. g,.
Ces S p ,,5 c -4 . o a ~$ . ~2 . 4, "Ac. %,,,-M. t 9. ,,, T,t+ " ( /eii SpeJ541'Testgeptiongo@ l CALVERT CLIFFS - UNIT 2 3/4 2-5 Amendment No. 168 ; O
.g r I of S
-- . . . - - - . - . .. .. .--. - - . . . . - - . _ . - - _ _ = _ . - . - . - . -
, 5 9 ,c.c, .. t .d 3. *2 . &
- 5+ 4 c,v i s, _ J c u . y .,
i f., 'S p-L fi < = 4.on 3.~2. ] "To4=( , r.4..y.+a N:. r o- u.. ., c. s . , ' h/4.2 PWERDISTRIBUTIO11 LIMITS 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F1 .: LIMITING Con! TION FOR OPERATI0li 1 3.2.3 The calculated value of F, shall be within the limits provided in a th um. l APPLICABILITY: IlODE 1*. g: With F, outside the Ilmits provided in the COLA within 5 hours i a. Se in at least NOT STAW8Y. or ! b. Withdraw and natatain the CEAs at or beyond the Long Ters Steady i State Insertion Limits of Specification 3.1.3.6 and reduce THERMAL POWER as follows:
- 1. Reduce TNERMAL POWER to bring the combination of TNERMAL i POWER and P within the limits provided in the COLR. and maintain th,e peripheral axial shape index within the DN8 axial flux offset control 11mits provided in the COLR. or
.2. Reduce THERMAL POWER to less than or equal to the limit {
j established by the full core power distribution monitoring >g system as a function of F,. 1 I h 1 i SURVEILLANCE REQUIREMENTS
- 4.2.3.1 The provisions of Specification 4.0.4 art not appitcable.
I 472."3.2 F intervals , shall be determined to be within its. Ilmit at the following i . a. Prior to coeration above 70 percent of RATED TNERMAL POWER after j each fuel loading. l At least once per 31 days of accumulated operation in MDDE 1. and l - %oN A Within four hours if the AZIMUTNAL POWER TILT (T) is outside the limit given in specification 3.2.4. ) I i - tal Test Exception 3.1
, CALVERT CLIFFS - UNIT 2 3/4 2-5 Amendment No. 168
) p.e 3o r3
5;,,, s. ~ . . , 3. 2. .s O 3/4.s 80WER DISTRISMIGN LIMITS SURVEILLAktE REQUIRDIENTS (Continued) g.s.a.a shall in detemined each time a calculation is required by - 3 7 a ,s. I using the incore detectors to obtain a power distribution map with all CEAs i pmg at er above the Long Tem steady state Insertion Limit. l 1 I l l I l CALVERT CLIFFS - UNIT 2 3/4 2-6 Ame'ndment No. 168 l O
,_., 2.a
i Spe . ro e ..:., T.2,t lO' 1 i - 3.'l 9/4
- POWER 91STRIN T10ll LIMITS
, '3.'2. 4 eter;4 arnamlAL paure TILT - T_
.l LIMITING COM ITION FOR OPERATION 8-C o 3.'2 A- .e,ev4. The AZIlamlAL POWER TILT (T) shall not exceed 0.030.
i APPLICABILITY: MODE 1 above 50% of RATED TREEMAL KIl0118 Ac. Tion A A With indicated AZIltmlAL POWER TILT deterst be > 0.030 but the0.10. either c power tilt within hours fi"r ne within the rs and at least aaea aa-
- subsequent 8 hours, the Total Planar Radial Peak Factor i ( and the Total Integrated Radial Peaking Factor (F are wi in the limits of Specifications 3.2.2 and 3.2.3. ,
[cl/da b b. With the indicated AZINimlAL POWER TILT determined te he > 0.10. operation may proceed for uo to 2 hours int Pe ateo F tor sia sio n are acto thin s vi Total of 5 anar cificat the Iotal s al 3. h 4
'#" (,,, a 3. seg nt operation for Ine in,.e or muss.. -...
i a nti the cause of the tilt is owable provided the go *.g , 0/C TutRNAL POWER evel is restricted to y,,2G(of RATB TREN14L
- Pau.
1 M-_%.. Am 4 % . ..,- - 2 . ,. , . a .2 -e,+...-+. 2
, r,4 , , C d o c < 'f l ... , P o w -r- Io 4: So *4 i SURVEILLAllti: afgif!RDIElfT$ "
13TC 'k _ b bou'l M The pr Mons of Tp, ctf1'cationgare nmo 1pa]bM - 4
~
M The AZIlsmlAL POWER TILT shall be deterwined to be within the Q limit by: i i
'+'
l
- a. Calculating the tilt at least once per 12 hours, and tb. U t co ectors to ces tne AssnuinAL R TIL vh and a ra a en NN_e" "
} 4b R,v.. .s. u . l
- .., _ .e...... ~ . . ~ . - s .. -. n. ..- c .p.eed,. .. .:
j 4 ..r,
% g THER'<A A L pun R. So t, . <g .- 4 p.,.e. _*
%g l
l A%.s , 90faf p r ae.ord. pr.s.A,d E= t- +L e. i d'"r= w *'-( T g .s . . . . c. , 4 s=.o.os .,+ i,,+ . , , p , t 2 L.m , g , af v4 fit .,- . . f , e J -i 05 M RTQ IJ ee Spe g Tes gteptignj.10pT = - -- ~- i I CALVERT CLIFFS - UNIT 2 3/4 2-7 Amendment flo. 163 sA.2
. ~
p o, .e foe
&-c.Fu.4o n '3. 2. Q . 1 0
- 3. '2. -t/tt- POWER DISTRIBUTIM LIMITS 3.25 =5
- M -icia LIMITING COMITION Fet 9PERAT!0N Gs0 Q 1
' Lt.o 3.7 5 +'** Th' f*11'"ine one related parameters shall be maintained within the limits shown: j l 1 [ Cold Leg Temperature s; 548'F
- b. Pressurizer Pressure 2 2200 psla*
^] l l )
- c. Reactor Coolant System Total Flow tate 1370.000gys) l
- d. ARIAL SEAPE ISEI, THERMAL POWER as specified in the COLE l !
APPLICABILITY: MODE 1 9 TgeMAL,Ocwp y ?o*g Act'N A CTION: With a of the above parameters exceeding its Itait, restore the 40
- O arameter to wi in its limit within 2 hours or reduce TREMAL POWER to ,
ess than.5( of RATD TWEMAL POWER within the next 4 hours. l SURVEILLANCE REQUltENENTS j
'75I 4:fr5,1 Each of the l
st least once per 12 barameters rs. shall be verified to be within their limits
%2.5.2 The Reactor Coolant System total flow rate shall be determined to' be within its limit by measurement at least once per 18 months.
$r e d
- s %. h oC e L . g, g I-s S p e , .C. . ,4 . .. 3.d.I j Nb N RA- M E T E R $"
Limit not a licable during either TWERMAL POWER ramp increase in excess of 54 f RATD TWERNAL POWER per minute or a THERMAL POWER step ( increase of greater than 10% of RATD THERMAL POWER.
- CALVERT CLIFFS - UNIT 2 3/42-8 Amendment No.163
!O o O
___.m___... _ _ . _ . S yc c ,a. ., 1 +. i O l
@ @ s G E aswrem q) g,4 4/4,9. pawn BIsterattau Lintisi ~ ~
~ 4.i
- 5. 4. I 3/4.2.5 .ama maassam Rcs A....,<, T,-p.,s.,e,.4 Fl . ,
O. p. < 4 , e F, - N- c uu , - G .. LIll! TIN Com! TION Pet OPERATION ONG l_.~.4 g. LC O'5.4.i tvert- The following O m related parameters shall be maintained within the limits shown: I b p. Cold Leg Temperature s 548*F l o Y. Pressuriser Pressure k 2200 psib l
- c. Reactor Coolant System Total Flow Rate 2 370.000 spa l 1 m , . _ .-
-..m ..m ...m. -
4 .'2 ! APPLICABILITY: - ON b _-$ ACHgg With- --~a' *
)
xc I ts 1<m13. resuore the parameter in - 'ithin its 11 mil within 2 hours erha** Tumi Pe* 10 i (less than 5%; #f RATS inM@gwithin the nex rs. f- l D ON C FJf2i, h Ep...a r)e 0 i
~
Ac. tom O A 4..i r W4 ~~
<f, O -" r"* ~
,h,'s,
' 4.8,6,4. Eachper at least once of12 the bremeters rs. shall be verified to be within their limits l g 5 4, g, -
4.2.5.2 The Reactor Coolant System total flow rate shall be determined to 6 1 % 3,4 g,4 he within its limit by measurement at least once per.38' months L'5
" L.
=_n p, ( 3 g SR I.4.I A IqdTE*.
4" lq3,,,,4 ,,9 t i..a p,.f'.~5-d. r-e
d
,I k
2 9-e:
" ' 'i P N'DD I c, ,3 . , 3 ,p+ . , A ')ox
{ w.% a ll QCPs - e- yP i A ppi ,, .t , i .: y bJ .4 e
~ __
Limit not applicable during et r TWEM4L POWER ramp increase in I excess of 5% of RATS TWEWIAL POWER r minute or a TBEMAL POWER step I increase of greater than 30% of RA THEW 14L P W ER l CALVERT CLIFFS . Uw!T 2 3/4 2-8 Amendment Ilo. 153 !O p$e I *F l l . - . - . . .-
$pec.r.c4.w '5. 3. I i
e 3, 3 t/et Ill5TRIMElfTATI0lf Sy9 (R9 _ sig.a.4 ***
, ,; REACTOR PROTECTIVE INITRLMENTATION _
pe _ +
- r. , m ....n ,,..,-s~~-.a g,c, o LIMITIIIS C01SITION FOR OPERATI0ll ** ** ,$.- rf * 'j,
- f'fC ,I.'.'. c' '[$r #.
- 5. s. I 7'..P .t .e.dm .vi uius ims.-..mion tiermets and
=g.
L3.1.1 bypasses-1rf i Ta ble 1 be
't.% t- % . 5. 4 _
APPL.1 cat 1LIII: .t _S.,[abi A *'d sd KJ.1GE: + 4 s 1: 5 ' ".0 ,1. ~
~
Ce, Q. > \ 9.]sAO,Eo-Jf _ _ . iao r E- -- - T< (M-- g, ,
- - ~ -
- c. p . % c. Co.O o n *-y , y % .
c, j na , si m , .4 ro, r ek E P' C-< ' * - SURVEILLAllCE REQUIREMElffs S~- JD __ _ _~ sR *.
'*' f M ,i ,3 4.1.1.1.I Each reactor protective Esat11mmnaert8a ehwiershall be 3%e. demonstrated OPERABLE by the performance of the tilAllNEL CNECK, CNANilEL LL' " CALIBRATION and CNAlelEL FilllCTIONAL TEST ==-- Ha== '"-' ; W ^^^::' r.d ;;
4he t;r-Sese *= Ma A t-1. Ka[ .6 9R 4.3.1.1. logic for the sses shall be demon M 7 to. _rtactor_3TARTUP_ ky r 'r..t' n sha 1 be demonstrated OP RAB 1_ performed.durin .th ed OPERABLE p ior n 92 daf e I4I5' -- eas o r O REFilELIIIG INTERV I affected by bypas during ope tilAlglEL j, CALIBRATIGII,i g testing of each channel
,,, , y,,
l 'A - g g,3'g ,q 4.3rt Tha REACTOR IP 5YSTDIWSNiilsfhM'E of each reactor trip'~ . is n shall be demonstrated to be within its limit at least once per _ ktVUELING INTERVAlr. tach test snati miuos at ausst one snennes per i Tune n such that all channels are tested at least once every N FUEL 111G I VALS where N is the total pueber of redundant channels in specific l actor3.3-l able trip -- function as shogin the " Total No. of Channels' olumn of j v y _=
~
n~ - - _ . VJrt1F ~ - gi, ; ,. , 4, ~{ b te 'T.~5.1-1 4* d e 4" ' - a - e i
- t. , ,, s p, s g . i. ',
pe.Ior *d Co. f
/' C '
g,, ,. u RP5 L c 4.., j
~
Orge 3IA64E 4 D ( . s+o.b le + o (> v A , <*"*W**** C g) pyg g .cL - ,( , .,4 . p p ' < 6 'at l '. * #* * '' A 'I r# w o v e. ' V ' *^ W t' .
- -g el )
Q Neutron detectors are exempt from respor.se time testing. CALVERT CLIFTS - UNIT 2 3/4 3-1 Amendment No. 186 O p $c IoF i 4-
f he.$r.4..n ~5.7.'2. I b1 j /b R,.+ .5 cL...,3 .r p s .-t%k RP5
....e.W 1
% yM t<. . + r ,p <+y ... J ,
J .e 5.-s.t;g :
. we . . . .,s .ke. - ($
b p.,g c .' . . l [ / . ,,, e t. . . i MS
~
5 O 3 " - 3.~3 4/4d-1R$fauMENAfgm -
.,- * ! REACTOREikijyfINSTRUMENTATIONG.sid h
LIMITINE CONDITION F04 GPERATION , L.C.O 35.2
- 3444 m. . a.._ _ .t._____ -..__m- . _ . / _< _ - _ . _ _ m g*
,' m ___ .. s. .m. . .. . . .'T...; r.
.r. r =s.- "' "" *'
' " - ~
APPLICABILITY: ^* '- 8 = T-'t * . " . - th)DEf 3,4 a 46~M^v S *e T"f g, m. .m a ,u.... r.*Ae 4 '/o '"^' ' '*' ' " 1
- 4. >C l'~l N* f g 60 G ) <.t. s 4 ."- J .y 4, y c,,a ,,g e l. J **s* *U y
" SURVE!LLAlH'E REMAIMES
- p. (,i e of
--^
V. s s "N ' a - .
- . 14 g . 3. t g hSdrht Each reactor protective SatMEientattwtfannel]shall be 3 a ."2 ~2.,
demonstrated DPERABLE by the performance of the CNANNEL CNECK, CNAINlEL s.,.2 4 CAL 184AT10ll and CilAlelE u e=---e r .L FINICTIONAL - m . 4.3 TEST 1, operations .;.. .. O
."^^2 .. .i .
3b.3 e
@ at Midid"d'...
t-t-! M = ' - 2. shall be demonstrated OPRRA8N O j. REFUELING affected by bypass IllTERVAL ion d rin ERAINIEL CALIBRATICII g ,-. y 6,p.. ,] . testtQeach lchannel
.: F..4 Q ~
.I 4.3.1.1.)
functioe, shall be demoThe REACTOR TRIP $YSTEFIESPINI5E TIME of each reactor trip ted to be within its limit at least once per LFUELINGINTERV . test snali In' wds as isast one cna , punctionsuchthat channels are i ed at least once ev INTERVALS where N REFUEL 11tG the total numb of redundant channe in a specific reactor trip fupction as shown in " Total No. of Chtenels' column of j Liableg :
~ - - __
on a STAHEED (, g ,, g,,3 ,, 4 ,,, p y ,,,, TEST 4 Asis g ...<t J L
,, ,-4. .4.e syp**s (a p a wel $#m4.# ' #%
_~ h l. b.1 Neutron detectors are exempt from response time testing. CALVERT CLIFT 5. UNIT 2 3/431 Amendment No.186 O n i .o
hc F. ed o 6 8 j .c Rp5 T ';,> % % L**j'i f'~' ' R- R (g l r e,, ,,,. ..
~ - '
L . a ,, , GTre'O,'--a r - < ~ ~ ' '.
- -- m e p% ,. ., c. t T r: n s - *I :- OPE M d -
~3 . ~$
-~
Wer8- INSTRUNENTATION i
- 3. ~5. 3 W44,4 SYSTEt1 /R95 -
I
)
REACTOR PROTECTIVE Lim.rm-mhun Q
**= _"T ' e ' -
- l j -
\
i LIMITING CONDITIO11 FOR OPERAT!001 ' LCO g ag g .4.4-- m , , . _ _ _ a
.y .
L 3.3 5; ==. ;' TO*; 3.0 : th " h 5d=""g __ l . ,
- g. ;
l. j APPLICABILITY:
,.e f m. in isois 3.3 i. M ooE i . J '1. ~ _
4,e g i, . . . v. u . . a M ooET 5 '5e + --a 5< s" -y p.y %a-~~ Rice,'s ,. i . . , a --d --y c a -d ' ' l g of i o CToNS M C,0 e t ,- ,s --.<-M y 'W* '#
./
, SURVEILLANCE REQUIRDIENTS
.g g w-r 7 I
N 4 .". . ; .1.1 Each - =tr FO;d'.; h.;;nn..;.16. channel shall be T.'f.'t 5 T . '3. 7.2 demonstrated OPERABLE by the performance of the GNAMG4r-GliGGKr4NAINfEt-
?*'!**^t!" t-M !""""EL FUNCTIONAL TEST operations during the N00E5 and at
, r, , p 3 the frequencies shown in Table 4.31.
(4.3.3.1.2 The logic for the bypasses shall be demonstrated OPERABLE pricF ~ to each reactor STARTUP unless performed during the preceding 92 days. The i total bypass function shall be demonstrated OPERABLE at least once per ( REFUELING INTERVAL during CNAINlEL CALIBRAT!011 testing of each channel l Niffected by bypass operation. 7 l i 4 1 ' ffunction
.3.1.1.) s hall be demonstrated to mbe within its li itThe REACTOR j
REFUELING INTERVAL. Each test shall include at least one channel per i 3
- function such that all channels are tested at least once every N REFUELING
- INTERVALS where N is the total number of redundant channels in a specific
. reactor trip function as shown in the ' Total No. of Channels
- column of j
(,, J. % . .., .( G- . . e s l F.< Q- F - 4. - '5 '3 ' 'T'2 l gp3 is , , , a * = . " . 4 " M 1%4, - S t. ., 4 J. I 1 Neutr$n detectors are exempt from response time testind CALVERT CLIFFS - UNIT 2 3/4 3-1 Amendment No. 186 O . g g h
l h c .F. - a .; e 7 3. t '2.- e & 3 'a' *$tt1 INSTRUMENTATION / sA.' i tt.'>,A. b ,,. 'L .y . A ... u,a,,,-7 ,- w N --.o..<
~
~
- 3. 3. ) La s/4.5.i 4EACTORJkailcTYVE3XSfAlipiE5 FATE - T d.-
*-'d
% e p ... . t< r %w ,g , ~
p.y ('d.Y t ' * $ t. .,J*o- Ci LIMITING CONDITIM FOR OPERATION r) . < . . . , .l. 4. o$ ha Y . . . . .> r * ; 4 ., L. . e r L , opr.hwt }
- e. . s. n,
- sartri r,,,ee..e a T.;,1. s o m il u 07- >- 2.n ; r. M a n, tL r;;;ur g e a c h. ir.n. _ ..;.ne.. e. =.; ,
. i APPLICABILITY: * * ' - '- hth *,. 0-1 _
ACTION: _^2 t - *a hMa t-I. M oO # # E:C (4a-4 5, w A ee GM) j s~ r"s e L* P ~~, v. .e c. c^ m . 'Y~~ ,' . . . t _er' U., cs y,aw g -
@,~_ _3 -- _ -- _
i svRVEILLANCE REQUIRmENTS ,,.u..~=-- p. ..'
, t.3. . P. -w_u .a . ~ ^~ r, . ., _r . ]~ --J e
N ' L A7 I
$$i 1.1,q 1 R.TrT".I.Il Each fenctor-protecbe instrumentation channel shall be demonstrated OPERABLE by the performance of the CNANNEL CNECK, CHANNEL -
g 9'3'g,I CALIBRATION I the-frequenc+ and CNANNEL emir. '- Rble '_M.FUNCTIONAL TEST ;g.- etu..e 4 . ;;,i, tM Z:5-snd st I
=
f.1'I.I.2 to es he logic for the b actor STARTUP un1 sses shall be demons sted OPERABLE pri
- total,c) bypass function sh performed during th receding 92 days he
' I be demonstrated OPE E at least once r @ .'4 O REFUELING INTERVAL du fected by bypass f4*.3.I.I.
g CNANNEL CALIBRATI ration. , sting of each ch el l 1 Ifunction) 1 REACTOR TRIP SYSTEM SPONSE TIME of each reac or trip 7 be demonstrated REFUELI INTERVAL. Each tes be within its limit at I st once per functWnsuchthatallchan hall include at least on channel per - s are tested at least o every N REFUELING-INTJAVALS where N is the tal number of redundant Shannels in a speciff e, (A . 5 reactor trip function a shown in the " Total No. Af Channels
- column off l
Mutter. deteGv. . art tirumpi irum . si,,c..ie tir toi; .y. A5 CALVERT CLIFFS - UNIT 2 3/4 3-1 Amendment No. 186 pme I .. G5 .
O O O y -- 5.1.i-t g cu d."';in fc.~,.h #
,,,C,. ,,,mTme i.',M ig . '
[ T 3.3,'(295 LQ c. -A '4] <=1 , g
=
,,:,>........- /
emaamm t [TWTALNO. APPtf3AStf I
]l' FUNCTleNAb-4 NET A 1 ( GF 1 (SPERABLEJ MODES ACTIN e 1. .anual Reacter Trin 2 1 2 1. 2 and * ~
1 ] $
~
Power Le.e1 - High
- 3. Reactor Coolant Flow - Low C
4/5G h 4 -,. "i
- SG]Q 3(U 4
[ SG (% 1. 2
- 1. 2 %
h b N
.. Pressurizer Pressure - High 4 d) .
2 3 1. 2
- 5. Containment Pressure - High 4 2 3 1. 2
- 6. Stea. Generator Pressure - Low 4/5G $6 3/ 1. 2 2 7. stea. ~ ,ato ,.ater te.ei . .,sG -
usG usG) 1. 2
% .. CalFiM .. 'ufg jE 3[ >
g,...m,.ai.ar...,-Pss.re . Q,
< 1. 2 g
- 1. e p
)
,. m _ ,
-~* '
ry '" '"'s. . y-n". c 0 (* 2 2 J L r
?, 6-A.a 'A
.t to.6 O P
~ rn.s k 1 0 ,'
o , Y 4 A 33 - m
?
v1
.p -
O O O g -YABLE-3r W R Q
- g -ATiet- t5 =
q * (t Ah e
'h M.l q M Nl GWEELS APFt20Wtt FUNCTIeWAL UNIT T9 TRIP M MODES ACTIMI h 1. Manual Reactor Trip # [ 1. 2 and6 1 4
r2. rower Level - High 4 2 3m 1. 2 2'l h
- 3. Reactor Coolant Flow - Low 4/SG 2(*I/SG 3/SG 1. 2 I'I f
- 4. Pressurizer Pressure - High 4 2 3 1, 2 28
- 5. Containment Pressure - High 4 2 3 1. 2 f
- 6. Steam Generator Pressure - Low 4/SG 2*I/SG 3/SG 1. 2 f A 7. Steam Generator Water Level - 4/SG 2/SG 3/SG 1. 2 f Y L8'
- 8. Axial Flux Offset 4 2Id 3 1 2'
- 9. a. Thermal Margin / Low Pressure 4 2I 'I 3 1. 2 I'I 2' i
- b. Steam Generator Pressure 4 2(*I 3 1. 2 I'I 2' Difference - High
'QO. Loss of Lead 4 2Id 3 1 28 4
- s 3 2
?. be. d. , e. . . . .. . I CL- ys [
', E C. c,r.. . r. - ..- T 1 ' , " RPS b o
n
=
o r-
- fosl , . ., f f . . , - Op., -* . s ,
O . o . N
" w O
__._________________.__._-._.m _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
O O O g T tinued) R. h EUKTM PteIECTIVE INSTRWWITATIN 41 r- /48 C'd f~ii!RDeF 5 A.I T aWWps i et m
" rein i a _ ^_ -u F[etus.
O W NELS ' l Ju1P GrdtAeLE Isets ACT195 e
/ J J *
/ r J
g II. Wide noe Logaritlunic e r > F1 itor . - A. d
- a. STARTgP and ing - J 1, 2 and N
of Change of Power - M
- 3. 4. 5 "'
4 0 2 3l
- b. Shutdown
[E Reactor g f Protection System Logic 6 1 5 1. 2* 47 Matrices
=
$ 13. Reactor Protection System Logic 4/ Matrix 3/Matri:: 4/ Matrix 1. 2* 4 Matrix Relays
- 14. Reactor Trip Breakers 8 6 8 1. 2* 4j
< , o., ~.. . . er cc. .y .
fs $ a7 . .C. m 4 . - s '*'*.3,
'Ws L$.c a. 4
% p l . 4,s 4...
ra ,# g 5-- D.,....., . c c L_._3, g y y G, 5...r...,. p '.> 3.~2, h g) J !"50 e b-Nlei 4., % ~ $ls -4 %g 3
\ 6 5
(re 6.< a s s.* r oV (L=-,e , l y p,,, e,7 , . C .a . .. ., ~5. 7. ' 2 3 'g
+ ..
% 843. Lo3ar.%ec lb b o Flut Moeb-c.k. ~t5 ^
O . O O
- 5. .a . . ... .i cc y, s p TAstt.3.3-1(continued) r.,
- v. .e-.
A+..,
.%., ,.T s, gy3 j.
- op. '
- 1. 3 . . - . .
~
~
; . (Ck. i.
r- '
~
N0. CEMWELS CRANutLS WTHCAEEK g 9Ftamulus 1 13dR1r i .ertRABLE lusts MTIM f5NCTIeAAL UNIT '
# r
- 11. Wide Range Logaritissic Ileutron r -
'I 4,3 h Flux Men 1ter j q
" a. STARTUP and Operating -
of Change of Power -
' h h 1
D} 0 2 3. 4. 5 1 A. 4 4.__ Shutdown w Protection Systes Logic 6 1 6 1. E' 47
=
{ %atrices M
" I 13. Reactor Protection Systes Logic 4/ Metrix 4/ Matrix 1 l' 4 w
3/ Metrix Matrix Reisys
- 14. Reactor Trip 3reakers 8 6 8 1. 1* 4 he d sc ss..- er ckp
~ ' " " '" * "-Y5 )
[ & pc,q ,+ . _
.N. 3,'RPs j fy I y- J T ,.h I .+. 4,, ,~ T"' " ' ~ m Y5. i ZlVch ,? ' b y3L.4,,Je u p S,.g - i rd E Ut s '
3 J.
O O O
- f. < J . vm. . o r - ct. 3,, g~, .t. ,,,,,, , .. ,, r et- ,n f., <;p ,..r; 4. , 33.s,"RM r. e,c - F - * . -, 7 7.~2,'W 5 I ,m -- < 4. -o.......,
p y i , ,4 , ~ . 4 . 4 .- - - s i. s 4. - '
~
g r-TABLE 3.3-1 (Continued) R. a g nAcm Punenn runnerana n D (/\ 9> Vx A. I N r manen , 8 g A . I . ] raammre t APPLICABLE
" FUNCTIGRAL WIT ( ,j P (OPERABLEg MBES ACTIM
- 9) e F11. Wide Range Logarttlue1C Neutron ]
7: 5 Flux Monitor d>
- c. 5
- g d p a. STARTUP and Operating -
of Change of Power - 4 2M 3m 1. 2 - 2 8 [ h Shutdown 4 0 2 3. 4. 5 3) [ 2
*g 12. c r Protection System Logic f' 1
% 1 4
* ' 13.ReactorProtectionSystemLogic[/tyixj / Mat x x 1. 2 4
$ Matrix Relays a
> Ae / ,
3
- 14. Reactor Trip Breake 6 UB 1. Zh 4 e -Q_ >' 4 <
m af , c.uk , 3,4 -a 5 y -g 2 E = 4 A,7 . 2. 5 5'g S .. s Q = i e i % yN d - 4 1 W O
O O O TASTE-h3-1-{Lmii._) -
=
g -REACTOR - PROTECTIVE-IN5TRWENTATIER-
** m
- A3 (s L A . ,J -uA.t g -
. ammas - - -
A m icasts FUNCTisNAL UNIT TRIP wr NesES ACTIGE c . Wide Range Logaritiumic Neutron - d 5 Flux Montter 8
- a. STARTWP and Operating - 4 2M 3m 1. 2 and
- 2' i
) '
Rate of Change of Power - High j
- b. Shutdown f6) 47 .tT 3. 4. 5 3 g f ^ Joi~rretection system Logic 6 1 6 1. 2' M
= i Matrices
- 13. Reactor Protection Systen Logic 4/ Matrix 3/ Matrix 4/ Matrix 1. 2* 4 ,
Matrix Relays ,
- 14. Reactor Trip Breakers 8 6 8 1. 2* 4
\
4 ,, 4 s. o u ,. , .c e6.y 3 for $p-e. f. . J .m 3~T.(j'PM g,, J. m,3, _ o f' e65.g { t,,s,..~..,t % - Op- ,4,~.,a p,,, c,g, , r , ,. i ... 4. T. 7, "R 5 [; e ,.. -- ,..o . . a .. : ;
- C e
) .
M _
. P' 7
V7 :
$ p-e f.e . + ..o 'T. 3. I l 1
! . 4.V e 4 e, p w , v O '^ ~ - l l : 3/4.3 INSTRUMDITATION l (,, J. . . .. .., . . F c 6 ys
,, 9,. c. r.r, m % ~'. ~2, TABLE NOTATION g g,4 , _ ,a ., p ,, - %%w P With the protective system trip breakers in the closed position and)
M *i 4 the CEA drive system capable of CEA withdrawal.f NcnE
- I The provisions of Specification 3.0.4 are not applicable.
f6 4. 1 may be bypassed below 10dof RATO TIERMAL POWER; bypass shall (b) d automatically removed when TRERNAL POWER is 110 of BATO WW .4 r TREINAL POWER. l M may be manually bypassed below 785 psia; bypass shall be p , omatically removed at or above 785 psia. (d') may be bypassed below 15% of RATD THERMAL POWER; bypass shall automatically removed when THERNAL POWER is 115% of RATED THERMAL l
**R
- r... 4e b i ~2 l M ma
%} R.(y4eAassad P.,g .,u o 5.c.w~@Ae_12%
m 4, ,,, n yof.. RATED
, ,-.,, , 2 gi o-THERNAL+ ;( ..AppgTn -
M O
' ee
may be bypassed jlur4ag_lesting pursuAn+ +a inac14 M ett, % ,.
' L' . Q. . .y . . . , . A,-. 4 v. {, . . .,,.1
_ 't.lt -4tp T P N be at least two decad of overlap between)he Wide Range Logarit c Neutron Flux Monito ng Channels and the #6wer Rance pL-%4, eut Flux Monitoring Chan sf , ACTION STATEMENTS With the number of channels OPERABLE one less than requi [CTIE1- by the Minimum Channels OPERABLE requirement, restore the ' inoperable channel to OPERABLE status within 48 hours or be in NOT STANDtY within the next 6 hours and/or open the J protective system trip breakers. - ACTIONf- With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may y proceed provided the following conditions are satisfied
- a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour. i;r it.;
te;ti .; : d : int;;..;;. Ota i;;;;rdh er-5;"r;::^ -yM ef 4 l 5** Du% ues,of c h y 4 4ech b 33.S,*ResLp k A -ivy 1.6.b.a CALVERT CLIFFS - UNIT 2 3/4 3-4 Amendment No. 149 O e
- +-
t
- p. e 4 oF l 4
=
1
, l Ipec Fie 4,.. 7.3.7 l Ce J. s.s., _ . .f cL y % .-
l $p*<.S. . 4. D. I, '
- Q% Q .4.Q
TABLE 3.3-1 (Continued) l 1 __ TABLE ESTATION l @S %4 ..J 5) bA"Md y / (With the protective systa trip breakers in the closed position and i the CEA drive system capable of CEA withdrenal. . j h ; i r. .. :'- -' " ::8 te.e- t a . a - =+ -- u -m;;, _
- I k beTrip may be breassed below 10d of RATB TREMAL p0WER: bypass shall automatically removed when TIEMAL of BATB p0MER is y,,10d TREMAL p0WER.
E+ (b) Trfp any be annually ed below 785 tag hypass shall be automatically remov t or above 785 ps a. Aa (8) Trip any be b (bd4' he automaticahssed reaved whenbelow TutRMAL15% of RATB p0WER is 115% ofTEEMAL RATS TNERNAL p0WER: bypass shall 4,v. ..u . ,' -6"5 e't #xe:@ l wrE Tg be ssed belt of RATB TIERNAL _ _. 83 w-w oo-o-sa %mo+xRTe3 Trip a'ny be bypasses emns testing pursuant to Special Test Exception 3.10.3. IO There shall be at least two decades of overlap between the Wide Range Logarithmic Neutron Mux Monitorin ( Neutron Mux Monitor.ing Channels. g Channels and the power Aange J
'Y AETIM STATEMENTS fS m
M1-d[4 ! t j(- ] by the With the nimber of channels SPERABLE one less than requiredl Minimum inoperable Channels channel SPERABLE to OPERABLE requirement, status within 48 hours or be restore the L ,g $ in NOT STANDBY within the next 6 hours and/or open the J ee . tyrotective system trip breakers.f
! A: TIN -
With the number of OPERABLE channels one less than the Total -
;I s
c. Number of Channels. STARTUP and/or POWER OPDATIN proceed provided the following conditions are satisfi : 1C JF a. The i rable channel is laced in either the bypassed
- t, '! or trip condition withi 1 hour. T,,,, in y.... vi M.., == mainw. . .. tr.; '::;;;.'1; zi; .:.pp=;
. ;. E S V} }i CALVERT CLIFT 3 - WIT 2 3/4 3-4 Amendment No. 149 lO 1
l fp .f. c. 4.. 7.3.3 3/4.3 Ill5TRilMDITATION
, TABLE 3.3-1(Continued)
TABL! NOTATION h AppucAarury U With t h* E m [ , ective system tripTmakers in the closed position and the CEA d we system capable of CEA withdrawal. a
- Ui 5 s I The provisions of Specification 3.0.4 are not applicable. 3 f j ~g (a) Trip may be b assed below 10d V of RATD TMERNAL POWER ass shall g be automat y removed when TNERNAL POWER is 310d '*
==At P=a. - P g
- 0) Trip may be manually bypassed below 785 psias bypass shall be automatically removed at or above 785 psia.
I l4 (*)
. 4 _l Trip may be ssed below 15% of RATD TNERMAL POWER: bypass shall 2 I I be automatica y removed when THERMAL POWER is 115% of RATD TMERMAL POWER. '
T d i { f (d) Trip may be bypassed below 10 4d and above 12% of RATD THERMAL POWER. . u
} [$ 5 I'I O If)
Trip may be bypassed during testing pursuant to special Test Exception 3.10.3. d i There shall be at least two decades of overlap between the Wide Range Logarithmic Neutron Flux Monitorin Neutron Flux Monitor.ing Channels. g Channels and the Power Range ACTIM STATEMENTS ArcgD E % g , a 4- Lo .c c e+a,I Rc r8 k Q ACTION /-With . .- __. . channel PERABLE
.~
e s keer ivan so n .imired
^'
t' N T.;n. C,.....el e OrIRARLE . .w;,-..;. . .;;..
' -- 0Tn"? -"- !!within 3TAnvii t: ZZithel nen etet.e ii;.L, o nours O t.;.N,
.Z.7.- mun -
ACT10N F- . rotortive nyttaa trin breakers. g( [ACTIO112- With the maaber of OPERABLE channels one less than the Total - Number of Channels. STARTUP and/or POWDt OPERATION may proceed provided the following conditions are satisfied:
- a. The ino rable channel is placed in either the bypassed
.' or tri condition within 1 hour. For the purposes o testing and maintenance. the inoperable channel may CALVERT CLIFFS - UNIT 2 3/4 3-4 Amendment No. 149
t :
- l
+ o ,
Sp.. .r . 'i.51 j O l 3/4.3 INSTMMMTATION 4.1
% +.. c <'L...a \ + o openmm w -s _ %
AcT oks A hours from time of initial loss of HABILITY: however, the inoperable channel shall then be either restored to SPHABLE status or placed in the tripped condition. Tb.~ W1 n one hour, all fu fional units receivi input' I the inoperable 1 are also placed the same LA> condition (either sted or tripped, as licable as , u that 7 ired by . ahawa for the P ----_ a A----1). ; g A ric*ss 6 1 It "' '-- N - d ZT" " s G -
; ==u / H'**' "
, may be bypassed for up to 48 hours while performing tests and maintenanc on that bM'aVu+ v,'u*c l' channel provided the other inoperable channe s placed Of*** *"
in the tripped tiaa-vp. .,@ @r 4. rce
**MM - 1 I
*$*,ine p'2 ab ACTION 3 - With the number of channess w-1_JZ' by the Minimum Channels SPERABLE requirement, verify compliance with the $W90181 NARSIN requirements of iess snan requ}zniD A . (, h Specification 3.1.1.1 or 3.1.1.2. as ap licable, within " s 4
- 1 hour and at least once per 12 hours t reafter. l
~
i ACTION 4 - With the number of channels OPIRABLE one less than required ) the Minimum Channels SPERABLE requirement be in BOT AND8Y within 5 hours; however, one channel may be bypassed for up to I hour for surveillance testing per Specification j 4.3.1.1.
. . . . # 6"e/ $
\ , e Q cf .5,
qpe, [
'p.,c-.* u- 3 % 3, g g -sc,,oe[Q.
,, 4 T ry t ri . + c.4 . ., -
R-;; c'? M S ,Q' l (,, J..e ... % .c 6. 5- N s d.@Cc- _ l S e,, . f. .. + . om 33. (1,h'de br< ht(T_ACEodM -_ (M, lo3a m W h A.% c6 mis"'j bNN"A CALVERT CLIFF $ - UNIT 2 3/4 3-5 Amendment No. 149 i O s.,. m
S p. 6 6 T.I.( 1 INSERT ACTIONS C,D,E,F and G (Page l of 2)
- 1 l
C. One or more Functions with one C.1 Perform SR 3.3.1.3. 24 hours i or more power range excore channels not calibrated with the E l incore ddectors. l C.2 RestrictTHERMALPOWER 24 hours I to s 90% of RTP I D. One or more Functions with one D.1 Disable affected Ihour automatic bypass removal feature Operating bypass channel. inoperable. E 1 hour . D.2.1 Place affected bistable trip l units in bypass or trip. AND 48 hours D.2.2.1 Restore automatic bypass removal feature and affected bistable trip units to OPERABLE status. E 48 hours D.2.2.2 Place affected bistable trip unit in trip. O
,s ,m
__ m._._ . _ . - . _ _ _ . _ _ _ _ . _ _ _ . _ . _ . . _ _. - _ . _ _ _ . _ . . _ . _ _ . . _ _ . _ . _ _ . _ _ Y
$pdndae %.K t (Page 2 of 2) 4 E. One or more Funcewwis with two 2 automatic bypass runoval NOTE
- features inci~..ble. LCO 3.0.4 is not applicable.
f E.1 Disable affected operating , bypass chanaala 1 hour i DE 1 E.2.1 Place one affected bistable 1bour i trip unit in bypass and place j the otherin trip for each affected trip Fnac*iaa. M . E.2.2 Restore one automatic 48 hours bypass removal feature and the affected bistable trip unit to OPERABLE status for each affected trip Function F. Required Action and ==~iatad F.1 Reduce THERMAL POWER 6 hours CompletionTime not met for to < 15% RTP. Axial Power Distribution-High or Loss of Land Trip Functions. G. Required Action and associated G.1 Be in MODE 3. 6 hours Completion Time not ma except for Axial Power Distribution-High or Ims: of Land Trip Functions. O um
f b p& s C. e.4e o, ~5 . '"5 , ~2. i 1 4 3/4.3 INSTR W DTATION
, M TABLE 3.31(Continued ,,,g ,;.,,'t 4.,
M sg.q] i q4.&ws_ sy i hours from time of inttfal loss of g . the i rable channel shall then. be either restored to status or placed in the ' , tripped condition. - 1
, vitain one hour, all functional units receiving an input from the inoperable channel am also placed in the same condition (either b u' *
! that required'by a.ypassed or tripped, as appilcable) asabove for t - ACTION B ,V TL 0;t - *--9 9T"I mi ^ * * -t - one.e we r .heas naA however, 48 hours while one additional performing channel'eay tests and asintenanc on that be **8,,% bypassed ^ .a,. for channel provided the other inoperable channel s laced j #7.".r.r.W 3-
'" th' *
@"f;M Q'.dh- ;Q.3)
! wiin sne number of ChRnels eranABLE one less snan requi = by the Minteum Channels OPERABLE requirement, verify '* ~* 4 . compliance with the $NUTDOW NARGIN requirements of , ["' g, Specification 3.1.1.1 or 3.1.1.2 as applicable, within I hour and at least once per 12 hours thereafter. O uun 4 - visa sne .-. vi s.n.nnwis ortnAsLE one less than required 1
- by the Minimum Channels OPERABLE requirement '
i STAND 5Y within 5 hourst however, one channel be in Ngf anybebypasse for up to I hour for surveillance testing per Specification]d 4.3.1.1. p j (re J. s . . . . . . F , L ~ r*- * "' *
#"I
l
$ubb 1.3.11,"Wrk Ray P. e 9 . . . C, . +.. 3 3 ~3, ~ ' W Qarts.ru. dea".Nsn 1%tk CL...sts
- l
- l. 0.. .s Try In . 4, .t . . r _
v.?P.T ACT'o*J . V ~2. h,= ssarAcr e O t
]kctiou _-
E i j tI . I 1 a t CALVERT CLIFFS - WIT 2 3/4 3-5
; Amendment No.149 -
- O4 J
pc.y 4 or 7 k
$yde.dx 3.1. Z INSERT ACTIONS C, D, E O 1 I C. One automatic bypass removal C.1 Disable affected operating Ihour feature inoperable. bypass chmanal.
DE C.2.1 Place affected bistable trip 1bour units in bypass or trip. AHH C.2.2.1 Restore automatic bypass 48 hours removal feature and affected bistable trip units to OPERABLE status. DR C.2.2.2 Place affected bistable trip 48 hours unit in trip. D. Two automatic bypass removal NOTE J features moperable. LCO 3.0.4 is not applicable. D.1 Disable affected operating Ibour ! bypass channels. D.2.1 Place one affected bistable Ihour trip unit in bypass and place i the other in trip. D.2.2 Restore one automatic 48 hours bypass removal feature and the affected bistable trip unit to OPERABLE status. l E. Required Action and as# M E.1 Open all RTCBs. 6 hours Complebon Time not met. l pay 5.47
p ,c . f. ~ 4 - m Y. 3 3 j 4, , s . , a - ~ , . , r cu ~ *s f,o %, ( le f. L* A * *' n * *
- YIN faAy
~ ingn%rv Frkron fin MoetW CLn>W 3/4.3 INSTRUMENTATION
~
d'.... , r c L m's TABLE 3.3-1(Continued) f.' ' %"" # ~1 vy,.- Dt " * * - *. fbypassed for up to 48 hours from time of initial loss of l I
' OPERABILITY: however, the ino rable channel shall then ;
be either mstored to SP status or placed in the l tripped condition. I
- b. Within one hour, all functional units receiving an input from the inoperable channel cre also placed in the same condition (either bypassed or tripped, as applicable) as that required by a. above for the inoperable channel.
- c. The Minimm Channels SPERABLE requirement is mett I however, one additional channel'may be bypassed for up to !
48 hours while perfoming tests and maintenance on that [ . channel provided the other inoperable channel is placedj l the tripped-condition. ' (ACTION 3- With the mmber of channels OPERABLE one less than required by the Minism Channels OPERABLE requirement. verify compliance with the $NUTD0681 MARGIN requirements of .
' Specification
- houtaAnueastinemen_3.1.1.1 or 3.1.1.2 as ap icable,withinj martw.
6 - O- ACTIONf- th the y the r of channelgAPERABLE one le nimum Channels N'ERABLLreovi han required
. be in NOT i t'. within 6 heur #W rar./ one channes may oe Dypassed ArioJG },fg te 1 kur fe sunemance est ng per Specification
} ww RT Acte oW G .
r, R T ' E 'a * '#
- C' pg L..,.e f
^- ^- - -
el-AC 0h sw mim 9 ERT _ 6/>QR-CALVERT CLIFFS - UNIT 2 3/43-5 Amendment No. 149 0 . g & D
9p.4rnkn T.3 ~5 i INSERT ACTIONS A, B, C, D, E (page 1 of 2) A. One Matnx Imgic chmanal A.1 Restore channel (s)to 48 hours inoperable. OPERABLE status. B. One channel of Manum 1 Trip, B.1 NOTE 1 hour RTCBs, or Trip Path logic RTCBs ===ari=**d with one inoperable in MODE 1 or 2. inoperable channal may be i closed for up to 1 bour for ' them- foi..w of an RPS CHANNEL FUNCTIONAL TEST. 1 Open the affected RTCBs. 48 hours l C. OnechannelofManualTrip, C.1 NOTE l RTCBs, or Trip Path Iagic RTCBs associated with one ! moperable in MODE 3,4, or 5. inoperable channel may be closed for up to I hour for I the performance of an RPS i CHANNEL FUNCTIONAL l TEST.
- j. Open the affected RTCBs.
1 D. Two channels of Manual Trip, D.! Open the affected RTCBs. Immediately RTCBs, or Trip Path logic affecting the same trip path moperable. p yG fio
SpdrdonT.3.3 INSERT ACTIONS A, B, C, D, E (page 2 of 2) O~ E. Required Action and associated E.1 Be in MODE 3. 6 hours Compktion Tune of Condition A, B, or D not met. AND QR E.2 Open all RTCBs. 6 hours Two or more ManualTrip, Matrix Wc, Trip Path I4c, or l RTCB channels inoperable forreasons other than Condition A or D. O I i J O l 9,p 7.f to
- j. . - . . - .
i j he.64 ow
~
a . 5. l Z. iO 3/4.3 IllSTRWWTATIM u f.s ...a er c% f, l
- TABLE 3.31(Continued) Au 9. . Wi
- a , "b 18,
- 9,PS I % .4 ..w . .- op..s. .j
! ( ! j j s .iv [ sad for a to 48 hours from time of initial less of' ILITY: er the inoperable channel shall then be either restored to SpERABLE status or placed in the W
- I M tripped condition.
j i] .!3 83 b. f.se the i Within condition one rablehour, allalso channel are functional placed in the units same receiving an in l 1 i{I4j. t-
,, s4 3 that requi ther bypassed or tripped, as applicable) as by a. above for the inoperable channel. }
2 - y %
.A.
- c. The Minisin Channels SPERABLE requirement is mets
,) { ~ j however, one additional channel'may be bypassed for up to ao o 48 hours while performing tests and maintenance on that )
f i ( .; 4 3 channelprovidedtheotherinoperablechannelisn1acai/ n the tripped condition. f s Iisi I t_ ! f ashen With the number of channels OPERABLE one 1 an required i - t t r
, by the Minimus Channels OPERABLE requiremen erify com
- pliance with the $ltVTD0lof NARG H requirements of j
- 1. v.i.i.i .. icable, within
! Na 4. . u ."' ::: and 3.1.1.1 x 3.1.1. at least once per 12.hours as apgreafter, t pun,- ...ni nunper of channels SPERA8LE one less than required 7
- the Minimum Channels OPERABLE requirement, be NOT BY within 6 hourst however, one channel may bypasbed for up to Iwhour for surveillance testing per specification;
.3.1.1.
$w .!. w 4.- J < w p p.,e Sg..N 4.o. T.~3. "'5 " RP S -
}& a-J Te,p I. , +. 4 . o.,
- i. J ' .
CALVERT CLIFF 3 - WIT 2 3/4 3-5 Amendment No. 149 0 7 p. ~5 . c 5
- . - . , . . .- . . ~ . - - - _ . - - . . . ~ . - -- _ . _ . - - - - - - - -- - -. - - . _ . --
O O O _ ^._ 9 e J.,_._ .r cl _o\, TMLE R, g w
, 9.. p. ~ 4. . . REACTM PJtWTECTIVE INSTMMENTATIM SMTEILIANCE REOWIRDIENTI i
a T ".hr.7 '/ @ p MC--Et e @ n CM-o. @ M.CT-M.3M .ES F s ,Ertt W et- G, i! g FWWCTIONAL MIT - CNECK CALIBRATIM TEST SEGUIR9-h T. Manual Reactor Trip MA M S/UM Ml 4 l J. Power Level - High @uAi) @U.M'S i
- a. Nuclear Power L.t @ 1, 2 ,
tA 3 :
- b. AT Power .RETWELIM Q 1 l INTDtTAL ,
. 3. Reactor Coolant Flow - Low 5 REFWELI M INTutTAL Q 1, 2 l l E 4. Pressurfzer Pressure - Hfgh 5 RETWELIM INTUtTAL Q 1, 2 l t
4". 5. Contafrument Pressure - High 5 RETWELI M INTutVAL Q 1, 2 l ,
- 6. Steam Generator Pressure - Low S REFUELI M INTUtVAL Q 1, 2 l .
- 7. Steam Generator Water Level - S REFUELI M INTutVAL Q 1, 2 l t low ife eru nT,,b .it 3
~
- 8. AxialQ1us4ffle'b $ REf9ELIM INTUtTAL Q 1 l g 9. a. Therinal Margin / Low Pressurt S EFWELIM INTUtVAL Q 1, 2 A.Ik l f
3
- b. SteantGenerator Pressure Difference - High S REFWELIM INTERVAL Q 1, 2 i
go l Y 10. Loss of Load M M MI
- 7 y a4 I.E t W 5 '. i .5 3 0 f;,,. f;,.. a ..e d v. 4 4 J 0 _
c . .a , a . . cA F-m f a e. ~. . . .w__ . ; n - t
O O O - L s k $ g -C= mmTm Msm-tan. sM,-m ra--== O raamiirs met $ 3 mig A
" CIWNIEL GAMEL FMCTISML SUUULIANK
.ruCTIsML WIT CRECK CRISMTIN TEST _ _Itte m ED h M M I. Manual iteactor TrfP
" 2. Power Level - Nigh ^ N3332 S/Uill
)lf kk 34. a 5[ '
> t i
- a. Iluclear Power S Dm,nm,gm Q I. 2
- b. AT Power S DM.RENELIM Q 1 !
INTENAL l w 3. Reactor Coolant Flow - Low S REMELIM INTE U R Q 1, 2 l A 4. Presserfrer Pressure - High 5 w RUWELINE NTEltTAL Q I, 2 l a 5. Containment Pressure - Migh $ RENELINE INTEltTAL Q I.1 l l
- 6. Steam Generator Pressure - Low $ RENELIM INTENAL Q 1. 2 l
- 7. Steam Generator Unter Level - S ItEFUELING IllTENAL Q 1. 2 l ;
Low l
- 8. Axfal Flux Offset S REFUELIIIE IllTEltVAL Q 1 l g g. a. Theripal Margin / Low Pressure S RENELIM NTENAL Q 3. 2 l f
- b. Steam Generator Pressure Difference - Nigh
$ RENELINE IllTEWAL Q 3. 2 l
.)\
= Loss of Load M M S/UN M $
o a 5 3 o,
&r cl. c ., ..n eC CL n-r c4 o
Fo . c~ .r . -u .. T.7 I,"R95 l 6, . . . _ . . . : 4 . . - 0;> +-, l
.r}
o j i
O O O r t i [3.'3. \ - 9 s g TABLE 4:9st'(Continued) *I R G . w g REACTOR PHSTECTIVE INSTileMENATIWII SURVEILLANCE REEWIRDIENS U-
'-3 k-h'd N - peggE5 IIHMttN O FUNCTION % UNIT _CNECK CALIBRATIOR TEST _
-aEENRED
- g. Wide Range Logarithmic fleutron Flux l REFUELINE IllTERVALUI J/UC 1 2 4. 5 l $
R Monitor ! f 12. Iteactor Protection System Logic flA IIA Q and S/UU) 1. 2 Matrices ,
- 13. Reacter Protection System logic NA IIA q and S/UUI 1. 2 Matrix Relays g Q4. Reactor Trip Breakers IIA IIA M 1. 2 and * [
w 4. Se J.<-~.. .r et.. 3,,
\
, Sc.,,.f.c.4.. T. 3. %,
"Rp3 L.g c .J Te[p 10 4 - + , g,, 4.s,, . ... .f ,. L . . ) , g ;
er %p*, f. 4. , 1 3.2, [ v A0 i g m is .. _ .. u..,- 5L #1 - a - l
= v
?
9 % s. s, _ . ., . c a.. , ., 3 5 6 f bp Sye.I.
- s 4. o 3. I .
y W. 4 , 9. y l'"i N % ' " " . . y A M., .. . .. 3 c u ~ ,i, A . i i
O O O g TMLE 4.3-1 (Continued) R r-- = MATT 94 PASTECTIVE IllsTMlWITATIN SWWEft1AIIt( EqWISO4Nf1 " O W ,3.'2.7
,e U
SR '>. '.~2.1 50?. 3.7.4 cm FeuCTIsel, ggES N WICE . I CMANEL taluRIEL SUWEILIJUICE FuuCTiemL.sult tuttg CALIsmTI.E TEsi aESSIRD
- 11. Range Legerf thefc IIeutron Flux $ RENELINE IllTERMLM S/ UNI 4rty 3. 4. 5 h -l N
I 12. Reactor Protection System Logic M M q and S/UG3 1, 2 Matrices ]
- 13. Reactor Protection System Logic 11 4 m Q and S/UDI 1. 2 Matrix IIelays Q4. IIeactor Trip Breeters M M M 1. 2 and
- R. .
Y he A . m .,, .s or C t . ,,, . ., r.,
$ p . , A ,,4 . . ,, Y ,3.1 , " pg>$
I .,s., . . i.,4. ,, o ,1.. 2 , I
.i 1+
1 P $ o - . LA g R - s a . t o ud
,\
Y rJ
O (, J. ., s . . , o r , t . ,. , o g ,, g , , u,,, ,, 7 g,,,,.,.,, o v., s c .,r... .., ,.2.. , Ro,r c. , ,.. c_.. . _ m,m , _1 . +. . ., - +
.'- ,,,,, _ g,p4,_
L . 2 , 9...o* g ,
,,j ,,
9 e-TABLE 4.3-1(Continued) g
=
h REACTOR ruviu. ave. INSTRUMENTATIM SWTEILUMCE REWIREMENT4 U <
# 4 l
P.
.- 5 .
3 CWWWEL IWWE5 N IMIG CWWWEL CIW WEL FWCTISMIL $5RVEILUWCE FUNCTIONAL UNIT - CNECK CALIBRATION TEST REOWIRED
~~.
I N nge Logarttluric liewtron Flux 5 REf3ELIM INTERVALW $/UW 4 -l m
- 12. Reacter Protection System Logic NA M q@ 1 O, 4, 5 Matrices sR3J,3,L -
' t't . _
M
~~
- 13. Reacter Protection System Logic MA Q 1 , @,, 4, Matrix Relays ~
SR 5.5.5.1 g 14. Reactor Trip Breakers MA M N 1, 2 and
- w L*6 =- -
4 Q4 . a i W3 , i
?
1 N
+
0 .- l LA "on
- C
% 3 !
D W o . Il W U l 6
O O O g
,G,, . , . -
" C .E 4.3-1 'G m u.._ .T Q R 4
P SR 3 3.lLZ. 5
$ SK 'L3.f2.1 sg 3.3.fl.3 CWWEE. MODES IN W ICE Y CHANNEL CRUMEL FUNCTIONAL SRVEILIANCE E e
FUNCTIONAL WIT _CNECK CALIBRAT!W TEST RE05 IRED 8 5
- 11. Wide Range Logaritiumic Neutron Flux 5 REFUELIM INTERVAL D ) sgt) 3, 4, .l g m Monitor E ,
AZ. Reactor Protection System logic M m Q and S/U m 1. 2 f Natrices
- 13. Reactor Protection System Logic M M QandSMll 1. 2 Matrix Relays R Q . Reactor Trip Breakers M M M 1, 2 and * !
y Ce i . e .., , . s a u .,.,. ., NJ ' v, " r-d.r.
., 1..., ~J. 3. *5,' Res L~-;. e uJ 7 .o I . t . , s ..
**- I * *- s. s g . .a., c. C CL.c p
{ f6, C, p* e . f. ~ . J . 3 7.3 ~'a r .. .,4 ,. . . 4 2 s c, s .t.,
** pg g 4,,., g F.
' 9
=
<~ A - -
x $ P -s s. . _ ot , . _ , , s y J 4 5 F. ', . - . . r. . . s , .. . Y '<.i,gp, $ i I. .~ . . . . at , s. , .- o,. .. , * . 3 ' - p , A >
. -- d -
e . G* A RTCQ . g, - '._ C CA % n .,, .,..s . ~ tek t - ( g 0 (17 ,I cpi; , _ . L. ( . .. ~ : s '-
h ..f.,=4.o s *
- k 4
l i i !O i i \
- .3/4.3 INSTRUMENTATION l
- w 4. . . ... - .rcu=-v
- TABLE 4.3-1(Continued) p, , p, ,,a , , , "t. t . T l TABLE NOTATION "RPS L gic a d T* in Ia 4 am i
gg With reactor trip Dreakers in the closed position and the CEA drive] ; 3.3, i, 6 system e = ale af crA withdeawaL Ag g g L,I j ] _ ___
*7 If not performed in previous 7 days. d
'__ P *
*'~
'} , _
- 3. 3 t .'2 k I 1m-m -
eat balance mdyAbovMi% of_BATER twra"*130WEA adjust
' ; i,, - . - _ . . . . . , _ m.. >to make the nuclear power si p .d o ' c Jgree with co' orimetric ce culation if absolute difference is > 1.5%.J P*~~~' Y l
During PNYSICS TESTS. these daily calibrations of nuclear power and %d'~ ~ h . 4 NoTM . AT power may be suspended provided these calibrations are performed . T upon reaching each major test power plateau and prior to proceeding l 40 the major tant er plateau.
- 3. t. 3 N -
'Kboys f POWER. recalibrate the excore detectors Af6 1 - which monitor the AKIAL $NAPI INDEX by using the incore detectors or c o.J J4,:..
i { c . "2. { restrict THERMAL POWER duri a-inum allowed TME
..-..... ;; zs. k_.eos _
subsequent 1 . ' th th:operations to 5 90%
--'st' r: "---*-- ofM=.
t_ _1 , la8 f L,, ny l l $~, g [ 6pve 15% of RATED TRERMAL POWER] adjusf /! 7 : *^"i--te M.. - erntom - c...r. - oi 6,70uring pMYSICS O' _ i TESTS g these daily calibrations of nuclear power and AT power may be ATrw-j unc( suspe provided these calibrations are performed upon reaching p....' 2 each majo st power plateau a W +a near w ine *a *ha ===+ - f or test steau. W o. No, rt. u ,4 4. = c. c 3.
- 2) 'A .
. .v+;i i L.
I
$.n3i5 jNeutron detectors may be excluded'frT2ME TION. L.t 3.~% e.7 l ucn E l
TR. 3. 3. t . '5 N OTE
- llot go ,. A h h,-f,,-Q uf,-l 12 hovr5 ,cf4rrTHEdmet PowM 4 lb*rMTP
. 2 l
1 I I i 1 i CALVERT CLIFFS - UNIT 2 3/4 3-8 Amendment No. 161 l t i 1 I tO af IO l P
- 3,
l Se~ 4 b 73.1 l ' I i ) !O ! 3/4.3 INSTMMENTATION ! i 1
- TABLE 4.31(Continued)
- TABLE NOTATION I
With reactor trip breakers in the closed position and the CEA drive j system capable of CEA withdrawal. l III If not performed in previous 7 days. l k Meat balance only, above 15% of RATB THERMAL POWER adjust ' Nucle) power Calibrate" p6tentiometers to make the nuclear power signals agree with calorimetric calculation if absolute difference is ** 1.M 1 Ouring PNYSICS TESTS. these daily calibrations of nuclear power cad AT power may be suspended provided these calibrations are performed l , upon reaching each major test power plateau and prior to proceeding
; to the next major test power plateau.
l . (3) Above 15% of RATED THERMAL POWER. recalibrate the excore detectors j b which monitor the ARIAL SNAPE INDEX by using the incere detectors or restrict TRERMAL POWER duri subsequent operations to 5 90% of the i maximum allowed THERMAL 1evel with the existing Reactor Coolant j pump combination. j (4) Above 15% of RATED THERMAL POWER, adjust 'AT Pwr Calibrate" ' potentiometers to null ' Nuclear Pwr - AT Pwr." During FNYSICS i - TESTS. these daily calibrations of nuclear power and AT power may be I suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the next l g or test power 01steau. __ i T.'F.2.4 h Neutron detectors may be excluded from CRANNEL CALIBRATI i A. NOTE 1 1 >
$y d , ., e m .. - . F 4. q, .,
j 6, ,,(me.., 3 %. I, " P,P5
^
l J , .,-e ,. , 4 . 4 . o , - op~ab % l 1 1 i i i t ] CALVERT CLIFT $ - UNIT 2 3/4 3-8 #aenement No. 161 l i iO i py 7 or 7
, - -- -- , ~ - -
- <; r . r . . . . . - 3. s.T
} O 3/4.3 INSTRUMENTATIM TABLE 4.3-1(Continued) TABLE NOTATION With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal. kII If not performed in previous 7 days. III Heat balance only above 1M of RATED THERMAL POWER; adjust " Nuclear Power Calibrate
- potentiometers to make the nuclear power signals agree with calorimetric calculation if absolute difference is > 1.M.
During PNYSICS TESTS, these daily calibrations of nuclear power and , AT power may be suspended provided these calibrations are performed ! upon reaching each major test power plateau and prior to proceeding l to the next major test power plateau. l I3) Above 1R of RATED TNERMAL POWER. recalibrate the excore detectors which monitor the AKIAL $ NAPE INDEK by using the incore detectors or i restrict THERMAL POWER during subsequent operations to 5 90% of the I maximum allowed THERMAL POWER level with the existing Reactor Coolant - Pump combination. l (4) O Above 1M of RATED THERMAL POWER, adjust "AT Pwr Calibrate" potentiometers to null " Nuclear Pwr - AT Pwr." During FNYSICS TESTS. these daily calibrations of nuclear power and AT power may be suspended provided these calibrations are performed upon reaching - each major test power plateau and prior to proceeding to the next major test power plateau. (5) Neutron detectors may be excluded from CHA M EL CALIBRATION. (,, ./ . c o se, s . - ,I e b *
- S' S F-r 9 r> < 4 ~ * - U b"RPS g ., u , _ , 4 s . , - o o- - 4 , - . ' '
CALVERT CLIFFS - UNIT 2 3/4 3-8 Amendment No. 161 l 0 - g 1O o r 10
i j q... c . . . 'i.T.l2. l 1 4 i !O i - I i i
- 3/4.3 INSThilMENTATION l
i
-TABLf-4.5-1 G ,M. 4 0, .l . . . . .,.,
.r.G....s\
- r- eg . r u .a. - 3. 3. 3 ,
-TABLE-H07AHON % t ,, , . .
r , , ,, , . , , _ - } With reactor trip breakers in the closed position and the CEJAhQ . tes. capable of CEA withdrawal. - TR 3.3 4/2
- r. ,p.. ,7 If not perfomed in previous 7 days. (
T Heat balance only, above 1M of RATS TREINAL POWER; adjust " Nuclear Power Calibrate" potentiometers to make the nuclear power signals 1 i agree with calorimetric calculation if absolute difference is > 1.R. - i During PNYSICS TESTS. these daily calibrations of nuclear power and i AT power may be suspended provided these calibrations are performed i upon reaching each major test power plateau and prior to proceeding j to the next major test power plateau. I3) Above 1R of RATED TNERNAL POWER, recalibrate the excore detectors l which monitor the ARIAL SNAPE 15EX by using the incore detectors or i restrict TNERMAL POWER during subsequent operations to 5 90% of the I i maximum allowed THERNAL POWER level with the existing Reactor Coolant - e Pump combination. [ l (4) Above 1M of RATED THERNAL POWER, adjust 'AT Pwr Calibrate" ' potentiometers to null ' Nuclear Pwr - AT Pwr." During PNYSICS l TESTS, these daily calibrations of nuclear power and AT power may be
- suspended provided these calibrations are performed upon reaching l
( each m.ajor
--a._ .6 test power plateau and prior to proceeding to the next niateau,
! 4R, 3. T.12.
- 3 )A Neutron detectors may be excluded from CllAINlEL CALIBRATION.
1 i i 5~ 4 ~ . ~ . c a,. . . .,
- F , sg,..r,, + e '4. 3 i , " RPS l .c< a s L + * = ~ - O p ,, . A .' g, U i
l CALVERT CLIFFS - UNIT 2 3/43-8 Amendment No. 161 l iO 4 6
- P'"Y
4 f $ p ,,, . C. , . 4 . . , ' 3 . "T 4 I l l O p....:Q R- _ ar) 33 4/+rl DSTRUNENTATION & A $) ( g, 5. 4- -3/4.3.- ENGINEERED Y FEATURE ACTUATION SYSTEM / INSTRLMINTATION LINITING CONDITION F ERATION * ' " ' ' ' j 5.5.s. h;t. E neered Safet Feat
.':tb., channels and Actuation 5 shown in Tabht AS b - -
Eb!M ha 1 be l DPERABLE riti tt.;i- tM; ett-9t: :d :- :ht;r.; .;;tt, tt.; ..;... .. .. M
- tt; T-!; I;t;9t
- :h;; ;" Mk ".0-0. -
{ APPLICABILITY: f.; :i:..- ir ic h ?.?-3
'oE k i, - 4 ACTION:a i
- a. With an ESF
, conserva instrumentation e than the value s channel trip setpoint lessaluescolum] in the Allowable n 4 of Tab 3.3-4. declare the nnel inoperable a apply the ' g {) appl able ACTION requi t of Table 3.3-3 un the channel is r ored to OPERABLE st s with the trip set nt adjusted j j u onsistent with the T Setpoint value. f i (li~ ~ Wiin 7 s M n Table 3.3-3.is .6 [st p channel ni inz w inoperable. -- - Ake the ACTIDN) 1 l 1 _ - NOTE - -- - - -- g_6 p.... e -. (. a a . .. -' = j . * = h * -J O SURVEILIANCE REQUIREMENT 5 s b .. . . (* - Wr - s#-ser_ 4.3.2.I.I Each EIFA M)r nt ":): channel shall be demonstrated 1 3 3.4.1 r..t.4 2 OPERABLE by the pcrtc+mance of the CNANNEL CHECK. CNANNEL CALIBRATION and CNANNEL FUNCTIONAL TEST operations ?.ri;; th: """" ;;d :t th: ". .w.nu es Q i 3 , 5 . 4 . 4. dr '- T Me '.3- 2. A. 4.3.".;.r_Jhe logic forthe bypasses shall De_cfmonstrated OPERABL uring ne at er CHANNEL /DNCTIONAL TEST of channey affected by bypa Cope ion / The tet!! !;;:!! 'r t'- . Shall De demonstratea vruuwLt. at 4R issu once per REFUELING INTERVAL ring CHA10lEL CALIBRATI0lltesting_of_ _l ( -g 5.3 A.3 each channel affected by bypass oper D. .-G~A s et=bl. , w r. ..,. F i
. . s ., , e
' - - ~ -
4.3.2.I.3 The ENGINEERED SAFETY FEATURES RESP 00tSE TIME of each ESFAS function shall be demonstrated te be within the limit at least once oer REFUELING INTERVANtest sh include at least one cha 1 per (function such that all channels re tested at least once e N REFUELING IIlTERVALS where N is the tot number of redundant channp1 n a specific .[ . E5FAS function as shown in ' Total No. of ChannelsA'lumn of
- Qable 3.3-3.
On s STAG 4E M D TEST 6Asl5 (
; CALVERT CLIFFS - UNIT 2 3/4 3-9 Amendment No. 186 O
p c. \ aG \b
ipecFi%4.o* 3. T . $ 1 i
- 3. 3 $/0:6 IRSTRUMENTATIM b
*s a . <l f*_-**
$ %.3.5 3/4.3.2 EntNrrREo sArriv rEArunt Act"= sysTid_ e = - -
<r. - .,. . . . , . ~ ~~ . a + - r 643 I
LIMITI M CONDITIO11 FOR OPERATION ( A s -. +... L . ,. f co...
~
,L.s 4. o pr%%.sg u, pp.g f g, , -
I L.c o /f.3.2.1 3her Engineered safet F ure Actuation Syst ESFA5 r,,,,, , r. .J l instrgma6tation channels and sses shown in Tabl .3-3 sha 1 be ! 3 ' .5
- 5 OP LE with their trip s ,.
% g, c;.q4 ints set consisten th the values s in l Trip 5etooint columr6 able 3.3-4.
-- M @'
T~ d""'"** t APPLICABILITY: As shown in Table 3.3 3. '\
- n. ep.. /, . .a.
j E110E8 [
- MAf, I%4e
, '. '. 4, 7
7
/'
i With an ESFAS instroentation channel trip setpoint less ! conservative than the value shown in the Allowable Values colon i of Table 3.3-4 declam the channel inoperable and apply the applicable ACTI0li requirement of Table 3.3-3 until the channel is] } , restored to OPERABLE status with the trip setpoint adjusted ~j ! Qsistent with the Trip Setpoint value.f , i j 2 mu __ ,,,,, .. .__ ..., _ 4 j _m _u ___. <_ ._u u_ ,,n , [h] G l g -
=wm-7-
f <;,$. . .' 4 [ [. a. 4.. e*y is o 'lo J F, ,,u r- e 4 . .
- ( -
SURVEILLANCE REQUIREMENTS
~ __
i UT' A M .;.I Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the ____ V5A CNA10lEL FullCTIONAL TEST operations during the .^:ZZ sd ;t t'.; '..,.....L.
- m. m wa. 6 JJ. .o. A*
& '- T d': 0. 2.
$.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during7 the at power CHAllNEL FUNCTIO 11AL TEST of channels affected by bypass '
operation. The total bypass function shall be demonstrated OPERABLE at 1 cast once per REFUELIM INTERVAL during CRAlelEL CALIBRATI0li testing of each channel affected by bypass operation. 4.3.2.I.3 The EllGINEERED SAFETY FEATURES RESP 0115E TIME of each ESFAS function shall be demonstrated to be within the limit at least once per ' REFUELI M INTERVAL. Each test shall include at least one channel per function such that all channels are tested at least once every 11 REFUELIM i INTERVALS where N is the total number of redundant channels in a specific E5FAS function as shown in the " Total No. of Channels' Column of able 3.3- Q -__ - An (w .. r b Ael % L ..l.s _C..s,.it..cc N t.r F - - - 0 1 .s+. 3 of .A . 4 , 4 . . . L-s 0- . 4 6 .L4 < u ' A -e 4. m f d ia e A,go c'*c*" r"8y -dr.s s. r I. I 2) F.t. n -% < . 6 4 w.% a'*4 9 ' P ' -' 4- N4 **-=+d W .pe. . 4 d
.l . . g p . a . p .m 4 . .
g ..<--t y < t s. * <4 u b, 4 . *- 4 .e-x -: -- r - -- -- CAL ERT cliff 3 - UMll Z - 3/434
~
.e4 .Mio
,. z a . A ,
I g 1 .rm
_ _ __ _ _ __ _ .._ _ _ __ ___._ . _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _m
$ pec F. ,= 4e o % 3. ~5. 6 l -
x __, m i C-ov e- 5,...., u.Jules -d ""*'~'d 8'- P
- m ., 4, ..., ,c v.,%. ca. - -2 r_ , . . . - . .u . .
- . . . . - .. . . s D& 4 4t e
G~)
- 3. 3 114r5 f Ill5TRUMENTATI0ll -
h . 0 5,4,1 v.A.e F h ..A Ocr M,+<- bg,c._ 3 j gy g 3/4.3.2 EMIMERED-SAFFYW-M_AnlRF-ACTUATION-SYSG; ::aimDIENTAi;0N _ LIMITI M CO M ITIO11 FOR OPE 1kdiD -
~* ~
Y i I g_c.o 33.b II.3.2.1 The Engineered Safe Feature Actuation instrumentation channels and sses shown in T e 3.3-3 sha be tem (ESFAS [ OPERABLE with their trip setpoints set consistent with the values shown in ' the Trip Setpoint column of Table 3.3-4. - f APPLICABILITY: * "- '- ? die-he-9 hobE5 1,'A -- 4 ACIIGE:
- a. lifth an FAS instrument ton channel setpoint less ,
conse ative than the ve shown in the llowable Values column of le 3.3-4 dec the channel rable and a 9the (d~. 6 icable ACTIO11 quirement of .3 3 unti channel l trip set adjusted
%restoredtoOPERABLEstatuswit
_nsistent with the Trip 5et t value.
&e h$nY) . .
N oTE - . P{O 4* hvion A,q,c'4 o <e. 4. G ...,a C,4. > . . , (~ ' SURVEILLANCE REQUIREMEllTS
. , ,, , 4 r ., , r ,. , t.
(. ,4 -. h _S I,-, q s t.c. 6 o n)
~ 4.3.i.i.f Each SFAS'1nttrumentation channel shall be demonstrated -
I .7*c gO g OPERABLE by the performance of the SNAINlEL-tllECK;-CNAINIEL CALIBRATI0li and (4 CalAIGIEL L-- d. Takim FUNCTI0llAL A 1_9 TEST . operations-during-the-HODESW tt th: '. a__.. des (T.M.2 he logic for the byp s shall be demonstrat OPERABLEduring1 the at er CNANNEL FUllCT! EST of channels affect by bypass i operat n. The total bypes , unction shall be demon sted OPERABLE at j les once per REFUELIM ERVAL during CEAlelEL CAL BRATI0ll testing o l L channel affected ass operation. f Q,3J.1.3- e(EMIIIEEREp_5AFETV .FEA ES RESP 0115E TIME of e h ESFAS' Tunction - 11 be demonstrated to within the limit at 1 stonceper] ELI IllTERVAL. Each test 11 include at least o channe1 ~per funct ~ ~suc h"that all channe are tested at least N every N REFUELI M INT ALS where N is the tot number of redundant nnels in a specift L '*1 function as shown inAhe " Total No. of Cha ble 3.3-3. s' Column of j t 1 CALVERT CLIFFS - UNIT 2 3/4 3-9 Amendment No. 186 ! O
- m. a8
i 5 e-< r. 4.., 7. 7. 7 1 l l Q j ! i 3.1. 7 1.T */*+-INSTRamATION a m a.a [ 2 11 nNeiertro-sArtTyMTurtr'-Ac5Afinfix ant-" me:mp .
- w. . .. .
i LIMITINs C0mma FoR orERATION ?.t-Wli g*;~f$ ff,.~j,f-f, $Q,*,,,'; ,g,;,,,,,,
- -,. _ ~
3.3~.2. 3 _ Engineered rety Feature Actuatt q .ro m c. 3.3. '/ inst ntation channe and bypasses shown i tem (ESFAS) ab e 3.3-3 shal r GPERABLE with their p setpoints set tent with the v '
- O he Trip Se,tpoint lumn of Table 3.3-4 s shown 13
_ y APPLICABILITY: As ' i= ' 9 h 3.3 3. s-p a... s cokM$, -_
- g. ins .a ., w s. e.. .- - A a7With an E3FA5 Instribentation channel trip setpoint less
. .-. < . c .. . . . a0 tu ikC G (5 conservative than the value shown in the Allowable of Table 3.3-4. declare the channel thoperable and apply the kV"l 48 Va
A ,7, appitcable ACTIm requirement of Table 3.3-3 until the channel is, aj (restored to OPERABLE status with the trip setpoint ad, justed j Q. . c. -- con.sistent with,th,e Trip Setpoint valuev b. With an shown ESFAS in Table 3.3-3. instrumentation channel inoperalle, take the ACTIM] .h,,,* _4./, p 8 . SURVEILLANCE REGl!REMENTS
,I/.l 4r5.24d- Each TSFAS instrumentation channel shall be demonstrated
.,.,,,7 OPERABLE by the performance of the CRAINlEL CNECK, CRANNEL CALIBRATIN and I.
3 .l * , , ., CRAIDIEL FUNCTIONAL TEST :;:=ti::;-dur' ; %e "E! d :t M: '7_: :!:: *( f,.'.' f, A showm in Yahia ' ? 2.- 3* b [the at pow,,er CHANNEL FullCTJ0llAL TEST of channels affected b operation. The total b ss function shall be dynstrated OPERAB at
) le3st once per REFUF each INTERVAL during CHAIN channel affected by bypass operat.fon. JI L CALISAATI0li test of j l \4'.-
CR$ SR "5.5'7' 6 R. 3 The b!uir.m mini 4fATUR 3 RESPONSE TINE 4f each ESfADc s icN'C. TjsM Tuncfionl shall be demonstrated to be wilhin the limit at least once per REFUELING INTERVALS E m testAhall include at least cnannei per every 11 REFUELI iINTERVALS where N is the tptal mnber of redundantfunction nnels in a specif such that all chancefs are tes i i sESFAS function as shownje the " Total No. of Cha s' Column of j Table 3.3-3 on a STA HrERtp 7EST SAsl CALVERT CLIFFS - UNIT 2 3/4 3-9 Amendment No.186 O p a t or \D
fp~.c.s.. ,:.3.9 o V
~f. 3 SMr3 INSTRUMENTATIM i
T i . s. 9 saser -eNetrate-wm+eAmt-asunaL s'<! v.. . ..... . =mieTu... a.-_- i m(..]. .._- e . - r= . s i m LIMITING CONDITION FOR OPERATION H + t a. . -3 e s- r ~. A e. . -4 x .........a a i L-( O (5'3.2.1 I naineered safet Featu Actuation system FAs) ~ ' " - - '
-5 i "f 3, 9 instrume tion channels and s s shown in Table 3. 3 shall be ~ * " * * *'- #
OPE with their trip set set consistent wi the values shown i ' 'y' ' < - 6. the rip Setpoint column of goi e 3.3-4. w cj_G% APPLICABILITY: / miwwn in isbis 3.5-3.-h oott ( 7,3.-J t) EIIE: . A. With an ESFAS instrumentation channel trip setpoint less 7 conservative than the value shown in the Allowable Values columni ,
. of Table 3.3-4. declare the channel inoperable and apply the applicable ACTIM requirement of Table 3.3-3 until the channel i ' (A '
restored to OPERABLE status with the trip setpoint ad. justed (consistent with the Trjp Setpoint value. -- (s. With an ESFAS instrumentation channel inoperable, take the ACTIM) Nshown in Table 3.3-3. g 'A4
- - - - - A u Q 3.'i'.p.1
'g SURVEILLANCE REQUIREMENTS ES 'Y r
~ '
I. . . 4. " . L-1.1 Eachb instrumentation _ channel shed be demonstrated r 17.9.'s OPERABLE by the perfonnance of the QIANNEL'CHECC CHANNEL CALIBRATIM and CHANNEL FUNCTIONAL TEST operations-diring-the-MODES-and--et-the-feequencies Mb Shown in isDie 4.J-z.
/4.J.z.2.4 ine ingic for tne bypasses shall be demonstrated OPERABLE during' the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at Q_..
\
- least once er REFUELING INTERVAL during CNAMEL CALIBRATION testing of J [
Qachchanne affected byDass operation {, ,,. g , g '3'q 'a D id The1NGINEERED MFETY TEATURES RESPON5l~T55ETf._tactriSI5D (functio hall be demonstrated _to be within the limit at least once per R'EFUELING INTERYAkCTa~ch test shall inciulelt'THTY'bne ChrnneT~per' A
" function sui'h' Di_at all channels are tested at least once every N REFUELING .I i
INTERVALS where N is the total number of redundant channels in a specific ESFAS function as shown in the ' Total No. of Channels" Columnif Qable 3.3 3.7 ,
]
wa STAcre uno 7667 6 Mis CALVERT CLIFFS - UNIT 2 3/4 3-9 Amendment No. 186 O tc7
O O O L _e 3_3.43
$2 TABLE t h's R.
T,. m,. T,. o s . - T. - .C
" LA.t l
c , CNNNELS
- - -o ,
'" F W CT,0 m L T Ag TS TRIP (SPGABLEgt MUSES.__j M g g 1. SAFETTINJECTI0ll(SIA$f g i (a. Manual (Trip Buttons) 2 1 2 12L4 Mr N ,
- b. Containment Pressure - High h 2h1 3 A-C A,
- c. Pressurizer Pressure - Low g g L1. 2 y 2. CONTAllOIENT SPRAT (
'r' C Manual (Trip Buttons) 2 1 2 1. z. s. 4 A' H
- b. Containment Pressure - High @ @ @ i
- 3. CONTAlleeli ISOLATION (CI5fOLA'9 LA' h. 3 fA* *
@ _Ranual CIS_(TripT _puttons) 2 I Z I. z. J. 4 6M '
[ b. Containment Pressure - High j e,. A. tA.2 A,% A .', f LA.3 .A, h
=
l
's G ** M.3
?!
N E '..!
}
e -
. qu o ,.,,, ,, s ._ ., r c L- 7 s, g-t n r;., S . - . c. ., .~ 3. e. 3, a:
p ' p ,. r .1 e. Le.e I A- - + 1 3 4 .n
,I':
t
O O O ' [er J.mu.., . F e L.-y - Q 4 p. . . r.. 4. ., 5. 5. 4,
" Fs M s i- a .. ~ ('I.3.5:-D :
i I g I TABLE S S=9- t= r- ' m " 6 .__ SAFETY FEATHE ACTERTIsli STSTDI IllSTIWelTATIGil AS l$ AlS) reamusit i APPLICABLE y i FUNCTIONAL UNIT TOMIP OPERABLE MODES . . ACTIO18
- 1. SAFETT IIIJECTI0lt (51
! d i
- a. Manual (Trip Buttons) 2 1. 2. 3. 4 ; E !
[ fb. Containment Pressure - High 4 2 3 1. 2. 3 7*
- c. Pressurizer Pressure - Low 4 2 3 1. 2. 3 f*I 7*/
i g 2. CollTAlleEli SPitAT (CSAS) { a. Manual (Trip Buttons) 63 @ @ 1. 2. 3. 4 C)
. Containment Pressure - H1gn 4 4 3 1. 2. 3 11)
Y '
- 3. C0llTAllWEIT IS0lATIOlt (CISh
- a. Manual CIS (Trip Buttons) @ @ @ 1. 2. 3. 4 1)
( 5. Contairement Pressure - High 4 2 3 1. 2. 3 j N f
-- ~
v_
.+
- A 4 Aei _ s M ..4... L-,.. c., ~ a, r_ ,4, ,,, l q$ p, j . .
s 5
- _m s a _
.s
*4 f 0
9 on ! 5 I
._.._. . _ . _ . . . - . _ _ _ _ _ . . _ . _ _ _ . .. .._..._._.m . . - . . _ . _
O O O l R.,. Q ___ O g TABLE W (Continued) g scg;i c;;_;._. - .+ - A r=>mm i s.i.a.., s,7. smw (4.21 m=E aC=rra q3 mm ggg as==mrmeQe m - U C a e 4. ........-.-.v.,% g b
~*
. mnual Ut31T Nand Switches 1/ valve I/ valve I/ valve I 2.- ~-3. 4 BJ b i E
" and Feed Head Isolation f -
MandSwitches) # , (A, ,3] NMadch- '
- b. Steam Generator Pressure - 2 e 1 steam 4. .
Low . rat
'6 b A '7- '
- 5. CONTAllteif Stw RECIRCUI.ATION A.4
- I y (RAS) Mh
- Manual RAS (Trip Buttons)
. 2 1 2 1. z. J. 4 6J
~
- b. liefueling Water Tank - I.ow @ @ g (M L4. ($ .
6
~
[-e <6sco.,s.. ,, T d 3,.,
! c;c s e, . . r. .a ..., ,. t; ,
pl\
= .
7 !
" E 6 A $ L g.s n .L P1. o- I T . .h
% a.
~ ,
O L9 Fi G f
\ . J-D ~
J!
=
->l
O O O O' <. c " w.as o r a L ny e, r,e Syc.f..s.,- T. : .1, " FwA S _ N t m ,,4 , -4 4,
@3,SQ g TABLE tS:3 Continued) l R h DIGIIIEERED SAFETY FEATURE ACTWATICII SYSTDLIIISTRWWITATTOR
-* A. tD (L A . 9 ( w E /T9TAk .
f fR4 EELS CWWWELS APPLICABLE a f5ECTIG11AL.8IIIT OF ERAIEIELS TRARIP N INDES ACTIGil I 4. fWLill STEAff LIIIE ISOLATI0li (# l l
! a. Manual (MSIV Mand Switches 1 Ive 1/ val # we 1,2.3.4 Y A,l '
and Feed lleed Isolation R MandSwitches) 2/ steam h] 3/ steam 1. 2. 3 77 [
. Steam Generator Pressure - 4/ steam Lp --
generator _ aenerator eenerator _1 S. CollTAllEEli SupF RECIRCULATI0ll R (RAS) f a. Manual RAS (Trip Buttons) h 4 2 3 1, 2, 3. 4 1, 2. 3 J
/ )
Q Refueling Water Tank - Low i 1 s T !' o I. n i i i g ,
" 9 :
W 0 c I [ B - ,
. j r
o vI W ! t i
O O O i w t ? ' C
~^ MlkT.T.']f g [Anbi Contiraed)
E = - __7_-s .., ,.. e u . n .... . . . _ e n * " E MIW11ml E i P TOTAL M. ORAMELS OUMIELS APPLICABLE y MWES - ACTIN
- yggygg et ggy 0F CRAMELS TO TRIP SPERABLE g
3 ISOLATI0ll if 4 g,,, , y,,g 7 $ [ U F ***" an 1/T . a"J ti: W8'**%'*%488 0 I l E !
- a. Manual (Purge Valve Control
" Switches) ;
- b. Containment Radiation - High 2 3 6** 8 Area Monitor 4 ;
g LOSS OF POWER j
- a. 4.16 kw R . W ay sus 4/ Bus 2/ Bus 3/ Bus 1. 2. 3 7 j t'
g Undervoltage (Loss of 3 Voltage) 3/ Bus 1. 2. 3 7*
- b. 4.16 ky L . ,... y Bus 4/ Bus 2/ Bus Undervoltage (Degraded y .
Voltage) - j 5-c J ss .. .- .F s t 3,, k he 2.se ,ss, , of O * 2 ' S m G. sp ,. f . . 4 . . , 7. 3. G W Cor Sp - c . c. <., J . .- _S . ..'s..',
- l A
=
o
< Q. S ,
- FOG t os/s h O 1 ea 0 0 g.
t,2 i h - 64 i G' s
O O O
=
p ' _o '
-TABLE-3r3-3-(Continued)-
% - aGINEstED4AFETY-FUTERE ACMTION SmW INSTREMMTATIM-5 **wn a m IC = c
=
c ma .. JFCIUuu1ELI,l TRI SPERABLC' l MODES . _ M N
'l i; FUNCTIONAL GRIT - a _. ~ w
- 150 - 2. g h , -
- a. Manuel (Purge Valve Control 6/PenetfEtion) Q7Penstfat1 A Q/Pepettet ) 6" 8 E
$ witches) *g g
- b. Containment Radiation - High j Area Monitor 4 2 3 6" j8
[ C .,-d." e* *...
- G
" 7. Loss 0F POWER 4.16 kv Elmergency Bus /pd3 I I3 1. 2. 3
- a. 2/8mf} \
;;; Undervoltage (Loss of Voltage) / / N g ,o g
- b. 4.16 kv Emergency Bus s 2/M 3 1. 2. 3 A46 ~~
Undervoltage (Degraded Voltage) g b ( M .1
.' 7 i
"U f
~
4~ S
- 1. sc s. . , .S c t . y ,
C. ~ a . ., 5.'s. 7," CKS^
\ t. ^ .
A.\ u A
~T )
y c
- o i
\ e N
~
I lN oO .d e c s
O O O
>M E
o 9
<r-i g
TABLE 3.3-3 (Continued) R. N U O ENGIIIEDIES SAFETY FEATWitE ACTWATIGIt SYSTDI INSTMIEllTATIGIl c Q immat
- p n C -19TAL-IID6 OguglEt3- CIAMELS APPLICABLE 5
4F-OUWWIE13 -TS-TRIP -OPUtABLE MOSE5__ ACTIGIl 3 FWIICTISIIAL WilIT
- 6. CollTAIIWEElli PUllGE VALVES t_ . m k-]> 4-e ISOLATI0li l^' g g g 7
U a. Manual (Puv1pe Valve Control ration) ITPenetrationf/Wtrittp . E usu Ac,..us
$ witches) r e -
A< a
- b. Containment Radiation - High 8
v/4 t Area Monitor 4 2 m 44 g (7. LOSS OF POWER
\ _g . g ,2 ,
Y a. 4.16 kw Emergency Bus Undervoltage (Loss of 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7 IVMI2 l M ~5 Voltage) M.4
- b. 4.16 kv Emergency Bus 4/ Bus 2/ Bus 3/ Bus 1. 2, 3 Undervoltage (Degraded Voltage) t
% J. ~ . - ,J a ,, [ r'
-o a r-. G* ,,c, ,4 . . . 3.c ' ; s x
;I' EOG - Lovs " 5 a
e 9 . y o
O O O 3,e cge mio- .F g
$ CL.5- 3 C" S -mFm 4% TABLE-hS=t-(Contineed)
P
'w
_ sArETY FEATuE Actaneitsystet rusTimertAires
$ 3. 3. 3, "(vcs A2
~
s,y- t ^ rue _ _[ 4,j w [ I 3. l.4. .% H ,y M
!FWCnemLWH '
g
. . CVCS ISOLATI01l 5
- a. Manual (CVCS Isolation 1/Yalve 1/ Valve 1/ Valve 1.2.3.4 6, E Valve Control Swttches)
[
- b. Ilest Penetration Room / Letdown IIeat Exchanger 7;, l 4' cp 7.eauro m y a 2 3 1.2.3.4 47
_A.3 f:8 9. AUXILIARY FEEDWTER ACT MTION g* f .
)
- SYSTEM (AFAS) w h ~ Manual (tup Buttons) 2 sets of 2 per 1 set of 2 2 sets of ? 1. 2. 3 6) s per s/s ner s/sf g, c_ ;
g u /s I h (stajgingegnei-tow
- c. sen . senerator ar uteh g %W 3
lO
- 1. 2 F
[ gc y. E [ su bw.., . F Ct.. .,
'3
& n i
a ., sp.c lc,;,4.:. 3. 3 s , J! E 1 , - eqc As Le3 c t J M ~ -. i e-
- '- .s ;
L) T. , P n
- V LU .
i O U
+
D 1
+
. . . . - . . . ~ . . . . . . . . - . . . . -
O O O h- J. . - s. - oF c L .- ,--, F., 9 ,. . r. .J .s 7
- 3. 3. 9, ' C vcs I s. t. -e .... %.3 1
^
Q h p TABLE (Continued) R_ Id h EMINEERED SAFETY TEATRE ACTUATIM_SYSTDI IllSTItMDITATICII
* (A. 5) LAt g w E
b k W. OFlfWINE ((TD4 RIP JRAMELS t0PDIABLC APPLICABLE MODES - ACTIgli U q FWIICTICIIAL WIT m , - . - 3
. . CVCS IsotArron .6 g e
?! a. Manasi (CVCS Isolation d>
Valve Control Switches) 1/ Valve 1/ Valve 1/ Valve 1.2.3.4 6 E [
- b. West Penetration Room / Letdown Heat Exchanger oom Pressure - High 4 2 3 1.2.3.4 7*)
R 9. AUXILIARY FEEWATER ACTUATION SYSTDI (AFAS) 0 1 (Trip Buttg) 2 per 1.2,3 7'
~
T Steas Generator Level - Low f 4/SG 2/SG 3/SG 1. 2. 3
. Steam Generator AP Migh 4/SG 2/SG 3/SG 1. 2, 3 7 1 0 5- a.- . c - - q.jD l c t c..,
s.c .,4.._ .. H- ~, t sua ,,2a g s s.4-S., ese4s i_,u - Va - ^'-4~ % c '-- - - i ,9<T '
? , i I . < . ,>
w .. c........ a ......... <n ...s t. ,.. r
' O a. 's1 - G . e. 2 t,,i . .,_,(is., s ) ( 3 s 123 '
q - ~ - - d
.a ,
O O O W. LN g YABLE-313-3-(Contivmed)- g h -tNorNEEnts sArriv-misaf-ACTMHON-SYSTEM INETEMNTATICE 2 @- 4A D MINIMUM c -no. courts aAmEts AertrCAstr E" A FUNCTIONAL 11RIT 9F-tN mNELS- T0-TRIP SPENAtti Mosts __ ACTION I 8. CYCS ISOLATION O q -
.s . nual (CVCS Isolation d Valve Control Switches) 1/ Valve 1/Yalve 1/Yalve E 1.2.3.4 ]
- b. We Penetration C" Room / Letdown Heat Exchanger Room Pressure - High --- -f- & 1.2.3.4 . D Ae s .ous 4J U 9- c R . AUXILIARY FEEDWATER ACTUATI Action C ;
SYSTEM (AFAS) m181 / . i b a. Manual (Trip Buttons) 2 sets of 2 per I set of 2 per S/G , 2 sets of 2 per S/G
- 1. 2. 3 6]
S/G
- b. Steam Generator level - Low 4/SG 2/SG 3/SG 1,2.3 7
- c. Steam Generator AP High _
4/SG 2/SG 3/SG 1. 2. 3 7 o a + R -n
- f-- 4 u ow.. .r ,L., .,,,
f\ G- < '37 - , . r. , 1. ., , 3.3.4,
$b f.sQnka (Op g
b , a Q .
'o ,
r I
Se < < , F , ci 4 . ~ 3. 3. 9-i j 3/4.3 IllSTRtMENTATI0li j t NWhi$*'* Y TABLE 3.3-3 (Continued) TABLEIl0TATI0ll " ($F M L q f caJ 4 *l l ntainment isciajan of non-essential penetra&f5ns is also initiated) by SIAS (functiefiel units 1 a and 1 c). / aur .- Q31 1
//
^
. When the RCS temperature is
(*) Greater than 325'F. the required OPERABLE HPSI pumps must be able , to start automatically upon receiot of a $1AS signal. 1 f i F(b) Bet n 325'F and 301*F. a ansition region exists ere the LE HPSI pump will placed in pull-to-loc nacooldown} A' nd restored to automat status on a heatup. . c) At 301*F and less, e required OPERABLE HP pump shall be ind h Qgo! red ( pull-to-lock and 11 not start automat ly. f - g r.'
^
t N 7E The provisions of Specification 3.0.4 are not applicable. . $.
- g G Must ce vrk^.E
- a4 i. ^^^- 5 d.;;. um raives are requiren artnABLE
,g4j 1 and they are open. f o;,gg VoA-.4 e ~
j O
'O bp/ Trip function may be bypassed in this MODE when pressurizer pressure is < 1800 psia; bypass shall be automatically removed when # {r sk 'l 3 g , ,4 , pressurizer pressure is 2 1800 psia.
' (d) M Trip function may be bypassed in this MODE below 785 pstat bypass shall be automatically removed at or above 785 psia. c ;f, - is.7 ., i.4- icsc.is) P$''< ~ i I'*4 '"
- 4 '- i g,, we S .l - . m C e a ' *
- 4 L ow 7 Pr' u 'c - M S ' *'
c o -4 , , ~ -+ y ,, , , ,, d +. be OPERA Gt E a. L - a LI
- h .e e4 **'u'5 ***'*4' k
?
.'5 L-
, cg ci,geg and de - ac 4 ? w a f'd ,
f u^C %f n -v- -- m, _
%e++ ** ** ******~
l y ,, ce r e e.d he s4***
,, pe p g ,
4 CALVERT CLIFFS - UNIT 2 3/4 3-14 Amendment No. 178 py 6 Fg
b ru 4 3.$. 7 - i a l 3/4.3 Ill5TRUllDITAT2011 { 1 TABLE 3.3-3 (Continued) l TABLE Il0 TAT 10ll i I 8 l' Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c). ! -fwl444 4 ) g i Q"/ When the RC$ temperature ist h Greater than 325'F. the required OPERABLE HPSI pumps aust be lable to start automatically upon receipt of a $1AS signal, j (b) Between 325'F and 301*F. a transition region exists where the OPERABLE MPSI pump will be placed in pull-to-lock on a cooldown and restored to automatic status on a heatup. l (c) At 301*F and less, the required OPERABLE HpSI pump shall be in l
; i pull-to-lock and will not start automatically.
k The provisions of Specification 3.0.4 are not applicable. . Must be OPERABLE only in MODE 6 when the valves are required OPERABLE I f and they are open.
- [*) ip function ma be bypassed in this MODE wnen pressuruer pressur is < 1800 psia; fypass shall be automatically removed when j
pressurizer pressure is 11800 psia. ICI Trip function may be bypassed in this MODE below 785 psia; bypass f i shall be automatically removed at or above 785 psia. i i a fh g 4$ Sp,%6 3.3.4[EsM5 4g 4 ,3 ,,g ., I %4 ~4.4.. . ' 1 i J l 4 ) CALVERT CLIFFS - UNIT 2 3/4 3-14 Amendment No.178 k
!O
- ,, su
) ip - c . f. ,. 4 . o , 33b 'O l 3/4.3 INSTRUMENTATION i TAtt171;rTContinueci
-TABLi-90TATION Containment isolation of non-essential penetrations is also initiated
- by $1AS (functional units 1.a and 1.c).
When the RCS temperature is: 1 (a) Greater than 325'F. the required OPERABLE HPSI pumps must be able l l 1 to start automatically upon receipt of a $1AS signal. ) (b)Between325'Fand301'F.atransitionrecionexistswherethe l 2 OPERABLE HPSI pump will be placed in puO to-lock on a cocidown and restored to automatic status on a heatup. (c) At 301'F and less, the required OPERABLE HPSI pump shall be in l l 9y"
- A pull-to-lock and will not start automatically.
#\[
- The orovisions of Specification 3.0.4 are not applicable.
Must be OPERABLE only in MODE 6 when the valves are required OPERABLE and they are open. )fkj 8
/~N (*) Trip function may be bypassed in this MODE when pressurizer pressure is < 1800 psia; bypass shall be automatically removed when pressurizer pressure is g 1800 psia. ,
'(8) Trip function may be bypassed in this MODE below 785 psta; bypass shall be automatically removed at or above 785 psia.
4
$,e J. cm ., .f G.-y '
- G. , 4 7 ,4 , 4 ... T. lA ,
) "an s i , .a _ , 4 . + . - 1 CALVERT CLIFFS - UNIT 2 3/4 3-14 Amendment No. 178 O y s-s
(e,.c e.- 3. T. 7
- 3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)
TABLE NOTATION i _ f Containment isolation of non-essential penetrations is also initteted by $1A5 (functional units 1.a and 1.c). When the RCS temperature ist (a) Greater than 325'F. the required OPERABLE HPS! pumps aust be able l to start automatically upon receipt of a SIAS signal. (b) Between 325'F and 301*F. a transition region exists where the OPERABLE HPSI pump will be placed in pull-to-lock on a cooldown and restored to automatic status on a heatep. , (c) At 301*F and less, the required OPERABLE HPSI pump shall be in pull-to-lock and will not start automatically, N s The provisions of Specification 3.0.4 are not applicable. i
*h Must be OPERABLE only inJ10DE 6 whpthe valvesgrequired yERABLf i and they are open.
}
f*I Trip O function is < 1800 psia; mabypass shall be automatically removed whenbeWasswd in u is 6E-pressurizer pressure is ?.1800 psia. ICI Tri function may be bypassed in this MODE below 785 psf a; bypass sha 1_be.aytomatically removed at or above 785 psia. 6 s.. ....-.c a..e, F,, $p,, . 0. .. A ., 3. T. 4,
" ESFA5 ( ~. i , ~ .s i , '
CALVERT CLIFFS - UNIT 2 3/4 3-14 Amendment No. 178 O
- e. , z .c m
Tg -, . r. . 4 . . - 3. s . 9 i i t O l 3/4.3 INSTRUMENTATION ! TABLE 3.3-3 (Continued) TABLE RDTATION Containment isolation of non-essential penetrations is also initist by51AS(functionalunits1.aand1.c). When the RCS temperature is: . t (a) Greater than 325T, the required SPERABLE HPSI pumps must be able l [ to start automatically upon receipt of a $1A5 signal. (b) Between 325T and 301T. a transition region exists where the l OPERABLE HPSI pump will be placed in pull-to-lock on a cooldown and restored to automatic status on a heatup. t (c) At 301T and less, the required OPERABLE HPS! pump shall be in < ull-to-lock and will noL31grt automatica11y. 7l ACT'ON (.
- The provisions of Specification 3.0.4 are not applicable. A.
N *TE .n
- Must De OPEPf3LE only in . ___ e when the valves are required OPERAB) and they are open. f Trip function be bypassed in this NOD; when pressurizer pressure '
O is < 1800 psia ypass shall be automatically removed when i pressurizer pressure is 3 1800 p:is.
, (c) Tri function may be bypassed in this NODE below 785 psia; bypass
( sha 1 be_sutomatically removed at er above 7a5 nata. N \ jar cJ . s . ., . . . . E cL. . .p s
\
fer (p*e.(-.L.us %'t.7, v 1,, J....,....- .I % ,s C, ,
<;p . , C, , . a 7.14,
** d -
"ESFAS t-9 CALVERT CLIFFS - UNIT 2 3/4 3-14 Amendment No. 178 O
pf 3 or 7
Sp , . x . . . . ., T. 's. + 1 !O f i i
- ,3/4.3 Ill5TRINIEllTATIM ,
s,. a ,~,, . , s cu v \ l TABLE 3.3-3(Continued) ,,, 4 , , c. , ,, w '5. ~3. 6, \' un-man "ESF A S ls - M~'I
- 011 6 - With the number of SPERABLE channels one less than the Total
- Number of Channels, restore the inoperable channel to
- SPERABLE status within 48 hours or De in at least 30T STASSY 4
! within the next 6 hours and in COLD SNUfD0lAl within the _ eah.rina 30 h==n.
.c se
_ . -,J,,e ! ASTB01tf . lit number of 9 LE channels one le than the Tota d'" ' " of Channels, tion may proceed vided the .,c lawine conditi re satisfied 7 5 , s . r- F 'EA-dsS ' C ,
,a s ,, .u.e -<e AcTiowJ A \ The inoperabl aced in either the bypassed r ,. w .c.. - -
R'$d* or tripped condition within 1 hour. T: .; ;;r;::r c. ei,....t 4 G* tut'.r.; sd s.h t. .._ U '. . is so.no.i ,es 9 - i'
,f Dr., i.i e iun;(' r p; tp hours from time of initial loss of A. 5
(<,=1 % * - ers- n u n ..___.er, the ino rable channel shall then be either restored to SPERAB status or placed in the g tripped condition. - O ( ye
*"d'*"
a^ ,,, e P4 5
. Within from t con r, all functional inoperable channel ion (eitherbypassed its receiving an nput' also placed in t same tripped, as appli le) required by a. abov or the inoperable A. fG d-
*~
.~ s a e ~ _ * ~ ' ~
t nnel.]as ,
,, g. A e y a4 ACT e a kJ Q{ ~ " '-'s**=***
% "' ~^- C': ::h =E***? :.;." . -..; h =' ^
- y. '. ." a e, .
however, one additional channel may be bypass r up to u ~< ?* 48 hours WM ;-fe-iaa + ==
- M d .. ... . m o. .
-ehennel provided the other inoperable channel is placed
?~ in the trippedjcondition.
With less than the Minimum Channels SPERABLE. operation may' (ACTICII 8 - continue provided the containment purge valves att maintained (clesed. _ p ASTt01848-- fliith the r of SPERABLE C is one less than t otal j Ilumber Channels, operati may proceed provided l i ble channel is pla in the bypassed cond on and t inimum Channels GP LE requirement is strated thin 1 hours one ad ional channel may be assed for up ,
- to 2 hours for su lance testing per $ fication LI m'
M s=.GnAit 5 md %L~ 3Q,1
..,.c ca..y.
9 "cas* CALVERT CLIFFS - UNIT 2 3/4 3-15 Amendment No. 161 l N3 ^C' j rn, Q![sytsr Ar e Jo[ WTWD 0 pp 7 . F lb
-. ~ - -w :
< p d , J on 3/t.4 INSERT C, D, E 1 O i C. One or more Functions with the C.1 Disable affected sensor Ihour l automatic block ranoval feature block module. l ofone sensor block module l inoperable. DE C.2.1 Place affected sensor block Ihour module in bypass.
D. One or more Functions with the NOTE automatic block ranoval LCO 3.0.4 is not applicable. feature of two sensor block modules inoperable. D.1 Disable affected sensor block modules. Ihour j DE D.2.1 Place one affected sensor Ihour block modulein bypass and disable the other for each affected ESFAS Function. D.2.2 Restore automatic block 48 hours removal feature and the associated trip unit to OPERABLE status for each affected ESFAS Function. E. Required Action and associated E.1 Be in MODE 3. 6 hours Completion Time not met. M E.2 Be in MODE 4. 12 hours O n ua
g,c . F. . 4 . ,. I.35 1 i i O rik k o A n u el M saire r px ( %%\u neAs teope,%Q 3/4.3 INSTRWENTATIM 4 l TABLE 3.3-3 (Continued hoe 4s .- G % ' for AFA5;
- ACTIM STATDENTS 00E. S A 36 Lets OrMLarf % bs, I
ACTIM 6 - With the number of OPERABLE cha ison~e1essthantheTota5 Act oy : Number of Channels, restore the inoperable channel to i m SPERABLE status within 48 hour M r De in at least NOT STA BBY - ' [within the next 6 hours and in OSLB455TDelAletthia-4he Acta ws /\A"9; M M.. G4 0 (ACTION 7 -
'W1th the number of SPERABLE channels one less than the Total Number of Channels, operation may proceed pmvided the following conditions are satisfied: l
! a. The inoperable channel is placed in either the bypassed or tripped condition within 1 hour. For the purposes of l testing and maintenance, the inoperable channel may be bypassed for up to 48 hours from time of initial loss of CPERASILITY: however, the inoperable channel shall then be either restored to OPERABLE status or placed in the tripped condition. - l ~
- b. Within one hour, all functional units receiving an input from the inoperable channel are also placed in the same ,
1 condition (either bypassed or tripped, as applicable) as ~ that required by a. above for the inoperable channel. I
- c. The Minimum Channels SPERABLE requirement is mets however, one additional channel may be bypassed for up to 48 hours while perfomfrg tests and maintenance on that /k channelprovidedtheotherinoperablechannelisplacejd
- the tripped condition. f A 4m With less than the Minimum Channels OPERABLE operatioTMily continue provided the containment purge valves are maintained \
4 1 (closed 7 (dCTI K - With
~ the number Number of operation of Channels, OPERABLE Channels nay proceed provided onetheless than the Totali 4
inoperable channel is placed in the bypassed condition and
- the Minimum Channels SPERABLE requirement is demonstrated within 1 hourg one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification
( 4.3.2. y J
; Sn J . s. ... . , . c e % . .g Qr J.sa -n.. . . F e \m $> $
('., , her r r* 4!.s 1 T.1, F , Q ,c.r. .A.4 % 3. d ,
" i q FA $ l ., e . M. J . e c n 5 '-
1 CALVERT CLIFFS - WIT 2 3/43-15 Amendment No. 161 l 1 i O Og g*
,- .-- - - - . - . .- - -_ . - . . _ _ - . -.-.- . - -. _ - .. ~ 1 i
~
5p, .,G , i .. .s f. 5. G i i iO 5,, J. s c., .s..., o f cA. ,,3 3
- f. , < p . L +. m T. 5 5, "EsFAS h 3/4.3 INSTRIslENTATION L *'i' e >d T4 . a ., d 't rI p '* )
l .
. . . 3 mam*-a-o g j
' -A8H91t-STATBIDITS-i b "
KTION 6 - With.the number of OPERABLE channels one less than the Totall thaber of Channels, restore the ino rable channel to OPERABLE status within 48 hours or- in at least 50T STANDBY - I . within the next 6 hours and in COLD SEUTDonal within the followins 30 hours. G.'eley ! AGR0164. - Tith
/e" F dm.ss iaw ;
i ro ruus u ch is one ss than b'*Md *r 4 or.e 88' ud - i gevow Total I ! of Cha sr operatio may proc provided 3 4 ng tions are s 1sfied: - y'"(a['h'
/.,w,4,Ah..
' a. The inoperable channel is laced in ett er the bynansed
,- _v_-- or teinand e d ition w i %4..c CL.. ,4 C . --- - ......:"ithi 1 hour. = r.: : _. -- 9
. th: P: ;; .',h d- r_:; - - 'Aa@
l i g opaggs Srrd 'r r; i:ja hours from; time of initialTos;s,,of Sh4 "* eruunsnavn newever, the ino rable channel shall then i
'- ' - be either restored to OPERAB status or placed in the -
i tripped condition. . L A'.'2 f l i 67W n one . all functio units receivi an input l ; rom the i rable channe are else plac n the same conditto either by or tripped, a pplicable)as G'- 90b - that utred by a. pas e for the ino f AC. Tion G ble channel /J py,~w -.d l [/H "'-'---- O.:nnefs-4PERAB:i .w i.-.4 %% -
' + " "
- S'**
; one additlanal rh.nnal may be bypassedhfor uD t *
- d '* I S *"
rs :$N :: - .%; te" geg~yp..r4 --d e n r ==-- - - = = + V - . . . * . 4 rd
'- - - ~ provided the otner inopersoie channel is laced m ... .s- k' etrippeyondition. ,,,,,,,,g '
p , ,. ] 4 With less than the Minimum channels cruunsu, operation continue provided the containment purge valves are maintat #C"_ 'I'f"TD closed .I ! or d r pe* Oil 11 - With the number of prUutsM channels one less than the Eot
% .A.
6 4.fr 1 Ilumber of Channels, operation may proceed provided the
- 3 7 inoperable channel is placed in the bypassed condition and '
the Mininum Channels OPERABLE requirement is demonstrated i within 1 hours one additional channel may be bypassed for to 2 hours for surveillance testing per Specification , <.a, . - ... .c n. ,e, ,,,i........ .a. , l Ct 5p*r%h..s I. ~5# ~2 , F.t- Tg.* = C. e " <* 5 T* To "BWA S i f g , ,.J .t...
\ "c RS" j
CALVElli CLIFFS - UNIT 2 3/4 3 15 Amendment No.161 l -
~ = _ - - ) ( b*
N _k d(DON i 4 oF S i p43r
e i 1 i SgdA7.t.e , i j INSERT ACTION C,D 1 1 l C. One or both Functions with more C.1 Restore all but two sensor 1bour ! than two sensor modules or modules and newiatad associated measurement channels measurement channels to l OPERABLE status, j inoperable t
- m i
j D. DG Actuatian logic inoperable D.1 Enter applicable Conditions immediately
- Required Actions for the
- OR associated DG made
- inoperable by DG4 mss of 1 Required Action and associated Power instrumentation j
Completion Time not met. a i ) i i f 4 l j l l pgp Sef k
a fphden 3.7. 6 4 i 4 j j i INSERT SR 3.3.6.1 NOTE i j ---------------NOTES------------- J
- 1. Testing of Actuation Logic shall include the l 1 verification of the proper relay driver output i j signal.
1 1 l
- 2. Relays associated with plant equipment that cannot be operated during plant operation are only required j to be tested once per 24 months.
4 , ! ___________________________________________..______________ j i i I 4 i i . s J 1 i i 1 4 l l i . 4 J e 4 4 't 4 1 l
y _ _ _ . _ . . _ _ _ . _ _ _ _ _ _ _ _ _ . . _ _ _ . . . . _ _ . . . - _ _ . _ _ . _ _ . _ _ _ i 4
$p c'.r:, a :n L % . ~7 o i
- l 2 1 I
i iO 4 { i 3/4.3 INSTRMENTATICW j y,,, J . . ., % ,,- . I A--/3 g a TABLE 3.3-3(Continued) ,,,, s. . .c. a . , r. ,.. .e . ,, j ACTION STATINENTS gpg g , y , . . ., - /
- [ ACTION 6 - With the number of OPERABLE channels one less than the Tota Number of Channels, mstore the inoperable channel to OPERABLE status within 48 hours or be in at least NOT STANDBY within the next 6 hours and in COLD $NUTDOW within the following 30 hours.
g ,7 g , s WON 7 - With the number of SPERABLE channels one less than the it,tal j Number of Channels, operation may proceed provided the M' y following conditions are satisfied: - i i l ! a. The inoperable channel is placed in either the bypassed , dd # "'*N ^ ' !'i or tripped condition within 1 hour. For the purposes of l F. - o f6. , testing and maintenance, the inoperable channel may be
- byoassed for up tc 48 hours from time of initial loss of y,,3 , , ,
"---'I
.{
l 4 0PtRABILITY; however, the inoperable channel shall then be either restored to OPERABLE status or placed in the i et ! tripped condition. -
- ,,f .
! b. Within one hour, all functional units receiving an input j j from the inoperable channel are also placed in the same ,/ i
- condition (either bypassed or tripped, as applicable) as !
- that required by a. above for the inoperable channel. l 1
i c. The Minimum Channels SPERABLE requirement is met; :
- however, one additional channel may be bypar,cd for up to
- i 48 hours while perfoming tests and maintenance on that !
channel provided the other inoperable channel is placed i the tripped condition, / j j A CT eob B . With @ thasi the M sji --- Phayla yERABLtdDHration may / , continue provided H{e containment purge valves are maintained / l closedj _ ITION11- With the number of OPERABLE Channels one less than the Tot 2 L Number of Channels, operation may proceed provided the i f inoperable channel is placed in the bypassed condition and , the Minimum Channels SPERABLE requirement is demonstrated i f I within 1 hour; one additional channel may be bypassed for up i to 2 hours for surveillance testing per Specification M sc v u.., em gyx e
~
v., 2 n . a q, E-+, W.-we c..a.+.. , . .a p. y..< J d"-*l .- r < o. - ' c ~ '- -
- u .. c., n . . . .s ,,- , . ., . c - ~ '-+- - - - " - -'
eheT, . ,~. . v , Me.<d h r.drea5"#4M.'e,Fnk b/ ~~ ['
-54 c.
o c- Lp,. c ,.i ac 4 .. m'd.- . % . , c. 4 , j CALVERT CLIFFS - UNIT 2 3/4 3-15 Amendment No. 161 c . , I , . . ,, ,- 7 . _ , 1 en c .... , . _ . 4 - , 2 .. ~ j l P.-ae 4 o r to
... .--. . . .. -.... ~._. -- . - - . - .. - . - . - - - . . -.. . ...
$g ult.)nn 3.1. 7 INSERT ACTION A O
I i A. One Rmantion monitor sensor A.1 Place the affected sensor 4 hours l module or associated measurment module in trip. channelinoperable. DE i 1 A.2.1 Suspend CORE Immediately ALTERATIONS. AND A.2.2 Suspend movement of Immediately irradiated fuelassemblics within containment. i I l l l l l O 1 pap %f 10
% p ,c . C. -. 4..
- 3. 3, .9 4
1 i
.t 1
I 1 ! 3/4.3 INSTRUMENTATI M s TABLE 3.3-3 (Continued) j ACTION STATDIENTS A c r otJ A 4CT100-4 - With the number of OPERABLE channels one less than the Total
; Number of Channels, restore the ino rable channel to j OPERABLE status within 48 hours or in at least NOT STANDBY within the next 6 hours and in COLD $NUTDOWN within the f i following 30 hours. '
l l .
.ACT30N-7--- With-the xb vi vratAtti in.u. iw ent Talm MME Number of-Channels; opergt16frinaylroceed ptorilled-the- cucvc5 I folk.-ir.ii ;;r44t4 ens ; ; ;;ti;f;& i. t.+ .. c,...,
mo r- -- b . . a ., i . .,a ! a. The inoperable channel is laced in either the bypassedi e.. ..,...,a , or tripped condition withi 1 hour. T;r tM "r ..s 1 tes"- - ' -intenanse, th is Hiet,1; sl,.....;.I ;g;;; e .._ . a. . ,. . ,... g fpd " ,M},. f;r ;; ^ 48 hours from time of initial loss of" 6 . 1
~
--'l 6' M M '-E
+= 0 Ennsu.uu .. v r. the inoperable channel shall then be either restored to OPERABLE status or placed in the
[A.9 i ,5+ *w'y tripped condition. - 4
$_ uqu- kan . all functw ' r't; . .;;;,;,,, .n input A* ;
-ffeEF-theMperable-4haftflel aus .lse pieceu in ^d _ -- '
$ % cug .-na- r m .. w m ,.4 .. s a-- > . . . ..s a . . u s --
gim c . s. i . 4 , m
.....;'::-" z m.,,
n -
. m ..
v ... n :rir rmr zng'. --
....r......__....
j g4 i i
'5
- c. Chr.r 1; ^^ll;;ABL : ..r,.;; t-44-ast+ # 'TfN
~.-'*d however, one additional channel may be bypass r up to
, . - . - - + 48 hours wMie-performing 0.de .uthnaintenance on-4 hat '**. - i
- shannel provided the other inoperable channel is placed u .-r
. o . , , 3. .j.. . . ' e ,,/ in the trippedgendition. (Q 4
~
[ . (ACTION 8 - With less Inan the Minimum cnannels cPERAsi.a,~ operation may l continue provided themtainment ourge valves are maintainej , osed. f l @ 0N 11 - With the number of OPERABLE Channels one less than the Totah j , Number of Channels, operation may roceed provided the
- i inoperable channel is placed in th bypassed condition and i the Minimum Channels OPERABLE requirement is demonstrated within 1 hour; one additional channel may be bypassed for up 4 to 2 hours for survs111ance testina ner Snecification J b
^ Q, / , , m. , ,I cW-y' I" d%<^"" . f e t. . s-.. 5 Y ps c,p . , g, ,. 4 . . .- 3 3. b F#' be fi * + ' * ** U*3 . ,. w EsEAS Lp .~.d- % C M ,, ] CALVERT CLIFFS - UNIT 2 3/4 3-15 Amendment No. 161 l J mssmpao Cw.2 l 4 g ja O 4
, ,. . a . ,
- d. $ .g i g g , c , f.
INSERT ACTION D f l 4 a 4 D. Two Actuation Logic channels D.1 Be in MODE 3. 6 hou8 l a inoperable. ) AND i DR i D.2 Be in MODE 5' 36 hou" ! Required Action and associated i Completion Time not met. i i i 1 i 4 k 4 N 1 A b i i 1 w l !O 1 4
O O O ! i Q TN R,
- 7 j
G w : g ENEINEERED SAFETY FYATURE ACTNTIN ST5 TEN INSTRWWITATIM TRIP VAEBES ALL815SLE VALUE3 FUNCTIONAL WRIT [TRIFor.i_di l UI I. SAFETT INJECTIM (SIAS)
"";;g
^
a_ - -' '! ';; ,m i ,piicable not ,,piit..ie h
- b. Containment Pressure - High f5 . 5 psig 5 4.75 psig R
- c. Pressurfrer Pressure - Low 1 7251 a, t 1725 psia
- 2. CMTAIIWEElli SPRAT (CSAS) or- e ,- i p r1p suttons; e i A,,,,ticette St."--!'e-k4 j R r-5 4.75 psig w
- b. Conta1neent Pressure - Nigh 5 475 1g L A.
i
-) .'. 3. CollTAllWEENT ISOLATIM (CIS LA- ;
- a. Manual CIS (Trip Buttons) t Applicab Hot Applicable i e, t 4.., m (s c,e s b. Containment Pressure - High g 5 4.75 psig i Q4.75 ,
O -J: := ;.;;E is;.AT:::: 4 " i t ^,,,,,iis.oie " "- ":dle 0 y a- - z? {'"!' ^^- " %" - u " a g J;;; ^^ ..; i. ;et;;; NM u--:- d L. A . 5 9
- g. '
3
- b. Steam Generator Pressure - Low >
.p 1 685 psia T) 9 o !?
imi. $*A3 U= siier,mi wr iis -Esa
..7, ...". i;;;;ti; . ;{Cr. -"* dial ; ~ ~ ~ ^?."ti--- 10 OI;; i ,itiated DJ A=
c 0 ' vl i T) . i 1 r I
O. O O i t 1 - I . g r-TAsLE F4-(Continued) Ra h DICINEGED SAFETT FEATURE ACTMTielt SYSTM INSTWENATIM TRIP VALUES U FUNCTIONAL Ell!T (TRIFAETPOW ALLSWIBLE VALELS a E
. 5. CONTAllesti SLN RECIRCULATI0li (RAS) $ !
! y r_ _.1 m ( ;, e t '
"-t ^- "-*'- 't a-"- ^' -
- b. Refueling Water Tank - Low hes tant i 24 i above tank
. CONTAIIO U T PURGE VALVES !$0LATI M' 3
- a. Manual (Purge Valve Control llot Applicable Not Applicable i htcais sF cAs.y A y Switchs) 3,,ggw M 3,3,7,gy7 Y b. Containment Radiation - Nigh 5 220 mr/hr 5 220 mr/hr 0 Area Monitor 5 LD55 0F h ,
- a. -B us Undervoltage 2450 + 105 volts with a 2450 + 105 volts with a I 4.16 (Loss kw L ....;f of Voltage 2 1 0.7 second time delay 2 1 0.Y second time delay j l
. 4.16 kw Emergency Bus Undervoltage 3628 1 25 volts with a 3628 + 25 volts with a j i j k C ;- :P' valta==) A i 0.4 **caad time delay 8 1 0 E second time delay f t LP A
3 V 9 i Se u ss.'. w af (L ,, n
-
- Fu- $c.r.~-i.% T.-=s.( 7 ,
G LovS _ 0 i D -
?
c I i k f
.A
.A i t !
O O O l N 3r3-4-(tontinued)- g -4NGINEEltED-5AFtTY-fEATURPAC15ATren-$YSTDI-INSTREMENTATTON iisar VidiiG w
- t A' 0 FUNCTIONAL UllIT /TRIPA6 POINT ALLel5SLE VALUES h 5 m
, . CONTAllWEIIT SIN RECIRCULATIk(RAS) $
L y g a. Manual RAS (Trip Buttons) Not Applicable Not Applicable -]
" b. Refueling Water Tank - Low 1 24 inches above tank 1 24 inches above tank bottom botton ,
- 6. CONTAIMMENT PURGE VALVES ISOLAT
- a. Manual (Purge Valve Control Not Applicable Not Applicable Switches) .
R. A t' b. Containment Radiation - High $ 220 mr/hr $ 220 ar/hr t', Area Monitor
- 7. [0$$OFPOWER M I ">. (3 . 7.
- a. 4.16 kv Emergency Bus Undervoltage (Loss of Voltage)
[-2450 2i 05 volts with A second time defay 2450 + 105 volts with a 2 1 0.Y second time delay
- b. 628 + 25 volts th a 3628 + 25 volts with a i
( i 4.16 kv Emergency) (Degraded Voltage Bus Undervoltage1 O f second delay 3 8 1 O J second time delay /\ a m 2 i il
=' LA.3 1
p ; f ra J . a .> . .. ., r A-~ ~,- s 'n i O o
% (~. . e f -
- 4 ' '* % 33.7 q,e j . s w s s. . ., e f . % --p C R.S"
~
1.. r,7 ' ' ~ 5' 3 ' A > 7eg,\r, t.,.'.
. - . .. t.A . e " ? - 'n .d t
O O O 5,- J.r .,~~- - . e- c- ,-, r . Q. . . F. .. i .. ~% 3. Et ,
^
"FCIA; 1 v . . . .# .4..,
g TABLE 3.3-4 (Continued) R r- ' h EIIGINEERED SAFETY FEATWtt ACTWATIGIl SYSTDI IllSTRWEllTATICII TRIP VALBES SETPSDIT ALI, Signal 4 VALBES 0 FuntTIGIIAL EllIT /# M
- 5. CollTAIIGElli SIN RECIIICULATION (RAS) _
Ilot Applicable llot Applicable ;1
.E a. Manual RAS (Trip Buttons) E
- 1
- b. Refueling Water Tank - Low 1 24 inches above tank 1 24 inches above tank botten Mtt--
- 6. CollTAllWENT PURGE VALVES IS01.ATIO11 nua alve Control llot Applicable [ Ilot Applicab y y b. Containment Radiation - High- < 20 or/ < 220 mr/hr SR 3.3. 7,2 O A "'"It'"
m
- 7. LOSS OF PO hWE t_A}. i l
- a. 4.16 kv Emergency But ilndervoltage 2450 + 105 volts with a 2450 + 105 volts with a t (Loss of Voltage) 2 1 0.Y second time delay I i 0.Y second time delay
- b. 3628 + 25 volts with a 3628 + 25 volts with a
( 4.16kvEmergency)BusUndervoltage (DegradedVoltage 810Jsecondtimedelay 8iOJsecondtimedelayg I , a . j p p, s. _ .,or 4 -y, ]A , g F.x 5 p,,. c , a. .. 4. % 6 -y
- N" FDG- L o V 5 " y o
- a i
- J 1
d d W N
O O O
.^
4-c O. u s . .. -I C N -.c5 G.c S p e i F.'e 4 .i % 3 3.k h( 4[I --
" CV CS \ s o L
s , i TABLE 3rl-4-(Continued) w m E ENGINEERED SAFETY FEATME ACTNT10ll SYSTDI INSTEWENTATIM 1 RIP-9AMES F W CTIOllAL W IT MSETPONT) ALL81MBLliVALUE$ k CYCS 150 TAT 10lf a
- 5 0.5 psig 5 0.5 psig E West Penetration Room / Letdown Heat
"( Exchanger Room Pressure - High _)
- 9. AUXILIARY FEEDWATER ACTUATI0ll SYSTDI (AFAS)
R st "m;;!!;; tie St ?--!'aM =
* ,( s. renual tiripouu73)
Y Steam Generator g a, . a ('N sY, Level - -194" -149" -194" to -149' Low lusive) (inclusive)
- c. Ste Generator AP-High S 130.0 psi 5 130.0 psid ;
(5 SG-A) or-(23 tiem_cenern-*me_4P-lifgh 51 . Psid -5 I'" " M1 1 j d__ L 4. 5 b 1 m ra s ED 2 9 o 3 9
\ ' ?
~
5 3 4 C _
) '
ammmme
O O O t l 9 4 +
- =
- .
- (c= t.._2) .l .~
w m E i-- . _M= L' ;;; "*i-- E;=iit5 =:=r:- a.a.b i ar i; _s ,,, P (L A . 3)
/fftIP $ETPi!NT7 ALL815 TOLE VALUES h.
v 711NCTIONAL BNIT f~ S h 8. CVCS ISOLATION g U West Penetration Roon/ Letdown Heat g 0.5 p 5 0.5 psig E
" Exchanger Room Pressure - High b UX ARY FEEDWATER ACTUATION SYSTDt s
- a. Manual (Trip Buttons) Not Appitcable Not Appitcable i'
g b. Steam Generator (A or 8) Level - -194* to -149" -194" to -149" > Low (fnelusive) (inclusfve)
- c. Steam tenerator AP-Migh 5 130.0 pstd 5 130.0 psid !
(SG-A > SG-8)
- d. Steam Generator AP-High 5 130.0 psid 5 130.0 psid g (SG-B>SG-A) j j I
3 f n : n a ; l e :me t i d A P g (,, J.~ ~ .. ~ .r G . , , a 2 be o- 4 -46 3. 5. 4 , g
--- .. .q ! , t , - t . . .I s._**
i~ CWA $ - v) N l l
O O O l
.s
.c .
d g DNi!NEERED SAFETY FEATutE ACTRATION STSTEN INSTEMENTATION SERVEILIANCE _RE9BIREMENT$ 6 h GR ' '@ (r3 3 v.43 1 : A CRANNEL CNANNEL FWWCTISML I CNECK CALIBRATION TEST REEB 7 FUNCTIONAL ENIT ,
.4 i h 1. SAFETT INJECTION (SIAS) h ];' h
" Manual (Trip buttons) M M i @ ^
M /
- b. Containment Pressere - High 5 REFUELING 4s-f;-t !
l c INTERVAL y c. Pressurizer Pressure - Low $ REFUELING Q 3, ". P s w INTERVAL _L
,3[_A 2 ._ mummut actuauan tanic m m - (pry-" 1. z. y t 4 IJ Y 2. CONTAIMENT SPMT (CSAS) Ag i'
{ ? I 3 M M REFUELING _n)
- r- D # - - -.i U rtp auttonsi l T !
Containment Pressere - High WAL7 0 ', j b. S REFUELING Q -1. 2. 3
+c INTERVAL j
y o . Automatic Actuation Logic M M @'8 W I 2.) , 7 '
- 1 46 CONTAIMENT ISOLATION (CIS)\ b Mh a
n ;
.s f{ = 7 Manual CI5 (Trin buttand M M REFUELING __ @ * ;
Ig b. Containment Pressure - High 5 It_EFUELI.N.G
- 4. j.
. Automatic Actuation Logic NA NA (N'8 W I. 2. 33
- t t
t 0 i.
. y1 4
4
- . i r1
~
C-
?
- . _ _ . _ - _ _ _ _ _ _ _ _ - _ ____-__-_--__-__-__-_-___--______________l
O - O O T P o . a- g TRett-+:9-t- R 'a '5.5. l (% s R 3.5. 5."2 R f g y - % -- - - _ _ w
.r g 4HGNERED-MPETT-ftATURE-AETWATNII-SV5795-Ill5TIMIEllTA""" __ .=s=_'_""" . w a;,- N o ~ % .\ ,,,
0 GIAIIIEL ISOES N IRICII h
=
a CaumEt CumEt rencTIan senvEIumCE
** FUIICTI0llAL WIIIT CREcK CALItitATI0ll TEE REOWIRED g >
- 1. SAFETT IllJECTIOlt (SIAS)h(o d E
- a. Manual (Trip buttons) M llA REFUELIIIG IIA
_ !='='*'_ , (b. Lessi.-..;. L w =ww - iiivu S REFUELING Q 1. 2. 3 NTDtVAL
- c. Pressurizer Pressure - Low $ REFUELIIIE Q 1. 2. 3 w
,,, an nuvAL y d. Automatic Actuatica Logic IIA M -
q 1. 2, 3 t* 2. CollTAIIWENT SPRAT (CSAS)
- a. Manual (Trip buttons) M IIA REFWELIIIG 11 4
_ IIIIERFAL
- b. Containment Pressure - High 5 REFWELIIIG Q 1. 2. 3 )
xIllTutTAL my
- c. Automatic Actuation Logic IIA M" g 1, 2. 3
- 3. CollTAllelENT ISOLATI0ll (CIS)' , ,
{ ' i
- s a. Manual CIS (Trip buttons) M MA REFUELIIIG 11 4
$ IIITUtVAL
- S g T tessi._... nessure - High S utretLIIIs v a. Z. 3) g ans t.ar# 2.
T l I c. Automatic Actuation Logic M IIA N 1. 2. 3 -
, .as.
d M $ce J sco u.. , .E 6- y s 'g C.,e Sg e1.a.,J. , 5 O, ' 3 " ,=g A 5 i..,i.. . . . . . .A., pp Q pQ g s kO $9 *
~- . .__ --. .-
O O O A __ _ h b~5 *-D-
.m g TAsLE4:sr-(Continued)
{ 8 h mEInEEREs sAFETT rEATHE ACTUATIM SYSTM INSTWWENTATIM SWVEILUNCE MWWWERS
-9 b IWBES ICE
, ___- - mL CnECK CALIBRATION IHT 7 rnCTrennt mI_t r .a n e A y 'j 5 4. MIN STEM LINE ISOLATION (SGIS)
M i I
*
- M REFUELINE
, [ j, s
- a. Manual SGIS OtSIV Mand Switches and Feed Head Isolation Hand f IN JTERV~
M} - J
> # (L Switches k 5 REFWELINE M. i
- b. 2 6 - - .2.ator Pressure - Low Q .
A J d;p INTERVAR Im 5 ,w . Automatic Actuation Logic M M @UW 1. Z. 3) J i Af 5. CONTAlleqENT SUMP RECIRCULATI N (RAS) Manual MS iTrip Buttons) M M mrwuInsi 3 _# , a. t 2 D b. Raf==:'ing Water Tank - Low M REFUELING Q L '. 1 INTERVAL , , , i e[ s. z. 3)
. Automatic Actuatle!LLogic t M m w-
. CONTAllWEENT PURGE VALVE 5 150t.A11on T
- a. Manual (Puqpe Valve Control M M REFUELNG M
{
= INTERVAL Switches)
Containment Radiation - High 5 REFWELINE Q 6,, 4 g (b. Area Monitor MIERIAL ]a
? T~ h e " s s * - f ^~s*> b 5 3
- C* q"< ' 4 - ?. '* 7, Q 3 ' c tu - g m, .
3 - a e
O O O - x 5 e A g f ,- T;;.: t.: : %.::c..d) R 3.g5.i (4 sa T.7 5.2(R e
~
g m THIl-wii = = : ._. - aHM -.ed*'* -- =- = r w E J _'. CIIAIREL M M S N 9511 G
- q CMIEEL GAlstEL FBIICTI0IIAL
" $5EvDt.1ANCE FUNCTIONAL UltIT Cll[CK .CALIBRATI0ll
' . TEE RE45IltEB b 4. MRIN STEMt LIllE !$0LATIOlt (SGIS) 8
~* d
- a. ManualSGIS(MSITMandSwitches E NA IIA REFWELIM 18 4 and.,
ea .ws Feed Head Isolation Hand IIITERVAL f 5 team Geierator eaa.u _Lnw S REFWELIM Q 1,2.3) MIITERVAL f
- c. Automatic Actuation Logic flA ~ na 1. 2. 3
- 5. CONTAIIGE!!T SIMP RECIRCtKATI0lt (RAS) k a. Manual RAS (Trip Buttons) MA NA REFUELIIIE NA IIITERVAL _
(b. Refueling water Tant - Low HA mustuME q 1, 2, I
- c. Automatic Actuation Logic flA 1. 2. 3 CONTAlllMENT PURGE VALVES !$0LATION
{ - a. Manual (Pur2e Valve Contrvl j flA NA REFUELIIIG IIA s s Swttches) IllTEltVAL ?
$. j b. Contafnment RadtatIon - High S REFMLIIIG Q 6** T g Area Montfor IIITERVAL , j)
N
. -,- i g g f,, /. w . . . F- CL+--s"s S y g, , e, g , . . G - 4.. , T 7. 7s 4
, < AS * ,h g s.. ..,. . . . .c % .s m p p, y A .. s.. , ~~5. '2; + ,
"ESF6s t ,a ev 4 - f ~.
O O O ,
'^
R e'
. sq , s.,,, 7;g A g ""5 '.? I "^ a;_l)
-] '-'_
a g smIwass4AmnemmE-acTunTIn-sVsm-INSTMNEmi. ,uh -sa w t 2 - . o n 5,, .l. . .,. . - ~ .t < t v. g 3.7.~/.1 M I T. '7. 4 I C c-' r. CMMEL M IN WIN 4 '" 35.4/ q <>r , CMNEL FUNCTISML SENILIANCE , FUNCTIONAL WIT
\"F'.FAJl ~i.- - * * ~ /
CNECK CALIBRATIN JIE REENIRED 3 !
- 4. MIN STEMt LINE ISOLATION (SGIS) ,
5 a .
- a. Manual SGIS (MSIV Nand Switches M M REFUELING M and Feed Need Isolation Mand INTERVAL Switches)
- b. Steam Generator Pressure - Low S REFWELIM Q 1. 2. 3 ,
INTERVAL ,
- c. Automatic Actuation Logic M M
#%'W I. 2. 3 ~
^ 5. CONTAlleqENTSWPRECIRCULATION(RAS) j u ,
h a. Manual RAS (Trip Buttons) M M REFUELING M f INTERVAL .
- b. Refueling Water Tank - Low M REFWELING Q 1. 2. 3 !
. Automatic Actuation Logic M INTERVAL M y M ll 1. 2. 3 y
- 6. CONTAIMENT PURGE VALVES ISOLATION M}
- 4. nua Valve Control NA E g
. ontainment Radiation - High Area Monitor _
5 REFWLIm INTERVAL
-~ Q
[ d j, s
?
, r-nh [A .9 J L
h i i R [A4.1 GR 3.7.7.7 - - - - Q 9,. r, , m CFT o Do . . g C..* A 14 d '= 5 $,
, ?. ,( CR$ AcW M Q .. 3.~,v,,4 . I' .ee 4. - 4 g L g'c et. -,f c ,, g g . t ,i g , _ c ._ q . , . . , , , ,d ,
o - w a t.n % t A V A , e c.n @ .d f vt3% \*s o p . _ _ _ _ M
.._._...m_ _._. .... _ . .... ._ _.-- _ _ .._..__-.....--_ .- . . . . - . . . _ . - . _ . _ _. - _ _ . . .
O O O 9t x m E D D -
;> 1D i tr- s' b j TABLE-4: Sat-(Contig U 3: {
( s' j E MIK ERED SAFETY FEAT H E ACT54TI M SYSTEM INSTW W ENTATI M $5 N EILUulCE RE W IRE E NTS
' ' .; Ei E C %
5 a% k b WE W a C C CTIN.L
. SHAL WIT CRECK CALIBRATIM . '
~ '~
3 #
- 7. LOSS OF POWER A. 7 "
A, M a. 4.16 kv Einergency Bus Undervoltage (Loss of Voltage) M REFWELIM Q 1. 2.3D - INTENAL l A
- b. 4.16 kv Emergency Bus Undervoltage M REFUELIM ^
Q 1. 2. 3 " ; fr .. ;;; Voltace) a;;;- .. . - CVCS ISOLATI Q West Penetration Room / Letdown m REFUELIM Q 2. 2. 3.3 4
/, ,t) {
Heat Exchanger Room Pressure - High INTEWAL j}
^ J\
O T 9. AUKILIARY FEEDMTER ' ( @ G Manual (Trip Buttons) O 3 A m M EV REFWELINE h l V - i b. Steam Generator Level - Low $ REFUELIM Q- I I. L i m INTENAL *4? '
- ;e k
=
- c. Steam Generator AP - Nigh $ REFMLIM Impat Q b? 1 _ s/\
-0 1
~
l 7 j $1 r-1uitimatic Actuation Logic m m $3 1. 2.D } t i n ( 5
*g 0 o y ; ;
aig ' 0.- J. - ._ or ca. y s T # J r c;,,. S p-, A ~ 4. , T. s. s, {. l
+f?i s v -
' mas r $, , I to ~. I I,.h yJ
.e a
L t
? l
,J.,- A :%, O O O 2-
? -T ' ^ ?-? (M ^ ^ - - O y g .smIwEn-inr_acrmnon-st.sanILuuts-asgenomm-- L S o O C' CRAlWEL f50ES N MICE CHANNEL CIUWKL FUNCTIONAL SutVEILUWCE f' FUNCTIONAL WIT CNECK CALIBRATION E RE451 RED C
5 >
- 7. LOSS OF POWER X d 3 E
- a. 4.16 kv Ese m acy Bus Undervoltage NA REFELIM Q 1,2,3 I (Loss of Voltage) INTERVAL
- b. 4.16 kv Emergency Bus Undervoltage NA REFKLIM Q 1, 2, 3
( (Degraded Voltage) i INERVAL j CVCS ISOLATION \ _ A West Penetration Room / Letdown MA REFM LIM 1, 2, 3, Q i' hHeatExchancerRoomPressure-High IRIERIAL
- 9. AUXILIART FEEDWATER
- a. Manual (Trip Buttons) MA NA REFELIM NA s : - - .'
fb. Steam Generator Level - Low $ REFK LING Q I,2,3 INTERVAL k= Q. Steam Generator AP - High 3 REFUELIM ,_ Q 1, 2, 3) QNTER_ VAL /
$ d. Automatic Actuation Logic NA NA 1, 2, 3 S Cae 4 . s. .,s s.n .V <t- ~e,< e. A . z .
r., ,, g. .. F. a , om 33.4, R ;g;a5 t .a . -s . 4 - - 9 J. m .. .~ I c "- > e
;. r;.,
.-o
, , r. 4 . . . 3 T.c ' q
. See d. ea n s ..- t #L- gs ~. . &
3 c.,, 9.,c..,.i. , 3.9, p
" C VCS i..'4.,' W
.d 9
t O O O "2'". p g - TE w.3-4 imu l - c' E 1 R g 4NeINEERED -SAFETY-FEATURE-ACTMTION U i
# n ""8
# sq 3.,:. 6.2 E
' C. CElugEL MBBES N NEIG O b N NCTIONAL ENIT GWUNIEL CNECK OUWNEL CALIBRATION FUNCTIONAL TEST SgtVEILLANCE 2 , RESBIRED ;
g h 7. LOSS OF POWER e$ 4rl
- a. 4.16 kw 6 . .ay Bus Undervoltage M RENELING Q 1. 2. 3 -
> (Loss of Voltage) INTERVAL
- b. 4.16 kv Emergency Bus Undervoltage M REFKLIM Q 1. 2. 3 i
(Degraded Voltage) INTERVAL r CYCS ISOLATION [8. A West Penetration Room / Letdown M
'r' RETWELIM Q 1. 2. 3. 4 l l
( Heat Exchanger Roce Pressure - High 72TERVAL j t
~
y 1 AUXILIART FEEDMTER [9. i
- a. Manual (Trip Buttons) M M REFEELINE M INTERVAL
- b. Steam Generator Level - Low 5 RENELIM Q 2. 2, 3 L k c. Steam Generator AP - High 5 INTERVAL REFUELIM
} J Q 1. 2, 3 INTERVAL ]
- d. Automatic Actuation Logic M M O M'I I._
h. 4- i "Q w ' o R .. ' 5
$e. J.s,.,ss.. .( d.--,es
" #""**" ~ '
T
* - r,- . <
,;, . . c. .4 . , T. L 9, _
0 p., <>;.. r. - i.., , 3 . 3 g V 1 ,, W A S lwv. I e ~ - l.O.o m
,* ( q q t ., , I a 4 . . . . n3ssI' i A
t
o o . o i i*
>=
'z m
p n t T 9 N=4- .I !? ! g h N
'd o
2 C.
<,, 4. -- . , .r A-fr %-- #.- 4 .,~4.3.6, Q.T.s@9b'fD -
CMMEL INKS N WICE g - CWuuKl. FUNCTISMt. METEILUNCE i FWCTieML. WIT "L#>ste% %.- , CALI88N888 EE murRe g > '
. LOS$ OF POWER -f f
'* a. 4.15 kw "- . ..;- - B 11 4 REFUEllM Q 1, 2, e (Loss of Voltagef us thidenoltage INTERVid, t M REFUEUM Q 1, 2, 3 I I
- b. 4.16 kv '_.....;y)
(Degraded VoltageBus Undervoltage INTERIAL j
- 8. CVCS ISOLATI0ll -
R
- West Penetration Room / Letdown QsqT.I 9 REf1P' LIM 1,2,3,4
- ,in Q t' Heat Exchanger Room Pressure - High INTERTAL w l
- 9. AUXILIARY FEED M
- a. Planval (Trip Buttons)
M M REFUELINE INTERVAL M\ !
- b. Steam Generator Level - Low $ REfvELIns q 1,2,3 .
f INTERYAL kg c. Steam Generator AP - High S REFUELING Q 1,2,3 l 3 i Q Automatic Actuation Logic M INTERVAL M 83 ~1 , 2, 3 1
./\
a l t a _ __m -m- -. ___
- s i M y i,e J. m s... . I et-- y s . _ __ . . _ . eac>rE - - . ' _ '_._ 3. 0
[ J' ; s. r. 4, <_,g< ,u i P
- p. c 3 .. .c. ..+.._
7
- i. r- . ., e ea --4.., ;>
E - .. . e t .,4 e +L, v , .. r. ,. 5 . . c, p + t , 8 u EsFAS ( ,-f r + -4 .~ + (*.g."v- rete 7 J e.w er .,4 pot pI & > N '
/ h.\ )
- 2 R. N,, , e-- .-4s ~. A pi 4 t%4 .. -.+ %- p**s4*d
- a ;
< 3 p .~. ..,4 l y g,,,.., ps. 4 , p - -t . , -e ***y . !
I.
- 4 ~d
- J **'re P *
- 1 #~
e qu. r
- d 4.
"*A*
Q _ n __
#rs tra ba @ ^ *
- 3/4.3 INSTRUMENTATION gAsks L1.7 franHnumn i
IAMf_ NOTATION i LA. containment 1 solation of non-essential penetrations is also initiat SIAS (functional units 1.s and 1.c). f 1
" ~
Must be OPERAsLE only in RupE 6 wh<1 the valves are required SPERABLE' l _ and they are open. f- ! 1) T logic circuits shall be tested manually at least e per (T days. g (2) 51AS logic circuits A-10 and 8-10 shall be tested with the 1 l exception of the Safety Injection Tank isolation v The $1AS logic circuits for these valves are exempted from testing during operations however, these logic circuits shall be tested at least I Dow # once per REFUELING INTERVAL during shutdown. c,L .,,,fc 5pil A (3) 51AS logic circuits A-5 and B-5 are exempted from testing during '" operation; however, these logic circuits shall be tested at icsst once per REFUELING INTERVAL during shutdown. O (4) CIS logic circuits A-5 and B-5 are exempted from testing during operations however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown. (5) 5G15 logic circuits A-1 and B-1 are exempted from testing during operations however, these logic circuits shall be tested at least once per REFUELING INTERVAL during shutdown. 6) CSAS logic circuits A-3 and B-3 are exempted from testing during operation; however, these logic circuits shall be tested at less once per REFUELING INTERVAL during shutdown.
$ ~ J. s < c. - . I cL. .g F, r $ p < f, r = + .. n 7. T. 5,
" C-s F A S Lo p 4 M- -
- l +"h CALVERT CLIFFS - UNIT 2 3/4 3-22 Amendment No.186 O
y kRc- %-oso P*S' (5 or %'
. . _ ___.-_.____.___.__.__..._.._____________.__.-_.___m..~._..____.m.. ...m..__ _ . _
<$p-. L ,s .., T.T.5 IO 3/4.3 INSTRUNENTATION i
o, s . ,-.- ., ' -3 c. r ,, 4,, . 5. 4 . . "T. 3. 7, j -s TABLE 4.3-2 (Continued) c. g 3 ~ i TABLE NOTATION ( <cc 4--**-- J e ' - .' a I q p.,EsrAs a - e r LT,* S ,- . 6 - 4. . -s ,
~ d . ' . ;,
Containment isolation of non-essential penetrationt is also initia@ SIAS (functional units 1.s and 1.d.- i flust be OPERABLE only in II60ETUhen Ine vaives are required OPERAS
- . and they are open. , -
! f The logic circui dallbetestedmanuallyat days. east ce per ) j g ,g,,.y (2) $1AS logi ircuits A-10 and 8-10 shall tested with the excepti of the Safety Injecticn Tan solation y es. The $1AS logic ircuits for these valves are ted from testing during. 4 op .ttons however, these logic ci uits shall be tested at least
- e per REFUELING INTERVAL dur shutdown. l
! N $1AS logic circuits A-5 a 5 are exempted from testing during operations however, thes ogic circuits shall be tested at least
- / once per REFUELING INT AL during shutdown. ,
l l N C15 logic circuits -5and8-5areexemptedfromtestingdurJng operations howe , these logic circuits shall be tested t'least i O N once per REFU NG INTERVAL during shutdown. SGIS logi circuits A-1 and 8-1 are exempted f esting during l operat however, these logic circuits shal e tested at least once .r REFUELING INTERVAL during shutd . l ) (6) , AS logic circuits A-3 and B-3 are empted from testing during 1 operations however, these logic cuits shall be tested at least i once per REFUELING INTERVAL dur ng shutdown. j l 1
~
m 2 LA.2 J l i d 1
- i 4
CALVERT CLIFFS - UNIT 2 3/4 3-22 Amendment No. 186 i O Ni,0 %-oto gg g l0 j P * *f
j 5p . r. -. + ..- 3. T . 7 l 1 !O i 3/4.3 INSTRUMENTATIgN I 4 l
- $,4 d. usw e- *E *k- t'> )
TABLE 4.3-2 (Continued) ,
,,,, 5 , , ,, 3, ,, .,;, 7, 4 ,
5
= "T=
we i -. si . . . . . . . . " l 1 Containment isolation of non-essential penetrations is also initiated ) ' ! by $1AS (functional units 1.a and 1.c). f t[Cl^ _-_ .., -- ___ : : .. ...... r n; M - m r}
.....,...,...y f(1)
Q The logic circuits shall be tested annually at least once per
@ days. g
) '
(2) 51AS logic circuits A-10 and B-10 shall be tested'd'with the l exception of the safety Injection Tank isolation valves. The SIAS l logic circuits for these valves are exempted from testing during i operation; however, these logic circuits shall be tested at least 1 once per REFUELIM INTERVAL during shutdown. l I3) $1AS logic circuits A-5 and B-5 are exempted from testing during operations however, these logic circuits shall be tested at least
- once per REFUELIM INTERVAL during shutdown. l (4) CIS logic circuits A-5 and B-5 are exempted from testint during ;
operation; however, these logic circuits shall be tested at least O- once per REFUELIM INTERVAL during shutdown. l 1 (5) SGIS logic circuits A-1 and B-1 are exempted from testing during operations however, these logic circuits shall be tested at least once per REFUELIM INTERVAL during shutdown. l (6) CSA3 logic circuits A-3 and B-3 are exempted from testing during operation; however, these logic circuits shall be tested at least r REFUELIM INTERVAL during shutdown. l
$re D aru's'=m *( 6 * *Y)
P.< Spe r. f. ..%m ~5 . 3 5, "ESVAS Lmie -A V'- - l T < , p CALVERT CLIFFS - UNIT 2 3/4 3-22 Amendment No. 186 O M fd 96-o'to p ,+ 10 p$e
,Nd animes se ' 4 seeemesa>6en**MW--=me thm94%B538-P+-NM7
, - =W e 6 8 X. h4d E 4 -.46 4 mW,.44 W 4 44 sd Esa.M,.4MS h 6MdeOE E ' ' O h M-.4MM4 h+$13M MN Od64= WE* # ' --hh..
O 1 1 J 7p n .r., s , n T. 3. 3 1, - { s Add Technical Sm .caticii 3.3.8," Control Room Recirculation Signal (CRRS)." s } I 1 4 h 4 1 e i 4 4 e l 1 I ) I 7 e b i 4 f f i-i e f f i e l 4 4 e i 4 a e I 4 i i T 4 f s 1 4 i 1 k e 4
- v. .
)
i
.c 3 4
l, gy I 1 ( . . .--~. -, _ _ _ _ _ . _ ......_.. . _. _ .. , _ _ . _ _ , _ _ . _ _,_, ..,, , _ _. _ . , . . _ _ _ ,, ,
CRRS 3.3.8 3.3 INSTRUMENTATION 3.3.8 Control Room Recirculation Signal (CRRS) LC0 3.3.8 One CRRS trip circuit and measurement channel shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CRRS trip circuit or A.1 Place one Control I hour measurement channel Room Emergency inoperable. Ventilation System train in filtered recirculation mode. B. Regired Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours O CALVERT CLIFFS - UNITS 1 & 2 3.3.8-1 Revision 0 pqZd3
2 CRRS i 3.3.8
! "O
\,,,/ SURVEILLANCE REQUIREMENTS l
SURVEILLANCE FREQUENCY I SR 3.3.8.1 Perform a CHANNEL FUNCTIONAL TEST on the 92 days ! CRRS radiation monitor trip circuit and
; measurement channel.
Verify CRRS high radiation setpoint is s Allowable Value of 6E4 cpm above normal background. i SR 3.3.8.2 Perform a CHANNEL CALIBRATION on the 24 nonths required CRRS radiation monitor trip circuit and measurement channel. l 1 ! l l 4 k CALVERT CLIFFS - UNITS 1 & 2 3.3.8-2 Revision 0 pay %O
. l
- f. $
O 4 4.3 INSTRUMENTATIM 3/4 .3 MONITORING INSTRUMENTATION i Radiation Monitorino Instrumentah LIMITING C ITION FOR OPERATION j . . 3.3.3.1 The ra ation monitoring instrumentation ch is shown in Table 3.3-6 shal e OPERABLE with their alarm / trip etpoints within the specified limits. ! APPLICABILITY: As s in Table 3.3-6. EllE: } a. With a radiation no toring annel alarm / trip setpoint exceeding the value shown in Ta e 3. -6, adjust the setpoint to within the } limit within 4 hours or lare the channel inoperable. ! b. With one or more radi ion nitoring channels inoperable, take the action shown in able 3. 6.
- c. The provisions o Specification .0.3 and 3.0.4 are not applicable.
IO SURVEILLANCE R IRENENTS Wu _ 4.1.3.1 F[hradiationmonitoringinstrumentationchahn shall be
- denostAed OPERABLE by the performance of the CHANNEL CN K. CHANNEL CALIB T1H and CHANNEL FUNCTIONAL TEST operations during th MODES and at j the requencies shown in Table 4.3-3.
i i CALVERT CLIFFS - UNIT 2 3/4 3-23 Amendment No. 161 l O
O O O g TABLE 3.3-6 R u- .~
'd
% RASIATIM MONITORING INSTRWENTATION arara=
e- DIAluKL5 APPLICABLE ALAM/ TRIP MEASURDENT E, h IRS M v. OPERABLE NBOES SETPOINT RANGE MTIM
. 1. AREA MONITORS g LA lO 4 Contaisement{ g ,
r* i_ puro , a r a . v.a .+ian 1 6 < 220 ar/hr 10-8 lo' ar/hr 16 ) ! f,Lle f 3,3,/o-l b. Containment Area High Range 2 1. 2. 3. h 5 10 R/hr 1 - 10" R/hr 30
- 2. rmn.tn riunai ~
R*
. Containment & Disc.use.. f eMeap fn !
*.cc,f
{ hl. Gaseous Act v Sp. g, ;f;e.bg) 3.4.14(,%u A., j a) RCS Leakage Detection 1 1. 2. 33 &4 Not 10' - 10' cpu 14
- l1. Particulate Activity Appiicable ), ,
) RCS Leakage Detection 1 1. 2. 3. & 4 Not 10' - 10 8cpm 14j
@ licable r ,8 ;
- m. noble ses uTiuent rionttors
- m. .- '
g - o ' 5 4
- 1. Main Vent Wide Range 1 1. Z. 3. a 4 10-' to 10' pC1/cc 30' 3 '#dt.__MainSteamNeader 2 1. 2. 3. & 4 104 to 10' R/hr 30y ;
- me t
. b 9 D.s w w 6 4 *38 E
~
~ ~4
'l gek 3.3.*3 \ ,
- bh ^ ~
-i n ._
(N:. .b,-) LiA~~** 6 ds f 9 7 - t N I
_ . _ . _ . . _ _ _ _ . _ m .__ . - __ _ . . . .. ... _ ... _ . . _ _ _. . _ . _... _ _ _...._ -. _ . ._ ...._. _ ._.. _ ... _ _ .. .. _ ._... _ .. . . _ . . _ _ _ . . . O O : - ..
. O ,
i t t t i i g TABLE 3.3-6 R
- i G .
w g RASIATIM MONITWINE INSTRWIENTATIM . t w n MINIIME E l C OIAIBIELS APPLICABLE AIAN/ TRIP IEASURDENT M 9PERABLE MODES SETPOINT RANGE ACTIG11 3 INSTRipENT e 1. AREA ISIITORS = basw= # h 4 g m ~3. A3.f. *#d. q a. Contatmuent %.n., , g ,. , f
" 1. Purge & Exhaust Isolation 3 6 5 220 er/hr 104 - 10' ar/hr 16 3 e -
- g. Containment Area High Range 2 1. 2. 3. & 4 5 10 R/hr 1 - 10" R/hr 30J *
- 2. PROCESS MOMITORS g g,_ j g
- a. Containment Seec. h 13.8+ ," PA 4 "
R. Y 1. Gaseous Activity 'I a) RCS Leakage Detection 1. 2 &4 Ilot 10' - 10' cp]e 14 Applicable i
- 11. Particulate Activity i a) RCS Leakage Detection 1 2. 3. & 4 Not 10 - 10' cpu 8
14
- Applicab
- b. Iloble Gas Effluent Monito j g
i E 1. Main Vent Wide Range 1 1. 2. 3. & 4 i 10# to 10' pC1/cc 3b iA
~R N
~?
a 11. Main Steam neader 2 1. 2. 3. & 4 104 to 10' R/hr 30} c > M
- P m
- P. t to ~
S - +
+ i
.m. _ ._ . . . . . . _ . _ _ _ . . . _ . . _ . _ _ _ _ . . . _ _ _ . -
. _ . ~ . _ . . . _ . . . . ~ . . . . . _ . . . - . ~ _ _ . _ . . _ _ . _ . _ _ . _ _ _ _ _ . _ _ _ . . _ . _
O O O ~ i L i i r Q TABLE 3.3-6 R. t morAria mimIn NSTammum L U n MINIMM ALAM/ TRIP KA55RDUT l C CNMNELS OPERABLE APPLICABLE MODES SETPO NT_ RANGE- ACTim h i A. v _ INSTRU M E e 1. MtA Mii- - @ b
- a. Cont
[.[ < a Pu m & Exhaust isos au en y 6 < 220 mr/hr/10-' - 10* mr/hr A Q . Containment Area High Range 2 1. 2. 3. & 4 < 10 R/hr 1 - 10' R/hr 30) l r=u22 rivative a D.smo. 3 c).. 7 G g y,,, g A.f g R a. Containment 4*eCs.k 2 AJ4, "M spu A h 3.s.n,apAesc* ,
- L.< hy b e4,k.. 5.& -. i
't 1. Gaseous Activit
~ l'
^
a) RCS Leakage Detection 1 1. 2. 3 & 4 Not 10' - 10' cpm 14 3 Applicable 1 11. Particulate Activity a) 'RCS Leakage Detection 1 1. 2. 3. & 4 Not 10' - 10' cpu 14j 6 [D. Noble 5as suent rionit I N Mai Vent Wide Range 1. 2. 3. A 4
+
10-' o 10' pC1/cc n , 1. 1 3 kl. in Steam Neader 2 1. 7. t_ a 4 o 10' R/hr i 4 E 4/I L, p x i g - i t
j hyd%5r4 3.3.lO l O { 3/4.3 INSTRUMENTATION f TABLE 3.3-6 (Continued) . TABLE NOTATION k . / Alarm set nt to be s ' (e.g.,s ointcontropecifiedinaco manual). rolled document
- ACTION STA ENTS ACTI 14 - With the number of ch nels OPERABLE less than utred by
, the Minimum Channels PERABLE requirement c y with the
- ACTION requirements f Specification 3.4.6.1
, ACTION 16 - With the number o channels CIERABLE less an required by 2
the Minimum Cha els OPERABLE requireme , comply with the ACTION requiremen' ; of Specification 3.9.9. y I
- h. '(AgJdlI33 _ Wit + heed channe190PERABLEJ1 M reaui m D Ine m n+=i= Channels nasa 4BLE requi nt i ftnitiate 3.3.10. A W "t'A h [r s n or *
/ 1) either restore the inoperable channel (s) to OPERABLE ngdays of the event, or /, . (2 (g (z) preparc e auinit a 5pecial port to the Comi on l pursu to 10 CFR 50.4 w n 30 days followi the l 3.3J D. B ev , outlining the a on taken, the caus f the l 1 operability, and plans and schedul or restorin '
L the system to OPE LE ttatut. 3.1.10.C
'N *
"t"'M # **"
- P "*k " ' * ' ^ ' ""
- 4. oPEAA&LE. shh rfLt /d ers, e ,-
3 39,p ( bHr 4e a a&% is mcedane ~% Spedres+ren S. b.9,
'* k*
CALVERT CLIFFS - UNIT 2 3/4 3-25 Amendment No. 193 O w.n
l Spmbh** 2 4. If i l i l l 4 1 i 3/4.3 INSTRUMENTATION ^ I b hcww y CM (~n 5: TABLE 3.3-6 (Continued) l
%). pe O cT Ah. b. " 2.2.5. ,
l TABLE NOTATION
- .- h t
(* Alam setpoint to be specified in a controlled document ( (e.g. setpoint control manual). l I ACTION STATEMENTS 1 ACTION 14 - With the number of channels SPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the
- . ACTION requirements of Specification 3.4.6.1.
l QCTION16- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the . l ACTION requirements of Specification 3.9.9.- __ 3 l (ACTION 30 - With the number of channels OPERABLE less than required by 3 the Minimum Channels OPERABLE requirement initiate the l
] preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours, ands j
- 1) either restore the inoperable channel (s) td OPERABLE f status within 7 days of the event, or j
] i *
- 2) prepare and submit a Special Report to the Comission '
! pursuant to 10 CFR 50.4 within 30 days following the l event, outlining the action taken, the cause of the , l inoperability, and the plans and schedule for restoringJ . the system to OPERABLE status. , i h bN un. f 4*)** h Sp5.f,o4, 3.7)0"IA*1* . I CALVERT CLIEFS - UNIT 2 3/4 3-25 _, Amendment No. 193 O e ys
C TS 3.3,2.I O 3/4.3 INSTEMENTATION TABLE 3.3-), (Continued) TABLE NOTATION g A,laJuf setpoint to be sp(cified in a contrtSWd document } W.g., setpoint con @l manual). / - Subwwpek[s. S pe.6 d . 3,4, ge,g ACTION STATEMENTS
% Wk sokm
%CTION14- With the number of cnanneis vrasves.s sess Inan required 57%
the Minimum Channels OPERABLE requirement, comply with tha/ IoM reauirements of Specification 3.4.6.1.f 4T .} KCTION J6 - With the n f channels UrtzAB less than requ1 D
. s the . Mini nnels OPERABLE rement, conoly w Lama ---* = af wri f t ton 3.9.9J Qi cn on 30 - with the numoer oT cnanness Urnansa less than required Dh the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours, and:
- 1) either restore the inoperable channel (s) td OPERABLE status within 7 days of the event, or ,
- 2) prepare at.d submit a Special Report to the Casuission pursuant to 10 CFR 50.4 within 30 da s following the event, outlining the action taken, t e cause of the {l inoperability, and the plans and schedule for restoring]
the system to OPERABLE status.j
%n bs<,,ntsw & C.Assy %
t
)
St ufse.As 3.s. o , nerM" . a _CALERI .CLIIFS - UNIT. 2 3/4 3-25 Amendment No. 193 O P*744
- . - . - . . . . - .-- - . . . . - . . . - . . . . . ~ . . - . . . . . .. . . . - . . . . . - . . . - . - . .- . . . . - _ . ._ .- O O O t i g TABLE 4.3-3 & r-
- RASIATIM MONITORIM INSTRUNDITATIM $WVEILLANCE REWIREMENTS CRANNEL MODES N WICK C -
CMNNEL GANNEL RNCTIONAL $5RVEILLANCE h 8' q vs IW h5 CNECK CALIBRATIO11 TEST REGUIRED E -
. 1. AREA Moll! LA . I l e
5
- a. C airunent
- - - R
" i puroe&ExhaustIsolat% S RERELIN M AL _JL - E l i
M Cont 4LiWHit Area High RangJ* ut.rwe.LKIllftRVAL
- 1. 2. 3 b.
t A,;7 . PROCESS MOllITOR5 R a. Contalrunent fu bucasa, af 6 p fr
- 4 c./ic.A .7.f.M y 1. Gaseous Activit
- gcr La.y M,4 @# ,
a) RCS Leakage Detection S R M I. 2. 3. & 4 4 l T
- 11. Particulate Activity i e) are 69 notection S __ R M I. 2. 3. & 4 S '
T1
- b. Noble Gas fluent Monitors ;
g 9 5
- 1. Mal Vent Wide Range S R M I. .&4 f,
?+ 11. in Steen Header S R M , 2. 3. & 4 y E
*o
)
g g b,w .st**~of h y S g a rA C71 3 3.7.I ,tOl**N'
,4 ,
j%.kr& ZO N O 3 -
*l "O
O O O i i L i g TABLE 4.3-3
RABIATIM MOIIITORIIIE IllSTRUMENTATIM SWVEILLANCE RESWIRDENTS l N- DIAlWIEL IWWES IN NNIG C CHAIEIEL O!AllIIEL TUIICTISHAL SURVEILLANCE !
CHECK CALIBRATICII TEST RESWIRED A JIISTRENDIT m c e [I. AREA MOIIITORS y' a. Containment
'* I 1. Punpe & Exhaust Isolation S ItETWELIIIE INTERVAL M 6 l ;
- b. Containment Area Hioh Ranoe S RETWELINE INTEltVAL M 1. 2. 3. & 4 l
, 1
- 2. PROCESS MOIIITORS ;
5:' a
- a. Containment
- 1. Gaseous Activity g ,l se 2.4X 1 se.
g,c Al O P) i { [ a) RCS Leakage Detection. S R M 1. 2. 3 & 4 Eg
- 11. Particulate Activity I[ _
a) RCS Leakage Detection S R M 1. 2. 3. & 4 )I ;
* ,w t g 'b. Iloble Gas Effluent rmnuars (
- 1. Main Vent Wide Range S R M 1.2.3.&4}
5 11. Main Steam Header S R M 1. 2. 3 & 4 y U
?p f g lb l 1 L i9 i!
4
- Fr F l 5 rF F i
'o
~
( 65 V 3 a i y h t f
?
l
I O O O - i i f i g TABLE 4.3-3 R
=
r-Id h IWWIATIN MONITORIM INSTRUMENTATION SWVEILIANCE REWIllEMENS [ N MODES N WRIG g C CINUNIEL CHAMEL FUNCTIONAL SURTEILIANCE g g Ill5TRWENT CNECK CALIBRATI0lt TEST REGUIREB
. . AREA MillITORS
.E a. Containment f.I U' ,
- R 7t .
. Purse & Exhaust Isolation S REFUELINE INTEllVAL M Q l (b. Containment Area Nigh Ranse s saretuus asvuivnL n a. c. 4. ay l db '
. rmn.us ri Ii90 SbwwgAp4 / '
*p< 4 b- 2A.#9 WCT l'l *
- R a. Containment
- 2. .ir,. bdrA 1,lS-o '
y 1. Gaseous Activi M 7 a) ItCS Leakage Detection S R M 1. 2. 3. & 4l s
- 11. Particulate Activity i
a) ItCS Leakage Detection S R N 1.2.3.&(I
. Noble Gas Effluent Monit
- 1. Main Vent Wide Range S R M 1. 2. 3. &
3 1. Main Steam Needer S R M 1. 2. 3. & 4 .
=
'b i - s s s 4 W
CTJ 3.3.34 i lC fl
.3 INSTRUMENTATION
. 3/4. MONITORING INSTRUMENTATION Meteoroloaical Instrumentation 4 LIMITING COND ON FOR OPERATION ) 3.3.3.4 The mete logical monitoring instrument on channels shown in . Table 3.3-8 shall OPERABLE. l APPLICABILITY: At all ines.
- aam
- a. With one or more r ut meteorological monitoring channels inoperable for more 7 days, prepare and submit a Special Report to the Commt n pursuant to 10 CFR 50.4 within the next l 10 days outlining e use of the malfunction and the plans for restoring the e nel(s) o OPERABLE status.
j b. The provisi of Specifica ons 3.0.3 and 3.0.4 are not 4 applicable 4 SURVEILLANC REQUIRDIENTS _ 4.3.3.4 Each of the above meteorological monitorin instrumentation chann s shall be demonstrated OPERABLE by the perfo nce of the CHANNEL CNE and CHANNEL CALIBRATION operations at the freque its shown in Ta e 4.3-5. I l l l CALVERT CLIFFS - UNIT 2 3/4 3-27 Amendment No. 193 O n '9'
. . - . - - . - - . - - . . - . . _ - - - - .=_ . . - . - . . . . . . - . - _ . - - - - - .
l ! cv7 3,7, 3,4 4 1 I
/4.3 INSTRIMENTATI0li
/
/ I i
i I ] , TABLE 3.3-8 . ilETE0lt0 LOGICAL 900NITORIllG inii R iATI0li j i MINIMUM CNA MELS INSTRIMENT DPERABLE j 1. WIND SPEED l a. Ilominal Elev. 30M 1 f b. Ilominal Eley. 1 l 2. WIND DIRECTI
- a. Nomi Eley. 10M 1
+
l
- b. inal Elev. 60M 1
- 3. R TEMPERATURE - DELTA T (10M-60M) 1 i
i o I i i 4 p l l l s CALVEM CLIFF 3 - INIIT 2 3/4 3-28 Amendment No. 176 l 4 $ P'T */ 3
i c1~J .c , 2, 3. + \ i , 4 l IO i A,1
~
.3 INSTRISIENTATIM f , TABLE 4.3-5 .
NETEOROLOC NONITORING iniiniiraniATION SURVEILLM E00IREMENf1 l CluuglEL INSTRUMENT CALIBRATI0ll
- 1. WIND SPEED
- a. Nominal Elev.10M D $A
- b. Nominal Elev. 60M D SA
- 2. WIND DIRECTION
- a. Nominal v. 10M D SA
- b. Nom 1 Eley. 60N D SA
- 3. Al ERATURE - DELTA T (10N-60M) D SA O i I
I CALVERT CLIFFI - UNIT 2 3/43-29 Amendment No. 176 l 0 pey 2 9'
hdndew 5.3.Ii } [O 3,k h Ill5TRilMElffATIM l 1.5.n @M Remote Shutdonm Instrumentation h- ! L Mmm comma rm murim M MD 30I M S The Menote hutdown[onitoring instrumentation channels shown in h
- Tab' eC .,ad Oshall be OPERABLE E rn . 1.. em enuJarnenai to-tw (CoM JiooG i
APPLICABILITY: MODES t I 2 and 3. _ l O, Ac11o0 j[5c' par.% C,n&%a safe.y i s A,t, i WE L Qallo.,ea #* #6h F.,.#re. . ., . , , g 9 -
;4% ,, +
i ALT
- 4 CTdith Ahs'"hu7mbe er_ - ---i 3----T, septoring)channelsbP'*hh st4han remefd by Jat(e 3.3-A41the I
channe to WrtRABLE status w1 thin 30 day reinune da--ahl Y-sih
- 40mu 6 within the 12 hours.
jg 4,, The provisionW' Specification 3.0.4 are not appitcable
- 1 m- ar. .o,..m C o pl,w h ..+ %+. .i SURVEILLAllCE REQllIREMENTS 6ei. mooe s - 6 Lem M.9 I
- 1 5.3.1 I 5.11. 2, geo - sted 8Praansr remote shu monitoringrumentatWanaal M1 @
nerfemarse theP""'8 CllECK end CNAN11EL h l EALIsuATIO11(poEerat',psest thgMdeuencies shognM Ta)W4.3-sp % onraa normally i eM es Iml ' las4e m <+ l CALVERT CLIFFS - WIT 2 3/4 3-30 Amendment No. 176 l O eos.4s
/
O O O t I, i TMLEM I I II ~I 'I '
~
R t Ret *h4Md ? I g nemt samous murtantes. sstumemina
=
l 8 sea ===r msmeen7 5 m tenu === tride Range Neutron F1g., i e l.. 2C43 0.1 -200% 1 E f.b Reactor Trip Breaker Indication Cable ing 1/ trip breaker OSE
$ i i
g i N1 .g Reactor Coolant Cold Leg
@ Temperature 2C43 212-705'F ,
1 i 2.g h Pressurizer Pressure 2C43 0-4000 fa 1
'i.g M Pressurizer Level 2C4 0- inches 1 5 0.b D 5 teen Generator Pressure 43 1200 psig 1/steen generator t* t .c. Steen Generator Level 2C43 1 to +63.5 inches 1/ steam generator i M
1 O. I. kd*4y Ilf t% j L G6=e Co.foA Sy dem %,,, < I%A.e.'3
' 3. (bdoe:S r.y144 G fm ,.I... S A cc h
**I'*4 Sy dea I-def 4o&t.3 rE 1 la.
a n Ilhen the 2C ed in the, instrumentation is 1 le. the wide range neutgflux sonitors 1 [-!
,N e auxilia eeduster pump room may 111 red to meet this During t period when m the i ruments are utilfred to the above requirement d.. .will _ ..t.be subj !
q i o the 4 [ { su 111ance requirements of e 4.3-6. / - j ;
- u. ,*
e" I i
SecA4,,,, 3,s.n d - b4.3 INS M ruv m 2 sR<m <&w> @ REMOTE SHUTDOWN MONITORING IW5i daWiATION SURVEILLANCE REQUIREMENTS S P,13.11.5 $ 6 13.11. 2. CNAlOlEL CNA101EL INSTRUMENT .g((SE CALIBRATI0ll j,4 M Wide Range Neutron Flux M l,b -
$ Reactor Trip Breaker Indication M NA 3 -g , j Reactor Coolant Cold Leg Temperature M REFUELING INTERVAL
'2. ,g 4 Pressurizer Pressure M REFUELING INTERVAL L4,q # $ Pressurizer Level M REFUELING INTERVAL 3.c $ Steam Generator Level M REFUELING INTERVAL 3.h M Steam Generator Pressure H REFUELING INTERVAL 4 .1 -
_ _ - - - - . 0 076 ~ ~ ~ ~ ~ ~ -
- 1. M e de. . &b4er, are udela d (e,% CHMNEL A'"
i CALi tt. ATooel. --- L. Ada s40c 7r *p E re a ke r $as!.h4 ,\ e A dv kd de#A L>thNuG L C.ALiBAAT>od._ _ __ __ i I, Reub4 7 I%+ 3 y L. Ataborlo0Ioat S OM fttsset $0n.4 erie $
- 5. m..:4.et3 be y He & t>~onl v.~ %.n Cesan4,e>
- 4. b+.c (..l.at S s4em y too,4 M.o 7 r4. c.%
3 CALVERT CLIFFS - UNIT 2 3/43-32 Amendment No.186 O e ,t.n
l he .c. ,..a . . 5. J. t 0
,O V
J t 3/4.3 HSTRUMENATIM Rfi,E3 IONITORINGINSTRUMENTAffp post-Accident Y rumentation - l L=T1. m . ,. .,a m . . 6' i 1W
%% iO 416,3,4- The ae+==a+=t4en
'A - - c channel shown in Table 3.3-10 shallpost accident monitoring be OPEAABLE.
(syLrp.yQ po a. <= e G APPLICABILITY: NODES 1. 2 and 3.
- - ~
p ,7.y. y j EllMr
- a. As shown in Table 3.3-10.
Q ggg b. The provis1ons of Spectffcation 3.0.4 are not appitcable.
+. ACT 005 q , po r.u c o- d . 4 e o, *M'y 's il. -es F.> r -- h F-*1**-
n- _ ~ - - SURVEILLANCE REQUIRDIENTS
.3r4.0 h post-accinent e6morpr-instrumentation cha3per snan ce demo ated SPERABLE by performance of the CMANNEL CN Wand GIAldlEL 7 4*l CAL 18AATION operations at ths. frequencies shown in a 4.3-10. e ,
% ,s v et u __ , - -
S R/, -ppl y 4 ,..% PAM s .. 4.. ,. , , ~i a '::, ' <. 4.3.le t 1 ch- '5, *3, s 0, t 9*
- Co , ~ 0 %kUEL C tCK hr ***k 3, t quser .i m a . r a +,. . cG e . -, t V* A ds y$
v e,, n . t , e ,-r 1 . r ed
@ L T.10 2. MOTE - -
u ,.,,, 4 , , , J , + , .( ,, , 4 R ,.c4.c /*u,} u~,, ...+... , <,,.- , . a c . e. p ,,, .4 r't . < ~i . . uw pi c Sy+t<~ *'C
, ,, ,, g ., A , J. G,. ,
C H ANNEt CG t lRR ADoO.
. g') , f,, ,,,,, CHMM Et. C AVFMohJ e.a e .b i.d...+..,,, et -, I c.wrp4 (" o 4..- rw .t. fg h*Nyvs. A Las trer om
@ t 0,3 , p., e fa G4A usJ C L. (4U6Q.4TioM e a.
{ +6 day ca . . - , +. n ., a . . ,. ., A - t , .a r, c ,, . ., v .a m _ _
-- ^_- * ~
CALVERT CLIFF 5 - W IT 2 3/43-33 Amendment No. 176 l AS -
> .c e n
l . . . . . ,... ... s l 09 Mehg,nwl f.cnJ4le ,,deg.dettameAh f' l h%4 hMef by sHees+ *real.e4 e4 l 4 *My . 4 .%4.<, .l J -l l, l
.}Ed .. c ,
- i al=t *Mflav fhG fic .trLefeu cJ, l' l N'}d 4 % '"* F4 lea +. g gga 4 .
( (_bf04 p.,.9 ,,a% A .A..,ia e l ,,,,< .g M y3 f,, peubt, MS i# e.J *ee.odied A,l - 4bp%,
. a.u .k= e[.
e a,1
~
N. - J . b%4 .
? 1 m r CC r ,I in a
8 - IlNDMI M.1 ; gagsggs g OP.AstE AtrIM
- IIISTREW ,
l I 7 . Contafrument Pressure 2
~
Aceto *JS
.,31 >
i Q l E. lifde llange Logeef tluste flestron Flux plonf ter 2 4 ,3, c,g.
# g 2.4. Ileector Coolant Outlet Temperature 2 Jt* t Ii 4. Pmssurfrer Pmssum 2 ,3t* ;
13,5! Presserfrer Level 2 ,3r* ;
, 17 J. Steam Generator Pressure 2/steen generator .,3r , l t4 #. Steam Generator Level (Ifide Itange) 2/steamgenerator .2t' !
' '3 '
gq g M '1 hillary Feedustet_Elow_Itat - 2leL_ ... . .L. _ , . i M .10-1 4- 9< llCS Subcooled flergin lionttor 1 . Jt" 1/ val =a. ,;2'-- 4'E-J9v-70ltV/ Safety-Valve-Acoustic 41ew-flenitori ;;
*^'
,g M.-PoltV-Solenoid Power-Indicattaa 1/ val : ! ):
? * -
g
%M' s L " der' Flow ,._
( 6 }3'. Containment IInter Level (Ifide Itange) 2 . d 2 (( 'p f7 Jt. lleector Vessel ifater Level a k-1915'. Core Exit Thermocouple Systen 2 locations / core ;- :_^_ . )t" ;
-o y~
l D g M 4 o d 'T A channel nas eight sensors la a probe. AchannelisePERARLEiffourormoresensors,oneor) CC: ; T more in the upper three and three or som in the lower five, are OPERABtE. ! m _
, e.
c.a... .a v..s., m. . . . , 7 = M
~2- AcmeAJs l
,J u
'b C -i~ sy-...q,
~_
S g h p.- Oi-,3,,.4 5] q p . <, L. w t.y,F z Aaog l c4 ,,,
"D '*0 o e,c,e fc .--~ < i . .y . , , v. . g,...- - --
%GP l
- -e
}.0-4 iess f k d
S i d Pdth 3.3.10 i a. 1 i !O 3/4.3 INSTRUMENTATION i ie. .E hh.A4 3 5 ' Y'3 ** 3 h
- A .r -
TABLE 3.3-10 (Continued)
=v i
1 [#Aftt'/ ld riff,Y'" ACTION STATEMENTS
;,j, ut.,
j 1
. ..r.l..w .iad l f
i M- With the number of OPERABLE- st-accident monitoring --Jps 1..+ mea f.t..'l
~
An., A ,c. channels less than required y Table 3.3-10, ett
)
l store S. ! j Linowrable channel to OPERABLE status within days or 1 A.m.= %;c,r in arr nu e 2 within MhFRAFB 12 gggg, ,& ' j
@f!6PS - With the number of OPERABLE post-accident monitoring h[*lM channels one less than the Minimum Channels OPERABLE a requirement in Table 3.3-10. G........ provia a% A ne i- 1.viu cnsnnei is ored to apreay 5,vystatus at th j g ext noe of sufficien rationJ , . p,, g j E5E5lPTb -
i j Ac,.a c., -
'With the number of OPERABLE post-accident monitoring channels two less than required by Table 3.3-10, either g'4 7f,,, s M*' Y[ " .%
mstore one inoperable channel to OPERABLE status within AN G,5~ Q@ days 6 Foe inacT anue--" within === nann iz noursk ( M - Wit he number of OPERABLE post-accident monitoring channels one less than the Minimum channelt spreme
- l Ac,i.s A requirement in Table 3. - /.'9h n
Jer restore the sistem to V sys 0 %== =communim g in snu w .suun,n...uan....r. t to 10 CFR... ._.. 50.4 a -30aine within days 7,,,,,,'.j, i. a 4W 8 following the event, outlining the action taken, the A. .,4 s-'ua. S M I j of the inoperability and the plans and schedule for ' reatneinn the ewstam to Opreaal t statue i 1 i
@- With the number of OPERABLE channels two less than required 4t fW C. by Table 3.3-10, either astore the inoperable chann_el(s) to i OPERABLE status within u rwom rs are veerinie GTYH5ifY thutting a='*y or: nevra
. A Arw E My g3,4, . Initi. nam,+ 7canima+ en assemate mesnoa y+= uai na monitoring for cop and1 Mt
, b[erenaA.e'h
- g
+ T . rreps ^ana sunalt a 5pecial Re be U.&I St.l.1 to the Commits ton 3 1 l pursu t to 10 CFR 50.4 within even , outlining the action t en, the cause days followi the the da .% ;. .u W g,,4.4.. iM W i Acm ' 6 in rability and the plans d schedule for storing i system to OPERABLE sta s: and _/ 3 e system to OP LEstatusattgnext i
'k.nestoresched refuelina. i l
CALVERT CLIFFS - UNIT 2 3/4 3-35 - Amendment No. 193 1 l IO ! P*y 5 4 6 1
9 JN R g M iihi-- - - n - M i- : ._ - - e a" i - * *'"* =_ _ _ 1 b DISTilgMENT 3 CBECK CALIBRATION
. 7 y. Containment Pressere M RENELING IllTERVE
@ l J. Wide Range Logarithmic Neutron Flux Monttor N l g
[ 2.): Reactor Coolant Outlet Temperature g N REFUELINE INTERTE It g. Pressurizer Pressure , N REFUELIINI IllTERTE l t3 I Pressurfzer Level M REF5ELINE INTERTR l 12.S! Steam Generator Pressure M REFWELING INTERFR l R 1A 7 Steam Generator Level (Wfde Range) M REFWELINE INTEltV R l i h y' "="': ; 7:;f 2 - C., R.R " h m..*- . . f. M + 7. RCS Subcooled Margin Monttor N REFUELINS INTERVE l
- y. . L,.,"-'a'= **? - .*=tf : 5' t:- NA 7-=_;_,_ l g,7
.L. ::?;--M 7;, ;. :;; :: ::,.
3). m g r -- ~ M u.-.= 7:,
=...
}
C 12'. Containment ihter Level (Wide Range) N REFUELINE IllTERVAL S l
}(.ReactorVesselWaterLevel N N4 u S-' pl.CoreExitUmnocoupleSystem N "U
- 0
. ine .Tornance o _ - _ _ =_ CM -=usu ;,,;..4fon exemptt"'fhe Core ErtFTL.--:: _lo gdt _
odes all e y R tronlc componsoffs.,Ghe core Exit 4; ;6 sple shalMe calfbrated pffer Masta11ation in,ane reactor core.ff J f- l p . .. A5 y i 4 Co= 4 a * -4 Hy4,.y 4 lys.e3 - 4(, 4
%q g 4. c o..< w c %~,
- r. _ a t ~. /
N "? * ** *>
- i m 2c.-g s a s. ,.io. 5 f ;
00 3. d . a . c..t a i.i.+ T , p. u , M M -~ d
- 5 g e g _ +<.
g-A_Cc t Cs 4 .- .., a e , .to l... U. lo c P.s.4. , 24 -+ L $ A.t
..,% .RL A . eg ?. 8.
9, 4 .o - (. N. . . _ -- _ A,gQ I
~ l M.( 3, I, 3a 9 I
- /./
- O .
! N 3/4.3 INSTRUMENTATION l 3 .3.3 MONITORING INSTRUMENTATION
)
Fire Detection Instrumentation '
- tru m n v M m e = 0 , m T1 =
i *
! 3.3.3.7 As inimum, the fire detection instrumentation f each fire i detection zone hown in Table .3.3-11 shall be OPERABLE.
never equipment in that fire detect zone is required , a With one or re of the fire detection i trument(s) shown in
- a e 3.3-11 inoperable l a. Within 1 hour es blish a fire wa patrol to inspect the i
zone (s)withthe perabic inst nt(s) at least once per hour, l' unless the instrume (s)is1 ted inside the containment, then. inspect'the contai at 1 t once per 8 hours or monitor the l containment air temper u t least once per hour at the d locations listed in Spe cation 4.6.1.51 or ur.less the instrument (s) is locate fire detection zones equipped with ! automatic wet pipe spr k1 systems alarmed and supervised to i the Control Room, th withi 1 hour and at least per 24 hours l l thereafter,inspec hezone( with inoperable instrtments and . l verify that the A omatic $pri ler System, including the water ' i . flow alars and pervisory syst is OPERABLE by CNA M EL j FUNCTIONAL TES . ! b. Restore the noperable instrment(s) o OPERABLE status within ,
- 14 days o .orepare and submit a Speci Report to the Commission '
! pursuan o' 10 CFR 50.4 within the next 0 days outlining the l sectian aken, the cause of the inoperabi ty and the plans and j sche e for restoring the instrument (s) t OPERABLE status. l c. T provisions of Specifications 3.0.3 and 3. 4 are not ppi cable. , 5 ILLANtt REQUIREMENTS i I
.3.3.7.1 At least once per 6 months, at least 25% of the above ired fire detection instruments which are accessible during plant operati
, shall be demonstrated OPERABLE by performance of a CHAMEL FUNCTIONAL . l Detectors selected for testing shall be selected on a rotating basis su i 4 CALVERT CLIFFS - UNIT 2 3/43-37, Amendment No.193 3 iO a
.-- -- - .. ..-.-. - - . - - - -... - -... ..... - .-.-. - .- - =- - - . - -.._.. . _
C TJ 3, 3,3, 7 f.I 4.3 INSTRIMENTATION SURV CE REQUIRDIENTS (Continued) that all det rs will be tested over a two year period. If ny detection zone am less than four detectors, at least different detector in that zo shall be tested every six months. r each detector found inoperable duri nctional testing..at least additional 10% of all detectors or 10 detec . whichever is less all also be tested. Fire detectors which are ina sible during t operation shall be demonstrated OPERABLE by the pe mance CNANNEL FINICTIONAL TEST during each COLD SNUTB0lAl exceedi 4 rs unless perfomed during the previous six months. l 4.3.3.7.2 The NFPA Code 720 ss B supe sed circuits supervision l associated with the detec alams of each the above required fire detection instruments I be demonstrated OP LE at least once per 6 months. 4.3.3.7.3 T -supervised circuits, associated wit etector alems, between the strument and the Control Room shall be d trated OPERABLE at least ce per 31 days. O i CALVERT CLIFF 3 - UNIT 2 3/4 3 38 Amendment No.176 l O p., 2 M
C7J 3. 3. 3.'7 O
~
R.I 3/4.3 INSTRUMENTATION TABLE 3.3 11 ,
~
i FIRE DETECTION INSTRUMENTS ! E NINDRIN IN51-is l OPERAB ROON/ AREA AUX BLDG, INSTRUMENT LOCATION M&I BE[ i 101/120 CS Pump Room 7 102/121 S Pump Room 7 - 105 Ch ing Pop Roos 3 106 Mis Waste Monitor Tank 1 107/209 Cools t Waste Monitor Tank 4 108 Pump Elev (-)10'-O' 1 201 Compone Cooling Pump Am 9 203 East Pip g Area 10 204 Rad Exhau vent. Equip Rm 4 205 Service Wa r Pump Rn 3 6 206/310 East Pi ing en Re 3 5 l 211/321 West Pi ing Rm 2 3 213 Degasif er P nm 1 0 214 215 216A 302/2C volume Control Boric Acid Tank nk Reactor Coolant Na -up Pumps U2 Cab 1 Rm
& Cable 1
2 2 3 ,Spreadi Chase 2 10 305/307/303 U2 Battery Rm Corrid 3 309 Main Steam P ing Area 6 311 Switchgear . Elev 27'- 6 312 Purge Air upply Rm 2 322 Letdown eat Exchanger Rm 1 Elev. 27'-0' Switc ar Vent Duct 1 2A Cabi hase 2A 1 28 Ca e Chase 28 1 l l
)
/*
Detection instruments located within the containment a to be OPERABLE during the performence of Type A Contal Rate Tests. not required t Leakage l i A Detectors which automatically actuate ' Fire Suppression Syst . CALVERT CLIFFS - UNIT 2 3/4 3-39 Amendment No.17 l O n v+ l
- . _- . . - ~. .-_- - - ...... . _ . - -. _ - . - . .- - -.
c rs 2, z 2. 7 O 8./
\
i i 3/4.3 ' INSTRUMENTATION
~
Tf.BLE 3,3-11 (Continued) j FIRE DETECT!0H INSTRUMENTS
- WIT I i
MIN INSTNylENTS OPERABLE i ROON/ AREA j All1_B1M. INSTRUMENT (0 CATION EgI {Wg ag[ ! 407 Switchgear Am. Elev 45'-0'" 8
. 408 East Piping Area 7 j 409 ast Electrical Pen Rm
- 3 t'
414 st Electrical Pen Rm " 3 416 D el Generator No. " 2 , 422 Die 1 Generator No. 2 . 440 Refu ing Water Tan Pump Rm 2 , Lley, 45'-0* Switch ar Vent 1 526 Main P a Exhau Equip Rm 8 l 527 Containee Ac ss 3 532 Electrical p Rm 3
- Eley. 69'-0* Cable Sprea Room Vent Duct 1
- Elev. 83'-0* Cable Tun 4
- 605 Auxilia Feedw er Pump lbs 2 fw Containment sida.
! UNIT 2 RCP ay East
- 16 UNIT 2 R Bay West 16 i i UNIT.2 ast Electric Pen Ares * '
j UNIT 2 West Electric Pen Area 1 4 Intake Structu Elev 3'-0' Unit 2 Side 24 l l 1 4 ~ Detection instruments located within the containment are t required to be OPERABLE during the perfomance of Type A Containmen Leakage Rate Tests. Detectors which automatically actuate Fire Suppression Systems.
+
8 Monitored by four protecto wires. f CALVERT CLIFFS - UP!!T 2 3/4 3-40 Amendment No. 191 O pyr 4 af 4
Se , . C. d. , 3.4. t i
.\
k . _ , , _ = f __ l j 3. 4- e atacta c=L=r surm JSc s 9C S_-L _ps - Mo OES I
--d 2) _
4 3 A . 4- - 4 l LCO
-* ' !.q ui' eactor __ M coolant loops.ead-4e4b-east 4ee-seelenW; - r' LA*i 3*4 4 ._ .
4eoirshall beg operation. APPL!cABILITY: IIDDEs 1 and Q V -
@ M A "Mece*+:en,ith be in at tre ie it tM-not sianothe ixV ;;;t within r;; ;;;.;;.
hou ;n'st = , _,_
- - - tr.
! 6 Mu "'O DILO j .n a ' 'm e +f - A.I J SR suavtrumet arquInnerrs h , 1.". .; The above required reactor coolant loops shall be verified to be J
'I'd *t.1
- l in operation =d Of-'r't; - r'r r:!=t at least once per 12 hours.
i i !O } i { I i i L 3 i 1 3 i j i i
~
, ~;: t ? int : ..p;;n '.10.0. A,]
CALVERT CLIFFS . UNIT 2 3/4 4-1 Amendment No. 149 O po$e f.c 1
$ p a c.. C. . +. o, 3. + . 5 O
- 3. +
O ~' '~ ~ ~ ~ ' ' ~ ~' l
-8/4-4 REACTOR COOLANT SYSTEM. (QCS)
( S L-opy MooE 3 .I l 1 3,4 $ 3/4.4.1 e00LikT innPS AND roniAMT c1Reu ! N 1 LIMITING CONDITION FOR OPERATION I.YS ' "P' "'***-**' ' h*" 6' '''#9
~
% oop #21 an at least one 1 actor Cools ociated 1 ( 4,
/ reactor c nt pump.
- 2. Rea r Coolant Loo 22 and at le one associa
.* rear eaalant a___a. ,
1.4 1 At least gne e' +b " eve ".:nter C;; hat L::;; shall be in A,i operation. APPLICABILITY: MODE f*' EJ.123: Ac.Ti 014 A ,4. .(With less than the above required reactor coolant loops OPERABLE. Ac' don Wstore the required loops to OPERABLE status within 72 hours or g -{ba in NOT SHUTDOWN within the next 12 hours. Ac.M 4 % With no reactor coolant loop in operation, suspend all operaticas c, inKiving a reduction in boron concentration of the Reacter (s Coolant System and initiate corrective action to return tk required loop to operation with'a ?-? her. fm . * - LC. 0 / ja.; All reactor coolant ; umps may be de-energized for up to I hourdup to em tJoTE I 2 hours for low flow test) provided (1) no operations are pemitted that would cause in.de,. of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10'F below saturation temperature.
# A reactor coolant pump shall not be started with the RCS temperature L C. O WT E 2 less than less than or equal or equal toinches, to 170 301*Fand unless (1)(the pressurizer water level is l 2)thesecondarywater temperature of each steaa generator is less than or equal to 30*F above the RCS temperature, and (3) the pressurizer pressure is less than or equal to 320 psia.
CALVERT CLIFFS - UNIT 2 3/4 4 2 Amendment No. 178 O O $ $
. - . . .. - - - _ . . - .. . - -. =.--.- .--
- 5 , c S. ~ + e, 14 . 5 9
! T 4 i 3/4.4 REACTOR COOLANT SYSTEM SURVE!LLANCE REQUIREMENTS e , 0.0.;.;.1 At least the above required reactor coolant s. if not in 345.'5 operation. shali be determined to be OPERABLE once per ays by verifying j correct breaker alignments and indicated power availability. N 4 1 3.4.5.I 0.0.1.: 0 At least =:tr rd cirr!:tt:; one cooling
= =t at L'A.2 100Ient once per 12 hours.shall be verified to be in operatio SR 3.4 5.2 ve c y s~ -- a . , s , .4-, i ~ et
.- ...w u ,. - $ , ~ , ,, a a >
i - S o ., cu.3 l '2. h i _ _ M.5 1 4 1 l I 1 i 1 1 1 i, i 1 CALVERT CLIFFS - UNIT 2 3/4 4-3 Amendment No.149 p 3, 2 F '2
_ . . . _ _ . _ _ . _ _ _ . _ . . _ . _ . _ - . _ . _ _ . . . _ _ _ _ . . _ _ - _ ~ _ - _ . . _ . _ . _ . _ . _ _ _ a & Ce.A es '3.A.S 1 i }
- 3.+.6 1 -10.--ss3 um M
w"r *s e mi~~re - maare - -- - ] c . -s.g+.. g . P . ay ~
- W a.A e o n l LIMITING CONDITION FOR OPERATION ek Rc.5 fe.c5 or _ S D C l_..ps
- y. 6 '.'.:.: X. At-4eest t ' 't . nt loops shall be SPERABLF4 4-)
e i i 1. A actor
/ genera ant Loop fZl and at least d its associated associated rea eam r coolant
)
l l
\ 4. I
- 2. actor Coolant op #22 and its ociated ste
( generator an t least one ass ated reactor lent ! P""P' , l 3. Shut Cooling Loop # , {
- 4. utdown Cooling #
% tperation least ,ge .
' 't: 21:.: rrirt loopf shall be ip 5-e 4..-u-- =F **s>
. A .~ APPLICABILITY: _ NODES F and N , s p ..c.. ... "J. 4 '? ,
1 O M: CL, ,(,,,Q Ec.ca ..p WS l-** (* * " d O C 5, 8 ** N E h *d l 'Q ==d ho 50cle e * -d T.4 S " RSh t-7s - M D E ( _'_ ',* ?.'. f_I_t .L' V d '- 2
, g f ? M *- a -_m_ _
D'
- l
, Actio?J B N in a5EcorrectNe'Ut50d N5 urn'de'recuirei3oiar'il lecB o OPERABLE status within 4 nours. -- peinCOLD$ NUT 00WNwith1B h
- - - - - - A.2
! '1 to C. l e.p g og ,e
% TM : :! - m;r--- y =
rr;; n, M *- ; reble-4*.M005 4.. A.6
^
l shutdown cooling pumps may be de. A per ? L. - M LC.O All energizedreactor for coolant up to 1 hour pumps fprovided (1) no operations are permitted 9'"*4 M b'T E. I that would cause dih'te of the Reactor Coolant System boron
~
concentration, and (2) outlet temperature is maintained at least 10*F below saturation tempe l ... 6 {,g
" A reactor coolant pump shall not be st
{ tc, o with RCSMemperature NOTE 2 less less than thanor orequalequaltoto170 301'F inches, unlessand(1)(the pressurizer
- 2) the secondary waterwater level is** W ' - ~
! temperature of each steam generator is less than or equal to 30*F above the RCS temperature, and (3) the pressurizer pressure is less than or equal to 320 psia. 0g : h1 Tr
- 9 ^^ ' t.. 0."^.3.
i j CA*. VERT CLIFF 5 - !! NIT 2 3/4 4-4 Amendment No. 178 4 b
j 5 p nAo 4.o. 3. 4. 7 i M Q
- T4 wm e mnen e sm Qw g;au,,,,, _ p e ,, ), ,,, = - = - -
! 3.4. 7 /:.:.: un = x,_ -- - A' ) ! shutdown NRnE; .c , {
- 6. w. .. .a .
untram comma roa opsnarson le, ,.u, 4.,s_?-3_ de__ A P m-i ~, i . c - m ,,4 . _ u s.A i LCO 3.4. 7 9:+:t3 a. ?! 'cr %vf the E fldje&% e
's R(ju^-f ht ehall be
. Q l
i l {gso fl. Re tor Cooient Loop ft1 and its pssociated steam pump, retor and t least one ass ated reactor lan)t L..I j 5 i kgf, 2. Reactor Iant Loop #22 its associa steam
, genera and at least associated ctor cool i r* E 3. 5 down Coolin Loop #21f , '
[TNWRT LCo i :J $ LA.t l G y. Shutdown ing Loop G/. . (QNoTEs "- 244 it e' t'- tx rh-t Mg; -hl' 5j-APPLICABILITY: and P v M-gig A) ,,g--
- O m u . . :. a t: c e.A.z , ... .+ .e
*l't 'Q 4
- w sy. 9 w }.
! a. .e 1-" JCh+ = c'--d x ' ... ;,. 0 :_"___, l ? M10V A initiate corrective action to re
'PI4 Statu5 0 " hir ^^^ ' " T " 9'"-^"" ri S C**.,A'it -
[r e reautred coolant loons
~
< . 2. b Q,
% k. =-_-1 ne ==, -- -
~
- k. < ==-.63 t c; , -
] y /en c' ~ W* J_r Y' oj
~
t..C. O n ,.
.........x,..... pumprmay .'..
utdown NaiE I "en, .ergized for up gQ,- r rovided (1) no operations are p.tnitted
- that would cause of the Reactor Coolant System boron concentration,and Nre outlet temperature is maintained at least 10*F below saturation temperature. a g , ,,
A reactor coolant pump shall not be started withfthe RC toegFerature
'# O less than or equal to 301'F unless (1) the pressurizer water level is l KJ OTE 2. less than or equal to 170 inches, and (2) the secondary water temperature of each steam generator is less than or equal to 30*F above the RCS temperature, and (3) the pressurizer pressure is less than or equal to 320 psia, b :s *---h! Tut m ."... + 11hS.
CALVERT CLIFFS - UNIT 2 3/4 4 4 Amendment No. 178 O wp
I S p , . r. a:.. 7.4,7 INSERT LCO 3.4.7 NOTES 2 & 4
- 2. One required SDC loop may be inoperable for up to 2 hours for surveillance .
testing provided that the other SDC loop is Operable and in operation.-
- 4. All SDC loops may be removed from operation during planned heatup to Mode 4 when at least one RCS loop is in operation.
l l l I O O p.3, 2 .c 5
he,C.e 4 .e 34=O O o
- 3. 4 W REACTOR M SYST M Qcc; L**PS E$oE 5, y,4.g :f:.:.: a = =s - -
= ==_.= t. .n o.a p ,, i,s
_ _- ___v = LDtITI M COWITIOR FOR OPERATION LCO "J. 4 . 2 -M;tt a. 464 east -' th: = $ nt oops 44stad-helow shall be OPERAB
% cs fl. Rea r Coolant Loop #2 and its associat steam ) i retor and at le one associated ctor coolant' A, !
. . Reactor Cool Loop #22 and it stociated ste generator at least one as cisted reactor lantj
- Pisip. 3 Se, 0.ww e
- 3. tdown Cooling p f2 Loopf28 p
. Shutdown Coo
'gr.5, yg 4L. it-tuttt p -' th ;hx =mrt '::;: 2.:" h in]
/ operation . 7 APPLICABILITY: E$ and s W O EllGR ~ - -
bd - -- -
~
d L pl-.-.--- ( I:, -- Ed 1 '
. A. l Action th 5 - """ "'"Y"- ='-* -f = 2 =t -- :- r .
K " initiate corrective action to return the required coolant loops A '
!^'" i.1-~. : ;i. ;,, -
'to' -0FERABLE
-- m, ce u. 4, .-.., . ..+.. o . status _ ;';.'.24,
. .%. . Or h '-
Chem, re e se e + , ne s . '., __ g, a.e me .. w a,u, C..~.."._._,._._...__..----,,,,,,,,,,ua-....u.
- a. ---- . ,
_A. ; LC.o All N -> 3-- -5,fgshuTdown coo 1tne pumos sarbe de.'__ energTredTor g :. . ..__. v. .."= vigno operations are permittec NOTE. l that would cause 444et of the Reactor Coolant System boron concentration, and ori uud.. - tained at least
~ M O*F below saturation reture3 :\:rature r eelis we 4 o .4 ,. Ae fA I ttor coolant than or equal shall not be st ted with the 301*F unless ( the presst'ri r C$ water temperature]l leve s ess than or eq to 170 inches. (2)these dary water
- temperature o ach steam genera is less th or equal to "F above the than or temperature, and 1 to 320 psia.
)thepres iter pressu slesh A "x !;::ag v... r.. -ga- 3_in $_ _
CALVERT CLIFFS - UNIT 2 3/4 4-4 Amendment No. 178 O -
**m 2
- we w m a n ,. ,
m3 p, w
. ,w u, w a
, y. , soc m i.py-ev eg iop 2
't
$9e-c.C e si ...
- 3. W. b i
a J 2 V i I M6 , LIMITING CONDITION FOR OPERATION (Continued) ACT10hJ j C g With no coolant involving loop inin$ ration, a reduction suspend all of ron concentration operations the Reactor Coolant System and initiate corrective action to return the required coolant loop to operation .TJii - :.m.. ._ _ _ _ j
'~' M.3 i SURVEILLANCE REQUIREMENTS 4.4.1. 1 The required @7. =1'Q 1oop(s), if not in operation.
3403 shall be determined OPERABLE once per 7 days by verifyiqlorrget breaker a and indirtted power availability for puJmp c - ;t..tA . =MD g f,
- Q 4.,.i.i.i 5 '.1. . ,
The requhtd steam generator (s), b ': SM: =d 0: rf. shall be determined OPERABLE by verifying the secondary side water level to be above -50 inches at least once per 12 hours. SR
- 3. 4 . 4 - l 4.4.1.3.3 At least one cool Q* !
g g,g,;_.-- ..... ..., ant. loonet{ east once per 12 hours.shall be verified to be in operation 1 4 CALVERT CLIFFS - UNIT 2 3/4 4-5 Amendment No. 149 O p3 7 oF 2
l Tyc' 4.'e c.4 .'.4 ~5.+.7 ) i !O I i ! 3/4.4 REACTOR COOLANT SYSTDI
- 1 l LDlITIM COMITION FOR OPERATICII (Continued)
I v a+ a.w q gig b. With i.,G bein involving a reduction inTration, suspend allofoperations
\
I ron concentration the Reactor 6 Coolant system and initiate corrective action to return the
- required coolant loop to operation 9^2'
- ::: i:_q _ _ _
h_ ___ M.3 i SURVEILLANCE REQUIRDENTS 4 l SR e The required shutdown cooling loop (s), if not in operation,
- 34.7.3 shall be determined OPERABLE once per 7 days by verifying correct breaker i alignments and indicated power availability for pumps and shutdown cooling LA.
loop valves. A,g 4 SR "
.r'd. steam enerator s - d u i . . . . . : ' - --^
j 3.4.7.2 TN'llftlysIThe y verifying sne secondary side *7 . j 1 to be above -50 i has at least once per 12 hours. l [ SR AA A+ 1 east one eseh oo shall be verified to be in operation
- 3. 4 . 7. I 6et-P-"9 - - ::::-- at feast once per 12 hours. *) I U
O ; I CALVERT CLIFFS - UNIT 2 3/4 4-5 Amendment No. 149 O P'y 3 oF 3
j i -S pecs. , o+. , 5.4.7 I l !O 1 1 LDt! TIM Com! TIM FOR OPERATIM (Contissed) - h_=_ %[.__ i t % WHk4o loop in operation, suspend all operations 1 Ac_ T ie t J 1 a reduction in boron concentration of the Reactor i g sg ant ystem and initiate corrective action to return the l required j a2+ loop t( operation r. I xO.4_J j
,l ._
i =maid.I'e _ = yf
} M i 20RVEILLAllCE REQUIRDWifS I
l GR
- 3. 4.7.~2. 4.4.1.3.1 shall be deteru The S OPERABLE once per s iy~7verifying dfred shutdown correct breakercooling loopy. if not in ope and indicated power availabili or pumps -- - -" - n= -
! T4.4.1. The required at enerator(s),i t is being used meet' ! } 3.4 . .a. shall be date ined'0PERABLE by ifying the sec ry side. # . j er level to be abov -50 inches at le once per 12 hou . j l SR shall be east verifiedonce to be inper operation 3,4,% l 4.a.t.u at inant 'oneQ_b'$hloo$ C ; e.wi..;., ...de, e at 12 hours. 'O I i i i CALVERT CLIFFS - UNIT 2 3/4 4-5 Amendment No. 149 O
- n. 2.m
. _ . _ _ _ . . _ . . _ . . ._ _ , _ _ _ _ _ . _ _ _ . _ . _ _ _ _ . . . . _ . . - . ~ . . _ . . _ _ _ _ . _ . _ . .
1 I 4h.b 2.4.i o i l0 e - - ,ea I 1 1.4. 8 o S/4 4 2 A SAFETY VALVES Qe,....,...- q LDl! TIM COWITION FOR SPERATIN
# 'd 1.c o "5. 4. IO 4.4.2.; :t.; Sh.; pressurizer codeM1ves shall be SPERABLE: b-Lift As-Found As-Left M+o o ve h Sett a Tolerance Tolerance 3R RC-200 00 psia +24/-14 1 14 i
A. A4ti.a k \ m RC-201 2565 psia + 24 _% +1 w .tk
- t R c 5 c .'id 1 3 APPLICABILITY: ES and 3.
, ,,4 g
\ ACIIM: With one pre er code safety valve'inoiierable, either restore the inoperable valve to OPERABLE status within 15 minutes or befn.80T-U'E N,3 ..g 3 gg)g 't 1;;;t r.; ;' 05.; i .. ;-..;.7'... ____.....,.E._" 4 -
i b p M*o f,ge/f ' EAB1kfYY:-IWDE54and . 4, 3 L. O : With no press zer code safet alve OPERABLE. spend all operatio involving post e reactivity SPERABLE shutdown w-ling loop int ration. f fatelyf sandphicean # L. t . 1 pp SURVEILLANCE REQUIRDIDITs 34.3 C. l . 2 No additional SurveIIIance Requirements other than those required by Specification 4.0.5. q,,, p , ,, 4 9, , , , , , , , ,, g , p., g se tuc n ODE R AG l.e. .. . .. , J ~ c w.t 4 +b e le * * . vu a T* dig P, .g , . , T(, g,4 g, g, sk,, p m_- ~ _ _ _ _
~
N Ac4i. % B .t<. e *e * ~ t** ** e3 fy* Twe s . f. 4 y .,e19 5 .k . p Both valves may be removed in NODE 5 provided at least one valve is replaced by a spool piece which allows the pressurizer to relieve (* ) directly to the quench tank. CALVERT CLIFFS - UNIT 2 3/4 4-6 Amendment No. 1B4 O p.g i .e 2
J S p . . .'F . , 4 . e 3.9.IO i j 4 i 4 ! LO 4 t l INSERT APPLICABILITY NOTE
- (Unit 2) i i
4 NOTE- 4 l The lift settings are not required to be within LCO limits during MODE 3 > 301 F for the 1 l purpose ofsetting the pressurizer safety valves under ambient (hot) conditions. This . l exception is allowed for 36 hours following entry into MODE 3 > 301'F provided a ! i preliminary cold setting was made prior to heatup. ; , l i t f i t i O O
%, 2.m
. . . - . - . . - - . . - . . - - ~ - - . - . - - . - . . - ~ ~ . . . - . - - - - . . . . - - - - ~ . .
j Ipecifi.4.# 7.4.II j Acu.w A wet. . t. 4 3,,....d f.3 . - e W a . i. ., .4 r,,, c iao i..., j .r . . bi.s4 ,, . t .,c
* = .p.. . i.i c . .a d & 7 2 4. .,
- er N. 4 8., . k .i... .., ..p...wi, j
, 7 . *J . h t
.e.-st.
.g e-
. .,e i. . % i c . r g4 , pogy ,, 43
. e ., , . - c. s , . L . y .,y w i v . . . . ..i ,,
L4 ,,,,,,..i,
, ,, 5 . ,,, , e
{ W REACTOR COOLANT SYSTEM Q
,g ,,g.
3,q,a{ .'0.0.* RELIEF VALVES j LIMITING CONDITION POR OPERATION ~ y LCO l 9tt:9 Two rated relief valves (PORVs) and the'* associated block i 4U valves shal be LE. APPLICABILITY: MODES }f 3
. =:= n.= --
g*y i i G n_. par. U q u J <ar d l+ & L
- S w w lly yel ;
A C' ' f A g. )(sne or both PORV(s7hn M::id tett 5:Y : within 1 hour clee the associated block valve (s) and maintain power to the - block valve (s). ; f{; ! AC. Pod ith one PORV ino rable ... t: ? _cr etin ttn rr=M Z; - j q e91- 'r wit in 1 hour eith restore the PORV to OPERABLE
- status or close the associated ock valve and remove power from l Artim h the block valves restore the
.Jhd., 5 days or be in NOT AND8Y within the next to OPERABLE status within the hours F and at or below 301'F within he following hours.
- l l
( Ac6og h ith both PORVs inoperable ,
-. --" ?^r";r, within 1 hour either restore the PORVs to G ...... v6nwr sn.n .....;.. ,
- i OPERABLE status or close its associated block valve and remove l l er from the block valve; restore one PORY to OPERABLE status '
4 Atpm ithin the following 72 hours or be in NOT STAND 8Y within the l 4 p next 12 hours and at or below 301'F within the following l l j 4 hours. ' j d. ith one or both block valve (s) inoperable, within 1 hour restore AC tioMS the block valve (s) to OPERABLE status or place its associated 5 C4g PORV(s)inoverrideclosed. Restore at least one block valve to
- OPERABLE status within the next 72 hours if both block valves are
- noperable; restore any remaint inoperable block valve to gg PERABLE status within the fo11 ing 5 days; otherwise, be in at i p, least NOT STAND 8Y within the next 12 hours and at or below 301'F l l within the following 24 hours.
1 j Ac.mN % The provisions of Specification 3.0.4 are not applicable. , N oT 1 I i Q VV, A ., DC S e. t d (*y k ~p*
- s t
#b,,ed 4
/ mod E "3 A pp l.c 4. t. 4y f ove 301*C #. u 5:i= 'Ol*T, Mdnt'r "' ' * ' 2;;i'". l CALVERT CLIFFS . UNIT 2 3/4 4 7 Amendment No. 178 O
n,n
l 6 pac.P. ,o,4 o u 3.4.I1 j l 1 l O I 4
$URVEILLAllCE REQUIRDIElfTS 4.4.3.1 Each PORY shall be demonstrated SPERABLE:
's. (At least once per dap by performance of _a CIIAletEL FilllCT10llAL J 3411.I GEST. t. :::: Pet "+ T1 , .,- . . . - g .
LA,g l g A fat least once per REFUELIllE IllTERVAL by performance of a tilAlelEL l } 3 4. il, $ - G BRATICII. ! M Each block valve shall be demonstrated OPERABLE at least once r 3 .h .1 92 days by operating the valve through one complete cycle of full trave j g unless the b ock valve is closed to meet the requirements of4%n un g, i 8F cE EnocMicationg.4.B = < - c -r ' ^ g *g ) *M _d [ 1
' g 3 4,l1.3 Pc,Sem
- w m e' b L M l 1
of ce d I' bd I
$3 l
l f i i l i ? I CALVEP.T CLIFFS 8) NIT 2 3/4 4 8 Amendment No. 186 9 ,2.a
l I l h p (c 8 e e, f.'e o 3. 4. 9 t f O ! o , 1 1.4 = m C = - uNT = = G a b O l y4 3 */' '." PRES $URIZER -- - - _ _ - - - - - i Ne.L % .F L * -4* es LIMITING COMITION FOR SPERATION I . * . The pressurizer shall be OPERABLEf 2 Ste r P M '? and wd ti l m, . least 150 kw of pressurizer heater capacit rana-ru of usaiu i...' -
- um - -
, , . The pressurizer level sham Tm maintninea within ar i 1
- b. -'
opera no and between 133_and 225, inches gimps wnen <;h chargi r re oper ng and letoown new is . . 6nen 25 GPM. . If roecharg1ns_[.. lM ! pumps operating and letdown is less than 25 pressurizer M vel mhall limited in ha+= aman ill ad 210 inches.\ l {,g APPLICABILITY: N00E5 Ig u glig: (;N. ,~,hfS. A icM bea4Q= r *g 1 Ac'oM = = - i
- . -1 pressurizer nopetablei: 'p; 34%ese restore the'.:;;;;;h - ,,,,,,,
Q(;:'::ri;4 0; ;t. p.;.;.ri;. L.21 thin 72 hours or be in at
-^
j AcT M u.;;. . e . ::;;', ! C r . . . . . , least NOT STANDIY wit @the next 6 hours and-4aJi&T SNUit0MN , Ydt"-t*=U~*n?"_'^. ! A O tC#J % With the pressurize :th .:'re P:- ik be in at least NOT i i A STANDBY with the rea tor trip breake:=s r ope,n within 6 hours and in ! ! NOT $NUTD0lui trithin following 6 hours.
- - =w~- :: ,
!l_0lf N' '? _
SURVEILLANCE REQUIREMENTS 4M-t The pressurizer water level shall be determined to be within the 349l above band at least once per 12 hours. _ n = -- _ __ dr e. F.y eap*eid y "I
"**k -
"*ewI b ak O w , .. - u .. . . . , , ,~ ~.
_ _ _ )_ 4 9_. s+ % ;
~ _ _ ,
3 _ ~ _ M. CALVERT CLIFFS - UNIT 2 3/4 4 9 Amendment No.165 l O n,m
~
y _. _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ . _ . _ _ . _ _ _, sp.<L6 3.4. G i 3 ,p h 4.4 Rf[CTORCOOLANTIFITEM 3 4 .13 (3/4 STEAM RATORS , 1 LIMITING CONDITION FOR OPERATION /
/
l (3.4.ytach steam egidator shall befptaABLE.] 8e in Me0E 3 la 6 b5 t APPLICABILITY: HDDE5 1. 2, 3 and 4. as,J 14 mos 5'/4 J 6 A *fJ ! @ _With one or more steam generators inoperable.jrestore j .m .
,su ... . 6ery so artuAsu statutgrior se increasin above g,y l
4 i L bsmss'* J CA*P l gn s p.e A b a 5.b, ,, EURVIILLANCEREQUIREMENT4 " W^ " I i < i .4.4.5.0 Each steam generator shall be demonstrated OPERABLE by perfomance { of the following augmented inservice inspection program and the j requirements of Specification 4.0.5. 4.4.5.1 Steam Generator Samole Selection and Insoection - Each steam generator shall be deterstned OPERA 5LE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1. P 4.4.5.2 Steam Generator Tube Samole selection and Insoection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2. The Inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4. When applying the exceptions of 4.4.5.2.s through 4.4.5.2.c. previous defects or imperfections in the area repaired by sleeving are not considered an area requiring reinspection. The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
- a. Where experience in similar plants with sistlar water chemistry indicates critical trees to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
- b. Thefirstinserviceinspection(subsequenttothepreservice inspection) of each steam generator shall include:
- 1. All nonplugged tubes that previously had detectable wall penetrations (>20%). and CALVERT CLIFFS - UNIT 2 3/4 4-10 Amendment No. 190 O cr.s 3.4.C mn 3/4 4 A A'S 'N "
(y, g wh e,.y4) - Q 1 r a s.o, .. w n e. M c P'P 32 3 l l
..- - ...- -..-.-- - - .-_-.-.~ .- . - - -. - - ._.. - -. - - - . -
j C YS & 4 3" 1 1 (M6,vEb ru .sfertw 3.413 3/4.4 REACTOR C00LAAT SYSTM 3 3/4.4.5 STEAM GENERATORS l LIMITING CONDITION FOR OPERATION ^ 3.4.5 Each steam generator shall be OPERABLE. I APPLICABILITY: $0'E51,2,3and4. 0 !; EIlGR: With one or more steam senerators inoperable, restore the d inoperable generator (s) to OPERABLE status prior to increasing T.,, above [200*F. \ SURVEILtANCE REQUIREMENTS OV64 fo .fEcr/c# 5 0 i I 4.4.5.0 Each steam generator shall be demonstratediPERABLE by performance of the following augmented inservice inspection program and the j requirements of Specification 4.0.5. s 4.4.5.1 Steam Generator Samole Selection and Insoection - Each steam j generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1. 4 4.4.5.2 Steam Generator Tube Sannle Selection anJ Insoection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2. The inservice inspection of steam generator tubes shall be perfomed at the , frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4. When applying the exceptions of 4.4.5.2.a through 4.4.5.2.c. previous defects or imperfections in the area repaired by sleeving are not considered an area requiring reinspection. The tubes selected for each inservice ir.spection shall include at least 3% of the total number of tubes in all steam generators; the tubes selected for these ' inspections shall be selected on a random basis except:
- a. Where experience in similar plants with similar water chemistry 4
indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
- b. The first inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
- 1. All nonplugged tubes that previously had detectphie wall penetrations (>20%), and J
L CALVERT CLIFFS - UNIT 2 3/4 4-10 Amendment Mc. 190 2 l crs a.+.c es e sig H o
' 9 -N,,.. ,. h al+ 4 - is, m d a m.ud h sad.- 50 pp I .F I
ke+ r. rg spapeasoa r.o i Af / oh 8)
$MV t. St,,rt i $AA)0 tl* t' A W Cr$ $
rMcRr r.r.9 za y Q 1 I3/4.4 REACTOR C00U NT SYSTEN l 3/4.4.5 STEAN GENERATORS i LIMITING CONDITION FOR OPERATION g ! 3.4.5 Each steam generator shall be OPERABLE.
~
APPLICABILITY: INIDES 1. 2, 3 and 4. i 3 EIIM: With one or more steam generators inoperable, restore the j inoperable generator (s) to optaABLE status prior to increasing T, above )s 200*F. - 2
.5ec I):.: rs t l W pee $esll4*a el- CWK3 s.4.1 l SURVEILLANCE REQUIRDIENTS D OfW
- b
! 4.4.5.0 Eac steam generator shal be demonstrated Op i of the fell ing augmented inse ce inspection prost andEtheby perforna h j' j Teovirene s of Soecification 0.5s
' f Steam Generator Mamole Selection nrd Insoection /I3 sti steamN
*" f 'he7
- 4. r nsii ..
R2i = vara e anu __-.. or selecting and) i s ina at laUt2s- minlaum number of steam generatorsgspectneu in JAd/ l Tanle( @ ( ,7 p t /skWf #
- 4. 5 Steam Generator Tube Samole Selection and Innoection - The steam nera or tube minimum sample size, inspection result classificat and t h* the corresponding action required shall be as specified in Table g* US] ,,
i- The inservice inspection of steam generator tubes shall be perfo tt i frequencies specified in Specification (OCEhand "he inanected tubes j shall be verif
'-W atio . ..
ptable per the acceptance crt".o r < a of en applying the excepu ons of {' I' _ i f.f f5<t. previous defects or imperfections in the area reps tnroug g g* g,y o -s ii.m ns ! not considered an area requiring reinspection. The tubes g g >4'g selected r each inservice inspection shall include at least 3% of the --- i total r of tubes in all steam generators the tubes selected for these - ._r inspecti s shall be selected on a random basis except: y i l . Where experience in similar plants with similar water chemistry indicates critical areas to be inspected then at least 50% of l the tubes inspected shall be from these critical areas. ! . The first inservice inspection (subsequent to the preservice inspection) of each steam generator shall include: All nonplugged tubes that previously had detectable wall
- penetrations (>20%) and i .
I CALVERT CLIFFS - UNIT 2 3/4 4-10 Amendment No. 190 i e
TeeIhiM'IIW} f CO i i i
- INSERT 5.5.9 INTRO J ff 2 ci 0 3 5.5.9 'Ihe provisions of SR 3.0.2 are applicable to the SG Tube Surveillance Program
( except as specified for individual requirements.
'Ihis program provides controls for the inservice inspection of steam generator tubes to ensure that structural integrity of this portion of the Reactor Coolant System is
=mir*=id ' Ibis program shall contain the requirements listed below.
4 O O
,ap /8 J 57
_ _ _ _ _ _ _ _ _ . _ . . ~ . _ - - _ . _ _ . _ . _ . . _ - . . _ _ _ _ _ _ _ . - _ _ - _ . . . _ . . . - . _ SdeIhie f Io^) Ta D i I/>se S'a s". 9 fIWL 5 oh 8 ) O Yk $ dA M hes>dfA {$hT 4. $wreI A^he fMf ^ M
- e SURVEILLANCE REQUIRDIDITS (Centtamed)
+ h Tubes in those areas where experience has indicated potential problems.
@ The second and third inservice inspections may be less than a full tube ins ction by concentrating (selecting at least 50% of the tunes to inspected the inspect' on on those areas of the tube sheet array and on t se portions of the tubes where tubes s
with imperfections were previously found. i "he results of each sample inspectioqJha11 sified into one of the Uv11 A 3three categorie gg ,g 1 Catenory Insoection Results i C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected i . tubes are defective. C-2 One or more tubes, but not more than 1% of l the total tubes ins c^ed are defective, or between 5% and 10% f the total tubes inspected are degraded tubes. [,I l C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective. 4to4e:(In all Inspections, exhibit significant p(>reviously 10%) furtherdegraded wall tubes must netrations to be included in thedLMEnareaa+=ae calcu ations. 1.4.5.1 Insoection Freauencies - The above required inservice inspections of steam generator tubes shall ne performed at the following frequencies:
- h. /. TheEffective first inservice inspection shall be performed after 6 Full Power Months but within 24 calendar months of ./
initial criticality. Subsequent inservice inspections shall be = performed at intervals of not less than 12 nor more than i 24 calendar months after the previous inspection. If at least 20 thepercentC-1 Category of the tubes wer)eorinspected (See Note if at leastand the results 40 percent of W were in tubes were inspected and were in the C-2 Category during the previous inspection, the next inspection may be extended up to a maximum of 30 months in order to correspond with the next refueling outage if the results of the two previous inspections ( / r
. ' NOTE: For Cycle an inspect of 15% of steam retor tube with ins tion resul in the C. ategory sh be accep e A#N l to ext d the next spection u o 30 month .o coincide ith
, the xt refueli outage. CALVERT CLIFFS - UNIT 2 3/4 4-11 Amendment No. 165 l pay e l'1 E 5 7
$te)hlCANCA) f $.O TpseY SS.1 l y 4 d-8. )
s . s .9 Ge Ge~ek HG) %de wa:/4sa Py l A.I -*w-amananmar-mem- ? = _ _ _ _ .. . _ .. - _ , - l were not in the C-3 Category. However if the results of either of the previous two inspections were in the C-2 Category, an ! engineering assessment shall be perfomed before operation beyond i - 24 months and shall provide assurance that all tubes will retain adequate structural margins against burst throughout nomal operating, transient, and accident conditions until the end of the fuel cycle or 30 months, whichever occurs first. If two l consecutive inspections following service under AVT conditions. not including tne preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection inte be extended to a maximum of once per 40 months. g,h , S., q t . If the insarvice inspecti n a steam generator conducted in accordance with Table .- at 40-month intervals fall in Category C-3. the inspe n frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until ubsequent inspections satisfy the criteria /,I of Specificatio . ,X }s the interval may then be extended to
^ - .
a maximum of once per 4Ymonths or 40 months, as applicable. 4 #.5. C. > O Additional, unscheduled inservice inspections shall be perfomed - on each steam generator in ac inspection specified in Table ance with the first sample the shut h _
- s subsequent to any of the fell ng Dns Q._ f. 9 -T)
Primary-to-secondary t originating from tube ube leaks to-tube sheet we](not including in excessleaks of the [h limits of specification .4.'6. ' ' y, fj
@ A seismic occurrence greater than the O s rating Basis / /
Earthquake, b () A less-of-coolant accident requiring actuation of the /A engineered safeguards, or
. A main steam line or feedwater line I' k)
The provisions of Specificatin o not opp y for extending
'/ the frequency for perfomine inservice inspections as specified in SpecificationsG.4/3.3.vand 11.
*!t #
h[ CALVERT CLIFFS - UMIT 2 3/4 4-12 Amendment No. 165 l f I b O pp 2od 67
$ffdop e Q ATo0/J V. O r,w.A s .c. 9 i o r .4 e1 l 0 g,7, g %.n Lei a (*- (uh TJe S&Va A P~q n
*/0.0 ; .asivn iv h ivii ava. r Q
-4UavuuAmeetrotmti,w...; 3 ;; ..?
-4:4/5:4 decentance criteria 3 As used in this Specification:
- 1. Tubino or Tube means that portion of the tube or sleeve which foms the primary system to secor,dary system pressure boundary.
- 2. Imoerfection means an exception to the dimensions, finish or l contour of a tube from that required by fabrication drawings or specifications. Eddy-current testin 20% of the nominal tube wall thickness,g indications may if detectable, below be considered as imperfections.
- 3. Decradation means a service-induced cracking, wastage, wear l or general corrosion occurring on either inside or outside of a tube.
- 4. Deoraded Tube means a tube containing imperfections 3,20% cf l the nominal wall thickness caused by degradation.
- 5. 4 Deoradation means the percentage of the tube wall thickness l l affected or removed by degradation, i
- 6. Defect means an imperfection of such severity that it exceeds
' ' , the plugging or repair limit. A tube containing a defect is defective. Any tube which does not permit the passage of the l eddy-current inspection probe shall be deemed a defective tube.
- 7. Pluccino or Reosir limit means the imperfection depth at or beyond which the tube shall be removed from service by pit ling, or repaired by sleeving in the affected area be: ise it may become unserviceable prior to the next inspection. The plugging or repair limit imperfection depths are specified in percentage of nominal wall thickness as follows:
- a. ori gi nal tube wa11. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40%
- b. Westinghouse laser welded sleeve wall............. 40% 1
- 8. Unserviceable describes the condition of a tube if it leaks l or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c. above.
- 9. Tube insoection means an inspection of the steam generator l l
tube from the point of entry (hot leg side) completely around l the U-bend to the top support of the cold leg. - CALVE 8ti CLIFFS - UNIT 2 3/4 4-13 Amendment No. 190 rge al Jr 57 1 l l
- . - - - . . - . . - . _ . . - . - . . - . . - - - . - - - . - _ ~ . - . . . . - . - - -
$N f 'O $oO l? 4 of 8 )
O . 3/4.4 " C ^: r " " _._____ j J ai EE-- i- C _;a i 3-
- 10. Tube Renair. refers to a process that reestablishes tube serviceability. Acceptable tube repairs will be performed by the following process:
a) Westinghouse Laser Welded 51eeving as described in the orts WCAP-13698 Revision 2 groprietary Westinghouse Laser Welded Sleeves for 3 Rep /4 Inch Diameter Tube ' Feedring-Type and Westinghouse Preheater Steam Generators Generic Sleeving Report." April 1995: and WCAP-14469 *$ cific Application of Laser Welded 51eeving for t Calvert C1;ffs power Plant Steam Generators," November 1995. i S.T,9.c$- l Tube re air includes the removal of plugs that were - previou ly installed as a corrective or oreventive measu l A tube inspection per SpecificationLed.34.fis required ! prior to returning previously pluggedFtunes to service. . (TIE,ses== __ tt - e.11 L M e- r S r]after completing the correspondi actions (plu or repair all tubes exceedi the plugging or reps r limit and a 1 tubes containing through I cracks) required by Tabl a. QQQl'A Followin each inservice'QQ~ction inspe QC
- of stas Jj t~kY genera or tuber,-the -
number o tubes p ugged or repaired in each s rator shall be renorted to th Commission within 15 dayv uan l } GD AFR 30 9---- -- l
- b. The complete results of the steam generator tube inservice inenartion.during the report period shall be Wi++ad to the >
efindnMsmpprior to March 1 of each yea (pursuant ta'10 CIA 50,4D
/ Ttis report shall include:
- 1. Ihamber and extent of tubes inspected. ,
i 2. Location and percent of wall-thickness penetration for each - l indication of an imperfection.
- 3. Identification of tubes plugged or repaired.
- c. Results of steam senerator tube inspections which fall into Category C-3 require verbal notification of the NRC Regional Administrator by telephor.e within 24 hours prior to resumption of plant operation. The wi ttten followup of this report shall '
provide a descri tion of investigations conducted to determine cause of the tu degradation and corrective measures taken to i 1revent recurrence and shall i,e 13mitted within the next 30 da l
* (!!OU*/b,W PY _
f ' t CALVERT CLIFF 5 - UNIT 2 3/4 4-14 Amendment No. 193 l esf/tillnnce (OMp Ic%- & lt**M Y w h N g, j G,an %~~ u mc4 .
O . O O i i t g TABLt M # NIND WI N W WER OF STEJBI asura4 TORS 75 K
- respecite sein assavict impecTim O
.h, mD 3
Presenice Inspection No Yes I 3 No. of Steam Generators per Unit Two lThree l Four Two Three Four First Inservice Inspection All One Two Tm [ _ Second & Subsequent Insenice Inspections One' One t One' One' j g h m w m w i) 24 y
- P g t-- <
> v b "
D TABLt WWTATIN : k
^
N
-4 8
The insenice inspection may be limited to one steam generator on a rotating schedule g encompassing 3 N % of the tubes (where N is the number of steam generators in the plant) if the % > results of the first or previous inspect'ons indicate that all steam generators are perfoming in k a y a like menner. Note that under some circumstances, the operating conditions in one or more steam y , 5 generators may be found to be more severe than those in other steam generators. Under such a circumstances the sample sequence shall be modified to inspect the most severe conditions. ( 3 8 The other steam generator not inspected during the first insenice inspection shall be inspected. g The third and subsequent inspections should follow the instructions described in 1 above. n 4 es
<@*b g 3 Each of the other two steam generators not inspected during the first insenice inspections shall t1 h m be inspected during the second and third inspections. The fourth and subsequent inspections b b!
g shall follow the instructions described in 1 above. g, o w _ s S T 1: u p! Q O
- - . . . - - . - - . - . - - - - - . - - - - - - - - . . - - . - - - - . . - - - - - - - --- ~ - - - -. - - . ~ - . - - . - ~ . .
' i l
+
suec.rk--2 .' N Q l sma ====am not moreCnes -2
;g se 4 151 asserta m uaum aus asserst .-. - saan ine _ a -- isuus action nequires E l mesult actlen siegatres mesuit E sempie aire inesult action negrires WA WA WA WA h M n einssuna of a suces per 6-1 6-z mene rius or repair sevective 6-1 suene WA wm 3 Q SG.
tubes and inspect 6.z rius or repair 6-1 suene addittenal 25 tubes la defective tubes and Fimp or wr. h , this SG. Inspect.eddittenal e5 tubes in this C-2 defectfwe tubes
$* 56. Perfere actten C-3 for C-3 result La r* of first semple FI i 6-3 rm - ectien for
%1 C-3 result of first WA WA g %
unple > q 6-J inspect ein tunes in mis etner aus i this $6. plug er repete are C-1 leone WA N/A O ' M defective tubes and Inspect 25 tubes in each g
- other $G.
6 9 une mes 6-z ,. . N' 24 heer verbei nettffcatten to IK irith but ne ection t-2 reselt of for R/A N/A iM
- medittenal second semple arttten fellemum purseent to . SG ore C-3 -
l D -J) lissettenal inspect es - . V 3G is C-3 In each 3G end plus f /e rre b N A er repete defective R/A N/A p* g,9g tubes. 24-hour verbal Isotf ficotten { to ist erith written
, l T
W -
$ = 3 h lihere 11 is the nuiter" of steam generators in the unit and n is the nus6er of steam generators O
[ o inspected thering an inspection k,
, $ 2.
l %. ,
" h-bi t
~
t i N o i
Sp cir., 4..- 5. 4. i 4 1 l O l
,.+
~ - - a s st t/' ' M REACTOR C00LAlli SYST 45 WAGE-3,434
@kaneDetection$rstem]s
! umrrma.m.g ==T= l y,g 4 0.4. , . - The following Ret.ctor Coolant System Leakage Detection Systems shall : b ta tuosphere particulate Radioactivity Monitoring System s- _ L,l n.4. Mnment Sep Level Alam System, and
/. t itumentAtmosphenGaseousRadioactivityMonitoringSystem)
APPLICABILITY: IWDES 1, 2, 3 and 4. ~~ O l C.O 3.04 4 wol o ppl <<.bre O' ~ 4:_
- )
A@g3 a. only two of t above requi Leakage Detecti for up to 30 day rovided Systems]b L q.* " g'P la 9 ERABLE oper n may conti a s les of containment sphere are obtai d and ana ed e per 24 hou n either the or d. O tred Gas at east Ob partico e Radioactivi Monitoring Syst s inopera i (Ce . E, f% othe e be in at 1 t 30T STAIS8Y wit the next hours i*g9,c4..y 7n i SNUT90lAl wi in the following hours. f T D,,'b ] %. With only one of the above required Leakage taction Systems be 2 2 OPERABLE, operation may continue for up to 4 da q vided that: A. g ~2 rak samples of the containment atmospher tained and j analyzed at least once per rs
* / The Reactor Coolant System inventory balance o
- h* I J Surveillance Requirement '.".5.2.; is perfomed at least once
- per 24 hours. S R 3.4.15.I P,
A , M.. m " 7 / Othemise be in at least B0T STAlesY within the next 6 hours and A. g .8 . in EOLD $ NUT 90l01 within the fo11_owing 30 hours. en 5l IIkNr.t e /w r d* U'A ~ ~ l tort .' op,r,+
/* s rbe ,;ro)y d.h fPfy==-
l Ac _=_ = --- AeTim D. Au "b"" O . 4,,- ' g ,,,
* **d*, s i' ap j g ( ~M abY CALVERT CLIFF 5 - LillIT 2 3/4 4-17 Amendment No. 165 1 O
fage lA5
5 p- eI e , .'4. '3 4 . t 4-l i l O A.\ 3/4.4 REACTOR C00LAlff SYSTEN SURVEILLAllCE REQUIREMENS STs -- 4. 4. 6. i The Laakage Detection Systems shall be demonstrated OPERABLE by: l I* i 8 *- l T. Containment Atmosphere Gaseous and Particulate Monitoring 3 4.14.2 Systems-performance of CIIAINlEL CllECK. CNAlglEL CALIBRATICII and 5.d. 84.5 CnAlalEL FilllCTI0llAL TEST at the frequencies specified in Table 4.3-3, and h Containment 5 Level Alaru System-performance of CRAlglEL 3* 4 ' l +* 4 CALIBRATICII a east once per REFUELIIIG INERVAL. l I r l l CALVERT CLIFFS - UNIT 2 3/4 4-18 Amendment No. 186 l. O py 2.F f
j $ pecS. ,.+... 3.4.t'5 I i 1 O i i 3. + h aM:+ mEACTOR COOLANT SYSTE[d C.M) _ 3/4.4.; REACTOR C00LANT SYSTEM Q AKAGE 7 - _ Y_' ' '_- l 3, 4, g J _ I LINITING Com! TIM FOR OPERATION b p"' *_'h* L.- c o
'3.4.13 3.^.^.2 Reactor Coalant System kage shall be limited to:
- a. No PT-
- F ,SOUWARY LEAKAGE, I b. 1 GPM WIDENTIFIG LEAKAGE,
@g. 1 Spaters andgallons-per-day through any one steamotal prn +a ==
A' en 100 j nerator, and i @ A . 10 GPM IDENTIFI G LEAKAGE from the Reactor Coolant System. APPLICABILITY: N00E5 1, 2, 3 and 4. vmv ACTION: $_ l A e m ocJ g With any PRES $URE BONDARY LEAKAGE, be in at least NOT STANDBY
- g within 6 hours and in COLD $NUTDetAt within the following i 30 hours.
4 M CT'Og
- g. ith any Reactor Coolant System leaka e greater than any one of the above limits, excluding PRES $URE Y LEAKAGE, reduce the A leakage rate to within limits within 4 hours s.r be in at least i Acrmy SNOT STAND 5Y within the next 6 hours and in COLD $NUTDelRI within g (the following 30 hours.
4
$URVEILLANCE REQUIREMENTS i
4.4.6.2 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by: 1 1 Ct&- teosphere particul i 1. ring the containee or gase)s j L_ dioactivity at less oer 12 hours. er I a i' j 2. With t aseous and par culate monitors i rable, j cond a ing the contai rdance with t nt atmosphere grab ample analysis i ION requiraments Technical
*g i I
- L___ pecification 3. . .I. t i
i CALVERT CLIFFS - UNIT 2 3/44-19 Amendment No. 165 l
- O p o $, l oI 3
5 re .c.,.a .. , 3. 4. i 3 ] l i i l i I i 3/4.4 SEACTOR C90LAllT SYSTEM l
$URVE!LLAllCE REQUIRDIElff5 (Continued)
Ib. Monitoring the co nt sump C1 arge frequency at Jeest once 12 hours, he Containee Sump Level Alars)fstem is / e i [ nantg, , SR r2% w-w- tw Ruetor cooiant sat. ter ink.oe at ienst
- 3. 4 85. l [once per 72 hours (iiring steady staD operation)and t least once
.4.s.l.D.
/ 1 per ze nours wnen reguirec Dy Am ept when / .
/ . gl I operJWng in the s)hdtdown coolin e, and /
5'v4 %*"TlN"'t :0*M*ll'l.oW""' "*P"'9" O sa
- 2.4,rs.1 & v,,. r Y sc.4.s.
w3.4'l .,,,om.4 . e.n--~+~c ws+% A * & witk de 54- = m G. e , s 4 e Tebe o , ,,, ,,,4, , 7,9 So,ve,ti-e< Ps 3, . L ,v,.H.,,< > Po esr- m
- O O
-A
' - - idoie _ Uel ce q u. e ral 4o Le g o , (.o rm ed s,d /
/2 f. ~ . .r a f4e a ,l., L ):.r l ,,,, & L'2-of 4 a ., e4- . p,, o . +
) l 1 1 J 1 i CALVERT CLIFFS - UNIT 2 3/4 4-20 Amendment No. 165 l l p y 1 oC 3
.____._m_______ .._ _ _._ _. _ . . _ _ _ _ . _ _ . . . _ _ _ _ _ _ ._ ___ _ _ _ _
CTS 3 /4. 4.7 1 0 ! l REACTOR C00UlllT SYSTDI N3/4.4 3 .4.7 CHEMISTRY C M DITIM FOR OPERATION 3.4.7 Reactor Coolant System chemistry shall be maintained withi the limits s ified in Table 3.4-1. APPLicABILI - At all times. M , IIIDES 1. 2. 3 and f
- a. With any or more chemistry parameter in cess of its Steady i
5 tate Limit t within its Transient Limit restore the parameter l to within its toady State Limit within hours or be in at 1 east NOT ST Y within the next 6 and in COLD SMTBel01 within the fell ing 30 hours,
- b. With any one or no chemistry par ter in excess of its Transient Limit, be at least T STAIE18Y within 6 hours and in l COLD S M TD0lAl within fell ng 30 hours.
i IEIDES 5 and 6: With the concentration of et l Coolant System in excess of ts chloride or fluoride in the Iteactor eady State Limit for more than i 24 hours or in excess of s Trans ont Limit, reduce the pressurizer i i pressure to 500 psia, applicab . and perfom an engineering evaluation deterni the effects the out-of-limit condition on i the structural integr y of the React Coolant System; detemine l i that the Reactor ant System remains cceptable for continued operation prior to nereasing the or prior to proc ing to IIODE 4. pressu zer pressure above 500 psia I SURVEILLAllCE ItDIEllTS 4.4.7 The actor Coolant System chemistry shall be date ined to be within t ' limits by analysis of those parameters at the f vencies spectft in Table 4.4-3.
/
l CALVERT CLIFT 5 - UNIT 2 3/4 4-21 Amendment flo.165 l !O CP O
- . - _ _ _ . . _ = . - . --_ _. _ -. . . . _ - . . . - -
CTS 3 / 4.4. 7 O
@3 3/4.4 REACTOR C00UWT SYSTEM TABLE 3.4-1 REACTOR COOLANT SYSTEM tilDGSTRY LIMITS
! STEADY STATE TRAlt$1DIT P LIMIT LIMIT D1550LV OKYSEN* $ 0.10 ppm 5 1.00 ppe
- CHLORIDE 5 0.15 ppa 1 1.50 ppe FLUORIDE 5 0.15 ppe 5 1.50 ppe O
/
- Limit not applicable with T.,,5 250*F.
CALVERT CLIFFS - UNIT 2 3/4 4-22 Amendment No. 165 l r,2.n
c.T 5 'T [ 4.4. 7 3/4.4 REACTOR COOLANT $YSTEM i TABLE 4.4-3 REACTOR COOLANT SYSTDI GDtISTRY LIMITS SURVLILLANCE REQUIRDIDTS , I PARAMETER ANALYSIS FREOUENCY , D1550LVED OXY N* At least once per 2 hours CHLORIDE At least once r 72 hours - ! FLUORIDE At least one per 72 hours ; 1 l l l O l l l l
\
l Not required with T , a 250'F. CALVERT CLIFFS - UNIT 2 3/4 4-23 Amendment No.165 l r O l l pSe3oF3
. __ __ . _ ___ __ - _ _ -. _ _ _ ...._. _ . _ . __ _ _ _ _ _ _ _._ - ~.. ___ _
sMen 3.4 15 i 1 3.4 @ REACTOR COOLANT SYSTEM { 3,4,fg M h PEC1FIC ACTIVITY j LIMITING CONDITION FOR OPERATION t.co ,y,ff @ The specific activity of the primary coolant shall be limited to:
- a. 1 1.0 pct / gram DOSE EQUIVALENT I-131, and
- b. 1 100/I pC1/ gram. ,
APPLICABILITY: MODES 2, N AU.12[
,kb~ f yIDDJfl. 2 antM')
A With the specific activity of the rima coo nt > r.1 C1/ gram DOSE EQUIVALENT I-131 but within t e all ab limit (b ow and ACf/*M to the left of the line shown on Figure _. operation may
/). continue or u to 100 ou s i gio tyr o ..-
[aneratina tibhe provisions of Specification 3.0. are
/4cf/*# A -- e t applicable. f JYeff
'h. With the specific activity of the primary coolant > 1.0 pC1/ gram O AW DOSE EQUIVALENT I-131 for more than 100 hours during one continuous time interval or exceeding the limit line shown on Figure be in at least NOT STANDBY with T,., < 500'F 8 within 6 ours. 3,4, ,y,,
's. With the specific activ'ity of the primary coolant > 100/I AC178d C1/ gram, be in at least NOT STANDBY with T.,, < 500'Fw . ithin G- 6 hours.
, 2, 3 / and 53 K With the specific activity of the primary coolant > 1.0 uti/ gram DOSE EQUIVALENT I-131 or > 100/l pC1/ gram,ffform the sa 1
'g pnu sDslysis requi.dsi.isf 1Eem e a) c1 we A. A.A unt4 km2 j4- sna#fie activity of tWorimary coolantAlfresto@ to within T its limits.
p e,& D60 $ ~'] wJL;. fy. %.4,4f'l C A th T > F _. mso to Ap 44 #i CALVERT CLIFFS - UNIT 2 3/4 4-24 Amendment No. 193 O nw
- - . - . - ~ . - . ~ . . . . . . . - . . . . . . . - - _ - - . . _ . . . . - . - _ . - . .
- . . - . . ~ - . . . - - . - . . . . . . . . .
WSsbk 3.f. / 5 1 i. O a 6 REACTOR C001Alff SYSTDI
$URVEILLAllCE REQUIRDENTS g g p The s ific activity of the p mary coolant shall be setemnes To a within limits by performance f the sampling and analy program o A,/
j Table 4. 4. i < I l 2 2 O ; J 1 3/4 4-25 Amendment No. 193 l CALVERT CLIFFS - UNIT 2 O er v1
t 1 g TABLE 4.4-4 R* r-PRINT COSUWT SPECIFIC ACTIVITY SWLE AIS AAnLYSIS PROGRAM i 9 k* TYPE OF MEASEREMENT Aus AnnLYsts SAMPLE AIS An4 LYSIS FRE05ENCY ._ MODES IW ISICE S M LE AIB AMILYSIS REEBIRED
~
Q{) 3 * *. I L.. *2 , l y 4: Gross Activity Determination At least TE b . 3f 4- 3q. m $it - D b> S ^ b2. t Isotopic 4.ts. LAnalysis for BOSE 1 per 14 days - SR 3. 4. t C.') 5t. E451YALENT I-131 Concentration
- S" Radiochemical for I Determination 1 per 6 sonths*
Q 1 - y o.rp I L 4. 6 3 ea . Isotopic Analysis for Iodine M Once per 4 hours. 6 [ 2 Including I-131. 1-133, and I-135 whenever the 395E i
= Ad -a Eq5IYALENT I-131 wo T-w g 34,q 7 A exceeds 1.0 pC1/ gram. } Soo* p j
and (L M One sample between 1 2 and 6 hours N following a THENGL
't4.IS.'2 PeutR change exceeding 15 percent of the i y '
3 RATER TWENWIL PeutR
= within a one hour i g ,eriod. ,a !
w -n ta n reu - m .. ;t. :: ;t.. c F
.-,s., t;.;t, .c ta r. : ., m= :,..
l # 1e to be taken after a minimum of 2 EFPO and 20 days of POIER SPERETION have elapsed since [* i
.s ter was last subcritical for 48 hours or longer. * > S 3. d f>. X : ,
A
~
kle + c - -- g, 94 m..a ~;
'""" ~ ~
t. 1 gF90 ,4 -
.. c.. a . .,
2o 4 %
,, a oF n .,
Moosg 1 g
- 4 -.
o p - ~ 4. % L-ve. e< r ,J ,,m g. ,. ,,, . , g ,, g ut e.c -- --
> av _.
L. . .
$ 7..e Si 4.o v 3 4 I$
1 i 1 3/4.4 REACTOR COOLANT SYSTEM l ) L t 5
- w 350 ,
,o I i d
k 1 6 1 ' k 1m s j 200 i k i n .____ l
- ' IMAOCFFAB12 -----
, l
- t crERADON ,
- ::: )
- s ;
't !
'i i l 160 s i
- n, ;
L i i t a
% l k 1 1 1 1
! 100 i k l t g % , t - AccErrAnus ' ' ' OPERADON ' i
,o i
i 50 4 4 i I O 30 30 40 80 00 10 30 ' 30 100 I PERCENT OF RA'un'rsn-a. POWER naar ...._-. 4 . t 5 -3 , A. i 905E EQUIVALENT I-131 PRDIARY COOLANT SPECIFIC ACTIVITY LIMIT VER$US i PERCENT OF RATED THERNAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY ! *1.DuC1/GRAN BOSE EQUIVALENT I-131 4 t CALVERT CLIFFS - UNIT 2 3/4 4-27 Amendment No. 165 l i I f)* ko $ 1
- ~ - -- - ----- -- -- - - - - - - - - - - - -
3pec s C. e d + o s '5. 4 3 !O A. 1 i 1. 4 -w.* =Ac= eMunt ==GRciD , ~3.4.5 x ,. . '76 t*'/ TEMPERATURE LIMITS i m _ - = = l f LIIGTING COWITIM FM OpDATIM 3.4.9-1 --a 3 4 9~- Q i L.c. O g LA.I ! SerDrt The Reactor Coolan ystem S ::;t & ;-::r i temperature 3 '3 j Q i - j and pmssum,sp((bg }in ,ed in accordance with the limitjines shown on i ! U. 9*". . '. .. ;. _u..._ 1.,,: . . .. r. . . a___.m. _._ n- ~n c~ ' - - - - ' - ' ~ ~ ' -, - - j l b. A anxime heatup of: l I l Maximum A11owable Heatus Rate RCS Temperature 1 j 30*F in any one hour period 70*F to 156'F j 40*F in any one hour period > 156*F to 246'F A, 7 60*F in any one hour period > 246*F ; l ^
- b. A anximum cooldown of: .
i Maximus Allowable Cooldown Rate RCS Temperature l 100*F in any one hour period > 200*F 40*F in av one hour period 200*F to 176'F O 15'F in any one hour marind < m er - t C. O fl A maximum temperature change of 5'F in any one hour period,
's.43 during hydrostatic testing operations above system design i No1E pressure. l APPLICABILITY: At all times. ,
hm.d With any of the above limits exceeded, restore the temperature l n or pressure to within the limit within 30 minutest perform an A.t (encineering evaluation tejyiimr-ine sne siivus susne sus-vi-unisx y S e.a8 - f on en sne Tracture__Mehness crecertian afthe emaeter Coolmfit/ A .2 pgdetermine that tne Reactor Coolant System remains acceptable for t nued operations or be in at least NOT STANDBY within the next 6 hours A efr** - and Mduce the and pressure to less than 300 psia. A ri r" . .;,, hin foi n 30 hours. _ 735_NMS)- b N O C . .es . 4 . .., A w ore; R p.,.a Ae4.. - A.2 su n he e .- o s wJ w t, . ,, < <. I . - - -_M\ kt_C..=J,4... is ce4 ,.d IIbSE 6I E CI'O'J C CALVERT CLIFFS IUliTT 2 - 3744-28' Amendment No. 178 O ry i .m s
S p a e .'F '. , 41.- 3. 4 . 3 INSERT ACTION C C. NOTE C.1 Initiate action to restore Immediately Required Action C.2 shall be PersTe.(s) to within cosapleted whenever this limits. condition is entered. AER Requirements of LCO not met C.2 Determine RCS is Prior to entering MODE 4 any time in other than MODE acceptable for continued 1,2, 3, or 4. operation. l l
%y 2 .F 5
-- - _ ~ - . . . - - . - - . - - . _ - _ . .. . . . - - - . - - .- -- . ..
l Ip ec I.ca +,oo 3.4.3 l 1 4 O 1 1 l i 58RVEILLAllCE REQUIRDIENS 4 A.i SR
-4.0.0.;.; The Reactor Coolant System temperature and pressure shall be 3.4.3. ) determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations. l
- I.4.9.1.2dhereactorvessel 4 erial irradiation sillance specimen l shall 4emoved and exami to determine chang in material proper es.
tred by 10 CFR Part . Appendix H. The suits of these L*3 - as nations shall be us to update Figures .4.9 1 and 3.4.9-2. j l i 1 a , i iO CALVERT CLIFFS - UNIT 2 3/4 4-29 Amendment No. 165 l O r p .e 5
h (>*C 4 @ s (01'04 3 4. ) j 4
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w/ 1 i A.I i 2500
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q .::=[ Q:g2 -+t-.- . -:.r.. -.g-- 4pc 7_. . . . .,.,.. .y W -# 'i T"" lT1hL M _E".-6 - ' I"1500 =: 4 -- - --# i.;;_p
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Eph::!: : ET $#l$.aaeg,.ggseo7gHR 500
- m b N M i M i~8 #
U 74 g---e r .E.(( -e w h 75$iIn$irim'Nh IT rmrnur.;.1nrmIt T - EN[d - N' "* l h:':=p IM' sis *ssunsI:== e : M.._-k 'l_ r
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M... : esiscop-m,DE = .==. A-anow r .
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0"~*.
' " 5' i RE la "i - - " u 'm O 100 200 300 400 500 000 INDICATED REACTOR CODE.KM YsMPERATURE, Tc, 'F 4
J w:=-
- 3. + 3 - 1 FIGURE ?." 55 A* I CALVERT CLIFFS UNIT 2 NEATUP CURVE. for FLUENCE S 4.0x10" n/ca' l REACTOR COOLANT SYSTEM PRES $URE TEMPERATURE LIMITS i
CALVERT CLIFFS - UNIT 2 3/4 4-30 Amendment No.178 p ), +oF (I
hubcairen 14/5
*--*""""'"-** A.t 4
2500 . . _ _ _ _ . . _ ._. l 2 -.---9 r - - - ' '
- : r =9-- -t- .. .
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1 Fr=esmnori n==== _ -- _ z - c- + +' -
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^
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. 1500
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. 7.
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e- e. . , - ; o 0 iFt5f$ 3N$k khh.Eh. 100
- . . . .l..
200 300 400 500 soo I INDICATED REACTOM COOLANT TEMPERAN Tc, 'F FIGURE % 4.rs E~ 3 .4 3 - 2. Q' CALVERT CLIFF 5 UNIT 2 C00LDOW CURVE for FLUENCE s 4.0x10" n/cu' l REACTOR C0OLANT SYSTEM PRES 5URE TEMPERATURE L MITS CALVERT CLIFFS - UNIT 2 3/4 4-31 Amendment No. 178 O V p.3e 5 or 5
3 CT5 3 / 4. 9. 9.2 lO
.\
\ 3/4.4 REACTOR C00LMT SYSTM
! /4.4.9 ptE15URE/TEW ERATURE LIMITS I Pressurizer mm _
.0. m . . . _
! 3.4.9.2 T pressurizer temperatu m shall be limit to: f a. A num heatup of 100*F in any one r period,
- b. A anzi cooldown of 200*F in any hour period, and 3
- c. A maxis m s water temperat differential of 400*F.
APPLICABILITY: At all t s. f
$113: With the pressurize t reture limits in excess of any of the
- above limits, restore the tempe ure to within the limits within l 30 minutest perfom an enginee aluation to determine the effects of i the out-of-limit condition he f ture toughness properties of the i pressurizer; detemine that he press
' continued operation or be at least zerSTA re. BY mains acceptable within the next for 6 hours ! and reduce the pressuria pressun to les than 300 psia within the l following 30 hours. } i l SURVEILLANCE IRWENTS i 1 j 4.4.9.2 Y pressurizer temperatures shall be detemined to within the ! 4 limits a east once per 30 minutes during system heatup or coo . The i spray er temperature diffemntial shall be detemined to be wit the ! limi . t least once per 12 hours during auxiliary spray operation. 4 i l i s l / 1 I i I l J i I l i j CALVERT CLIFFS - UNIT 2 3/4 4-32 Amendment No. 165 l !,O h j page IJ l 1 i
. - ~ - . _ _ - - - - - - . . . . - - . - . - . - - - . - . - - - - - . . - _ _ - . _ . . -
d l $ g>. S. ,= %e w 3.$.I2
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t l l lO i 5,+ g m,0. mem coun mmrCRh
- = =
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- 3. 4 . I'l M p , ,, 4 , . a. . . , (.L T OD) $ w 4.-
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A. L. Top %.+- s ul i,, oPF unt E 1 i ,% .,~,..c 64052 c c. sie 1 i LDt! TIM COWITION FOR OPERATIM
,e , , , . . .a. m% = -
1 l __
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! 'f. .".'. t '. '. -f. .; ;. x,. _ ::Z. ; :^ ^! ^^ ::' ~ - ~ ^ 1: i'.' b Zt ; ! tco g.4.. i '2 [""'$';2--'r
; " ~
22' 4 h"[ en e r i J. Two power r reitefvalves( h a trip i setpoint ow the curve in Figure _ with their . j associa valves open, or - u th a trip setpoint belowfe.-e, l J. A sing th curve ire . a j Figure with its associated block valve open ind a Reactor oo' ant System vent of 11.3 square inches, or e. j f. A Reactor Coolant System (RCS) vent 12.5 square inches. ! I.b hi ressure safety injection (HPS!; s8 shall be l disabl y eithe ving (racking out r motor circuit i breakers from t electrical power sup J circuit, or by lockin j shut their di arge valves. LA I i
- c. The HPSI p actor operated val (MOVs)'shall be prev ed !
l from a tically aligning HP pump flow to the RCS placingj thei ant' switches in null
- r r-* & ]
j l 't g_more inan one OPERABLE high pressure safety injection pump . I d u . = :::n = e' ;;; ;. ;. - . . ;- - x;. . ... , .. _ _ _ ;_ . -'--t "; ' t: tt *** ::d ".x ::rf. it must be under manual L L A. i f' control and one of the following restrictions shall apply: L C.o 1. The total high pressure safety injection flow shall be ! - limited to 5 210 gym OR t tsJ.4 e l l l 2. A Reactor Coolant System vent of a 2.6 square inches shall 4 exist. ' L- A . I
. When not in use, the above OPERABLE HPSI pop shall have its handswitch in pull-to-lock.
j A9P ApPLICARILITve "- . 07; *** Oz;_, .^,.;7; '; ; ",0;". ;;.[he _RC$ j g van l { N ctr E N ((o < 5 square inchle_ e.,fo o g y gg -g j a,etJ f. .t s p. . , ,,, ,, , g
- l t c. o 163*3*) nom 5_4,5, d4.
- No't E '2 f When on shutdown cooling, the PORV trip setpoint shall De 5 4 . l Q Except when required fcr testinR, q._g ,3
} CALVERT CLIFFS - UNIT 2 3/4 4-33 Amendment No. 178 m <. t F 4 i
4
i f sp.c..f M .a 3.4.17 M\ lO 4 e-c..s,Jw. 7L, ./ A.J.* O W ka-k mf g as! 4th .Ae Se **4 j 3/4.4 REACTOR COOLANT SYSTEN ,Ar fm.n i LIMITING CONDITION FOR OPERATION (Continued) 7 A.[IHth one PORY ino rable in MODE 3 with RCS temperature < 301*F 2 } M*4 8 pr in NODE 4, r restore the-inoperable PORV to OPERIBLE status within days or de i ~ I
> 1.3 square nch vent within (s) pressurize the next 48and vent hourst the RCS maintain the through a i Acreov b ICS in a vented condition until both PORVs have been restored to l .DPERABLE status.
1 i A [With one PORV inoperable in MODES 5'or 6. either restore the i 4 eUg g pinoperable PORV to OPERABLE status within 24 hours, or depressurize and vent the RCS through a > 1.3 square inch vent (s)
- within the next 48 hours and maintain tee RCS in this vented Agry b , condition until both PORVs have been restored to OPERABLE status. ;
With both PORVs inoperable /depressurize and vent the RCS through
's. [a t 2 6 square inch vent (s) within 48 hours pnsinssin sne m.a in 1
! 44 #*8 5 . msu wn mon unm vun.. one vr - re PORV and a vent of l g 1.3 square inches has been established or both P0RVs have been J
- trestored to Spreamir statun a
- . An the eve altner Ene runus or the vent (s) are used to 1 mitigate RCS pressure transient, pecial Report shall j prepa and submitted to the Come sion pursuant to 10 CF 50.4- l 4 withi 0 days. The report shal' describe the circumsta es
- int ting the transient, the #ect of the PORVs or v (s) on vent ;
! l' th,nerence. transientandanycorrecKveactionnecessaryto l
% With less/han two HPSI pumps'Jinabled.muce at innat two nr 2
-- - un r . -- m mui r.to.incD withi fteen minutes e.. .
disa)N two HPSI pumps within the nex r hours. ) With one or re nrst icop riuvs' not preve te from automatical I aligning PSI pump to the RCS. inmedia ly place the MOV . 4/ i l handswit in pull-to-override or shu and disable the aff ed NOV or olete the affected HPSI hea flowpath with'in f i rements of
;hou ADA implement the action f
1 (Spe fications 3.1.2.1. 3.1.2.3. d 3.5.3 as applic e ow exceedin 210 gym whi suction is aligned to t 1
. ~ M1tn HP51 RWT and RCS vent of 2.6 squa inches exists, l
4.f l 1
- 1. distely take action to duce flow to less than o equal l
to 210 gpm. , i l i
- c m w e tet - .
j 3 CALVERT._ CLIFF, - UNIT 2, 3/4 4 34 Amendment No. 193 i 4 2. i & l ( A f oe *
- w t. N!sZ pues AJ c d ;.Je se4~ 4 w & Sm= * *I%
I sordk J hiedy 1,.h +(, e m;~.m of w #4 { k ny t'4 m d4 of Air J'*p l} & $U 4 L - . - - .. . . _ _ ..
$ pec.C. e.4.W ~5. i . I '2, I
} l $ 3/4.4 REACTOR C00LAlff SYSTEN i i LDlITING CSSITIN Fet SPERATICII (Continued) J ' f 2. rify the exc above the ve flow conditi allowable pres not raise for the given ] i temperatu Figure 3.4.9-1 Figure 3.4.9 2. A-
- 3. If a sure limit was , take acti n accordance
( with cification 3.4. . J.. *h; 7. ;. 0 ;;;;; -' * --* *' et' : ! ^. 0 ;- : ^ g-? '- "- Q __ No4
~.
. a t ., . "
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j 4. L p . r.. .d a. i2 L . 5 l e f + "' 4 -'^ ' -
** o $ R C.5 "T". W 6 3sso p )t i SURVEILLANCE REquI - _ ~ _ k. -- ---- -. -
4.4.9.3.1 Y shall be demonstrated SPERABLE by: I N a. erformance of a CRAlglEL FUNCTIONAL *ka samv actuation 3 4.l~2.4 ekann.1 but emeludina valve Giln days priorp tester)(a conditiairin which t _ 1s . _ red SPERABLE - .
- es men . r. u y. 6. . ..uvr . .. um rum is required i GPERABLE.
! 6. performance of a CNMNEL CALIBRATION on the PORV actuation l 5 .82 5 channel at least once per REFUELING IllTERVAL. l t 54. 3'4*g*3 c. Verifying the p0RV block valve is open at least once per 72 hours l when the p0RV is being used for overpressure protection.
- d. -T ng in acco ith the in cation 4.0.5 w %s test requirements)
-[ g l rsuant to Spe
' Y The RCS vent shall be verified to be open at least once per a, 4
- q * )
1 4.4.9.3.) 12 hours w hen the ventis being used for overpressure protection. f4.4.9.3.3 All high pressure safety injection pumps except the above
; PERAS _ all be demonstrated inoperable at Ioast once per 12 hou]rs
, y verif gt the or circun ors rs nave seen - . ;;; irw ru s r -- i lec al power su circuits or verifying t discharge ves are A, i 1 ed shut. T tomatic opent esture of t igh pressu safety g ,_ ja-Haa 1aa Vs shall be w find disabl least onc r 12 hou ve its ha itch in pu 3 'M 'l :The above OPERABLE pop shall be verified) Q.e;'.;tleastonceper12 hours. l i Ver. F y = . , . .
% .,r om, ypg, c' ~ o 4 e - e - b i .e . .r . y.w g
- q "4 % DC5 .%e. p., s '2 t, ,, , , ,
3, q, ), q Except when the vent pathway is locked, sealed, or otherwise secured 1 in the open position, then verify these vent pathways open at least j Q *d p, , once per 31 days. 1 } CALVERT CLIFFS - Ull!T 2 3/44-35 Amendment No. 186 i E i l-9y s .c +
. .. .. -.. ~ - . ~ . , . - . _ - . . . . - . - . - . - . - . - . - . . . - - . . - ~ - - . . - . . _ . . _ . . . .~.-..a l l
., I f b#& 8' ***4 awe 3,4,\] I T 1 i 4 i 4 I I
- 1 4
i k t - ) f 3see a i e 3 1800 i
. Sees nes uw. m mes. !
I l Sa'F 443 PSIA' ' I ee'F 443 PSIA i l i 17e*F S18 PSIA ! 1e4'? Se3 PSlA l [ ? 340 8'F 74e PSIA See ~a I 2 See% SSS PStA l se4*F 1:se Psia .I b ! 'e see see see see see ese i , i ACTUAL asActon cooLAuf Taaspanatung 1;,,*F j 4 j v-l ~5. 4 , 12 - 1 -( 4 _ _ _ i CALVERT CLIFFS UNIT 2. for FLUENCE 5 4.0x10 n/ca' 3 NAIDEIN PORY OPENING PRESSURE vs TEMPERATURE i j CALVERT CLIFFS - UNIT 2 3/4 4-36 Amendment No. 178 i 4 e 4,C+ p$ 4
- CTS ~5/ 4. 4.1 O. I
.l
{ i 3/4.4 REACTOR C00UWT SYSTEM l 3/4.4.10 STRUCTMAL INTEGRITY l ASME Code Class 1. I and 3 Camponents
- M COWITI M FOR OPERATIM i
j 3.4.10. The structural integrity of ASME Code Class 1. 2 and 3 esponents
- shall be intained in accordance with Specification 4.4.10.1.
- APPLICABILI
- ALLISDES.
l Ellgt:
- a. With t structural integrity of any ASME Class 1 componen s) not confoming to the above utrements, mstore the strue ral integrity of the affected es ;
its limit isolate the affected c nt(ponent(s) s) prior toto within increasing t Reactor Coolant Syst emperature more than 50'F above the sin temperature requi by NDT considerations.
- b. With the structur integrity of ny ASME Code Class 2 component (s)notc feming to above requirements. restore i the structural intog ty of t affected e onent(s) to within '
its limit or Isolate af cted component ( ) prior to increasing the Reactor at System temperature above 200*F. O c. With the struefural in component (s) not conf r ng of any ASME Code Class 3 the above requirements, restore the structural inte ity of th affectedcomponent(s)towithin i its limit or isol e the affect component (s)fromservice.
- d. The provisions f Specification 3.0. are not applicable.
SnifEI'LUNCE RE S 4.4.10.1.1 Th structural integrity of ASME Code Class 1, and 3 components 11 be demonstrated:
- a. r the requirements of Specification 4.0.5. and
. per the requirements of the augmented inservice inspecti program specified in Specification 4.4.10.1.2.
/
CALVERT CLIFFS - UNIT 2 3/4 4 37 Amendment No. 178 i O ry i .e 2
' l l i OS 3 f 4. 4. l O. I
- O !
l 3/4.4 REACTOR COOLANT SYSTDI ! SURVEILLANCE REQUIRDIDif$ (Continued) i n addition to the requirements of Specification 4.0.5. each Reactor Coolant flywheel shall be inspected per the roccamendation of j Regulatory LAnoust 197 .psition 7 C.4.b of Raoulatory Guide 1.14. Ravinian 1. i f4.4.10.1.2 Anamentednservice Insnection Feedwater Pinina /The unencapsulated welds Procrander Main Steam and Main ter than 4 inches in 1
- nominal diamet in the main steam and main ater piping runs loc.ted
- outside the tainment and traversing s y related areas or to
- atsd j comprtae adjoining safety related as shall be inspected per th) 4 4 followi eugnented inservice inspec program using the r,pplicaW l i rules acceptance criteria, and te r procedures of the A'RE Boi r and !
i ure Vessel Code. Section XI 983 Edition and Addenda th h Summer 1 l 1 . for Class 2 components. 1 Each weld shall be ined in accordance with t bove C IE Code N.I
- requirements, ext that 100% of the welds sh be examined.
- cumulatively. ing each 10-year inspection terval. The welds to j be examined ing each inspection period all be selected to i provide a resentative srvit of the nditions of the welds. If 1 these ex nations reveal watc6ptab structural defects in one or
{ more ds, an additional 1/3 of welds shall be examined and
- ins tion schedule for the re red welds shall revert back fa ,
i interval had begun. If itional unacceptable defects ' l [ detected in the second s ing, the remainder of the we shall l
- 1so be inspected.
I ?
/ bee C o .,c ., s s,,, .F
, c h Sa s For CL.p 4 .c 5. 0, l " AJ -m4, .4.W C,a , o k i t i i e 1 Reactor coolant pump flyuheel inspections for the first inservice 1 inspection interval may be completed during Unit 2 Refueling Outage
. No. 9 in conjunction with the reactor coolant pump motor overhaul program.
CALVERT CLIFFS - UNIT 2 3/4 4-38 Amendment No. 178 l O py 2J2
- - - . . . _ - - - ~ . . - - - - - - - ------ - - -
! Jm ed* sW. 7 l P*1e oari i i Q g. g. 7 :Rea v Cob Lp fig el byda P~y-M 27 ] SURVEILLAllCE REQUIRDENTS (Continued)
- m mo
} g4.Y.J#def
. _1 m.. i. u _ >--m_ a ... ,__
- Coolant I
/each Reactor ' f 9 '^ *" 354//
j tg f ion / shall 4.b of be inspectedide Regulatory per theRevision 1.14. recommendation 1, gj u.'de of ;g herf) E4.4.10.1.2 Feedwater pin AnamentedInserviceInsoectionprocramforMainSteamandMain]
< no - The unencapsulated welds greater than 4 inches in nominal diameter in the main steam and main feedwater piping runs located outside the containment and traversing safety related areas or located in compartments adjoining safety related areas shall be inspected per the following augmented inservice inspection program using tne applicable rules, acceptance criteria, and repair procedures of the ASME Boiler and Pressure Vessel Code, Section XI,1983 Edition and Addenda through Sumner 1983. for Class 2 components.
Each weld shall be examined in accordance with the above ASME Code requirements, except that 100% of the welds shall be examined, cumulatively, during each 10-year inspection interval. The welds to be examined during each inspection period shall be selected to provide a representative sample of the conditions of the welds. If these examinations reveal unacceptable structural defects in one or more welds, an additional 1/3 of the welds shall be examined and the inspection schedule for the repaired welds shall revert back as.if a new interval had begun. If additional unacceptable defects are detected in the second sampling. the remainder of the welds shall O' also be inspected. - l l Sec. D;:ces si * *) O Y y (f$ 3,'{. to 3 ' A Sin E cde cis s 1, 2, a! 3 dog.& 4 3 actor coo M p f1 el inspec ons for th irst inse ice inspectio No 91 conjunction ntery ma e complet during Uni 2 Refueli Outag th the re or cool nt ump motor ver
/ ['2 )
CALVERT CLIFFS - UNIT 2 3/4 4-38 Amendment No. 178 l' O Pgc /r if 57
I crs 1H . 4. ll 3 4 REACTOR COOLANT SYSTEM 3/4.4. CORE BARREL MDVEMENT LIMITING C ITION FOR OPERATION 3.4.11 Core ba 1 movement shall be limited to less than Amplitude Probability Distr ution (APO) and Spectral Analysis (SA) ert Levels for the applicable THE L POWER level. APPLICABILITY: MODE 1. AE10K:
- a. With the APD and/or exceeding t applicable Alert levels.
POWER OPERATION, may p caed provi the following actions are taken l 1. APO shall be measured a rocessed at least once per l 24 hours, ,
- 2. 5A shall be measu at least nce per 24 hours and shall be processed at less once per 7 s, and
- 3. A Special Re , identifying the se(s') for exceeding the applicable ert Level, shall be pre red and submitted to the Comuni on pursuant to 10 CFR 50.4 thin 30 days of l O b.
detecti With the D and/or SA exceeding their applicab Action' Levels, measu and process APD and SA data within 24 hou to detemine if t core barrei motion is exceeding its limits. ith the core bar 1 motion exceeding its limits, reduce the core trel motion t within its Action Levels within the next 24 hours o in NOT ANDBY within the following 6 hours.
. The provisions of Specifications 3.0.3 and 3.0.4 are not l
applicable. l CALVERT CLIFFS - UNIT 2 3/4 4-39 _ Amendment No. 193 i
- O
, ,. p
___.____m _ _ _ _ . _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ . . . . _ _ _ . _ __ J CTS 3/4. 4. l l 3/4.4 REACTOR C00UWIT SYSTDI htytILLAllCERggurtDIDf75 4.4. Routine iconttorino Core barrel movement shall be det ined to be less n the APD and 5A Alert Levels by using the excore tron detectors to meas APD and SA at the following frequencies:
- a. data shall be sensured and processed at att once per y
- b. da hall be measured and processed least once per i
I l l 0 - l l I 4 CALVERT CLIFFS - UNIT 2 3/4 4 40 Amendment No. 178 l I
- O i
p Se "2 . P 2
(T5 3) 4.g,Iq_
/4.4 REACTOR COOLANT SYSTDI 3/4. 2 LETDOWN LINE EXCESS FLW LIMITIIIG ION FOR OPERATICII 3.4.12 The bypass we for the excess ow check valve in the letdown line shall be closed. ,
APPLICABILITY: MODES 1. 2, nd . i 1 ACIIDR: With the above bype va open, restore the valve to its closed l position within 4 hours or in at t NOT STANDBY within the next ! 6 hours and in COLD within the 11owing 30 hours. I
~
l
$URVEILLAllCE QUIRENDITS ,
4.4.12 he bypass valve for the excess flow check valve in t etdown line all be detemined closed within 4 hours prior to entering E4 f MODE 5. O l l , CALVERT CLIFF 3 - UNIT 2 3/4 4-41 Amendment No. 178 I i iO e_y ioi
i c T5 3l1.4 13 I !V . 4.4 REACTOR COOLANT SYSTEM j 3/ .13 REACTOR C0OLANT SYSTEM YEnTS LIMITI CONDITION FOR OPERATION d 3.4.13 One actor Coolant System vent path consistir.g of two sole id valves in ser s shall be OPERABLE and closed at each of the fell ing ! locations:
- a. Reactor essel head j b. pressurize vapor space APPLICABILITY: M00E5 1 nd 2.
1 j EI1Q!i: } i
- a. With the reactor we el head vent path i rable, maintain the inoperable vent path losed with power ved from the actuator of the solenoid valves in the inoperab vent path, and:
- 1. If the pressurizer va r space nt path is also inoperable, restore both inoperab vent ths to OPERABLE status within
, 72 hours or be in at les t STANDBY within 6 hours, or
. 2. If the pressurizer vapor ce vent path is OPERABLE.
' restore the inoperable act r vessel head vent path to
, OPERABLE status withi 0 day or be in at least NOT STANDBY l within 6 hours,
- b. With only the pressur er vapor space ent path inoperable, f
maintain the inopera e vent path clos with power removed from the valve actuator f the solenoid valve in the inoperable vent j path, and: ! 1. Verify at est one PORY and its associat flow path is
- OPERABLE thin 72 hours and restore the i rable
- pressur er vapor space vent path to OPERABL status prior to en ing N00E 2 following the next NOT SN of j suff tent duration, or
- 2. store the inoperable pressurizer vapor space ven path to ,
- PERABLE status within 30 days, or be in at least l l STANDBY within 6 hours.
i e The provisions of Specification 3.0.4 are not applicable. ! 1 s l CALVERT CLIFFS - UNIT 2 3/4 4-42 Amendment No. 178 l O
cts 314.4. q I . R. I 4.4 MACTOR COOLANT SYSTDI SURV CE REQUIRDIDITS l 4.4.13.1 Ea Reactor Coolant System vent . shall be demonstrated 9PERABLE by tes each valve in the vent th per Specification 4.0.5. 4.4.13.2 Each Reactor lent Sys ont path shall be demonstrated 9PERABLE at least once per E IlffERVAL bys
- a. Verifying all ma iso n valves in each vent path are locked in the position.
l b. Verify 1 ow through the Reactor Coo System vent paths with the v valves open. l l O l I CALVERT CLIFFS - UNIT 2 3/4 4-43 Amendment No. 178 l l lO . l po3e 2 oP 2
$(>ec.F.,.4,,- 3. 5. t 4
5/4'5-"E"'Ency c0it c00 tin sysTois <rces)
*5. 5 3,5.I 2l
- 5^* "C" "5 b -
AI LDlITIM COGITIM FOR OPERATION
- 3.5.1 Each Reactor Coolant System safety injection tank shall be OPERABLE with j 't,@ isolation valve open(
l % A contained borated water voltane of betmn 1113 and 1179 cubic feet of borated water (equivalent to tank levels of between 187 k. i and199 inches,respectively). I A boron concentration of between 2300 and 2700 ppe, and { 'd . A nitrogen cover-pressure of between 200 and 250 psig, i ' APPLICABILITY: p L.t i A g ,,, , m: MDES 1._2. and INSERT ACT tom ( - 8e in Mg 3_.3 '*_._ 5 ^ #""3 _[(/- r.,, . . ,. , 4 (. ., 4.. . l
;g 4.[With one safety injection an inoperable, e;e. ,. m. . rxat M c ~ d ,- 4 a & d in utM: 9 t. store the inoperable tank to OPERABLE 1^ -
, A,4..., Lstatus within m r fin within the next.12 - c l Oeurs. 24 t,7 k Ng,g i
)b4 6 b. With one safety injection tank inope ed; t th u;'.te we' e Mig closed, either 4amediately open the isolation valve t
q 4 '*
- r be in NOT STANDBY within hour a be in 50T $NUTDOW within the next 12 hours.
2 4 h ..,. h [ L
- 3 C M
- j 6 1
_rg , 5] svRvesttact arovrameurs .NS N D,
- 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:
SR 's, At least once per 12 hours by: l -1, Verifying the containen borated water volume and nitrogen
't .5 . i .3 cover-pressure in the tanks, and
'S, Verifying that each safety injection tank isolation valve is
,,j open.
1 1 4 i
. CALVERT CLIFFS - UNIT 2 3/4 5-1 Amendment No. 149 l
1
- O 4
p =. 3 e IeP] I
,' Syss. ss se n 3. 5. l . i 1 1 , i 1 INSERT ACTIONS A i i e I l' A. One SIT inoperable due A.1 Restore SIT to 72 hours 1 to boron concentration OPERABLE status. not within limits. l. QR Li i One SIT inoperable , ! due to inability to ! verifylevel or pressure. i
+
1 i INSERT ACTION D i i : i i ! D. Two or more SITS D.1 Enter LCO 3.0.3. Immediately ! inoperable. 4 i h l i i 1 1 I i i l i i 2 I l P*Y oF 3 4
5 p-. C. . 4.o, 3.5. I I O 3/4.5 DIEMEEY CHE C00 LIM SYSTDt3 (ECCS) SURVEILLAIICE REllUIRDIDITS (Contissed) SR
- 5. 5, t ,4 % At least once per 31 days by verifying the boron concentration of the safety injection tank solution.
SR g. A. least once r 31 days 3Een the nCS pressure is above 200 I* b Ydeg glpowy to snejsolation valve operator is _
.-..c ,,;._;:::s - --
SR 7.G.7 T inin e nours or.for to enterins1BDE 3 fromJWDE 4 by verifying ia local in 44 is_ open_._y #(ation at the adTve. that the'fank isolatieff valve [, Ntsafley injection once per REFNt'LIIIS IllTERVAL by v ifying that each t Iisolationvalve i ns automatically undet' i e of the foil ng conditions 1 l
- 1. When the pressure exceeds psia, and L*6 i u 2. Upon eipt of a safety action test signa Sf3 3. Within ene hour prior to each increase in solution volume of g 14 of-nomal-tank-wkuc by verifying the boron concentration @
l ht b O l l I l l 1 l i l l l l CALVERT CLIFFS . UNIT 2 3/4 5-2 Amendment No. 149 I !O l p.y. ~5 - r 3 I . _ - -_
$fCt[IC4ftOQ3, $, Z l
1 p,[ .3/+r& EMERGENCY CORE COOLING SYSTEMS (ECCS) gg4 S/++t' ECCS 2:YSTM - ::::; ;. ; A; ; l; ;-,; ;;3 . /), / '
- LIMITING CONDITION FOR OPERATION _ _ j LCO M Two 1-f
- ;rf:- ECCS shall be OPERABLE d f. ..e J,f,2, ?"'?,"st ::--.;-:::d ^'s '[
fa. One OPERABLE igh-pressu safety injec ion pump,
- b. One OP low-pressu safety inj tion p op, and
! c. An OP LE flow pat capable of t ing suction f he bll
- i refuel ng water tan on a Safety jection Actuati Signal and aut tically tran erring sucti to the contal nt sump on a" Rec culation Act tion Signal.
f .A_PPI P ICABILITY: MODES 1, 2, and 3\. T : - fvf JoA J 4. N$6 g,2 l D Mo 0c44* __f [fgffcA.f f. With on CS noperable, restore e nopera le
- subsystem
"'"" d th'- th: to OPERABLE hour
---* " ka"-4statusr within 72_/522,s or be in NGI truce- .aWA W.uech
} \ /,. # WOJ. 5 t< t~ IL NeuAs l [Cr/0N (, f.Intneeventth ECCS is a usted and inJeu ... . . . .
l Reactor Coola System, pecial Report s 1 be prepared an
- submitted t he Coen ion pursuant to CFR S0.4 within (
, 90 days d ribing e circumstances theactuationand) - 4 total lat etuation cycle date. / t-1 yf 0M b Y SubsySYM k' J (C b y G l g6 M d/L 8 ; i ANb $7'[(MLT /80fg , Of Y ft.23 floal '
- tlx L tiol 3 'V"*r 40 x .smie i l
Andwdj,l g V $ fccs With pressurizer pressure 2.1750
- (
- 2.
, CALVERT CLIFFS UNIT 2 3/4 5-3 Amendment No. 193 ;O f .u 2
;. - - - - - -....-..-. - - - . . - . . ~ _ . . . - . - - - - . . - . . . .
b y. de M 3 b.$ i lO ! l l 3 5" @ EMERGENCY CORE C00LIllE SYSTEX1_iECCS) h
! 3 3,3 g/4 A Z u.o_JtfB5Vu tm - .s,ims 1. 2 AND Yf21750 P1FKh ~[]_
(7%,7",$/ [ h k ,r/=// d%
- LIMITIll8 C0llDITI0ll FOR OPERATION /J. .F w/,e 13#
{ '_> : 2 t9.1
-_ = - - _ _
l f3.5.2 Two independent tCC5 subsystems snesi se vruuisLE with eacn j subsystem comprise.1 cf
- a. One OPERABLE high-pressure safety injection pump, f
- b. One OPERABLE low-pressure safety injection pump, and l c. An OPERABLE flow path capable of taking suction from the .
- refueling water tank on a Safety Injection Actuation Signal and
- automatically transferring suction to the containment sump on a l Recirculation Actuation Signa 1 7
] l APPLICABILITY: HDDES 1, 2 and 8. /,, , / f enhavetadt h * =h18, restore tham ho ablB h , 1 g un sw ... to mOPERABLE f
- status within 72 hours or be n T g,,g 3 f,, /l within @ 12 hours, gg i Jo. an une event the tcu is actuated and in,1ects water into sne l
Reactor Coolant System, a Special Report shall be prepared and i i submitted to the Connission pursuant to 10 CFR 50.4 within l ! l ; 90 days describing the circumstances of the actuation and the ] total accumulated actuation cycles to date. l i-l Le Dsh.sm 4 cley, fn l 4t' N6*b 3.02,
" Ec.O op,A
- i i
i t l l . i b idMth nressurizerf ressure g ling Ssta.) g { i
! CALVERT CLIFF 5 - UNIT 2 3/4 5-3 Amendment No. 193
) lO 11L. 4 f'r F
6pg.s.C s h ** 1. 3. k s i~..... a . s 3/4.5 EMERGENCY c0RE COOLING SYSTEMS (ECCS) gpe .t.4 3. K.'2. , SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystes shall be demonstrated OPERABLE *:
)
- a. At least once per 12 hours by verifying that the following valves are in the jhdicated positions with power to the valve operators removed:
l Valve Number Valve Function Yalve Position
- 1. HOV-659 Mini-flow Isolation Open
- 2. MOV-660 Mini-flow Isolation Open
- 3. CV.306 Low Pressure SI Open Flow Control ,
j
- 1. At leme+ *a..
m , aa1 daye hy. _ SR 5.L A.2. : s, c , % %. Verifying that upon ontainment sumpa isolation Recirculation Actuation Test Signal, valves open. e.m -- " , .4,
%by "'#*#'
f.[. Verifying)that automatic in the each valve flow path (manuas, power-opers6cu that is not locked, seale , or o _ y --.e.. .. .. .a 4. .m4+<nn. te <a ( C . A + I * *2 + o} ej MT17Ey.r bQ _ 4te enerset easition)] a . . wy a visuas inapec6 ion unico rura i ssa 6na6 no avvas usui an u sva. trash, clothing, etc.) is present in the containment which could
/~'i be transported to the containment sump and cause restriction of d ("/ the pump suctions during LOCA conditions. This visual inspection shall be performed: ,
- 1. For all accessible areas of the containment prior to l establishing CONTAINMENT INTEGRITY. and
- 2. Of the areas affected within containment et the completion 1
of containment entry when CONTAINMENT INTEGRITY is-
- i established. -
- c. Af Within 4 hours prior to increasing the RCS pressure above 1750 psia by verifying, via local indication at the valve, that CV-306 is open, f .
Whenever flow testing into the RCS is required at RCS temperatures of I 301'F recirculate and RCS less,water the hig(h pressure suction fran RWT safety injection isolated) or thepump shall controls of
. Technical Specification 3.4.9.3 shall apply.
^ F --
CALVERT CLIFFS - tlNIT 2 - 3/4 5-4 , Amendment No. 178 9 - .- pp a y n
! .5 pac Cech., 3.F. L i j lO l 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECC$) { SURVEILLANCE REQUIRDIENTS h Each ECCS subsystem shall be demonstrated SPERABLE*: j Q) At least once per 11 hours by verifying that the following valves 9 are in the jhdicated positions with power to the valve operators removed: Valva Number Valve Function Valve position
- 1. MDV-659 Mini-flow Isolation Open
- 1. MDV-660 Mini-flow Isolation Open
- 3. CV-306 Low Pressure SI Open Flow Control Duc.uv.s ef c.heay. O h At 1 att once per 31 days by:
SpeMa 3 J 4, ass o. :r W.
. Verifying that upon a Recirculation Actuation Test SignaD s g. "" containment sump isolation valves open.
eve 4e
/. V.r.2. C 3,g,gE .
Verifying)that automatic each valve (manual, power-operated orin the Cflow path that is not e d in natition H** C. A t iges t n os *-pfEp bD, is in its correct position'. _
. p. sy a visual ins mon unich verme snew no avv.,
etc.) is present i the containment which could
.,. . 6.y.,
)
O l trash, clothi be transport to the containment the shal formed: and cause restriction of su tons during LOCA co itions. This visual inspec n
- 1. For all accessible areas the containment prior to e ab11shing CONTAINMENT NTEGRITY. and
- 2. f the areas affected ithin containment at the c letion of containment entry n CONTAllMENT INTEGRITY s-
- established. - _
- e. Within 4 ho prior to increasing RCS pressure above '
sia verifying, via local dication at the valv hat __,,,,_,_ f N [Whenever ow testing into the 5isrequiredatRCStemp/ratureso 301*F a less, the high press safety 14 ection aL=a RNall 4.eu + = net i, a + ar fauctin from eWT inn
~
lated 1/or th9f controls o ! f echnifal Specification 3.4 73 shall apply. / g l CALVERT CLIFFS - UNIT 2 - 3/4 5-4 Amendment No. 178 nus
1 I gpc ci @i ro.4.o , 3.5.2 l O 3/4.5 DfERGENCY CORE tooLIns sYSTDes (ECCS) SURVEILLANCE REQUIRDIDITS (Continued) I t least once,per REFUELING _IllTERVALby: 1 1 Veri ng the Shutdown Cooling tem permissive r 1 r ock prevents the Shut solation valves from bei 11 Syste sucti with a simlated LA,y3 actual RCS pressum si e > 30g psia. sR 3. A visui impaction of the contatment s=p ad veri ing that the subsystem suction inlets are not restricted
'j 3. ') ,9 debris and that the simp components trash racks, screens, etc.) show no evidence of structural (distress or corrosion.
- 63. Verifying that a minimum total of 289.3 cubic feet of solid [ !
granular trisodium phosphate dodecahydrate (TSP) is l contained within the TSP storage baskets.
- 4. Verifying that a sample from the TSP baskets provides )
adequate pH adjustment of water borated to be representative of the post-LOCA simp condition. 6R At least once per REFUELIllG INTERVAL, during shutdown, by: 15.2.6 9. Vertfying that each automatic valve in the flow path 4 actuates to its correct position on a Safety Injection l Actuation test signal. ' O -SR
- 3. f.1g Y. Verifying that each of the following pumps start automatically upon receipt of a safety Injection Actuation 1
Test Signal: ;
- a. High-Pressure Safety Injection Pump. .
, . , ,f ]
- b. Low-Pressure Safety Injection Pump. g c d's IfcI(d>
], f,5, "/$
~
1 i M.2 2.7 v* ' # > '-
- h '957 P"- P ' b P5 * ~^ *
- 4 "' ' #
- 5. .,l,J.cl ae4- 4em sy i I
~
*D5 CALVERT CLF FS - UNIT 2 3/4 5 5 Amendment llo. 185 O
nsr4
. . - . . - - . . . - . - . . . . - ~ ~- - . . _ - - - . . - - . - . - - - - - . - . . . . . . . . - . . - - . _ - . . . .
i ! { sm4 k, a.s 5'
~
iO
~
l j 3/4.5 EMERGENCY CORE COOLING SYSTDt3 (ECC$1
$URVEILtANCE REQUIRDIENTS (Continued)
- p. At least once per RarutLINE anituvAL by:
- 2. Verifying the Shutdown Cooling System open-permissive interlock prevents the Shutdown Cooling System suction isolation valves from being opened with a simulated or actual RCS pressure signal of a 30g psia.
'j '
- 2. A visual inspection of the containment sump and verif'ying '
I that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens. L etc.) show no evidence of structural distress or corrosion. M 3.551 @ Verif ing that a minimus total of 28g.3 cubic feet of solid [ granu5ar trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets. Se, 3 5 5 2- @ Verifying adequate thatpH a sample fna adjustment the TSP of water baskets borated provides to be representative of the post-LOCA sump condition. ' T. At least once per uruunt Anit.svAL, during shuteown Dy
- 1. Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection O 2.
Actuation test signal. Verifying that each of the following pumps start automatically upon receipt of a Safety Injection Actuation l Test Signal:
- a. High-Pressure Safety Injection Pump.
- b. Low-Pressure Safety Injection Pump.
p.4 CAP G..es A.L 3.nh "Ec.c S -De CALVERT CLIFFS - UNIT 2 3/4 5-5 Anendment No.185 O
,., e
Spwfe.As. 2. 5. 2. O 3/4.5 EMERGENCY CORE C00LIllG SYSTDt3 (ECCS) SURVEILUWICE REWIRDIDITS (Continued) l By perfo ng a flow balance est during shut followint comple of HPSI System ifications that ter system flow char eristics and verj si e NPSI Pump Syst . ng the followl ow rates for a , A. i
. The, pun of the ree lowest flow I s shall be gre r than 470 spm. _ ,
3.5.7.3 @ [d ' 'i' &@o rih',"lThe'""'}Md'f,,*pd" t pursuant to(5 pep (ficatAn 4 s.5.)
.k
@ :na.n:ce no-gpmnD &
- ~ m' I ge <th e-c h Eccs panyi deselsyJ he J J
\
g 4e,.i .]/w foM h p n= kc' 4h*" b ' ^, ' 4o Q (egulrt) cicatIJf Pfuct i
]/
v HPSI Pump System is a HPSI pump and e of two safety i ection headers. These limi contain allowances or instrument error drift or fluctuat . CALVERT CLIFFS - UNIT 2 3/4 5-6 Amen h nt No. 149 O n+n
[ fCeboA353 l ? 3.I 3/4.5 EMEMENCY CORE COOLING SYSTEMS (ECCS) , /' ! 3 5.3 3/4.5.3 Ecc$
- L a m a Com m e pot OPERATIoM LCO 3.5.3 e 3 : & , one rece ; ; ;,. = :
WhI = TkNJ
- 2. ;n- :.; shall be k'
i Jdd OPERABLE: r ) a. One' O LE HPSI pisup, and 1
- b. An flow path apable of t ing suction f the
! refuel water tank n a Safety ection Actuat n Signal nd dA' y aut 11y transf rring sucti to the contai nt sump na
- Reci lation Actua on Signal.
(- . l APPLICABILITY: N00E531and4. k ** J ' 3 s; / A a With no fee 5-eubeysirem OPERABLE, restore at least)one )9 / EGG , //cf/oA' f'- (subsystas-to OPERABLE within the next.at,gours Qstatus Q within 1 hour or be in C0ta SMTDoW 4 i hloN8" ,b. In the event the ECCS is act ated and inject water into t a Speci Repo shall be pared and su ted to the } Commi ion pu uant to 1 FR 50.4 withi days descr ng the l ./2
- ci tanc of the a ation and t otal accismul t a untio ycles to te. -
y
)
! $URVEILLANCE reg lIRDENTS
- c u Requ
' '3 ' g t
& c l8 II0t,Uttu& GK Me AyliceiW: - 1 ra Acadue A'z
- st 3 5.n.t sR.s.C 2*b j
l sR 3R 3.S.22
.3 , g ,2 3 sR . 3. C 2 L S R 3 ,r.2 8 ' js
"'g ff9 y y Between 325'F and 301'F, a transition region exists where the OPERABLE HPSI pimp will be placed in p'u11-t cooldown and g {pg, l
{g matared to auta== tic status on a heatM _o-lock At 301*f and on a thd less, 3 _, required OPERABLE HPSI pump shall os in pull-to- ock and will A t start automH ically~. At 301*F a less, HP5F Mg use wm me ) condu3t4d in aje6rdance with T nical Speci cation 3.4.)d. . i g'3
/With pressurTrer~piissure < 1750 psia.]
CALVERT CLIFF 5 - UNIT 2 3/4 5-7' T /p t. Oh3Amendment No. 193 sc4 (. I i, O 1 l
Ty c. G. c. 4... , 3. I. 4 1 O
- 3. 5 -s/4.s anGDCY CORE COOLING SYSTEMS (ECCS)
~
- 5. 5. 4- -3/4*4 REFUELING WATER TAMK Rw%
LIMITING CONDITION FOR OPDATION L.C O -S*;4 The refueling water tank shall be OPERASLE.adthe N. A minimum contained borated water volume of 400.000 gallon)
\. A boron concentration of between 2300 and 2700 ppa, g
- 8o 5 A minimum water temperature of 40*F. and K. A maximum solution temperature of 100*F in MODE 1.
APPLICABILITY: MODES 1. 2. 3 and 4. - ~ " - - ^ I Ac4 m , I.r r i s- t* L -- 4.- E '
- With the refueling water tank i rable[resto% the tank to . ,J.4 LE status within 1 hour or be in at east NOT STANOBY within 6 hours A>,
A. ,. % "' and in COLD $NUTD0lNI within the following 30 hours. SURVEILLANCE REQUIREMENTS
., sr::
O tist- The RWT shall be demonstrated SPERARLE-g a. At least once per 7 days by: 3*S43- -
- 1. Verifying the contained borated water volume in the tank, g and
'5. 5 . 4. 4 '- 2. Verifying the boron concentration of the water.
b.' At least eara nerJ4._ hours by verifying the RWT temperatureg Coutsideairtemperatureis<40*Q ' su.a. i y ---
%. s o.
NoTF A.RwT b.-- [c.4'm i. co - c , wl . . f . e so mof I k,k Org4.ec R\A/T j d . A .. I .' ~ .% g i 09EM PAS 7 L"UF 5
., s4,
\ b 'T ., s4 ,d -ai e r A , p., a .e ..+
Q R.% i.~.4 CALVERT CLIFFS - UNIT _2 3/4 5-8 __ Amen h nt No. 14g
- N.,
jR y,s, y, z jra u 3, p,M,gfe,,,,s ,., ,fm ,,d a r .
,. o ,,9 r,rej g& *d do be- pe.1(eum e d whe r. a mble - lcm/er=I"*'C f2 )I
- 9. OrJ>
y ve<.4y !?ur bo<&d ude< temper.::we a nov f./}24 /N),/
--_ _ x-py .fi I
$PcSc.4 tor 1,(..!
I 1 1 1 !O i l
'3, (, @ C W Tall # TENT SYSTEMS 3.( . I d [PRIMMY CONTA letDIT m u - rt .. m, _a i
i LIllITIM CORITICII FOR OPERATICII Lco 3.( .l @ Primary CONTAIIBelf IllTESRITY shall be maintained." & i - APPLICABILITY: IIDDES 1, 2, 3 and 4. g{g g jj,}gQgg] l Acnua A - [EL g: Winhet orfmafr)CONTAtlBWIT s2EERITYIw'
' restore C0lfTAIIBUDITI thin one hour or be in at eas STAllDBY within the next
{ Acri.418 3 6 hours and in COLD SWTDOWil within the following 30 hours. 4 l ! I i SURVEILLAllCE REQUIRDWITS l (4.6.Ff Primary CONTAlletENy!IITEGRITY shpl be demonstrjefd:} l t
$ 'At least once per n days by ver1Ty1pl that all penetrationb not capable of being closed by OPERAB.E containment automatic i
i isolation valves and utred to be closed during accident conditions are closed valves, blind flanges or deactivated l - automatic valves secured in their positions, ex, cept for valves
- f that are open under administrative control as semitted by J c' l t$ pecification 3.6.4.l a I
@ Ily ve ying that each cont
} <th uiwata of 5 eciftption 3.6.1.3.fnt air lock is/h complianpith A,4 l i c. By verifying Enst sne - .ei.t hatch is closed and sealed, r10r i to entering MODE 4 foll ng a-shutdown where the engionent atch ; by conducting a Type B test "_ ggin '.; gf
- y .'# I k rh f
, N$
- 4L
.<h g bG en purge containment vent isolation valves shall be o ened forl G
j cont 7nnent pressure control, airborne radioactivity contro , and Kg<i surveillance testing purposes only. jjy
) 8 The shutdown cooling isolation valves may be opened when the RCS gfN g temperature is below 300'F to establish shutdown cooling flow. o 5 Except valves, blind flanges, and deactivated automatic valves which & G are located inside the containment and are locked, sealed, or
'9 otherwise' secured in the closed position. These penetrations shall be verified closed during each COLD SWTDOW except that such verification need not be oerformed more often then once per g2 days.J 4
CALVERT CLIFFS - UNIT 2 3/4 6-1 Amendment No. 164 _ PJ* TM* '7'"I"b^' ht A ia *e J 'a' 8 9 e.,4. A 3.6LI
- d ete A fir c. Wa E ** M M uMt. & ( % 4 L..by 0.4e. skry r.ge*m,P L.L r M e
,rm r 9(a.os7 } 96-04L pay lY &
6 p.e ,C 4 .~ 3 ,c..( O 1s ri (Fro "4 *
- 3 ,
hverifying that the containment blind flanges are installed and sealed, prior to entering MODE following a shutdown where the blind flanges were removed, by conddcting a Type B test per 10 CPRPart 50, Appendix J. Ifonly one blind flange was remove, ' only that blind flange must be Su bir,c.e.. 9. c.b p fh @c.Lbn 5,o "Almwabbs W
- O h
I O e, zn
,c. , .rn
S pac. b b h 3 i !O
/4.6 C0llTAllptENT SYSTDi$
g,, tys, ,,a of ch.,p \ 3/4.6.1 PRIN'RY A CONTAll0 TENT l Sn Spect e.Me 1 4. ls i
* &aa.k "
! LIllITING CftllDITI0ll FOR OPERATI0li [ ' j 3.6.1.1 primary C0lffAIlstEllT IlfTEGRITY shall be maintained.* t { AEf11CABILIIY: MDDES 1. 2, 3 and 4. ~ 1 gGK: Without primary CollTAIlgtEllT IllTEGRITY. restore CONTAllBitilf INTSITY within one hour or be in at least 110T STAllDBY within the next 3 6 hours and in COLD SilWTD0lRI within the following 30 hours. u i SURVEILLAllCE REQtlIREMElfTS aaan d luh*I _
.m.y
=
t 4.6.1.1 primary C0llTADetDff imi Miiv shall be demonstrated j E 3.f .S.2. $ Atnot least once ys by verifying that all penetrations ** 40 i capable ing closed by OPERABLE containment autoratic 4 isolation ves and required to be closed during accidant i condition are closed by valves, blind flange hectivated wYWie i automatic valves secured in their position . excep, Tor valves , that are open under administrative controlgg ' M( 4 i opecirwanen _s.am.i. g, L
, requirementsthat verifying of Specification 3.6.1.3.
each containment air lock is in compliance w g c. By verifying that the equipment hatch is closed and sealed,
- u J to entering fl00E 4 following a shutdown gthe endiament tchbrior by conducting a Type B test ._ ..qgg inmeosl Sh kk hop D'""f ?
rogen purge containment vent"- isolation i 5.It ~1.4.'1.1 # containment pressure control, airborne radioactivity _ control,gand survelilance testing purposes on1 M j jg_ w.re .f The shutdown cooling isolation valves may be opened dthe RCS u temperature tu below 300*F to establish shutdown cooling flow. [Ye.16 3 2 M Exce$ocatedinsidethecontainmentandat are valves, blind flanges, and4deactivated automa otherwise secured in the closed position. ocked. sealed. or hese penetrations shall be verified closed during each Col.D SilUTD( except that such verification need not be perfomed more o' ten then once per 92 days. CALVERT CLIFF $ - UN!_T 1 !/A 6 1 Amendment No. 164
,, . ' 7 ~ UJ der E. -
VM L ga AS, a n.v, ., 9. A y ,.t.u .. g ; ams m.g v ur,ua g a ,e .w.Ak+< <~ns. ( Q ~_l~,Z[OL~31~~~~' - -- y rp l %-oT7
T,0 SfCL*Gicr&J l f Coah>ame led RA Tdisp, %~
~
$D St [ f ll fMd Ik1
/(.i C0llTMIDIDIT SYSTD15
! 3/4.6.1 PRIMARY CONTAINMDIT ! CMTAIlplDIT INTEGRITY i
- f.. unm C m. r .pinAn.
1 ! 3.6.1.1 Primary CMTAIIBIDIT INTEGRITY shall be maintained.' ' 5 l APPLICABILITY: ISDt31. 2. 3 and 4. [
- Without primary tellTA!WWif IllTEGRITY, restore tellTAIIBEllT -
- within one hour or be in at least NOT STAlWBY within the next M 6 hours and in COLD SHUTD0lAl within the following 30 hours. 'N qs l
SURVEILLAllCE REQll!RDIDITS wt[g i 4.6.1.1 Primary CONTA!WIDIT INTEGRITY shall be demonstrated: d Q'D v T , y g 4." At least once per 31 days by verifying _that all penetrations-not capable of being closed by OptRABLE containment automatic D b
*I s\gs
'g isolation valves and required to be closed during accident d conditions are closed by valves, blind flanges, or deactivated & )
.Q $s automatic valves secured in their positions, except for valves #
that are open under administrative control as pemitted by
]
l 4 g .$ 4_ q g weification 2.5.4.1. l i 7M
* (b. By verifying that each containment air lock is in compliance wi
,, A t_he requirements of Spe_cification 3.6.1.3.
m q 1 -
}j t k g
* . Dy vernying s to entering sne equipment naten 4 following a shu closeo ane uusi H FrioB where the equi istch (d .[
3
- 3 g .3 was y conducting a Type test per 10 CFR Pa .
] Appendi . y _
- s. m - _
_ Hydrogen purge containment vent isolation valves shall be opened for' containment pressure control, airborne radioactivity control, and p surveillance testing purposes only. . The shutdown cooling isolation valves may be opened when the ItCS , temperature is below 300*F to establish shutdown cooling flow. 7 Except valves, blind flanges and deactivated automatic valves which are located inside the containment and are locked, sealed, or othemise secured in the closed position. These penetrations shall
, be verified closed during each COLD SlWTDolgt except that such
( verification need not be perfomed more often then once per 92 days. 7 CALVERT CLIFF 5 - UNIT 2 3/4 6-1 Amendment No. 164
- O l
v8e p,7e 47 457 ) 94-047.
, , . _ g ., ae s, s-A 2 43ew m _. so 4 - 2 -J- .$.- a_ . e J 26 4ha.. 4. 44_a . - - - 4 u.h 4 .s_f,..A.a=-,.4,_aA._h.AmJ.E49.--.*dh_N-,4J._4La 2_#_m1.4h-24 e.hd4 _A-e. 4 a LAu._m_ -6 _ amaA.
** $O99 k CSf thm
, QnYQlrfrMfnh iO -
x"mJ ( < t .+m. z )a N j sy m -i- ,-se d n.=ge..re d sesw *i. 4 ~ e.te,i
%c s y=.e iw '
-r ed. -
- u. e i
Type B test per 10 Part 50, . Ifonly cesblind was a onlythatblind Aange beteneduni estingisrequiredby echnice! ) s 4.6.1.2. __ -_ / 4 , d 4
- l i
4 1 1 l lO ) i f i 1
- i
- 1 1
1 l 1 AIRC % - o't2 4 Q i i pp W8 f67 4 J
---, o
~ _ _ _ _ - - _ _ _ . . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ . . _ _ _ _ . _ . _ . _ _ _ _ _ _ . _ _ _ . _ _ . . _ _
sr.f.ob 5.r..I !O I 3* b @ CONTAllgtEllT SYSTBt3
,7,6.[ M h kM& d CONTAlletF M Cantainne I noe i LDt! TING C011DITION FOR OPERAT100t M/dd8L]6
@ ContainmentQea"5igefiGb shall baDisrftarta: .
I @ Tanximum allowable containment leaka rate. . as specified int i specification 6.5.6. ' Con Lea age Itate esting Program." $
$ A combined leakage rate of < any L nE .05D :um. for all i penetrations and valves subTect to tvnna I and C tests Sg /W 9'
. r ip=>v ns== m h e c Lf**e.r spes#=4 .&m la s en,4*h e.m 4.5.Q 1 APPLICABILITY: IIDCES 1. 2. 3 and 4. bM G : With either (a) the measured overall integrated containment ' MI ' e rate exceeding the acceptance criteria specified in the Containes l j Leakage Rate Testing Program, or (b) with the measured combined leakage
., rate for all penetrations and valves subject to Types B and C tests i h3j exceecinlPudp L.. restore the overall integrated containment leakage rate A'3 i to within the acceptance criteria specified in the Containment Leakage Rate Testing Progrgr ana the comunnec leakaa. cate var au =r: rations ===_ 4/U M;.
) atsiveu mun, u to Tvna a and c +==+<EeMan Ahafi af eaid1 tt 0.5F L.] prior j i j
- to increasing 'the Reactor Coolant System temperature above 2(0*F..
~
j , l t
.Sas IAscws,. 8" deape l l
fer .5pue.f,se4.n f.o i j $URVEILLANCE REQUIRDtENTS % .7,,s M ,,e ? 4. /s I4.6,1.2 The containment leakage ratesuairne-mstratas at/tne] j I anwnwuin tasD(schedule 6Shall be defermined in confonnance I with the(j&4=a, ! Qriteria, methody,,and provisions specified in 10 CFR Part 50. Appendix #. _ l
~ F g Perfona required visual examinations and una/m tastME in 1 A)L'l M; 4 g g,g,g __ _ccordancewiththeContainmentLeakageRateTest'ngProgram.)
a i led.psnh h4 , aced 4' i e~k+ .1,- AD +,a% ) ( i i i CALVERT CLIFFS - UNIT 2 3/462 Amendment No. 193 1 i O
! $6-o57 P'?
5p/4.w4ra,. 9.0 i l O f 3/4.6 CONTAIIMENT SYSTEMS 3/4.6.1 PRIMARY CONTAllmENT Containment Leekane l 4 l LIMITING CONDITION FOR OPERATION
}
y.1.2 Containment leakage rates shall be limited to:
'+ @ ASpecification maximum allowable containment rate, g, Lea leakagge Rate esting Program.", as specified
* .5.6, "Conta lg
'I, i I Q jd A combined leakage rate of LJ(17):000 Sodii3for 11 EAC %-OSD 1y y penetrations and valves s Type 5 and C tests (presjaetzed }et..) 4J;g 5 g ,w d g g
, 4,
*$U hlCABILITY: MODES 1,2,3and4Q "bd b^b ^S
[**b 54' i
\ : With either (a) the measured overall integrated containment es age rate exceeding the acceptance criteria specified in the Contalmeent
\ 1 Leakage Rate Testing Program, or (b) with the measured combined leakage 4 rate for al trations and valves sub. ject to Types B and C tests {
exceedi , restore the overall integrated containment leakage ra , to within ceptance criteria =aarified in the cantainamt t makaaa Rat /J Testin Progr sna sne connined leakane rate fae all none<: rations a qp g3 f ( ; va s to increas t Type B and C testsfo leMhan ormdll ';o OAO L.) prior Reactor Coolant System temperature above 200* k \
- SURVEILLANCE REQUIREMENTS CaJrrf.D The contalnment leakage rates 6 hail " "'-utrated@
Lfo'lowifa test schedD1e anSshall be detehnined in confomance with the eria, hod anc provtsions specified in 40 CFRJeft 50 Aseena1x JD [d46Ary _ _
}
j
- a. Perform required visual examinations a teetJ1 in I hg4q6-057]
accordance with the Containment Leakaa te lesting Program. , dp redeles n3 __ e%tb- @ (..chtm4 Lip ga T,J+,,Q
' ca % eme.t &
l lok-tedia I l CALVERT CLIFFS - UNIT 2 3/4 6-2 Amendment No. 193 1 lO J W 05-]
i Spu.bb A.6.1 1 !O ~ 3/4.6 CONTA!I94ENT SYSTEMS k SURVEILLANCE REQUIREMENTS (Continued) 1 -
- b. T ad to ts ha 1 nd et th ga a P( p ig $ h in is of 4 n s xc t or te ts n 1 ng i 1 k k i
- c. A s al be te a . tr t 0 LE 4'
% h Su ve I ce Re i t 6. 3 .
tt s s 1
- d. A1 B n C es le ka ca eu t ui ,,
ob e d a ny rt a o t;gvaue. -- - 8 - J } Contai nt purge olation val es shall be strated ERABLElt i any ti upon ont ing HDDE 5 rom POWER OF TION MOD unless ' the 1 st survell nce test been perfo d within t past 6 ' b mon s or any t after bei opened an prior to en ring 4 from s down modes y verifying hat when th measured i j- leakage rate added to t e leakage r es deterni pursuant to 4 f
,6.f.2.a Jechnical So <ificatie t. .2.S for 11 other T B or C D tratiand she com>T leakage r e is less t or equal to g
*60 b - .... . , ,. he leakage ate for the ontainment p e isol on valves hall also compared to he previous 1 measured akage rate o detect ex ssive valve egradation.
. The con inment pu isolation Ive seals s 11 be replac seals at frequency t ensure no 1 ividual seal if 4 with . remai s in service greater the 2 consecutiv fuel reload ycles. i 4 l 1 i i DELEYE 1 ? J___- -m. e< l
. . _. L . 1, E
_ a. .. L. . . a'e.r.y. I q CALVERT CLIFFS - UNIT 2 3/4 6-3 Amendment No. 189 I O
?"Y * $ '
.%-o57 l ss. - 042-
1 Seac.F A., s.6 2. O
- 3.6 6 CONTAINMENT SYSTEMS
- 44+
- C9 (PkJ@RY COMAINENT)
- a.6 2_
Containment Air Locks LIMITING CONDITION FOR OPERATION Lco 3,4,2, 3.'.1.3 containment air loci @sh I be OPERABLE with:
$ 'Both d s closed except when fhe air lock is being undd.for 1 4 no Jea ransit entry and ext one air lock door shat (through be closed, theand containmeg, then atJ p h R,
f_ F L A.2. h no ra 1 air lock leakage rate of(Q.05 Q _
- @ _ -g
*"T,w&pecifieal in(S[sdicalteM. lY Centsineent '
R j APPLICABILITY: MODES 1, 2, 3, and 4. Ih
,,pf,y,f;,,9pf,g h
~
},gJJgi: -ggZgM 4 Acm.e
- a. inn d at6air lock inoperableN, t +a-- +ha = a ept c
as a result of ang"h" >aperableI
'+-a==r=++"* f p4.
' AA,e , or be in at least NOT STAND 8Y within the next 6 hours and fin COLD SNUTDOWN within the following 30 hours.
- b. Witn an air lock inoperable due t an inoperable door gas t: I
! 1. Mal ain the remaining door f the affected air loc closed 4,7,, 4,4 Acc.,. 4 an sealed, and 4 (uv dw I40 L- 1. etters the air inek en prnABLE ttatus within days or be l in at least HOT STAND 8Y within the next 6 hours and in COLD Acno# B CSHUTDOWN within the following 30 hours.
A TAfGW krn^t shrf.c I 4 2
$URVEILLANCE REQUIREMENTS 3 4,4 i 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
i a. A te e ch op ni g, ex ep w en th ar o i e fo it p1 et e en at 1 s o e e 7 h r b
, e f n t t h s 1 le a s 0 00 2 9. s D i e b p ec si n lo as r n en t 1 e e Q t oc sa i es u ze t c ps n p s r o 1 p g p
By pahin in k*'h@ % with de C stain-senf Mate E*te EsRS Q
~
r_....,__._,o.
...y..... .. . ..
, e m. .., .. J,.. ny D8WE CALVERT CLIFFS - UNIT 2 3/4 6-4 Amendment No. 189 l O
e.> v lAl/CH,-OC']
INSERT 3.6.2 A. B, and C O CONDITION REQUIRED ACTION COMPLETION TIME , 1 A. One or more -----------NOTES----------- ; containment air locks 1. Required Actions A.1, with one containment A.2, and A.3 are not l air lock door applicable if both doors ! inoperable. in the same air lock are inoperable and , Condition C is entered. I
- 2. Entry and exit is permissible for 7 days ,
under administrative l controls if both air l locks are inoperable. J A.1 Verify the OPERABLE 1 hour door is closed in the affected air lock. AND A.2 Lock the OPERABLE 24 hours door closed in the affected air lock. AND ) 1 A.3 --------NOTE ------- Air lock doors in high radiation areas may be verified locked closed by administrative means. Verify the OPERABLE Once per 31 days door is locked closed in the affected air lock. p,c w
bferScA% 3A 2-I CONDITION REQUIRED ACTION COMPLETION TIME B. One or more - -- -- - - - - - - N OT E S - - - - - - - - - - - containment air locks 1. Required Actions B.1, with containment air B.2, and B.3 are not lock interlock applicable if both doors mechanism inoperable. in the same air lock are inoperable and Condition C is entered. i
- 2. Entry and exit of containment is permissible under the l control of a dedicated i individual.
i ) B.1 Verify an OPERABLE 1 hour i door is closed in the j affected air lock. J. AND B.2 Lock an OPERABLE door 24 hours closed in the affected air lock. AND B.3 --------NOTE ------- Air lock doors in high radiation areas may.be verified locked closed by administrative means. Verify an OPERABLE Once per 31 days door is locked closed in the affected air lock. O e, w
CONDITION REQUIRED ACTION COMPLETION TIME l O C. One or more C.1 Initiate action to Immediately l containment air locks evaluate overall l inoperable for containment leakage reasons other than rate per LCO 3.6.1. Condition A or B. ! AND C.2 Verify a door is I hour closed in the affected air lock. AND C.3 Restore air lock to 24 hours OPERABLE status. l lO i i i
- O ppcHJ7
6(* cAden 3.(. 2. INSERT ACTION NOTES 3.6.21,2 and 3
- 1. Entry and exit is permissible to perfonn repairs on the affected air lock components.
- 2. Separate Condition entry is allowed for each air lock.
- 3. Enter applicable Conditions and Required Actions oflIO 3.6.1, " Containment," when leakage results in exceeding the overall containment leakage rate acceptance criteria.
I O O e ,e c.n
Apa, $,4w 34. L l INSERT SR 3.6.2.1 O SR 3.6.2.1 - - - - - - - -- - - - - - - - - - N OT E S - - - - - - - - - - - - - - - - - -
- 1. An inoperable air lock door does not l
l invalidate the previous successful l performance of the overall air lock l 1eakage test. l 2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1. 1 Perform required air lock leakage rate In accordance testing in accordance with the Containment with the Leakage Rate Testing Program. Containment Leakage Rate Testing Program O I I O pay Cal?
_ . .- . . - . _ . . - _ _ - . . _-. - ~ _ _ . . - . ._- - - . - 5pu.Co.. Awa 3.f. 2., O 3/4.6 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) t t 6 R 3.(,.L 7. acharfock an e opened at a
$ -O
\ i O CALVERT CLIFFS - UNIT 2 3/4 6-5 Amendment No. 189 l i O payc 7.r 7 las-os, j
$ ec.C~.e s .e n b. S Y O
7,G @ CMTAIIMil(T 1Y1TEMS
- 3. 6. 4 LIllITIllG CMDITIM FOR OPERATIM tCo 3.6.t
- ME Primary 1.0containment and 1.8 psig. internal pressure shall be maintained APPLICABILITY: N0 DES 1. 2. 3 and 4.
Acs sou A ' /AgIlDK: With the containment internal pressure outside of the Itaits l labove, restore the internal pressure to within the limits within 1 hour or
/be in at least NT STAND 8Y within the next 6 hours and in COLD 511UTDOWN
, $within the following 30 hours.
SURVEILLANCE REQUIREMENTS SR 3.6.4.l @. The primary containment internal pressure shall be determined to De within the limits at least once per 12 hours. O i l CALVERT CLIFFS - UNIT 2 3/4 6-6 Amendment No. 189 l 1 4 i O y a q.- t 7l
59 ,J .,. 3, m ~3. 6 . c5 O 3.L -3/4;fr- CONTAINMENT SYSTEMS
- 3. t. . S 0/' :.1 " M C MTA M ENT
~
Air Temperature A. LIMITING CONDITION FOR OPERATIM t.co '5. 6. 5 3.5,1." Primary containment average air temperature shall not' exceed 120*F. APPLICABILITY: MODES 1. 2. 3 and 4. Acred A ., EILQl[: With the containment average air temperature > 120'F. reduce the average air temperature to within the limit within 8 hours. or be in at i
/least NOT STANDBY within the next 6 hours and in COLD $NUTDO W within the j g ,y g ,,, Afollow1J5 30 hours.
l SUR'EILLANCE REQUIREMENTS SE 3 EaE T 4:6r4.5. The primary containment average air temperature shall beff";h eriu ocas averf9T"W-Ine tentbersiurcs et tne iv'.Mb iscations md) (L A , g l sha be eteriranea at least once per Z4 hours: fTocation Qr6;; I . G- [
- a. ntainment J. Containment eactorCavith (
l l CALVERT CLIFFS - UNIT 2 3/4 6-7 Amendment No. 189 l O - pr y- ie\ l
- - - -..-. - - .- - - . - .- -.-_ - . = - - - . -- .-- . . .. - . - -
l h p c . G . , .A . , e 3.6.l O 3.6 -444,6 CONTAINMENT SYSTDt3
-L'; . e .1 g [RIMANf
, CONTAlf00ff Containment etural IntadritT)
LIMITIM ComITION FOR OPERATION 3,4rh4 L. ;.. . ". me = The.2..1cd.i.. .. m m ....,..M L.c.o.nta.inm.ent w ...3s sha.l.l..be.kam+ntdaed e _ - - . . = _-:. =m APPLICABILITY: MODES 1, 2, 3 and 4. " t s w ... . .. ...y v. .- e-.-- u --_.6 not conto ny so AttrwaA ~ {; ' requirements, r M....NiestructuralJf"teority to withi imit ithin 24 hau,a 4r be in as least usi ETAIDBY within the nexv 4 gj. li hours and in COLS $NUTDelAl within the following 30 hours._F 6L h.l.2 v.,$ c, A:..,A gg,4,,,g .,, f, g ,,,,,3,,, .g , m ,,3,, ,
& %* Lak.:.saA %hs .s, .. .s t.ea tr .m a *a A gy F 50RVIILLANCE RE 1REME hs .N. [es-( _____
~'
l 4.6.1.6.1 Containment Tendons. The containment tendons' structurai ' integrity shall be demonstrated at the end of one, three and five years following the initial containment structural integrity test and at five year intervals thereafter. The tendons' structural integrity shall be demonstrated by a visual examination (to the extent practical and without O dismantling sample of at least load 21 bearing tendons components of the anchorage) (6 dome. 5 vertical, verifying no abnormal degradation. Unless there is evidence of abnormal and 10 hoopof and a rep)resentative degradation of the containment structure during the first three tests of the tendons, the number of tendons examined during subsequent tests may be reduced to a representative sample of at least 9 tendons (3 dome. 3 vertical and 3 hoop). 4.6.1.6.2 End Anchoranes and Adiacent Concrete Surfaces. The structural integrity of the end anchorages and adjacent concrete surfaces shall be demonstrated by detemining through inspection of a representative sample of tendons (reference Specification 4.6.1.6.1) that no apparent changes have occurred in the visual appearance of the end anchorages or their adjacent concrete exterior surfaces. Also, inspections of the pre-selected concrete crack patterns adjacent to end anchorages shall be performed during the Type A containment leakage rate tests (reference Specification 4.6.1.2) while the containment is at its maximum test pressure. Qr d sc o $.. - . f" ebe.a.y.3 C. Sp, ,. . C . a . . , 1 O, "AL.,s.u.a C . A < = 1. " CALVERT CLIFFS - UNIT 2 3/4 6-8 Amendment No. 189 l O n s.c c
-- - . .. - .. - - ._-- .. =
. _jfC*)iCAUWJ T O.,
h 5e+ 9~ T. 6 cg n m g,7,4 covele CodweA TN*' %$* Of" f3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Structural Intecrity LIMITING CONDITION FOR OPERATION
~
3.6.1.6 The structural integrity of the containment shall be" maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6. APPLICABILITY: MODES 1, 2, 3 and 4.
! : With the structural integrity of the containment not conforming to t e a ove requirements, restore the structural integrity to within the limits within 24 hours or be in at least NOT STANDBY within the next (6 hours and in COLD SHUTD0WN within the following 30 hours.
$URVEILLANCE REQUIREMENTS l
1
#.6.1.6.1 4 -Containment Tendons. The ntainment tendons' strug(ural {
integrity shall be demonstrated a e end of one, three and ive years ' following the initial containme structural integrity tes and at five year intervals thereafter. e tendons' structural inte ity shall be O demonstrated by a visual sample of at least 2 verifying no abno ination (to the extent r tical and without dismantling load bearin components of the anchorag endons (6 dome, 5 vertical of a representative nd 10 hoop) and degradation. Unless there s evidence of abnormal d degradation of t containment structure durin l the tendons, t number of tendons examined ring du,gsubsequent the first three tests tests of bej may l
, reduced to a epresentative sample of at least 9 tendons (3 dome, y L3 vertical nd 3 hoop). -
4.6.1.6.2 End Anchoraces and Adleent toncrete Surfaces. T 'e structural integrity of t e end anchorages and a jacent concrete surfap)es shall be
. demonstrated y determining through nspection of a repres ntative sample of tendons ( eference Specification 4.6.1.6.1) that no ap rent changes have occurr d in the visual appear nce of the end anchora es or their Ud adjacent c crete exterior surfac s. Also, inspections f the pre-selected concrete rack patterns adjacent to end anchorages shal be performed during t e Type A containment I akage rate tests (refer nee Specification Q.6.1.2 while the containmen is at its maximum test ressure.
CALVERT CLIFFS - UNIT 2 3/4 6-8 Amendment No. 189 l O pp,12 .d 5 7
INSERT 5.5 6 l (fAft- 2. OY .3) 5.5.6 Concrete Containment Tendon Surveillance Program l This program provides controls for momtorms any tandan degradation in p.ni.M concrete enntainments, includmg e&ctiveness ofits corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operation The Tandan Survedlance Program, %iaa W~W, and acceptance criteria shall be in md.c.ce with Regulatory Guide 1.35, Revision 2,1976. f The provisions of Survedlance Requirement (SR) 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Progrsm inspection fr-h l l l l i l l l l i l l l I fape /3.f 57
.5pc.&. A *a .3.6.1 O
f 3/4.6 CONTAIIBelf SYSTDIS SURVEILLAllCE REQUIRENDITS (Continues) T w 4.6.1.6.3 Containment Surfaces. The exposed accessible interior and exterior surfaces of the containment including the liner plate shall be visually inspected in accordance with the Containment Leakage Rate Testing Program (referenceSpecification4.6.1.2). 4.6.1.6.4 . Any abnormal degradation of the containment structure , detected dur ng t above required tests and inspections shall be reported l to the Commission pursuant to 10 CFR 50.4 within the next 30 days. This l ! report shall include a description of the tendon condition. the condition of the concrete (especially at tendon anchorages), the inspection u procedures, the tolerances on cracking, and the co'rective actions taken, j n h hscassoa of M3 \ /
& $ p.(sssken 'bsOp *
% A g .. S d eur C-= d vol8 l l l
lO t 1 l l I l l CALVERT CLIFFS - UNIT 2 3/4 6-9 Amendment No. 193 i !O I a
ff G o' ho' eA h=") $*O fp$9 . To b O 01 3 (#3) ' Alt)M M d*hJ W ** "" g g, (, [oackAL('r
& CollTAllelENT SYSTB5 50RVEILLAllCE REQUIRENDITS (Continued)
MTCoiitil~numitflur~ faces. The ex s accessible interior 'nd ! exterior surfaces the containment, in ing the liner plate 11 be (A , L( ! visually ins in accordance with t ontainment Leakage te Testing l LProgram (refa a hef fication 4.6.1 . [.f.8 G.6.1.6.y . Any =hamal degradation of the containment structure r A.l setectes du ng t Gbows requifiibtestsN1111Daha11 be reported j
. to the C ssion Mucsaantaa av un w.ww1 thin 30 days. This l l report sha 1 incluse a description of the tendon c on, the condition '
of the c rete (especially at tendon anchorages), the inspection ! procedu . the tolerances on cracking, and the corrective actions taken. I i ! < ) \ ey og SM ee' Ireste. .
.,g) h
^
C. /t
. ,ys. i) tep dO' '
b.] u -z I & e '}r r ! O l l l l l CALVERT CLIFFS - UNIT 2 3/4 6-9 Amendment 110. 193 O , 1
- l
$pe. r #.~ T.6 3 O
3/4.6 CONTAINNENT SYSTDi$ 4 3/4.6.1 PRIMARY CONTAINMENT l Containment Purce System M TING COMITION FOR OPERATION 3.6.1.7 containment purge supply and exhaust isolation val shall be ! closed by 1 ting air to the air operator and maintaining solenoid ! air supply valv energized.
- APPLICABILITY: M00E 2. 3 and 4.
EIIR: % n ! a. pply and/ one exhaust isolation valve
- With open.oneclosecontainment the open valve purg (sithi ne hour or be in at least NOT 4 g
STANDBY within the next 6 hours in COLD $NUTD0lM within the , j following 30 hours, g 4
- b. ' With one containment purg upply and/o haust isolation valve N inoperable due to high kage, repair the Ive(s) within 24 hours .
j or be in COLD $ HUT ithin the following 3 ours. I
$URVE!LLANCE R RENENTS 4.6.1.7 e 48-inch containment purge supply and exhaust isolation y es
, shall detemined closed at least once per 31 days. by verifying that pow o the solenoid valve is removed. O
=fhst po ksc<b en J Y' Y **Y f
{ j g~ ~a 4, _ _ . j , i i o.1H k
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f c) 6- 047-i
l l sp cS<.Aon s.r.4 1O
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) 3. f. Q CMTA1104ENT SYSTEMS
'3. fo. (s D 5tmausuunTIORAND COOLING SYSTEMS l
i (Containment SoraMiinum i __ __ LIMITING CONDITION FOR OPERATION &,;U,,f 6.i.g:y;fyi( t Ca* 2.4.6 Two independent Containment Spra/@_ sN11 be OPERABLE [r5
- u,spra syssum capsois or sexin ucsivu u v sr= nui en a 59 ... ni j pray Ac ation Signal and Safety toma call transferring sucti ection Actuation Signal a to the containment sump on
( pA i ci lati Actuation Signal. Each spray system flow pat rom the
- o inment sumo shall be via n OPra r thutdown coolinc cat murha=:r m- ,4
! APPLICABILI11: MODES 1, 2, and 3*. 8^'I 'O (I'M &
- o fdf 4 ke#
g,, A ._lACTION: W1th one Containment Spray System inoperable, restore the Ate.ne,
- ete j \ inoperable spray system to OPERABLE status within 72.hoursPbr be in at g,, g ,
st fl0T STANDBY within the next 6 hours and in LCIds anuavungwithin the l W** [hf(E_t]a Iis"6pKs l a
&#sof im :.:..;.1,a .se s.4.t.e-SURVE!LLANCE REQUIREMania g
~
i @ Each Containment Spray System shall be demonstrated OPERABLE:
- a. At least once per 31 days by: bb
__/_ _ ! 1. Veri ing that upon amerAcuirati6n actunsion) Test Sign A. ! the c si. 1 .6 s isoins rtvalves ,nn snu s at ec lation mod low v11 ay erERABLE s down cop 5pn 4,j SC 34 6 5 -- he exchanger i establ _ eds- , , ebai 4o . D Verifying that each v ve (manual, power-operated, or w w.d
- automatic) in the f1 path tha_t is not locked, ses d,or g. ~
- otherwise secured position 5sAositionea to same -ut 6iorz
. Fraprtne ,wi on aAontairmant PressGre-litch/tesBgsignal, j S - 8H 6.& .. v WahG b b 1 s on an
- G,.,,3st At least once per nuutLING INTERVAL, during shutdown, by
- J.<Aaler i e
s,, iA.I l
- 1. Verifying that each automatic valve in the flow path actuates !
to its correct position ansne supwur istr esras =p. signal._ ib Verifying that each _ spray ! Sf 't.&.t .L starts automatically on @ g,4 L ppProprisse carasjtes_tJgig .
- g 4 _
1 ] i M *e With pressurizer pressure > 1750 psia. AhT5 j CALVERT CLIFFS - UNIT 2 3/4 6-11 Amendment No. 189 d
}
} lO pp I.( .c l / n-m
- . . ~ - - - _ - _ _ - . ~ - _ - = _ - - . - . . - . _ . - - . . . _ .
l q y , . c, - 4. . . 7 . G . 4. i l INSERTS SR 3.6.6.1 and 3.6.6.4 ! Surveillance Frequency SR 3.6.6.1 Verify each containment spray manual, power operated, and automatic 31 days 3 valve in the flow path is not locked, scaled, or otherwise secared 4 in position is in the correct position. SR 3.6.6.4 Verify containment spray pumps developed head at the flow test point in accordance with is greater than or equal to the required developed head. theInservice
- Testing Program i
i 4 4 O 1 O e, zes
Cfg e f . . , 4 . . ,, 3.6.6 O ! 3/4.6 CONTAIMMENT SYSTEMS SURVEIL 1 JUICE REQUIREMENTS (Continued) M 3 b 9 J, Atjenst once perfyearsALpprfoming ani, or . i.finT O
..cn n resopoand vertrying each spray nozzle is u structeo.
to l O CALVERT CLIFFS - UNIT 2 3/4 6-12 Amendment No. 189 l O 9y us
. - ..-.- _~_- - .. . - . - . - . . _ . - - . - . - . - - . . -.-
Q , , I, . 4 . , , 'T. d . b I p Q
'5. 6 -6/+rt- CONTAINMENT SYSTDis *' '
_ [' ' ~ ~ __i3__P _' ' b i l '!. 6. 6 4/4.e.e 1EPR2STURIZATJ0r[AND COOLING SYSTEMS 3 h. w ntain-Cool - - System LIMITING CONDITION FOR OPERATION _" *V Lto "P. 6. 4 4.0.^." Two ups4 tainment brcuianseranc cooling nde. be . RABLEdf Is ero uni w so en s m .m ."2 l APPLICABILITY: MODES 1. 2 and 3. 42. sum yiDNCN. w m--a ^ YWitho ro@ of required containment 4Liz4fc1rcu3at1rn ane' d *NS cooling inoperable and both Containment spray systems Ijd"',*1 M Ac v io u C OPERABLE restore the inoperable group of air recirculation ends a ** # cooling units to OPERABLE status within 7 daysfor De in at least - A c7. . u t'. NOT 5NUTDOWN__within 12 heurt. - ( L , L
% (s e u + p i. a . ; . %
Acwou C h '1 tith ttirli'eW44gTrERTonunits af __
~rinoperable
- Q _.. and asis > cooling L- '7-both Contfn'gr_m sz.u;listteilPE ment Spray
'*^* ^#
bstore at least one 7 __airMIulatgb and cooling Ar* on E /to OPERABLE status wi n hours or be in at least 0 *'..',' "' @
\within 12 hours. Restore both above requirt.1 groupsof$0T SN/"7 (g3 g...,,,,., / containment air culation and cooling units to artuABLE status within sys or be in at leasty0T $NUTDOWN within 12 J E yhours.
g O~ Actou K With one group of required containment air recirculation and cooling units inoperable and one Containment Spray System
* **# A
/ Inoperable, restore the inoperable Containment Spray System to
* *" C ' (OPERABLE status within 72 hours or be in at leastf0T $NUTDOWNj ,
A cw oi.e r-ywithin12 hours. Restore the inoperable group of containment air l s recirculation and cooling units to OPERABLE status within 7 days , i
^<-"o*8 1"
---(of initial loss or be in at least d10T SHUTDOWN within 12 hours. J l SURVEILLANCE REQUIREMENTS 4.6.2.2 Each containment air recirculation and cooling unit shall te !
demonstrated OPERABLE:
\ At least once per 31 days (n.a.arnownts stn.,mtSIDg
\@peffig each ugiram the contgprroomp O CALVERT CLIFFS - UNIT 2 3/4 6-13 Amendment No. 189 l
- y. u .
. . . . . - . . .n 4....s . . p. , W c
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_>-....Q g' O' D.8 A.y c.w.- o.- . c-L. c es =ew h 4 *
- w e. e
- g. . a l,' (
yoge o
I T p -c L . 4 . , ';. 6 6 4 3/4.6 CONTAIIMENT_$YSTEMS i SURVEILLANCE REQUIRENENTS (Continued) l l
#" 3' y Verifying that each unit operates for at least 15 minutes.
! " II
% Verifying a cooline water flow rate of g 2000 spe_to each_
coolino rare fullyunitiwhen open.f the full flow servRe . ivr meet valves) sg M .5 b. verif At least starts automaticallyonce per onREFUELING the T-aa-i"? INTERVAL test signal. by&ying % that each u i i e g f .1 ~
._ a .4.. x g
( lO i I 1 i .I CALVERT CLIFFS - UNIT 2 3/4 6 14 Amendment No. 189 l I
- O p), 5.F 5
- - - - - . - _ . - . . . . ~ . . . - - .. -- . ~ . - - . . - - . _ _ _ - - _
l
- g., s . 4. _ ..c.F l
i O
- 3. 6 @ CONTAllMENTJYSTDis 3.6.T 6 10 DINE REMOVAL SYSTEM l LIMITING CONDITION FOR OPERATION t,c o 3 ,4 ,'y Three independent containment iodine filter trains shall be 1
- APPLICABILITY
- MODES 1, 2, 3 and 4.
4e.g.y 4 ,, With one iodine filter train inoperable, restore the inoperable n to OPERABLE status within 7 days or be in at least NOT STAMBY within i he next 6 hours and in COLD SNUTDOWN within the following 30 hours. j d Arveou C. - ' l SURVEILLANCE REQUIRDIENTS
@ Each iodine filter train shall be demonstrated SPERABLE:
( l 't. At least once per 31 days on a([ASSTRED TL3FTA56 *
% 5,(,,p g uns, in.n@w 6vn6mi wp Tiow snmuun we um Ti Ur- L A, t i !
. charenal aKorber train ary.&rirying snet the train opePates
- or at least 15 minutes.
i At least once maintenance onper the REFUELING INTERVAL HEPA filter or charcos adsorber or ( ) after anbstructural usings, or 4 (2) following painting, fire or chemical release in any I j ventilation zone f.ceenunicating with the system by: i
- 1. Verifying that the charcoal adsorbers remove 19M of a '
halogenated hydrocarbon refrigerant test gas when they are tested in-place in accorelance with Regulatory Posittor.s C.S.a and C.S.d of Regulatory Guide 1.52 Revision 2 March 1978 } while o i 1M. perating the filter train at a flow rate of 20,000 cfm
- 2. Verifying that the HEPA filter banks remove g 9M of the 00P l when they are tested in-place in accordance with Regulatory Positions C.5.a and C.5.c of Regulatory Guide 1.52 Revision 2 March 1978 while operating the filter train at a flow rate of f 20,000 cfm i 1M. j
$,, J . s , a . .. . F d . c., s 6 <; p ,. .C. . . + ,, , 5. o.
" A . . . . a , + ,, e (. 4 . . l . "
CALVERT CLIFTS - UNIT 2 3/4 6-15 Amendment No. 189 l E. % fts +r*;*s 4.1 /whrt. m ks;n
)
pO
,e. ue . + am
.1b dat.
=w __ - _.
=
l ,.r3 g
. jfe5 pska & @ ) . sy n W m bod t o ToseN 1 T. s. n I*pnnn f
!O l 97.y Ves);ld oa Rl bled,'af b'in.- (M) [ld
?/'.: rn=rur tyttra K '
j 7Q 7to.3 ionin u n = ~ ,,. g.,o L:== :a21m g ;,a ,,m - Three independent containment iodine filter trains shall be APPLICABILITY: MODES 1. 2. 3 and 4. Ellg: With one iodine filter train inoperable, restore the inoperable train to OPERABLE status within 7 days or be in at least NOT STANDSY within l I the next 6 hours and in COLD SNUTDOWN within the following 30 hours. J i
/ re e brg w, s1 su9 o S $bAA*f C fy 7pec) LJ /d I*^l e n';;:_ r : = ^/"::; ; T T k'l'#'E"I ' l O.6.a.1 tacn iocine filter train snais ne o.. .. 6 . ;; 0,=:= = = 9
{ a. At least once per 31 days on a STAGGERED TEST BA515 by ! initiating, from the control room, flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least 15 minutes.
- b. At least nee per REFU ING INTERVAL or ( ) after any ructural mainte ce on the HE (2) f lowing paint filter or cha os adsorber usings, or g, fire or ch cal release in ny
[ A*) ation zone c e nicatino wit the system by: [ LLll b h Verifyina that the charcoal adsorbers e 996,efa1 y Mated)rcrecarjorrrefrigpptnt t hen they are - , tested in-piece in suwi usnce witrr --,awrv Po,+uu is c.m
, entwJ.cJof Regulatory Guide 1.52 Revision 2 dw a7A3 '
while operating the filter train at a flow rate of 20.000 cfm 1 1M. ($ ll a. h Verifying that the HEFA filter banks (emove t 99% of the DOP when thav are tested in-place in accorcance witn Regulatory /A.7 fosit u.a anm r J- = W Guide 1.52 Revision 2 jm_.- Q4 19ffwhile operating the filter train at a flow rate of Z0.000 cfm ~+ 10%.
$ e g 4. ()eube/'N A A35
' 173 410 %
.o CALVERI CLIFF 5 - UNIT 2 3/4 6-15 Amendment No.189 l O
p4es s
oc .G ,. 4 . o - C+8 O 3/4.6 CONTAINVENT SYSTDQ SURVEILLANCE REQUIREMENTS (Continued) [ ff., nnin .n says after removal that a laboratory analysis of a representative carbon sample obtained from an adsorber tray or from an adsorber test tray in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revision 2. March 1978, demonstrates a removal efficiency of 2 95% for radioactive elemental todine when the sample is d tested in accordance with ANSI N510-1975 (130*C 95% R.H.).
- 4. Verifying a filter train flow rate of 20,000 cfm i 10%
' during system operation when tested in accordance with ANSI ) N510-1975. After every 720 hours of charcoal adsorber operation by: Verifying within 31 days after removal that a laboratory analysis i of a representative carbon sample obtained from an adsorber tray or from an adsorber test tray in accordance with Regulatory ! Position C.6.b of Regulatory Guide 1.52. Revision 2. March 1978, I i demonstrates a removal efficiency of 2 95% for radioacuve elemental iodine when the sample is tested in accordance with ANSI N510-1975 (130*C, 954 R.H.). l ^ Subsequent to reinstalling the adsorber tray used for obtaining i i the carbon sample, the filter train shall be demonstrated i OPERABLE by also verifying that the charcoal adsorbers remove ' s O
' 2 99% of a halogensted hydrocarbon refrigerant test gas when they are tested in-place in accordance with Regulatory Positions C.5.a and C.S.d of Regulatory Guide 1.52 Revision 2 March 1978 while operating the filter train at a flow rate of 1 20,000 cfm i 10%.
j ] (,,, d.sc , m .. .I eLa-s's pg $ p ,c F . 4'. ., 4.0,
~~ A s ... ,< <<,A h e Ce A ro's I
J 1 CALVERT CLIFFS - UNIT 2 3/4 6-16 Amendment No. 189 l l O y , .e 2
~ ~ ~
RS M.'on h W1M ~ P W W " i'E (pne N 04In O s s II
~
frTP
- /:.; _m - m,_
"- E -A ^ 7. G. a -... . . ( ^- . . .. _ _ _-^,
f Of,//, c [ Verifyingd.t.' 7; n-x fr: --**-- == -Mhat a laborato analysis of a representative carbon sample obtained x __......x.......-M n__mera W Lde"7 with(Renw'EterYJe5TT1on.Livenf QIJMegulatory Guide 1.52 Revision H.Utar.atOnzar osmonstrates a removal efficiency of 2 9M for radioactive elemental iodine when the sample is tested in accordance with ANSI N510-1975 (130*C, 9M R.H.).
. Ve fying a fil train flow ra e of 20,000 cfm i s ing system ation when ed in accordanc th ANSI Jil sto.to7s
- b. AfM every 7204uw= af eka M =da#-- -f--+4an hA Verifyingy :: A; 'ter z: :Ut}iat a laboratory ana' vais \ f fe [,/1. C of9 a<represemative
- g ;,w -- + carbon lample obtainedEr= .., 2 rir Lf,7
-- } - -
. - " r:0n Lnce with
~
u' atory _ " yosi,pei C.6JMenut' 'torf , Rev'liitin , Qiametf"19FE1 comonstrates a removal efficiency of 2 9M for radioactive elemental todine when the sample is tested in accordance with AN51 N510-1975 (130'C, 9M R.H.). puoseg sIrei talling tyt sesorper tyey used ODtainin the ca O i sg tha ff1Mr train shaW be demon g g,ll,6 erifying that the cnarcoal assoroe re tore _ ry n % ,23 s Cer a aM5.e=> Regulatory Guide 1.52 Revision 2
- liarmrurwwille operating the filter train at a flow rate of . _,
20,000 cfm i 10%.
',a a enc' /,*
7 A 3 1; n j:ACf N ) , O '/ _ ,J" i i i } l ,4 l CALVERT CLIFFS - UNIT 2 3/4 6-16 Amendment No. 189 l 1 lO 1 ) a ikf e 37./57 a
_ __ _ . . _ _ ._____ ___ _ . . _ _ _ _ _ _ _ _ _ _ _ - ._m _ ___ . . _ 4 n.Is. &.., 3. 6. F 4 O 3 3/4.6 C0llTAllMENT SYSTD15
)
SURVEILLANCE REQUIRDIDITS (Continued) l i '
- p. At seast once per REFilEIllG INTERVAL by
i l
- 1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 6 inches Water Gauge while operating the filter train at a flow rate.of 20,000 cfm A . 2.
l 1 10%. yQ e ,,,, , , , 1, , , ,, q
- '5'et L ' S.3 A Verifying that the filter train starts on t4eserfraty estsignal.7; Q Af ter escnthat by verifying ---iete the HorPAgarusi . yli.._remove filter banks .. vi >e 99% nr.raofniter bank]
the DOP when they are tested in place in accord.nce witi Regulatory ~ Positions C.5.a and C.5.c of Repenatory Guide 1.52 Revision 2 March 1978 while operating the (11ter train at a flow rate of 20,000 cfm i 10%. j
\ After each complete or partial replacement of a charcoal adsorber i
bank by verifying that the charcoal adsorbers remove t 99% of a halogenated hydrocarbon refrigerant test gas when they are tested 1 in-place in accordance with Regulatory Positions C.S.a and C.5.d of Regulatory Guide 1.52 Revision 2 March 1978 while operating
- the filter train at a flow rate of 20,000 cfm110%.
! g. After maintenance affecting the air flow distribution by testing in-place and verifying that the air flow distribution is uniform within 120% of the average flow per unit when tested in accordance with the provisions of Section 9 of " Industrial Ventilation" and Section 8 of ANSI M510-1975. 6e J.sem - DI A -VS
- p. , g ~..r., +.,, E o, "A .L . - . s , ,4 . - c.t~I g
-- n --
S tt 1 .(. 0 2 heb regetu9 En f. A -bMeg in . To acwJ~u A c ue de.cig g,R . S.a A+,k4, f".W e M O yFM
~ %~ . c.p.m (yrn).
CALVERT CLIFFS - UNIT 2 3/4 6-17 Amendment No. 189 l O y , .e 2
( p+ 7 < IC J Is- ) Q .. s.7,11 V^FTP l l m ass d Monet nar/ner arruse4mc Infratutf),vy- - ~/ ( N'jf, Verifying that the ressure drop across the combined HEPA filters and charcos adsorber banks is < 6 inches Water Gau while operating the filter train at a flow rate.of 20,000 e 1
- s e e D;.r e> J s le d fl. ff 7,6,9b**
L Verifying tsrAS tatt that sinnal the filter f train starts on the appropriat3) d d**/W g,ef;fw j
~
ach MTjit or " iL pf ==_v n r i",er nam
*TR5" A./
- k, .0 //,4 fying tiat the HEPA f hnksgramovu t vvg 0" r,ne D0D n they are tested in place in accordance w' th uistory O s s .a.. ;.n.c e u ators Guide 1.52 vision 2
\ un11e operating the ft ter train rate of -
20,099 cTm i 10%. I* 1 wh'15 MWC \ f,y, jf, b te ach_*=lat#er partial replac=Wof byfverifying that the cnarcoal assorbe_rso - t charenal Marbe 3
-- vs m (fe g,p h 55 ;
malnated n vcarpon reptferent smastMen Eney are l g,g in-place in accordance witntRegaawwry rosltip = = ! R ulatory Guide 1.52 RevTsion Ztnacen my while operating 1 Iter train at a flow rate of 20.000 cfm i 10%. i After maintenance Tecting the air flow distribu n by testing in- lace and fying that the air flow distr ton is unifom% ,') I wit in i 2 of the average flow per unit tested in
! accorda with the provisions of Secti of " Industrial t_ Vent tion" and Section 8 of ANS! N_510-1975. 4 NN^We I ff 0 L/ 5.s l op S oh 52 3 ,a.k '3,0,3 4
~
g'"phedle k & rrrp Te},02, we:es. . U --L w _-y,m s._ A. - -. m \
,i 1 ,
CALVERT CLIFFS - UNIT 2 3/4 6-17 Amendment No. 189 l O ro.rs,
1 l SydrJ r,s T 3.~7 i i i t { , - ~- We h wef.h kelesy$ i f r- S p A . G ., 7.L.5, f 3/4.6 CONTAIlgiENT SYSTDi$ 'D 4ra~dI,.f 4 % ///' l 3/4.6.4 CONThlfg(ENT ISOLATION VALVES l LIMITING COWITION FOR OPERATI0li 3.6.4.1 Each containment isolation valve shall be OPERABLE.* ' APPLICABILITY: IIODES 1, 2, 3, and 4. AGIlgi: With one or more of the isolation valve (s) inoperable, either: j a. Restore the inoperable valve (s) to OPERABLE status within 4 hours, or
- b. Isolate each affected penetration within 4 hours by use of at least position, or one deactivated automatic valve secured in the isolation
- c. Isolate the affected penetration within 4 hours by use of at least one closed manual valve or blind flange; or d.
Be in at least 110T STAllDBY within the next 6 hours and in COLD 5HUTDOWit within the following 30 hours.
- e. The provisions of Specification 3.0.4 are not applicable provided that the affected penetration is isolated.
O SURVEILLAllEE REQUIREMENTS 4.6.4.1.1 Each containment isolation valve shall be demonstrated OPERABLE# prior to returning the valve to service after maintenance, repair, or replacement work is performed on the valve or its associated actuator, control, or power circuit by performance of a cycling test and verification of isolation time. l Valves that are normally closed may be opened on an intermittent
@% is under Iont'ainment ource administrative
' solation valves isolation control.
times will only applyh flDPE 6 mhe va' ves aremuired to _Mm-" Vand they are open, fisolationti HDDES 1, s3for contalnment rge isolat' on valve s MA for and 4 per Techni 1 plM. Specification 3/4 .1.7, during (whichti these valves must emain closed. IYM CALVERT CLIFFS - UNIT 2 3/4 6 18 Amendment No. 189 l O ( ivva..-% e Og cone cre w iesi used).w, r<n - c.,+. NRC % owt yg
._ ___ _ ~..__ ___. _ _. _ _.._ _ _. _ . _ _ _ _.-._.__.__.___ _ _
$ p ec. . F . < s.+ .. "J. 6 , 3 5
!O j '34 $ fir:t CONTAIl91ENT SYSTEMS y, 4,, 3 t/0.0.7 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION
" U 4,6,4,4 Each containment isolation valve shall be OPERABLE.* '
APPLICABILITY: NODES 1. 2. 3 and 4. EllGE: With one or more of the isolation valve (s) inoperable, either: L.. ) ore sne r :::raMe valvMs1 to er--= Mtatus mrMan hours._ W j w .. A 6, ,, g ,,,,e
\ . . t ,,, -.
,.gv.g. ,i,,m, ,,q.. . . i,,4 A. ,, g, g M 'oM Kfisolateeachaffected tion within esii.1 as - --
1 east one deactivatet _ tic valve securs the isolation bf~ , w*N Ay, 4 c - - position, or-A U fc'
- C 'Gj
% !solate the affected penetration within urs by use of a --
,least one closed manual valve or blind ang or -U esiou A. 2 Ac r.ov Be in at least NOT STAISBY within the next
- O -
'd.
A [SNUTDOWN within the following 30 hours hours. 7, and in_COLfl,3."2. ,4 C.2
;,,; =
l
. 1 -. . iziens OT > T1 cation 3.0.4 not applicjkTe provideTi at the affected tration is i ted. f ~ 3 l
_ _ _ - - -- _ __ 4. O O 77-g] C Na __ m - Acrich ro,s3 (, -
- A.6
$URVEILUWICE REQUIREMENTS Di T.6.4.1 Each containment olation valve shall sesonstrated OP LE
prior returnin the val to service after ntenance, repair. ' rep cement work s perf d on the valve or s associated act or. c trol, or power cire by performance af ryr14aa **** and .rificatian J M(' L A - f isolation time. .7 Co 4.4.. A415 WoTE: Oay y .wi e 4. p,.,.4. [.,A,_ p 44., m
+- c, a -
g * *' . " -- 4
*J oT E : o27 ,pp .c u
^
g c 4 p..i. . % r t .- p 44. [ cA.
- c. i .. . t
-Qe Cov .e <. p e .
AC' ' *"5
- Valves that are normally closed may be opened on an intermittent w e t. s basis under administrative control.
contan. ..s purge isolation valves isolation times will only apply in N0DE 6 when the valves are recuired to be OPEP_^='r and they are open ( Scht h: t' :: ' r ...J..:- --' -" ; "-' et h: ::h;; '.; . ?r g fg l ^G i . 4. s anc
- per s w6nni6si .,m rt'^ '"' " 1.?, ... irig Ng Q}. C 6... v ivra must ru= sin 6. .. . -
CALVERT CLIFFS - UNIT 2 3/4 6 18 Amendment No.189 '
$o.e .I . w s . ~ a f C%. -< * >
p,, g , c . f, , 4 . . 3. '5. h m ,, p me- I .& (p
/ S6-04 2 ~
. - . . _ . . ~ . . - . _ - - - . . . _ . - . . . - _ . . . . _ - . . _ . - . _ . . - . . - . . - . - - .
SpCub~343 INSERT 3.6.3 REOUIRED ACTIONS A.2. B.2. & C.2 , M A.2 NOTE , lealatian devices in high raant- areas may be ven6ed by use of administrative means. , Once per 31 days for isolation devices Verify the affected W4;c:1 flow pathis outside caatsiament. isolated. l M Prior to entering MODE 4 from MODE 5 if ! not gifv i..id withm the previous 92 days ! for isolation devices inside cor.tainment j i i M B.2 NOTE I=alat= devices in high radation areas may l be veri 6ed by use of administrative means. Once per 31 days for isolation devices ) Verify the affected psion flow path is outside containment. iaaintad Priorto entering MODE 4 from MODE 5 if not performed within the previous 92 days ! for isolation devices inside containment. M C.2 NOTE Isolation devices in high radiation areas may be verified by use of admimstrative means Verify the affected pe;osi flow path is Once per 31 days isolated. P'y 2 p.
S pec.L4.s 3.4.3 INSERT 3.6.3 ACTION NOTES 2. 3. & 4 NOTES
- 2. Separate Condition entry is allowed for each penetration flow path.
- 3. Enter applicable Conditions and Required Actions for system (s) made inoperable by emainmentisolation valves.
- 4. Enter applicable C#ims and Required Acbons of LCO 3.6.1, "Caa*=ia=aat," when leakage results in --Mag the overall contamment leakage rate -:+2-=4 cnteria.
l l i P'y 39 " l I
k/c 8' . 4. e n 3.6.3 i U f 3/4.6 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) D. 4 . Each containment isolation valve shall be demonstrated OPERABLE duringThe COLD 5NUTDOWN or REFUELING MODE at least once per REFUELING INTERVAL by:
, 3, q erifyf aa that on est nt isoist uni.pannel_ A or i-
- test signal, each req Ja m a;.Ct,actus_t p g-solation position. ep jefylggyjg y Q.
l , T '!:-"* thet e e#Cet:'n ::t ".:d';t'= "';h in Ch:x;l A 16VRt94-(*& C;.....,e'. ll tea , ', 5:'.h ;er't'=f n ;;' ed cer.t;' ---- t = r : ':!'"e" > ut.;;; t; th.'- t_[:I:t'= in
~~
l . e in t _ each M'i@FfilW=na i a:n es sional, each required isolation valve actuates to V L l its' isolation position.
<R r, , (,, *g , c. M The isolation time of each power-operated or automatic s
containmentisolation valve shall be detemined to be within its limit when tested @ ntl o Tectona,LJpect ucation 4.0 R l A,3 h -- or .
--c Tv.g P. g. ..]
O I l 1 4 1 CALVERT CLIFFS - UNIT 2 3/4 6-19 Amendment No. 189 l O
$$$Q ff O
i l Q -e X...<... L T.I o i l b l 1.3 t NTt RvM FNT gn0A; h l M ,g ) 3 T*10 3/4.6.5 00PGWSMOLE-GAS-60Hilet--
- umrms comma rea OPEnATIm 1
i 3.6.5.1 Two independent containment hydrogen analyzers shall be OPERABLE. i APPLICABILITY: MODES 1and{ g113:
"4 f % With one hyd analyzer inoperable, restore the inoperable 1 analyzer to status within 30 days or:
- g <';I. r_ ----; - - _it; a spe'fal prepa're and
- - ' -_ a c ---M r ---- m --
report o'the' Commission
- = -
l 7 A c t ion c E", bl.de n d'a " pursuant t pecification 6.9.2 w in the following days, j laue4 .c rik outlinin he action taken, the ause for the inoper 111ty. I l p g ,45,0 up__ and tb lans and schedule f restoring the syst _M GPE"??I status, or to j 4.- % 1. ;t h;;; R? .il_ ::V Winin ins nun o .-i ..- L,$ j N T c'J C , ith both hydrogen analyzers inoperable, restore at least one i noperable analyzer to OPERABLE status within 72 j at least NOT STAllDBY within the next 6 hourgy)ours or be ingg'{ , i j Ar* at; E D ' '
- o
/ _\ Specification 3.0.4 is not applicable to this requirement.
- An . .v 4
> Jew , L, y*l l
w-i 4 i SURVEILLAllCE REQUIRDIENTS
$G.i.L7alihWfogen analyzer shall be demonstrated OPERABLE at least bi-week 1 on a STAGGERG TEST RASIS by drawing a sample from the Waste Gas (['
ystem rough the hydrogen analyzer. f g-,g'a 'g (4 Mr.1.3 Each hydrogen analyzer shall be demonstrated OPERABLE at least once r ys on a ETAGGERED TEST SA515 by performing a CllAIBIEL us ng sample gases In accorcance witFmH0Yunu....: 3 -- (comme ion . r y , C3 h CALVERT CLIFFS - UNIT 2 3/4 6 20 Amendment No. 189 l O y sa,
.~. - ~ ~- _ .- _..- - - - -._. .- .- . - . -. . _. .. .
4 T5 3. c. 6, / WED 70 % E C T 'ok! ~5 3 (3,*410 PAMI) O
- 3/4.6 CONTAINMENTSY$TEMS t
l 3/4.6.5 COPSUSTIBLE GAS CONTROL Hydronen Analyzers l l LIMITING E01 BIT 30ll FOR OPERATION 3.6.5.1 Two independent containment hydrogen analyzers shall be OPERABLE. EfMCABILITY: MODES 1 and 2.
- AU.1GE
- s. With one hydrogen analyzer inoperable, restore the inoperable j analyzer to OPtRABLE status within 30 days or:
- 1. Verify containment atmosphere grab sampling capability and prepare and submit a special report to the Commission pursuant to Specification 6.g.2 within the following 30 days, outlining the action taken, the cause for the inoperability, and the plans and schedule for restoring the system to OPERABLE status, or
- 2. Se in at least NOT STANDBY within the next 6 hours,
- b. With both hydrogen analyzers inoperable, restore at least one inoperable analyzer to OPERABLE status within 72 hours or be in O c.
at least NOT STANDBY within the next 6 hours, Specification 3.0.4 is not applicable to this requirement. i SURVEILLAntt 2EQUIREMENTS 4.6.5.1.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least bi-weekly on a STAGGERED TEST BASIS by drawing a sample from the Waste Gas System through the hydrogen analyzer. 4.6.5.1.2 Each hydrogen analyzer shall be demonstrated OPERABLE at least oncepr g2 days on a STAGGERED TEST BASIS by perfoming a CNAlulEL CAL!suTI0li using sample gases in accordance with manufacturers' ) recommendations.
/
l CALVERT CLIFFS - UNIT 2 3/4 6-20 Amendment No. 189 l O n,-
h e . F. %+.., 3 . 6 . '7 i O 3.6 fftd CMTAINMENT SYSTDis 3.6. ~7 '3/4.^.3 kOMBUSTIBLVGAS CONyROD [ ectri rooen Reco iners @ LIMITIM C M DITIM FOR OPERATI M
# 3.' 7 3.6.5.2 Two fndsedndContainment Hydrogen Recombiner Systems shall be
. -au=r-APPLICABILITY: IWDES 1 and 2. e p wi - e
^#'#Q sp/,c44) .. _
D*N A % : With one Hydronen Recombiner System inoperable, restore the noperable system to SPIRABLE status within 30 days or be in at least NOT
/$TAND8Y within the next 6 hours.
bN_ hCT'01[ __
$URVEILLANCE REQUIREMENTS
@ Each Hydrogen Recombiner System shall be demonstrated OPERABLE:
% 'At least once per 6 months Dy veri 1ying curing a recombiner__ 7 system functional test that the minimum heater sheath temperature L'1 increases to y 700*F within 90 minutes and is maintained for at j O
deast 2 hours., , g At least once per REFUELI M INTERVAL by: S P, T . C ."7. 2 erfoming a CHANNEL CALIBRATIM of all recombiner instrumentation and control circuits. K Verifying through a visual examination that there is no sfR t . C.. 5 evidaara a' "-- 1 endt ns within the recombiners -- - oose wiri or st ural connecipns, deposit /P L ^ - gn matert ,etc.)
A D '4 I h Verifying during a recombiner system functional test h penterA..earntemper rw m rvene to pzpo t within ours 4'
,u mMntained for east 4 hours
% performing Gnw a continuity _6m warity of tha Mater electrlsel circuits 5j-and resistance to ground tatt ~/ u, N 3 C 7. + /IE Mrffig the ~~ v .- iiun usu si=6 m (to grswfid for any er phase shay iv.J vw s CALVERT CLIFFS - UNIT 2 3/4 6-21 Amendment No. 189 l
- O py I .F 2.
T p-c . r. ..a .. T. 6. 7 O INSERT 3.6.7 ACTION B B. Two hydrogen recomtaners Is.1 Verifybyadministrative 1 hour inoperable, means that the control function is maintained. M Every 12 hours therenner AIE! B.2 Restoreonehydrogen 7 days recombiner to OPERABLE status. t i (
- O p or g # 7 oI1
g,fuA*. 3 E. C./ M OJ EO 70 S E'r TioM 3, 7 lO r 3/4.6 CMTAllelENT SYSTD15 3/4.6.6 PENETRATION R00M EXHAUST AIR FILTRATION SYSTEN LIMITING CONDIT!011 FOR OPERATICII I 3.6.6.1 Two independent containment penetration room exhaust air filter l trains shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. gI13: With one containment penetration room exhaust air filter train l Inoperable, restore the inoperable train to OPERABLE status within 7 days or be in at least NOT STAISOY within the next 6 hours and in COLD SNimMRAI within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.6.1 Each containment penetration room exhaust air filter train shall be demonstrated OPERABLE:
- a. At least once per 31 days on STAGGERED TEST BA535 by initiating, from the control room, flow through the HEPA filter and charcoal adsorber train and verifying that the train operates for at least l 15 minutes.
I b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone connunicating with the system by:
- 1. Verifying that the charcoal adsorbers remove 199% of a halogensted hydrocarbon refrigerant test gas when they are tested in-place in accordance with Regulatory Positions C.S.a and C.S.d of Regulatory Guide 1.52 Revision 2 March 1978, while operating the filter train at a flow rate of 2000 cfm i 104.
s t CALVERT CLIFFS - UNIT 2 3/4 6-22 Amendment No. 189 l O
-y mz
- . - _ _ . - ~ . - .- . ~ _ _ . __ . - _ _ . - - - . _ - .
a r (
*j f ) -9fb 6 $0NTAIMMENT SYSTEMS 7 ,7,12 4'; e o - PENETRATION ROOM EXHAUST 61R FILT' RAT 1035YSTEM QM l
LIMITING CONDITION FOR OPERATION
- Ltd.T,.7,4 i . .o.a Two independent containment penetration room exhaust air filter trains shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3. l I g "' With one containment penetration room exhaust air filter train nopera:ble, restore the inoperable train to OPERABLE status within 7 days
/
4 4 r be in at least NOT STANDtY within the next 6 hours and in COLD SEUTDelAt I ! /icfi n M ~ tthin the following 30 hours. I i SURVEILLANCE REQUIREMENTS l 0.0.0.1- Each containment penetration room exhaust air filter train shall be demonstrated OPERABLE:
- Sk3'7'O'I k. At least once per 31 da o t STAGGERED TEST BASQi,4y initiating A .)
through tne HEP M Ser and charcoa
,O /Trom the control room f ,
{adsorber train and verifyinJ that the trainfoperates for at least i D minutes. i b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ! ventilation zone coernunicating with the system by:
- 1. Verifying that the charcoal adsorbers remove t 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with Regulatory Positions C.S.a 4
and C.S.d of Regulatory Guide 1.52. Revision 2. March 1978, i . while operating the filter train at a flow rate of 2000 cfm
)
(d t. Diggu.,s s ) c oJ Oh" C]1n @ L. hev- [ptd. I ic i## w;<LiA c,E'L)li .
\
. \
"' W [ j , j. )svs4,lkekbay &zs-en r' "
l' (L-- CALVERT CLIFFS - UNIT 2 3/4 6-22 vrre A P/ Amendment No. 189 l H< l 4 O O
~~
l ! l[-fudt*A f ve40 th:d,$ yVm g,A GJl 'f U ' T ! d!Wu s~S U ~ p f' A Za se+ ((, Il j (PA N 8 *S-I O Arid Sur, Il V FTP 3/4.G.G ?"r' ?"?""' : .r.; riruattet ATR FitinATinN tyttru _ 1 LINITING CONDITION FOR OPERATION l l 6.6.1 Two independent containment penetration room exhaust air filter trains shall be OPERABLE. 1 APPLICABILITY: MODES 1. 2 and 3. - Ell 2H: With one containment penetration room exhaust air filter train , inoperable, restore the inoperable train to OPERABLE status within 7 days C or be in at least NOT STANDBY within the next 6 hours and in COLD SNUTDOWN J ghinthefollowing30 hours. g f jee D: g, s s.'eo a .,,,
. 2 '/ isd
$URVEILLANCE REQUIRENENTS 6 d, d A M /;[,/M
;;..;;r.U... . ransun air v iii=> u . ... .ii.ii
- s. At least once per 31 days on STAGGERED TEST BASIS by initiating.
, from the control room, flow through the HEPA filter and charcoal l adsorber train and verifying that the train operates for at least i 15 minutes. j
- b. At least on er 18 months or ( after any structu mainten on the HEPA filte charcoal adsorb housings, or (2) wing painting, f1 chemical releas n any I b' 7/ .
i ation zone connuni ing with the syst y:
.V ing that the charcoal adsorbeg 99Adr a enaten,.mycrocarbon Tetrigep rrt te I' 'll' b testea 1 e.hev are ace in accordance witn merm*nTery norm m -e'C d i ~7 Regulatory Guide 1.52.levision 2.uset'il?78) whi ing the filter train at a flow rate of 2)00 cfm j
. m. -
g,s 4 im
~
4,4 alssh pins [ Q 1 l CALVERT CLIFFS - UNIT 2 3/4 6-22 Amendment No. 189 l
- O l ey n&s'
ss. LA. 3. r.. c ; l g-104 B O To S Getio AJ p i 5
/4.6 CONTAINMENT SYSTDt3
$URVE!LLANCE REQUIREMENTS (Continued)
, 2. Verifying that the HEPA filter banks emove 199% of the 00P when they are tested in-place in accordance with Regulatory Positions C.5.a and C.5.d of Regulatory Guide 1.52 j Revision 2. March 1978, while operating the filter train at a flow rate of 2000 cfm i 104. .
- 3. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained from an adsorber tray or from an adsorber test tray in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revision 2. March 1978, demonstrates a removal efficiency of
', 2 90% for radioactive methyl iodine when the sample is tested in accordance with AN$1 N510-1975 (30*C, 954 R.H.). 1 ' 4. Verifying a system flow rate of 2000 cfm i 20% during system , operation when tested in accordance with ANSI N510-1975.
- c. After every 720 hours of charcoal adsorber operation by: I i Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained from an adsorber tray 1 or from an adsorber test tray in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2. March 1978
! demonstrates a removal efficiency of 2 90% for radioactive O methyl iodine when the sample is tested in accordance with Q ANSI N510-1975 (30*C, 95% R.H.). l j s" 1 CALVERT CLIFFS - UNIT 2 3/4 6-23 Amendment No. 189 l O n us
g_ 3, , . , , i 1 O I a
- 3/4.6 CONTAlllMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) f2. Verifying that the n6rn iih m senh . - ve r 99% of the D0P F when they are tested in-place in accordance with Regulatory j Positions C.5.a and C.5.d of Regulatory Guide 1.52.
Revision 2. March 1978 while operating the filter train at a flow rate of 2000 cfm i 10%. - t, i 3. Verifying within 31 days after removal that a laboratory
- analysis of a representative carbon sample obtained from an 2 adsorber tray or from an adsorber test tray in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revision 2, March 1978, demonstrates a removal efficiency of i
2 90% for radioactive methyl iodine when the sample is 1 tested la accordance with ANSI N510-1975 (30*C, 95% R.H.). ! 4. Verifying a system flow rate of 2000 cfm i 10% during system operation when tested in accordance with ANSI N510-1975. l e . After every 720 hours of charcoal adsorber operation by: j Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained from an adsorber tray i or frtwa an adsorber test tray in accordance with Regulatory I i p Position C.6.b of Regulatory Guide 1.52. Revision 2. March 1978 l demonstrates a removal efficiency of 2 90% for radioactive 4
- methyl iodine when the sample is tested in accordance with
( ANSI N510-1975 (30*C, 954 R.H.). $ S't ' Dis wstoa b C n , l Sf tel l t 4 hlos) T,0 \ N ei/) i j A- I M. &J f ' ) I I.a i 4 I i i i
! CALVERT CLIFFS - UNIT 2 3/4 6-23 Amendment No. 189 l j !O l C 2-i
$pcohteAvim 3
- w I
raSu+ C.T.II ('
\
IM'9* ., a F,5, // v*FTP g,gM,,,b , eveL sk'n"I 3/4.6 CONTAINMENT SYSTEMS ASI d. I'#'[# SURVEILLANCE REQUIREMENTS (Continued) f'Y' I 7' A k. Verifying that the HEPA filter banks [emove ? 99% of the D0D when they are tested in-place in accordance with Regulatory (Fouerons da ane t o.wacer0 Guide 1.52 / A.)
- Revision 2.01arth4912, while operating the filter train at a flow rate of 2000 cfmi 10%. -
$e p' /[' d % VerifyingCwitflin 3f days After rimoval] that a labora analysis of a representative caroon sample _ obtained A ')
(dserdrAfav 6F fr6fii an adssiferAes tray in acco with( AtetoryMI1 tion.A6"b of)Re u ry Guide 1.52 RevisiofFZ.LMarch )f7#, demonstrates a removal efficiency of 2 90% for radioactive methyl iodine when the sample is tested in accordance with ANS! M510-1975 (30'C. 95% R.H.). (6. Verifying aperatt a tem flow rate of ZDJVcfm :t 10% during>ytt ' d ,'J hen tested in accordArife with ANSI N510-1975. 6Mr every 720 drs of _chdal adsorber pptration b V',:riffingfgitMe-31-days-af ter removtI) thatl laboratory analysis of>_ representative carbon sample obtaineg[,from f an>csorcerAr s6 ,5, II; C 6/tos-ch acsercerma pey)1n accordance witn segula / rN Qosilacfi C.eMi Meow +1rtory/ Guide 1.52. Revision 2.da '7 i demonstrates a removal efficiency of 2 90% for radioactive ( methyl iodine when the sample is tested in accordance with bl ANSI N510-1975 (30*C, 95% R.H.). CALVERT CLIFFS - UNIT 2 3/4 6 23 Amendment No. 189 l O U fggt bo
N Fo 7o Sect,ov T. 7 1 [3/4.6 CONTAINMENT SYSTEMS j SURVEILLANCE REQUIREMENTS (Continued) 1 Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample. the filter train shall be demonstrated j OPERABLE by verifying that the charcoal adsorbers remove t 99% of the halogenated hydrocarbon refrigerant test gas when they are
- tested in-place in accordance with Regulatory Positions C.S.a and 4
C.S.d of Regulatory Guide 1.52. Revision 2. March 1978. while operating the ventilation system at a flow rate of 2000 cfm
+ 1M.
{ d. At least once per 18 months by: i 1. Verifying that the pressure drop across the combined HEPA 1 filters and charcoal adsorber banks is < 6 inches Water Gauge while operating the filter train at a flow rate of 2000 cfm 1 1M.
. 2. Verifying that the filter train starts on Containment Isolation Test Signal.
b
- e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove > 99% of the 00P 1 when they are tested in-place in accordance witE Regulatory Positions C.S.a and C.S.c of Regulatory Guide 1.52. Revision 2
- March 1978, while operating the filter train at a flow rate of i
2000 cfm 1 20%. ' l W f. After each complete or partial replacement of a charcoal adsorber j bank by verifying that the charcoal adsorbers remove t 99% of a halogenated hydrocarbon refrigerant test gas when they are tested
- in-place in a
- cordance with Regulatory Positions C.S.a and C.S.d i
- of Regulatory Guide 1.52. Revision 2. March 1978, while operating '
l the filter train at a flow rate of 2000 cfm i 10%. ] g. After maintenance affecting the air flow distribution by testing a in-place and verifying that the air flow distribution is uniforz within i 20% of the average flow per unit when tested in accordance with the provisions of Section 9 of " Industrial , i Ventilation" and Section 8 of ANSI N5101975. 4 d i I i . CALVERT CLIFFS - UNIT 2 3/4 6-24 Amendment No. 189 l l 4 J
;O l
9y 1 or 3
gg sbi(*fsfiddl B
- 0* %
V 3/4.6 CONTAINMENT SYSTEMS SURVEILtANCE REQUIREMENTS (Continued) I Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the filter train shall be demonstrated . OPERABLE by verifying that the charcoal adsorbers remove t 99% of the halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with Regulatory Positions C.S.a and C.S.d of Regulatory Guide 1.52. Revision 2. March 1978, while operating the ventilation system at a flow rate of 2000 cfm i 10%.
- d. At least once per 18 months by:
- 1. Verifying that the pressure ' rop across the combined HEPA filters and charcoal adsorter banks is < 6 inches Water Gauge while operating the filter train at a flow rate of 2000 cfm
( i 10%. J SE LM 3 % Verifyino thatATIe~ filter train starts onLentriC AN /v '/,3 e I. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove 199% of the DOP when they are tested in-place in accordance with Regulatory (% ( ) Positions C.5.a and C.S.c of Regulatory Guide 1.52. Revision 2 V' March 1978, while operating the filter train at a flow rate of f 2000 cfm i 10%.
- f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove t 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with Regulatory Positions C.S.a and C.5.d of Regulatory Guide 1.52. Revision 2. March 1978, while operating the filter train at a flow rate of 2000 cfm i 10%.
- g. After maintenance affecting the air flow distribution by testing in-place and verifying that the air flow distribution is uniform within i 20% of the average flow per unit when tested in accordance with the provisions of Section 9 of " Industrial entilation" and Section 8 of ANSI N5101975.
CALVERT CLIFFS - UNIT 2 3/4 6-24 Amendment No. 189 l w2 ,+ 3
[Vkcf) lyr4 ?.: A) O Y ll Y l l'l j q & ' ' ' L" ' ' ' " '
.[ a$ uy [. T. it (pine k d in O f,5 e ll MW h,ll e w m asms
$URVEILIANCE REQUIREMENTS (Continued) 1 8ubseg o reinsta g g the adsorbe ray used for obtaini th on sample.#le filter train all be demonstpd ed q __ mir hyferiifing snet tne cnarconi aasoroersfrapove z yy4 o / 4.7
, g 'f' jl'h <t.le haJagenatis.myarocargosrterrigeeent_ te testea in-place in accoraance witn gagetut _ _ ./ithen~they are.. C.sa=1iilP}
-- ^^
q.* 4r Regulatory Guide 1.52. Rev1sTon Z.@= '-- f.. Al whil ng the ventilation system at a flow rate of 2000 c .g ]
~
k.Atleastonceper18monthsby: ed syk,.~ lx,p:J -
.& g, o </, <
7.T",11. J (. Verifying that the ressure drop across the combined HEPA N filters and charcoa adsorber banks is < 6 inches Water Gauge - while operating the filter train at a flow rate of 2000 cfm . L 10% ee p;scw'"' * $ ' (ll!. Verifying that the filter train starts on Containment dFJff b NC ( Isolation Test Signal. 7,7, /t;" P RfFS ] M'
~
\.
d 5, 5 /l. 4 f eriffiWdiMhTRIPA Tift'e7 sin ~f-(- A E i;; V'4ee4en U< ; e they are tested in-pla_ce in accordance witn neguistory pmG' i (GikTons,f*.5.hasnd m a Regulatory Guide 1.52. Revision 2 a Sh# T
- l l Mardi J5734 while operating the filter train at a flow rate of f,*gh* /#l MU }'
. syfe L,y f/97 2000 cfm i 10%.
) g",(,/l.h k. n =-4 ^$ rM aM-repligmentwi . Grecoal 12- t,, ' Y' i ' Jerifgnsj aAggamaydypegtemov -te
~
hen tseiem are_07tested 42 l 1 lace 5 a'ccordanciwitEQe_g'_uh_ EoryMtiont CMand M d) A-l .egulatory Guide 1.52. RevisTon 2 m wit e operating
- the filter train at a flow rate of 2 m 1 10%.
Intenance affecting t air flow distributton by sting \ (g. After " 4
% in- ace and verifying tha air flow distributio ge flow per unit when unifonn T cA,]
i hin i 20% of the av ed in
- accordance with the visions of Section 9 Industrial u ventilation" and etion 8 of ANSI N510 1 .
1 1 i 1 . l t
\
i CALVERT CLIFFS - UNIT 2 3/4 6-24 Amendment No. 189 l lO i l pay Q'
I fA
- OA.) 3. 7. 4 SfedE i
iO l 4 3 , -) y LANT SY$TDts c- CTutfmer cyth M d 'S afetv Val LIMITIIIS COMITI0lt FOR OPERATICII 4 A A- x- ^- 's 3.7.1.1 All Ain steam line code safety valves shall be OPERABLEh (gp y,7,/ . APPLICABILITY: 2a -- 5'?MP v f Lou 2
~
. a.fe ~C$skl.
l*p, Cd'
- s O' y /*_ s ced M3 C }
$ 1 both te ctor cfolant Isops and atsoc(ated Steam geflerato operett'on(and ylth/One or more main steam line coot saTety P.
vsives Inoperapie. ope tion jn N00E5 1 2_And 3 may_srncaed #1 LI [.)O A ; eD/ vidad. that#within urs,dTDIWF3NW135(Fepable p1veQ orett to- - --- = 'm um or the Power Levei-nign trip setpolni - Ts reduced per Table C othgrwise bejn.AllenstDT_EAIRBY within the next 6 hours and trCCOLDAUTDOW1 $thip/the/foll.swintb he s,y _ [h} (w Ws) ~It yv1,1 [b. With one reactor coolaht ioop and associated stealE~fMM M ope ation and with one or more main steam line code safety valves a ociated wi 'the operating steam generator inoperable. - O ration i E 3 na proceed provi,ded:
/ l' l
\
\1. That t least 2 in steam 11 n operating team generato are OPERAB code safety, halves on the and operable valv is restored o 1
l
- 2. hat withi 4 hours the f OPERABLE atust otherw e. be in at ast Il0T ST Y within i the nex 6 hours and in COLD $59 within the 11owing 30 hou . s
~
Theproyl'sions[Specificationg4arenotplicjble) hof tf+t b ht. f g/ ;d t' peef r oCr h a t-
/
A.
/fntr/into
\1 int code @typsTe vsives/During thijAime, at least311geraittedge
;wo malnyteam dererstne OPERABIL gwww safety valvepplir ste,amperator OPERABLE. L,2 CALVERT CLIFFS - UNIT 2 3/4 7-1 Amendment No. 163 O
ry a1
. . _ .$jeejh*cel.'*9 I*1 l .. _ __ -
4
- O 3/4.7 PLANT SYSTDt$
SURVEILLANCE REQUIRDIENTS 19., 3,7, /. / 0." No additi 1 Surveilla Requiremen other than ose reg
" ^/fication y Sper .5 are appl ble for t in steam ne code s ty
, valves'of Table 7-1. '
. . , _ .y - r, . y y y y- y r v- -
f
< tw ml as y v 4+ s -
d'n w a
?.& nes, ast. J; % 4be. Z Ase' let ypsuv.,ee Tnr..af r i 1 Te rfl A4
,' ~W f
?'*1 '
- l PM* f* / AM '
_ L.. L. r . . - ,* i r .- c.. >
- r . -
i l 4 a J lO l
< I i
I e I i CALVERT CLIFFS - UNIT 2 3/4 7-2 Amendment No. 149 O Pqe zh 4 i
O 3/4.7 PLANT SY5T as TABLE @ ItAKIISSI ALLWABLE POWER LEVEL-WIM TRIP ! POINT WITN IMPERABLE STEAM LINE SAFETY M VALVES But1NG OPEEATI M \ ! t l ,0 PNe {jW.) MAKI$8lMIphER0 ! SAFETY VALVES en di f Eef / MAKIIGN ALLOWASLE LEVEL-RIM POWER TRIP SETPOINT < l g6 ,j/Pf4fEnf7 0F RATED 7" Lama.L Pausal ; DPERATIM ITEAM SEllERA _ L_ Io f Yl q 4d m g IO7< , 7 93' l f 77 f4 ! 5 O l I CALVERT CLIFFS - UNIT 2 3/4 7 3 Amendment No. 163 I O s,c as
l O 4 2 3/4.7 PLAllT SYSTDt$ 4.7 1 i STEAM 1AFETY VALVES PER LOOP / l VALVE IRIMBER LIFT SETTING 5* ALLOWABLE ORIFICE IIZE
/. a. RY-3992/4 935 5 psig R /
- b. RV-3993/ 1 35-995 psig J
- c. RY- 4/4002 935-1035 psig [R d.
-3995/4003 935-1035 psig R i 'e. RV-3996/4004 935-1065 psig R
. RV-3997/4005 935-1065 psi R
. g.
RV-3998/4006 935-1 psig R
/
- h. RV-3999/4007 935 5 psig R 4
/ '
- O l l
l i i 1 i Lift setti tAoi a tven steam line are also valves 1 tween '995 psi ble if any,2 - r valves Itft'between L),l 935 a 035 ps the 4 remai ves lift betweeri 935 and , 1 ps19 ' { CALVERT CLIFFS - ilNIT 2 3/4 7 4 Amendment No. 163 l O w a4 4 f
! 1 ! l I I f I !O i l w a systas
- 37
! 3,7,3 m- @nM l j ! Aux 111arr Feedwater Systen Mfh)) i d ! 1 . LDETING COWITIM F08 SPERATIM 1 i [ DIS 3,7,I d8.3?D Two auxiliary feedwater trainnftonsist g of one team-driv' and ! unser-aru m - - m atec iow capable o automat 11y L,df 4 initi ng fl Ghall be SPERABLD GP steam-d van tre shal 4 on of pop angnes for a tic f initiati and j in tandby p.- . I APPLICABILITY: MODES 1, 2 and 3. l EHR: l DF IN' ith any single pump inoperable, perform the following: l j h With No. 23 motor-driven pump inoperable:
- M " Align the standby steam-driven pump to automatic M*l j
4 hpg 6.g dnitiet M within, . tus within 72 hours or be in NOT $ NUT 30W x 12 hours, and bL%cy %d/s
~~
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