ML20092B848
| ML20092B848 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/04/1992 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20092B841 | List: |
| References | |
| NUDOCS 9202110157 | |
| Download: ML20092B848 (243) | |
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IABtE Of CONTENTS SELL 101) SECl10!1 fl92 1.0 DEFINITIONS 1.0-1 stJET1 tlMilS_ LIM 111NG SAFE 1Y SYSTEM SETilNGS l 1.1. FUEL CLADDING INTEGRITY 2.1, FUEL CLADDING INTECRITY 1.1-1 A. Reactor Pressure >B00 psia A. Trip Settings 1.1-1 and Core flow >10% of Rated B. Core Thermal Power limit (Reactor 1,1-1 Pressure s 800 psia C, Power Transient 1.1-1 D. Reactor Water level (Hot or Cold 1.1-2 ShutdownCondition)
- 8. Reactor Water Level Trip Settings 1.1-5 Which Initiate Core Standby CoolingSystems(CSCS) l.2. REACTOR COOLANT SYSTEM INTEGRITY 2.2. REACTOR COOLANT SYSTEM INTECRITY 2.2-1 tlMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.1. REACTOR PR01ECTION SYSTEN 4.1. REACTOR PROTECTION SYSTEM 3.1-1 !
l A, Sources of a Trip Signal Which A. Test and Calibration Requirements 3.1-1 1
Initiate a Reactor Scram for the RPS B. RPS Response Time B. Maximum Total Peaking factor 3.1-2 (MTPF) 3.2. PROTECTIVE INSTRUMENTATION 4.2, PROTECTIVE INSTRtNENTATION 3.2-1 Isolation Actuation -
A. A. Isolation Actuation 2-1 Instrumentation _., . Instrumentation B. Instrumentation Which Initiates B. Instrumentation Which Initiates 3.2-1 or Controls HPCI or Controls HPCI l
C. Instrumentation Which initiates C. Instrumentation Which Initiates 3.2-1 or Controls RCIC or Controls RCIC D. Instrumentation Which Initiates D. Instrumentation Which initiates 3.2-1 or Controls ADS or Controls ADS HATCH - UNIT 1 i K:\wp\techsp\h\tocul323. pro \323-110 1.
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LIST OF TABLES little liUA EA92 1,1 frequency Notations 1.0-11 3.1-1 ReactorProtectionSystem(RPS) Instrumentation 3.1-3 Requirements-4.1-1 ReactorProtectionSystem(PRS) Instrumentation 3.1-7 Functional Test, functional Test Minimum frequency, and Calibration Minimum frequency 3,2-1 Isolation Actuation Instrunentation- _3.2-2 l 3.2-2 Ir.itrunentation Which initiates or Controls 3.2-5 llPCI 3.2-3 Instrumentation Which Initiates or Controls 3.2-8 RCIC 3.2-4 Instrumentation Which initiates or Controls 3.2-10 ADS
- 3. 2- 5 Instrumentation Which Initiates or Controls 3.2-11 the LPCI Mode of RiiR 3.2-6 Instrumentation Which Initiates or Controls 3.2-14 Core Spray 3.2-7 Neutron Monitoring Instrumentation Which 3.2-15 Initiates Control Rod Blocks 3.2-8 Radiation Monitering Systems Which limit 3.2-18 Radioactivity Release 3.2-9 Instrumentation Which Initiates Recirculation 3.2-20 Pung Trip 3.2-10 Instrumentation Which Monitors Leakage into 3.2-21 the Drywell 3.2 11 Instrumentation Which Provides survelliance 3.2-22 Infomation 3.2-12 Instrumentation Which Initiates the 3.2-23a Disconnection of Offsite Power sources 3.2-13 Instrumentation Which initiates Energization 3.2-23b of Onsite Power Sources HATCH - LNil I vii K:\wp\techsp\h\tocul323. pro \323-110
LIST OF. TABLES (Continued) lddt' lillt EER 4.2-1 Isolation Actuation instrumentation Surveillance 3.2-24 Requirenents 4.2-2 Check, Functional Test, and Calibration Minia n 3.2-27 Frequency for Instrumentation Which Initiates or Controls HPCI J 4.2 3 Check, Functional Test, and Calibration Minia n 3.2-30 Frequency for Instrumentation Which Initiates or Controls RCIC 4.2-4 Check,. Functional Test, and Calibration Minimum 3.2-33 Frequency for Instrumentation Which Initiates-or Controls ADS 4.2 5 Check, Functional Test, and Calibration Minimum 3.2-35 Frequency for instrumentation Which initiates i or Controls the LPCI' Mode of RHR l 4.2-6 Check, Functional Test, and Calibration Minimin 3.2-38 Frequency for Instrumentation Which initiates or Controls Core Spray _
4.2-7 Check, Functional Test, and Calibration Minimum 3.2-40 Frequency for Neutron Monitoring Instrumentation Which initiates Control Rod Blocks 4.2-8 Check, functional Test, and Calibration Minimum 3.2-42 Frequency for Radiation Monitoring Systems Which limit Radioactivity Release 4.2-9 Check and Calibration Minian Frequency for 3.2-45 Instrumentation Which Initiates Recirculation Pump Trip 4.2 Check, functional Test, and Calibration Minian 3.2-46 Frequency for Instrumentation Which Monitors Leakage into the Drywell 4.2-11 Check and Calibration Mininn Frequency for 3.2 Instrumentation Which Provides Surveillance
- Infonnation 4.2-12 Instrumentation Which Initiates the 3.2-49a Disconnection of Offsite Power Sources 4.2-13 Instrumentation Which initiates Ene gization 3.2-49b by Onsite Power Sources HATCH - UNIT 1 vill K:\wp\techsp\h\tocul323. pro \323-110
T 3m N'
z Tabte 3.1-1 Cont'd) i t
c Seram . ,
Operable 3 Number Source of Scram Trip SW Channels Scram Trip Setting - Source of Scram signalis
.--e (a) Required Per Required to be Operable 4 Trip System Except as and,cated Below -
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.l 12 Turb.no Stop Valve 4 . $10% vafve closure Automatically bypassed. when -
Closure from full open turbine steam flow is below ' ,
Tech Spec 2.1.A.3. .. that correspondmg to 30% of rated thermal power as measured by turbine f*tst stage pressure.
Notes for Table 3.1-1
- a. The cokemn entitled " Scram Nunter" is for convenience so that a one-to-one relationsNp can be established I between items in Table 3.1-1 and items in Table 4.1-1.
to a b.1. There shall be two operable or tripped trip syctems for each potential scram signal. If the nunber of ;
7<n operable channels cannot be met for one of the trip systems, that trip system shad be tripped.
b.2. One instrument channel may be inoperable for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to perform requered survestlances prior to entering
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other applicable actions, provided at least one operable channelin the same trip system is monitormg that parameter.
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V, c. WitNn 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at g eater than c+ 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed 7
based on a calculated value of the radiation level expected during the test.' The background radiatum level and I associsted trip setpoints may be adjusted during the test based on either calculations of measurements of actual m redsation levels resulting from hydrogen injection. The background radiation level shall be determmed ~
$ and essociated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establisNog normal radiation levels after
{po completion of hydrogen injection and pnor to establisNng reactor power levels below 20% rated power
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B43ES FOR SURVEILLANCE RE0VIREMENTS 4.1 REACTOR PROTECi]ON' SYSTEM (RPS)
A. Testina Reauirements fqr the RPS The minimum functional test frequency and allowable _ outage time specified
- for RPS instrumentation are based on the NRC-approved reliability analyses performed in Reference 1. The analyses considered the Hatch-specific design, including the ATTS equipment-discussed in References-2 and 3.
Included in the Reference l' analyses is justification for one instrument channel to be inoperable for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to perform required surveillances, provided at 1 cast one operable channel in the same trip system is monitoring that parameter, prior to entering other applicable actions, HATCH - UNIT 1 3.1-15 K:\wp\techsp\h\3-1-lul. pro \323-103
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BASES FOR SURVEILLANCE REOUIREMENTS Deleted liATCH - UNIT 1 3.1-16 K:\wp\techsp\h\3-1-lul. pro \323-0 e
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BAsf5 FOR SURVE!LLANCE REOUIREMENTS
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_ BrtSLS FOR SURVEILLANCE REQQlRLMEN15 4.1.C. References
- 1. NEDC-30851P- A, " Technical Specification improvement Analyses for BWR Protection System," March 1988.
- 2. NED0-21617-A, ' Analog Transmitter / Trip Unit System for Engineered Safe-guard Sensor Trip Inputs."
- 3. NEDE-22154-1, ' Analog Trip System for Engineered Safeguard Sensor Trip inputs - Edwin 1. Hatch Nuclear Plant Units 1 and 2.'
HATCH - UNIT 1 3.1-18 K:\wp\techsp\h\3-1-lul. pro \323-103
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Objttthe Objttus:
1he objective of the Limiting Condi- The objective of the Surveillance tions for Operation is to assure the Requirements is to specify the type operability of protective instrumen- and frequency of surveillance to tation. be a! plied to protective lustru-merd ation.
5ptLLU U110M $ptillji!.UFd 1he limiting Conditions f or Operatic 9 The ineck, functional test, and of the protMtive instrumentation af- calibration minimum frequency fer fecting each of tno f ollowing protec- protective instrumentati?n af f ect-tive actior s shall t o as indicated in ing each of the following protec-the corretponding O table. tive actions shall be as indicated in the corresponding SR table.
Ptrinihtactitm 1LO_lible s!Llabit
[ A. Initiates isolation Actuation p,. initiates or tontrols HN1 3.2 1 3.2-2 4.2-1 4.2-2 l
C. Initiates ir Controls RCit 3.2-3 4.2-3 0, initiates or Controls ADS 3.2 4 4.2-4
[. Initiates or Controls the 'a . 2- 5 4.2-$
tptl Mode of RHR I. Initiates or Controls Core 3.2-6 4.2-6 Spray C. Initiates Control kod Blocks 3.2-7 4.2 7 H. timits Radioattivity Release 3.2-8 4.2-B
- 1. Initiates Recirculation Punp 3.2-9 4.2-9 Trir J. Monitors leakage Itito the 3.2-10 4.2-10 Drywell -
- t. Provides Lurveillarte 3.2-11 4.2-1)
Information L. In"intes Disconnection of 3.2-12 4.2 12
~ Of f site Power Sources M. Inittnies incrgitation tiy 3.2-13 4.2+13 Onsite power Sources N. Arms t he Lou Low Set $/itV 3.2+14 4.2-14 System
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NOTES FOR TABLE 3.2-3
- a. The column entitled 'Ref. No." is only for convenience so that a one-to-one relationship can be established between items in Table 3.2-3 and items in Table 4.2-3.
b.l. When any CCCS subsystem is required to be operable by Section 3.5, there shall be two operable trip systems. If the required number of operable channels cannot be met for one of the trip systems, place the inoperable channel in the tripped condition or declare the associated CCCS inoperable within 12 hours. If the required number of operable channels l cannot be met for both trip systems, declare the associated CCCS inoperable within I hour. b.2. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable actions. HATCH - UNIT 1 3.2-9a K:\wp\techsp\h\1P3-2323. pro \323-170
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$' INSTROMENTATION WHtCH Iri!TIATES OR CCNTROLS THE LPCI MODE OF RHR }
i t 6 1 -: Ref . instrumem Try Required Tre Settmg Remarks t . $.- No. - . Cormition Operable I Q ' (a) Nomenclature Chermels j per inp j } .y i _ sen u . 4 , i
- 1. Reactor Vessel Water Level Low Lew Low- 2 2-113 mehes trenates LPCI mode et RHR i t (Level 1) [
s" s l'; 2. Drywett Pressure H:gh 2 51.92 pseg irrtietes LPCI mode of RHR. A>so i l initiates HPCI and Core Scray I {, and provides e i.em .a sW { {' TOADS. 1 l 3. Deleted f i' 3.a. Reactor Vessel Stearn . Low 2 1335 Perrmsseve to close Reorculation Dome Preseure Desenerge Vafwe and Bypess Vetve [
!' w !
- . 3.b. Reector Vesset Steam Low 2 1422 pseg* Permsseva to open LPCIinsecnon N
Dome Pressure velves !
- I
~
l 4 Reactor Shroud Weter Level Low 1 2-202 inches Acts esr. . . _ a to <frwert : i (Level 0) some LPCI flow to contamment ; D sprey l
/ t d S. LPCI Cross Connect N/A 1 Vaive not trotsetas annuncester when volve
! j Velve Open Annune:stor closed is not closad l ] ro > i n k- 7 I
- = t i,
t e
/
' 7 ,
/
*This trip functeori shen be s500 psig. - !
l. i w . i 4 { i ro . . f '. .W ru . 4.n3 ' 9 i O 1- w ; ro , W ! ! t ) i N [
~
i l 3 i
, ~ , . _ . . . ,, ,. - . . . . _ . _ _ . - . ~ , . - . . _ ..- . _ . . . , _ . , ._.m . , - . _ _ _ _ _ . - _ . . ___ .__.__
Z Notes f er Table 3.2 5
-4 O
X e C The ceiumn entrtied ~Ref. ?Jo." is only for converwence so that a one tMme Mat onstwo con be
= a.
estebteshed bet vree, stems m Table 3.2 5 and stem in Table 4.2 5 [ b.1. Wtwes any CCCS subsystem es regsred to be operatde by Secuen 3.5. there shall be two merab8e tr p systems. If the reque ed number of operetde chanrets cows be met for one of the tr p systm. rJace the enmerable chenne8 en the tnpped conditio* or oeclare the essocietad CCCS inceeeable writwn 12 hours. If the eequeed nurnbee of operatAe channets connet be met for both tm syst-ms. l declare the assoc +ated CCCS ;,%.44 mthen 1 hour. b.2. One errstrument chard may be mcpetable foe up to 6 hours to perform requwed s.srvesmes pnce to entenng cthee arg4catde ecte. W I e-* N M. I T / c* O CT 7 e U / 7
- l T l Y '
N teZ N W
- a 9
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~2 ah eo h u
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. r.
r r r c mi ymmhe l r v o le o su Ser v r t i r. yc u Se r t h r t eu r s t c e w y t c an ee rf P eu rd n c un nee u oec ee ny eth1s 2 te so oru t e lns I n R e D r et RP CD of : S C CF oe t e see w hpet t nr a i nt mo. r h -. p et v chlc e e2 r he n t s Tb Wtnirie pwd O- lA1
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I!- v 1 a k> Id3 lC e t f1ATCH UNIT 1 3,2-16a K:\wp\techsp\h\lP3-2323. pro \323-105 , I
ries es 1m Tetk 3 2-7 [> 4 cm I a a a T% co8un n een=d " Ret. tdo? is eWy foe c%wm e so that e one tow r.r=ws to can be est44.h3 tint men items n Tetde 3.2-7 end cems m Teth 4.2 7. c l b 4 b.1.. For the START & HOT ST ANOBY pos. ten of Ybe Mode Eastch. There sheE be twe opetete of tw3 sw*t.r-r5 for each potenhat te'p corattacc.. If the tempernems estebbsbed by the cedumn cemet tw enet for one of the twe try systems. The condkt cn mey cost for up to sevan days proww$ed .hst du-mg that t*me t% cperetWe system es feone!!v testad smmedsetefy and dely TSeeemfter; si thrs cted non L*s's km,v then seven days. the system shall be tryped. If the revne nertts estabbsbed try thrs ctdumn cennot be enet for both tre systems, ttw systems sheti tw tW b,2. One enstrennarat charmet may be mope-eth for up to 6 hours to perform remmed survedlences peer to emermg other oppbceb8e actwr4
- c. One of the four SRM mputs may be bypessed.
- d. The SRM and IRM t4ecks naed not be epacet4e m tee Run Mode. Thrs functwm es bypassed when the Made Sw.tch es g4sced in the RUN possten.
- e. The APRM end REM rod teocks need net be Ope <etde m the Start F. Het Stendby Mode (Encept 12% AFRM Rod Ek cu
- f. The RBM es cedy reemred whao core the mat power es 230% and the hrwteg condresen defmed m Sww 3.3.F e rsts,
- g. Thrs tnp es Operstne m Power Opeeetxm and Het Stem'bv Mode, end Refuel Mode when any cone of eed es wethfro wn. Fact ecpi. cat 4e to cent of rods remow=d per Speerfeca+e 3.TOL w
Withd+ewei of control rods ss riot permetted dm requered surve. nance testmg. j h. a > N X. i K ' D l C O 7 to V / J w T W 5 FN) W r%D W 7 O / W r%7 W f ea O t.tv
4 4
- =
+ 3a
=
-4 TaNe 3.2-8 kontJ
, (">
T Ref. hvstrtsmer*t Trip Regated Ter Settmg Acteen to tee teen of Re*na4 s } a t4o. Combteon OperaNe there are ret two gernin j . (a) fdomenete Charm 4s er snpsmi tre systems per Tnp q [ E. s. ture Syven it4 I 4 _ 5. Mam Steem Lane . t4. 2 s3 twnes asotare the mecherv_al one tng pee vnp l Radseteen Moretor normal fun vacuur-n pur=1p and the logpc system wdB power backgreund Wand semi condenser esciate the (e) ewhauster mecherocal vacuum curry and the pand seeicendenser enhauster. ! e. The column entrtled *Ref. No.* es ordy for a.,.;..a.-.e so that e oretoene reistionstup can be estabieshed between items in Table 3.2-8 and rtems in TeSle 4.2-8. b.1, Whenever the systems are requwed to be operable, there shan be two operable or inpped tnp systems. l If tNs cannot be met. the m&cated actron shall be taken. b.2. One instrument channel may be inoperable fee up to 6 hours to perform required survedances pner to entenng ls other applecable actions.
- c. In the event that both off-ges post treetment radsetson moewtors become snoperable. the seector shen be w placed in the Cold Shutdown wetNn 24 hours isniess one morwtor es sooner made operable, or edeoaste sitemettve
- monitoring facsistees are evelable.
ru 4 1 to
- d. From and efter 'ho date that one of the two off-ges post 1 ee= .: redetson enoretors is made er found to be inoperable, s. mad reactor power operation es perrneswbie dunng the nest fourteen deys (the snowable sepeer twne), provided that the snoperable morator is tnpped en the downscale posrteen.
! 7C e. WstNo 24 hours prior to the planned start of the hydrogen is11ection test with the reactor power 3g at greater than 20% rated power, ttie normal fuB power red.etion background level and essocseted snp setpoints mey be changed besed on e caeculeted value of the ra&attora level espected cunng t the test. The background ra&ation tevel end essociated tnp setpoints may be adyssted desemg
% the test based on erther calculatione or measurements of actual ra&etion levels resu!trng from a hydrogeri insectiert . The background redentson level sher be detemuned and essocseted trip n setpoents shaR be set wittnet 24 hours of etHrstabhshrng nor-rimi todetion leve6s efter w AGv.,
t [ of hydrogen irgectiori and pnor to estabbstung reector power levels below 20% reted power.
/
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+
t.d i N W rv j W 9 O
/
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. . . . _ . _ . . ,_. m .. , .. .._ . _ . . _ . _ .. . . . . . . . _ . ~ _ -. . . .. _ . _ _ _ . . . __ .
t
- y TetAe 12-9
-4
, O INSTRUMErJT ATiON WHICS4 i*nT1ATES RECTRCUL ATION PUMP TR;P j Z !' s Ref. Instrumart Tnp Requeref Trg Settmg Remarks '! PJo. Condtion Operatde j tal P&omenclature Channels E. .. per Trp
--t S ystem
! w - i .. . 2 *"
- 1. Reactor Vessef Water Level Low flevel 2) 2-47 snches S4,0 Power crurst be reduced and the j ( ATWS RPT)'" mode swrech pieced = = mode ether then the RUN fAode.
]
- 2. Reactor Pressure %gh 2"*' s 103S psg Power trarst be reduced and the
] (ATWS RPT) made swetch pesced m o made i, ' other than the RUN Mode.
- 3. EOC - RPT** 1. Turtene stop 2"* 1. Stop Velve Tops r w t ,,a pumps on Voive Closwa s90% Open - turtane control watwe fest
!- 2 Turtune Contree 2. Control Velve closure or step waive closure Valve Fest HydretAc when reactee es > 30%.'" = Coeure Press Tnp Pomt i 1 i w te) The colurrm entrtled "Ref. No." is only for corrwerwence so that e oneto-nne relatonshrp con be estabhshed 1
- between items en Table 3.2-9 and items in Table 4.2-9.
- ru j
1-k o (bil. Whenever the reactor es in the RUN Mode, there shalf be twe operabie tw systems for each parameter for each operstmg recirculetx>n pump. If the regaired nurrtper of operable charmeis connet be enet for one of the l 4 trip systems, piece the inoperable charmelits the trtpped condstson or take the indicated eenon wettura 14 deys. i !? the requered ruumber of operable channels connet be met for boch trip systems, take the mdeceted action { withrn 1 hour. I u (b)2. One instrume it charmel may be snopereb8e for sep to 6 hours to perforr i roomred sw veeTeences p. :Pr other oppi ceeie oct.ons. to enteneg l 4 / l n
$ (c) Antecipated Transients Werbeut Scram - Recirculation Furnp Tnp 7 (d) End of Cycle - Reorcuistion Pump Trip
( -- c ! -/ (el Erther of these two EOC - RPT smems een snp both rearculet.on pumps. Eoch EOC - RPT system wa enn ef
- ,7 2+ut+f-2 fest closure s gneis or 2-out+f-2 stop waive signats are recenred
?
5 W
- (f)t . The requirement for these channels spr e es from EOC-2OOO f#WD/t to EOC. The RF'T eystem may be pieced status for up to 2 hours to provide the regimed montfdy survedence.. If one EOC-RPT system es inoperable 1 en inoperabie {
_E w tonger then 72 hours or if both tEOC4PT systems are senutteneousfy moperable, en orderfy power reduction we be immednetely iratiated and reactor power wdi be <30% witfun the nest 6 hours ru
" (f)2. One iristrument channel may be inoperable for trp to 6 hours to perform regared survesliences pnor to ectenng e other applicable actsons s
3 S w. 4). Esther of these tw ATWS-RPT systems can tnp both recircuistion pumps. Each ATWS4FT system wilt tnp if 2-outef 2 reseror low weter level s gnets or 2-out-of-2 cesctor high pressure segness a o receewad i fu W s
> O
. _ ._. . . _ . _ .-. , . . _ _~ . -. . - - _ . - _ _ - - . . _ . _ 4- - - - . _ . ___- .,,- . _ . . _ . . _ .
Tatde 3.210 [>-4 titSTRUM9T ATION WHICH MO*4fTORS LEAK AGE INTO THE OR v'WEtt b l C Requsted Opeestde ( z Ret No. S* M E-6 s 1--stnenent tct CFWs c*r Sv*+-m
] (my Tech Spec The 1.me-g Cond+te s f* ~
Dryw 81 E yerment Dren Sur-e fiblM) 1 3.6.G.T. ccws$on of the Leekey Flow integretor D-tacwen Syst=m e , prmnded i tb)(d) Te e Spec m sect.en 3 6.G. 2 Drywett Floor Drem Surnp 3 5.G.7. Flow integ-stor 1 M1 (e) 3 Semimet:en Detector for l l Morwtonag Air Peticulates T Mt set 4 Scmtdiewon Detector for Mo stoong Redood.ne T M) tel 5 GM Tubes foe Moestormg Noble Geses w l
- e. The column entitied "Ref. No.* es ordy for a:.. . ac ;e so that e one-toene reletreestap een be estatd+shed between l 1
N stems in Table 3.2-10 and items m Totde 4.2-10. '
>=*
l b.t. Whenever the systems are reguwed to be cpeestda. t*ere she4 be one operab8e er inpred system, if rNs carnot be met, the irwicated action shall be taken. 7 b 2. One irstrument channel rney be enop-reble for up to 6 hours to perfo m requwed survedences pnce te enta mg yr* other appbcetds actxms. The two fiow integ stors, one for t5e egumment drein stsmo end the other for the floor drem sump compose cme tw,c
$ c.
mstrumant system. Two sode4od de scmtdatien detectoes, one for moratormg et perscule*es and one for e t 7 formg redoodme. cormnee two bes c e4tn .. ..; svstems. A bete sensmve GM detector foe c~ -Mrs eth gases composes e fourth besec instrument system. Art sitemete system to dete mme the lesetege flow m o menuel h (9::r system whereby the twne between sump pump starts is mrwetored. This time interval wa detemune the seek ege flow beceuse the voeume of the eump is known. W e N d. For e r .L;.a ordoemation; performs no cont ci functxm N
- e. Kgh setpoint ederm wdl be set ttiree ttrMes above been ground red,eben. Forh,rre eierm w4 be set beiew becwg ownd V radietson. Specsfic veives wiH be estabbshed during syst=m sterti.rp.
C
/
W N tak s 26 N
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. mt ai n c
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; f oe co e n
p do-c - l 1 t srs r t ef e . ts n p eb e p e am u r r el o s was s 2 t 7
. 81 m eu pa s e
o t ut o t a re& c ew e L.. eopn r ed 3 n - nt et c h s u f cas r e r - : e_ E a c 2 . n2 o s s ee n a c a e ei m n e or a epme l e e e l w e e
..dc oa o
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- ego . mbae
. t n . t r r d t i a e1 8 u t e
E e t a i h t g e e o de.ea e q rh q T n b e e b; dr cb( e ec reah s e O N o-
- o. e r
a eN h4 tee t t a d s e m m a s mh ac w t s oei d wsa o c d E n n e ee r m vh e h t n r t r e r o e ha cE a tdr s hst he r o tnwowVa e etRt h re1 1 me oW t sO eb h l f r h n r h r s e eh eg e e c ur h f r s;fSn ; b sToige t f w o2 eD t e oe e d e
. a r e u ;o e lwrb m t d s r p n dr p r snn e 4 y rT r ew o o sd sr o o
et e - mu d-n e,g o to wle ow o t ae S g hH eU t f s al e t d e eo r c c mcn eO; a em s t ek nn o t he s e t h re nedt s pe mt dew.s t b e d r. 4 dsi t r S r dr r e r r oT e m r e T d n na u o pr e ieho u o t. uht ehuh u o s o , eO ep o c su n h t sh e 4 e b tn et a c es h h T yc rd R edo h l n e soe- aeqr t w sn f b r si w lbH mla 6 r de s 6 r p . ot 6 mhe to r r s o oc n Jew pm .wot at h r E e
-m e M r s e
r o o c ast e s &e sdt f o e pea f l t ;h w t sf p a ei dr m t y ie n p o e p
.t i n o ol yc o e r e ue o r
e nn r r t eei o nt - nsa o
- a. d r nt a e e t c t
- b. p ei d D t 't n i
d v., . elt e n t s e dc r o r e ah e e r e e y r e' r o se r o e ue . oe n m.ht rl r e1 s n nn lei ee f e ee pn e o _ g mit f i eyr t e f r N ne vd t le r u mn n mtctwid v n a ae4 r le tpaot cihn ie f o1 y 2 h e he nb a r ee sw b a r s s e t e oh o n n o ner ts es op - h o R eb pG ei
- b a
r e wdu e c no ensb b a r e d3 t r c r o w. p e P r sc t o est e e es g . r shn r e p decl e s r p e ce o gys fS e s o etu de d es Me hs t now no n iysn eeo o sb l f n -da e y
.a ns r e
rp et m o er em rpor d J f owd a yn r adeny s i n e e
?T i ; to b
s md so e b bu pgo n a - o u be t a n e e a 0
- a. o n b m a
mo d c. Aut Cs t s ;dh mt deah n vr y ce7 d b _ Nom r 3
. r av y ah n Oe e- -
uS y y coebe h h c f r e a un - ;sl a a n CaE i Lh ; o. s hd s bm m.C
.l s p u oe e 4
f. mO . t Ntrnee n n r t t sw s m. . o m. e Rt e r ei t ht w soF t e . . o o o . . neg s ;r s s e sn oir G c m e r o L- y o 4 t C le s nn s a o op ah i s e o n Pt ss
" e. f f s ict n
o eg a n s s et prete 6 e bree d n om <t e +te hanh w n hc w~p d ;; s ou et e dne 8 e s B rd at y n r r y hte h m ;. - eon' hc t h ;; d le-. t n ee ea t ihe t t . p-m r t o e-. . wh o t a n a c ae wf r
. sh;tre t
c=e h-nte t r t os a r t w s t e p u d e pxl u e O f o heh-. g- f h es
.h t ;
prebo 6e a eid nlb r mE S Se e d tTe ie ,r 4- lb mp eb d n r L pd oem a c d m d e e n t e nd . d Dr en t t s e u aa o -. c ep ie - nd nmr a alp aat u ne r nr n oB m-ut l s o cAa t e C n o g t+ hO e A nR oEP 4cr
~.
i
.nd 4 t o ao t ns e r e
i p a e n am se n w o l leeewh p sa r g or hw i a et hc R ele emn n ea ge nh ac Rt u hp n uh e v e 3 h6 e6n h( e) ( sb i p t p s n ir ee o het t he nWee t, r ci hir o.r n n tVton wils as t ir a enhe W n is e t w t s h s r e t aioa. t nht ws y r m d y cyteo gt eu t nhr eeRseh Wt n e ar ah leSr c Oo i o u t Inin e Te L Cnc Oo Dt i Dot H Edrc 4 eo si Oo f I 1 2 1 2 T.. 2. '
- s. b c c d. e e f f 7s./d #[ le[ r(# tw kw'w" tno'wtW3 mN'*
c-w
- _ :
I>4- n1 , C= *. .- W,t$w o o . 1a~ i i ]. )1 ii 1 , :1 <l ;li# :l ; ji ;li! , l i!1d :1
I l I I fJCTES 508 T AOLE 3 2 T 1 (Conter-esi
.a n
i 1 l t Th the mar rber of l [ g.1. Wah tb- i w d t m the power egierntwn. steetts. ** hot s*midown c.ondition and wr: r C operati*e cherwwls less there t% requwad operetAe charmats, wwtsete the peegApened sitewe z. twthrA of e-mentomg the opewope ete parameter wittwa 72 houes ord Q l
~
- e. esthet restore the moperatde channe4s) to opecable status wsthm 7 days of the ewnt. or l
- b. prepare and sutcut e spectal report to the f4RC ptresuant to Speerficatson 6.9.2. wettv t 14 days fobowmg the event outtevng the act+on taken, the cause of the copersbehty. end the plans and schedule foe restoneg the spam to operable stetus.
g.2. One mstrument chermal may be mcf 'et4e for up to 6 hours to perform required survadences poor to entermg other appfecat4e actions
- h. A channet contams two detectors: o e for md range rootde gas, ered one fe efug% re"2e net 4* gas.
Both detectors must be operat4e to emsedar the charmel epaestde. l
- i. Ar:strumentatum stwit be operstae wth contmucus serr#veg empatAty ettwn 30 memstes of en ECCS ectue*mn duneg a LOCA. See Section 3.7.A.6.c for the UMITTNG CC*4DfT!ON FOR OF'ERATct.
W 4 N W Or 7.. t u
/
fD O 7 ve V
/
7
/
w T W s N W N W 7 O
/
W N W 8 w N b
TABLE 3 212 [>--s
$ f*tSTRUMIt4TATfCN WH!C84 (NTTIATES THE CTSCCMECTICM OF OFFSITE POWER SOURCES e
C Z Actma to t.e Teken 4 af flw Mente of Required Channels Ter Settmg Re<psered Operatae
~ Operable Requered Ref. No. Instrument ChWs 4 NM Vet te) m) h?s To T v Sc?
2 Sus 2iBus greater then or e<rsel to 2800 1 4.16 kv Eme cency Bus v-dts. At 2800 vetts twne detev Undervoltage Relay w,B be less thern er equal to (less of VoPtega 6.5 sec. Cerdteoril g-eater t'wi or eesar to 3250 (c) 4.16 kv Emergency Bus 21 Bus 2iBus 2 vatts. At 3280 vo tse twne deiny UndervoMege Relev weit be less then er eat.ad to (Degended Voltage f 21.5 sec. Conditton) W N e
" NOTES FOR TABLE 3.2-12 W
tr j
- s. The colurre entrtied "Ref. No.* es only for c-.. a xs so that e oreto-ene reietconsNp con be estathshed X.. between items in Teble 3.2-12 end stems m Table 4.2-12. l
/
d
/
- b. Tbs mstrumentation as requered to be operable durmg reactor startup, power operation, and het shutdown.
I c+ c.1. Weth the number of operable channets one less then the requwed operable channels operaw mey proceed rD h untA perforrnence of the nest regsred instrument functional test pMed e inp sognel is pieced in the y LOSP lock-out re8ey logc for the appbcable irtoperable chaemel
/
p c.2 One tristrument ched mey be inoperable for up to 6 hours to pe twm reW surveisances pner to q entenna other appkcebte actions. , W s N W N W 9 O
/
W N W 8 w O C3
y : Tat 4e 3244 w
$ INST 8tuMENTATION WHtCH arf.tS LOW LOW SET SSV SYSTEM C
z Requered
.[ Opera h ~
Tnp Charmets
. Ref ' . Cerditmn pee Trp nom instn m et P W eture Sysww Tno Setww: bmeds
- 1. Reactor Vessel Steam Dome Hoh 2* s1054 pseg Pressure
- 2. Rehef! Safety Valve Mgh 2/ waive 85. + 15. -5 The lantmg coedtzen Ta W Pressure . ps g of eperaten et these evntchs es prowded in Spectheateen 3.6.H.1.
w N 1 N w CL 7.: s fI r s e to
"' The column entitled "Ref. No." is ordy for cormemence so that e one-tisme relationship can be es'atAshd between y a. .
y items in table 3.2-14 and items in table 4.2-14, s f b.1. With the requerements for the trurumum number of OPERABLE channels not satrofied for one tre system, gasce the l q inoperable channel in the tripped cond6 tion or declare the associated system inoperabie witNn one hour. Weth w' the requirements for the erwemmum rwmber of OPERABLE channels not satrsfied for both tnp systems. declare the E w associated system inoperabie withrn one bour. m , w b.2. One instrument channel may be inoperable for s:p to 6 hours to perform required survedleraces pner to entermg l other applecable actions. l s O s. w
- N
'W 8 w O CD
I I T at.ae 4.2 1 2>
-4 l ISOLATION ACTUAT!ON INSTRUVENTAT3CN SURVE!tLANCE REGU$REMENTS instrument Fu w:trormt Test ins-enmaet Cet4 sten t
Ref. ms1run=nt Ctwck Mmsmurn Fremy Idrwmm Freq;ency ?Anwmm Freesemy
= No. I wtrument
&) itt
[ 1 Once/opersemg cycle l
~ Oncelshtt Once warter 1 Reector Vessel Water Level (Leve!s 1. 2. and 31 Oncelstuff Once/ quart ar Once4perstmg cycte l 2 Reactor Vessel Steam Dome Pressure (Shutdewn Coohng Model onceiguerter Omeierstmg cycte l 3 Drywell Pressure Ome' shift O mefweek(el Ev**y 3 menths t?)
4 Men Steam trne %me Redentson f4one N/A Eveev 3 month
- l 5 Mam Steam troe Pressure W
. Once/ ope etmg cycie I Once tshft Cncelessner 7
ru 6 Mem Steem Lme Flow once4peretng cycle I a once/que ter l 7 Mam Steam Une Tunnel Once!shft Termerature 7- Every 3 months l Reactor Water Cleanup None N/A S [ Syrtem Dfferentief Dow e Once/ouarter Onceivetmg cycle l t7 9 Reector Weter Oeenup Once/shsft y
" Aree Ternpeesttre D l / '
7
/
e* T b.* t N t.a.P N W 7 O
/
W N taf 8 aa N e*
l 1 l' i- ~j --.e Tet4e 4.21 tCont'd)
'n
= Ref_ Instrument Check Instrument Ftmetxm.d Test - Inst-ument CeMirsten
- l. .,. No. Instrument . fWwnunt Feequeracy - PAnimum Fee <psenev Saner'sen Frequenev e w i n, E
10 . Reactor Water Cleanup . Onceishti Once omerter Oncedopeatmg cycle 4 , w
- Araa Ventdetrots Dttecentral Tempeteture 11 Cor denser Vacuum F4cne PuA Every 3 months 12 DryweN Radistum Once!sSett Oncetqueeter M Once/upereewg cycle 13 HPCI Ewe ven,- Aree Oncefstuft Oncerque ter Onch.e.s cycle Cooter Arrt. erst Terme eture :
- 14. HPC1 Steem Supsdy Once/sNft oncelguerter oncetoperet.no cycs.
Pressure
- 15. HPCI Steam Line AP Oncelsht Once/ouerter Once/operetmg cycle (Ffowl u
. 16. HPCI Tuebme Exhaust Or.celshft Once/guerter oncekm cyce.
N Daphragm Pressure - ro t.n 17 HPC1 Sw..av., Chamber Once/stuft Oncerquerter Once/operstmg cycle Area Amtmant Termeret are 7
/ 18 HPCI Suppression Chamber Once/shft OnceIgtsarter Once/operstmo cycle d Aree Offerentsal
% Air T..,v.mn ie to "y
19 RCIC E.- ;;,,,, , Ares Once/sNft Once/querter Oncekpeeetmg cycle y Cooler Amtmmt
- T..,v ei h,ie -
s y 20 RCIC Steam Supply Once/shet Once squarter CnceJoperstmg evele w Pressure a tu W 21 . RCIC Steam Line Oncelstuft Once/ quarter Once W . 4 cycie w AP (Flow) t-
] 22 RCAC Tur*nne hhaust . Onces sNft Once!querter Once/opeestmg cycle
/ Daphragm Pesure w
N w s ee M w
1]lI'll!,IIl 1Il i1 I ! l1Il1l l i' i1IlJ1:) iI Il.l1il l l_ l n . o i y e e t c 4 c lcy a re e n y c c - t haqu g v _ C e- ) t m - tn F k sr i.. . e , m p v w u a. r l o e
/
c e t s
. c c n n in M. O O -
t s e _ T dny c ea t:
- e r u uq r r F
; F eW r
t e t e r ras a r
- a. eun u e r le q e r
e
/
e e ht r ee
-. wr t c c e 8
b p f s e . d
) s n n 1 b a g s r. ua InA f O O 2 n e
e .
. e e (r 4 a o c
. c n e w r e
o e c h r p C p e e la a o ( lb a = b r l e i o n 1 T f s o o v r H a n t t : 2 r o o o d r % e t 4 f c e ior lb ; e s fa w a e e u p - r lb r q e - T a N t o e n t e r d m e w-
+-
p o e. y o o r r e i c - o kc ne o t n e f r mr b o b r e o e he e
- t e
e 1
. e p e
f r e M ht Cre t F f t u f t u a 2 s b p g t t n n s s t 3 ;- l la o t w e T. l e i e e ht h t e r r m c c le -_ s s r u u r ~. O n O n o s b a y e r u o t o t e. r a. t s . T ht h n o n /s I 9 e n 6 e t .
;. i e r r s ht d o a e
; e t s n
-.. m e n s p : p
; e is u
-. it h -.
m r -. d n w e f o - w a d e r a e r 8e L, f o 1 m s b r f t a 6 e y 2 e s e r e e p ln 4 e r t p h e t o le o s b t o la n n 4 s b n n s
. i m e a i a e H h
*. T e t io u : t c
h s e c t a t w o n s n t y o y N i s a d e s s u e e t f r h
=. m lb f
e m s f le - u e e b l a q t. . s R
" i t t i, r a r
e n i e d e nn >n i e e n r i oA sse ae e ce s s air e reA er d ln e n e e w t a m w c v e w o p o n hc a dt r e o n s s n e e r r r t n t n a :
-. ht e e ,
t n pArut pAlau e e u H o
-. a r r a
p r e r t a i t b -. o e ue a f t _ n r Ste r uenr Sb e e mi d e d e g s n s n u r u
. c m o o r Cnp Cmr ep h s - p - t r t . .
Ch am l t t I I af m o r p . m e a it a . d s n e Chfie c ib u n u a f n r r s e RCT RCDT a r t r e b u t e I e t t s e t s e lbe b t a . h s r n o a a le n t T e I a m O t C c s D f. eo 3 4 1 2 R N1 2 2 e b b c d
%4_."t- '? -: ,
C=[ w W'y:uma f n c./ttyrny,t/7'* 7. p WBNWeW'*o uo'WeW9w s b V r_ W 1 4t. < j(iqlid,$ ;jj j ,
. l- i!.)liai 4!j!)a3 11 . ,- ! ,! t , 4: 44
- i
x [
---+
Notes for Tabte 4.2-1 (Cont'd) n
- r i t-5 C i 2 ,
m-
--O ~
- e. This instrumentation is exempted from the instrument funct,onal test definition. This instrument -
functional test wdl consist of injecting a simulated electncal signalinto the measurement charmis.
- f. Standard current source t< 's which provides an inst.mnt channel elignment. Cahbration using a radiation source shall be made once per operstmg cycle.
Logic system functional tests and simulated automatic actestion shell be performed once each operatmo cycle -i for the following: 7 N
- 1. Main Steam Line isolation Valves 8. Reactor Water Cleanup Isolate Cl
- 2. Main Steam Une Drain Valves 9. DrywellIsc4stien Vaives
- 3. Reactor Water Sample Valves 10. TIP Withdrawei X
):E
- 4. RHR - isolation Valve Control 11. Atmosphenc Control Valves V
- 5. Shutdown Cooling Valves 12. Sump Dram Valves r+
(D 'I Standby Oss Treatment Q us
- 6. Hesd Spray 13.
" 7. Dryweil Egypment Sump Discharge te Radweste 14. Reactor Buiking Isaistion
- r
/ - The logie system functional tests shall include e cruration of t:me delay relays ena timers necessary o
w k for proper functioning of the trip systems. - w N W 1 9 O
/
M N M e O
1 Table 4.2-2 ' 2>
-4 O Check. Functional Test, and CaWation FA6 mum frequency f or instrumentat+on r Which tratistes or Controts HPCI e
Imtrument Cat,t, rat,on C Instrument Check instrutnent Furmtiond Test i 2 Ref. Merwmurn f requency fAnemum Frequency Minimum frequency [ No. Instrument (c) l (b) pL Once/ quarter Once/operatmg cycle l 1 Reactor Vessel Water Level Once/stuft (Level 28 Once/ operating cycle l Oncelsh:ft Once/auarter 2 Drywe!! Pressure N/A Once4;perating cycle 3 HPCI Turtuns Overspeed None Once / quarter Onceluperating cycle l 4 HPCI Turbine Exhaust ' ,Once /stuf t , Pressure Once/ quarter once/operat.ng cycle l 5 HPCI Punt Suction Once/stuft Pressure Once/ quarter Once/uperatr g cycle l 6 Reactor Vessel Water Level Once/ shift W
. (Level 8)
N Once/operstmg cycle t Once/stuft Once/ quarter y 7 HPCI Pump Cischarge Flow 8 Deletect X.. [
/
9 Deleted c+ (D O
"Y V1 V /
- T
/
w T W I N W N W
-1 C /
W. N W I w N w i _
.> i i{ . g - v L [ [7 3y Ft:PEy' .!* ' r. c rti 1II 1
l n, xy le-
? c c an r y c
br eu s' g' eq ht n C er ) n it t F c o a r n ( n e em a p mu um 3 y / o r a r e e . . t s r e c n iP na E v O n N o - - t s r K l a e ny oc dy i n t cnu e c g uq r n f ebl r t e it t F t r a r n a e em mu u q p um / /o tr in e e s A c c 2-
)d. / n n
't InM N o O 2 b
e - n 4 o n C e a ( lb c' 2 a . 2 T 4 r o %m r , f s o te it b e la
- a. t o e T N r y e
- c n k n ce' e eu t o'
h q t C er t F f N e. r o2 n /s - em e e e. e2 - mu um _ o n c n r o t a3 t r n r N o N htoa lb e s I P nA sT en ci n s ie m n e e t vi nd on ca r f o2 - y 2 ln 4 oe l sb ia "o. nT
. ' r Ni e' e f
.s g b e m .
Rte a' m r r a e " i o' t h w s n S C oo de e nl Pit e t e oe c n lt i w ig o t
.n a l e iv t nt e e s v s e m d e
d e d e d e ne eL sL e oM L er eb. n u r r pe d me t t t t r le e e dk I t s e le le e le nn oa pt u a Clu uh n D D Pia lois i D D CT SW HF cb l e at
., h s f
eoL RNl e 0 1 1 2 3 4 5 6 Te 1 1 1 1 1 1 a. jyO3 ,c" -
- - . g oD 3o oJ fC XM /eD"(sJmD/7/WTW8NGrW. 7O/WtG4wNW t
t ' ' 4 , a + 4
V T% . Notes for Table 4.2-2 (Cont'd) ;
--4 m '
c b. Instrument functional tests are not required when the instruments are not required to be operable or
,t. . .
c_, ere inpped.- However, if functional tests are missed, they shall be performed prior to retuming Z the instrument to en operable status. ' w
- c. Cohbrations are not required when the instruments are not requer>d to be aperable.' However, af ,
celibrations ese missed, they shall be performed prior to returtwng the instrument to en operable status,
- d. Deleted.
4 .. e-N i N i M3 ' Logic system functional tests and simulated automatic actuation shall be performed once each uperating - cycle for the following: 7C
):E
- 1. HPCI Subsystem 3. Diesel Generator initiation i
't
/ 2. HPCf Subsystem Auto isoletion 4. Area Cooling for Engineered r+
re > Q sn Safeguard Systems 3::r The logic system functional tests sheH include e celebration of time falays and timers necessary for i
/
- proper functioning of the trip systems.
m W I I N W l .
?
N l W D
*1 '
O'
/
W . N i W t i i
,.m -- . ,, _.
i
,4 y -
Table 4 7 3
'o Check, Functional Test. and Calibeation Mnemum Frequency for instrumentation z
, Which initiates or Controis RCIC *
[ 'E Ref.. Instrument Check Instrument Furictional Test ~ Mirwmum Frequency - nnstrument Cahbretion L FAnemum Frequency 5 No. Instrument - . Minimum Frequency
~ .1 N (c) 1 Reactor Vessel Water Level (Level 21 Once/sNft : Once/ quarter Once/ operating cyc e . ll 1 ij 2 RC!C Turbine Overspeed Electricafi None N/A Once/ opera *mg cycle Mechanical None N/A Once/ operating cycle 3 RCIC Turbine Exhaust once/sh:ft Once/ quarter once/ operating cycle l .
Pressure '
-r 4 RCIC Pump Suction Once/sheft Once/ quarter . Once/ operating cycle Pressure
- l. ;
5 Reactor Vessel Water Level (Levels) Oncelshtt' . Once/ quarter Once/ operating cycle
] >
[ ru .. i a y 6 RCIC Pump Discharge Flow- Oncefehift Once/ quarter Once/operateng cycle
-l .
)
7 D ieted N '
/
[
/
8 Deleted '! r+ (D ! O 1 7 "* tn t
/
7 i / . .k 1 W ? .. T f 1 w ? I 4 ru
- W .
ru i W
< v. ,
't .
'M ?
O
/ +
W i i to i W. i l ! t w , r\3 . M . t i i t t- ;y . - - , s 4, - - , - . > -
1 T ABLE 4.2-3 (Continued) P H instrurret h instrume.1 Check instrurnent Function 4 Test Cav.netion PArumum Frequency Minimum Fe,quency fAnimum Frequency Ref. No. (b) (c) 2 tat instrument
--4 9 Deleted w
10 Deleted 11 Deleted 12 Deleted Once/ operating cycle None 13 PCIC Lope Power Hone failure Monitor W Once!querter . Every 3 months 14 Condensate Storage None W 7 Tank Levet Every 3 months w Once/ quarter l 15 Suppression Pool None Water Level 7 1
/
Notes for Table 4.2-3 t
/
r+ The cc4umn entitled "Ref. No." is only for convenience r,o that a one-to-one reietionship can be (o a. i O established between items in Table 4.2 3 and items in Tebte 3.2-3. l y m
/ b. Instrument functional tests are not -required when the instrurnents ers not required to b operatWe 7 or are tripped. However, if functional tests are missed, they shell be performed prior to returning f ~ the instrument to an operable status.
T W t N W N W 1 O
/
W N W I w N o.-*
Z Tabte 4.2-4 P
--4 m Check, Functsonal Test, and Calibration Mrumum Freq sency for instrumentation z Wtich Irvtiates or Controls ADS e
instrument functionat Test Instrument Calbration c instrument Ct,eck Mrnmum Frequency
= Ref. Mrwmum Frequency Mrumum Frequency
[ No. (b) kl leL Instrument Onceloperenng cycle l Once/stuft once/querter 1 Reactor Vessel Weter Level llevel 3) Once/ quarter .Once/ ope-sting cycle l Reactor Vessel Water Level Onceistuft (Level 1) Once/stuft once/ quarter Onceloperenng cy te l 2 Drywell Pressure Once/ quarte Once/operstmg cycle { 3 RHR Pump Descharge Once/stuft Pressure Oncelquarter Once/ operating cycle l 4 CS Pump Discharge Once/stuft . Pressure Once/operstmg cycle W None N/A
. 5 Auto Depressurization 7 Low Water Level Timer W Once/operarmg cycle W Auto Depressuriretion None ft/A 6
Tuner 7 Ncne None Onceloperstmg cycle M 7 Automatic B!owdown d
/
Controf Power Fai!ure Morator r+ ro O Notes for Table 4 2-4 r sa t The column entitied "Ref. No." is only for convervence so that e one-to one ref etionship can be
/ e. # established between items in Table 4.2-4 end items in Tabfe 3.2-4.
f.-. T W 6 N W N W
-1 O /
W N LaJ t w N N
( 1 y.
-4
. Table 4.2-5 '
m i :r Check. Functional Test, eruf Ceferation M rumorn Frequency for instrumerrietton g' ' Wtuch trutietes or Controls the LPC8 Mode of RHR !' Ref. Instrument Check Instrument Funct onal Test .. Instrurnent Cobbration - g No. Minimum Frequency. Merumum Frequency Mmmum Frequency
- [el Instrument (b) (el 1 Reector Vessel Water Level Once/stuft '- Once/ quarter- Once/opeesterra cycle ' ~l (Level Il 2 Drywell Pressure Once/stwit Once/querter Once/ operating cycle l' I 3 e. Reactor Vessel Steam once/stuft " Once/ quarter Once/ operating cycle .l-Doms Pressure 3 'b. - Reactor Vessel Steam Once/ shift Once/querter Onceloperating cycle..
Dome Precrure , 4 Reactor Shroud Water Level Once/ shift once! quarter Once/ operating cycle-' (Level 0) w
. 5 LPCI Cross Connect Velve None .Once/ Operating cycle None 7
w Open Annuncistor
- ui l
7: i i
):E 6 RHR (LPC1) Pump Flow . Oncelstatt once/ quarter Once/operstmg cycle -l i .e p 7 RHR ILPC3) Purm None .N/A Once/ operating cycle to Start Timers n
t 7 i y" 8 Velve Selection Tirners None N/A Once/ operating cycle , s ! p 9 RHR Reisy Logic Power None Once/ operating cycle tbne
.y Failure Morntor l
i wg N W N
.U l '
c O
/
W N I' I M ' 't: w t N w- tm'-" v' =
l Table 4.2 6 [>-4 c7 Check. Func1.cnal Test, and Cabbraten Mrwnum Fretsuency for instrumentetkm r- WNch trutsates or Controts Core Sprey 1 Instrument Functions' Test instrument Cahbratron Instrument Check E Ref. Mrwmum Frequency Merumum Frequency Mirwrman Frequency q'"" No. (bt 'el 1 Instrument Once/quartee Once/ operating cyck l 1 Reactor Vessel Water Level Once/sNft (Levelil Once/sNft Once/querter Once/operstmg cycle l' 2 Drywell Pressure oncelquarter Once/ operating cycle l 3 Reactor Vesset Steam Dome Once/stuft Pressure Once/ operating cycle OnceAfay N/A 4 Cote Spray Sparger Diff erential Pressure once/ quarter onceloperetmo cycle l S CS Pump Discharge flow Once/stutt W N None i None Once/operstmg cycle w 6 Core Spray t_oge Power CD Fedure Morutor Notes for Teble 4.2-6
.X. /
T he column entitled "Ref. No." is only for convenience so that a one-to-one relationstwp can be [
/
a. r+ to established between items in Table 416 and items in Tebfe 3.2-6. r3 7 m C
/
7 w T W f N W N W 9 O
/
W N W 4 w N w
h 4 y > Table 4.2-7
-4 .
....g l z . Check, Functional Test.'end Cahbrateon M.ramum Frequency for
., . Neutron Morutoring knstrumentation Wiwch trutsates Control Rod Blocks Z . .
[ Ref. instrument Check . Instrument Functional Test ,instrurtant Cahbration No. ' Mirumum Frequency . Merwrnum Frequency Merumum Frequency 1 Instrument (b) (c) (d) i 1 SOURCE RANGE MON! TORS
- a. Detector not futiin NA SMIU, W 1 NA-
- b. Upscale NA SMiU. W R-
- c. Inoperative NA S M'U, W NA
- d. Downscale : NA SMIU, W R 2 INTERMEDI ATE R ANGE MONITORS ;
- a. Detector not fullin NA SM"I, W'*I NA'
- b. Upscale NA SM"I, W8 'I R ,
- c. Inoperative NA SMIU. W I*I NA
- d. . Downscale NA SN"1, W I*I R y 3 APRM o
- a. Flow Referenced Sanulated Thermal Power-Upscale s NA SM"I, O R f b. Inoperative NA SNIU, Q NA
/ c. Downscale NA SM"I, O R l 4
/
- d. Neutron Flux - High,12% NA SNIU, O R r+
co 4 ROD BLOCK MONITOR c1
- r y a. Upscale NA SN"I, O - 'R 3
/ b. Inoperative NA SNtD, O NA
# SM"I, O p c. Downsente NA R
~
m w 5 SCRAM OfSCH ARGE VOLUME e N W e, Water Level-High NA Q R w 4 . V g Notes for Table 4.2-7 s
" The column titled "Ref. No.* is only for convenience so that a reto-one relationship can be established e.
-y between items in Table 4.2-7 and items in Table 3.2-7. '
~
$ b. Deleted.
, _ , .~ ._ . _ __.m_
[ Table 4.2-8 ! --4 o m Check, Functional Test, and Cafibration Minimum Frequency for Radiation ,
, a . Monitoring Systems Which Unst Radioactivity Release r~
f Ref. Instrument ChecL instrument functional Test instrument Calbeateen > [ No. fAnimum Frequency Minimum Frequency < fAnimum Frequency 1 instrument (b) (c) (d) 1 Off-gas Post Treatment ' Once/dey ' Once/ month (f) ' Every 3 months l
. Radiation Monitors 2 Refuehng floor Exhaust Once! day . Once/ quarter (f) . Every 3 months l-Vent Radiation Monitors 3 Reactor BuMing Exhaust oncelday once/ quarter (f) Every 3 months l-Vent Radiation Monitors . .
4 Control Roem intake Once/ day once/ quarter (t) Every 3 months l-Rad ation Monitors 5 Main Steam Line None Once/ week (f) Every 3 months (g! - Radiation Monitors N E I g Notes for Table 4.2-S
- a. The column entitled "Ref. No.* is only for convenience so that e one-to-one relationship can be
{ established between items in Table 4.2-8 and items in Table 3.2-8.
/ .
f b. Instrument checks are not required when these instruments are not required to be operable or are '
/
n tripped. However, if instrument checks are enissed, they shall be performed prior to retuming the 7 vi instrument to an operable status, t
/
7
/
s.* T W I N
.W N
W 9 O
/
W N W I O
i
.$ : --4 Notes for Tat >le 4.2 8 (Cont'd) '
rn m, c. Instrument functional tests are not required when the instruments eve not required to be operable or i a t. are tripp.ht However'. if instrument functional tests are missed, they shall be performed pno ' ;
=
Q to returning the instrument to an operable status.
- d. Instrument calibrations are not required when the instruments are not required to be' operable or are
~
I tripped. However, if instrument calibrations are missed. they shall be performed prior to retum- - ing the instrument to en operable status.
- e. Deleted. g w
- f. This instrumentation is exempted from the instrument functional test definition. This instrument 4
w j functional test will consist of injecting a simulated electrical signalinto the measurement channels. .j g '-i
>g g. Standard current. source used which pr..ovides en instrument channel afignment. Calibration us. ing a t
/ radiation source she!! be made once per operating cycle.
c+ m r3 !
- r sn
" Logic system functional tests and sirnutated automatic actuation shall be performed once each operating
- r I
/
- cycle for the following: l
~o u
4 1. Secondary Containment Actuation , w 't N. W e 9 O
/
' ta3 N
w i l h
, _ v ,.. , , m v.~ + b -~~
Table 4.2-9
-t b CHECK AND C AllBRATION MIN! MUM FREQUENCY FOR INSTRUMEfJTATION WHICH INITIATES RECtRCULATION PUMP TRIP 4
Instrument Functicnal Test Instrument Calebration Instrument Check E Ref. Minimum Frequency Minimum Frequency Minimum Frequency [ tJo. isL 'n'trument Once! quarter once/cperating cycle l 1 Reactor Vessel Water Level Once/ shift (ATWS RPTI M once/ quarter Once/ operating cycle l 2 Reactor Pressure Once/shft (ATWS RPT) 3 EOC - RPT Trip None l a) initiating Logic None Once/ quarter, Once/operatinD cycle None b) Breakers None Once/ operating cyrie c) Response Tirne None None RPT 10gic + BreakersI 'I Notes for Table 4.2-9 fa) The column endtled "Ref. No.* is ordy for convermenco so that e one-to-one relationsNp can be 7 A established between items in Table 3.2 9 and items in Table 4.2-9 us (b) An ATWS recirculation pump trip logic system functional test shed be performed once per operating cycle. X.
/ (c) The EOC RPT System Response Time shall be that time interval from initial signal generation by the associated
[ turbine stop valve limit switch or from when the turbine control valve hydraulic control off pressure drops below the pressure switch setpoint to complete suppression of the electric are between the
% fully-open contacts of the recirculation pump csrcuit breaker. The response time may be measured by to l h any series of sequential, overlapping. of total steps such that the entire response time is measured. Each test shalt include at least the logic of one type of channelinput, turtsne controf l
f
/ valve fast closure or turbine stop valve closure, such that both types of channelinputs are tested
' # st least once per 36 months. The EOC-RPT System Response Time acceptance enteria essociated with f q turbine stop valve closure shall be K 155 rnittiseconde; the EOC-RPT System Response Time acceptance , W criteria assoasted with the turbine control valve fast closure shet! be K 175 rnifliseconds. I N W N W 1 O
/
W N W 8 se O to
, . e ' [F*
l' l l { j ny o ti n c a 's r e s s s s ht ht ht ht h b uq t n n n n t n ia er f c o o o o CF d( t m m m m m nm e u 3 y 3 y 6 6 6 - y y y mm ue r e r e r e r e r e r n v v v v v t e E E E E E sM n i n io ta t n t s . e n r n r ey e e v u T c e e r n ts t a n e u t w w s. deto n oq e ou pt I ht ht ht b Hta r tr e cr ht ht d pn . o nF n n n n n e .ts ir t e f l u o o o o o h d e m yl e F m )(c m m n m s el pb e r u c u /m h h at r n e w y t nm e
/
e
/
e e
/
e b pa nre r s ew c c c c c a on ur n n n n n t t p qD e mr uM a o O o O O s e eo r le ei r e r e an bh F ht ts 0 b r e at 1 o o r g mo ut in 2 n a let e pn 0 n c orur mi 4 b t a r n eu 1
- w eg r e p e bt e w e 2
4 Mak e l b a t s pm or e na T n o oru t o lb -iL oe r o it b n e st dt er a t as f la i r o T r r s e o e iui r b o e r t h qp h t t d t e r d ai n o e g r t -a C o N m y in ui o-. dMn c qn e ni. o - k n r r t ah - u ef c e e t r r ic eu' n t e or ae s p t. s h h q y y y y y o n o eW C er a a a a a e t e
.T t F )
b d' d d d d et r nb e a r n / / / / / t la emt e e e e e a mla l n mu c n c n c n c n c n ht s rio uh t p r iot um r u o o O O O o s n t s s y c t ed n n u s ir n iM e c me um ieh e F n r r h t t o t ,
- k. ie sf d c n . inre ne es e e0 v ep h s h n-1 s e C wim o2 c heb t dere r 3 oe tnh ie r a f l e s iu s yab h wye qt es dr T r e o n dh t t et, ol n
p e g si is r n an ic in ?m iude eo ia m u t d in oe qs e r i Do r r S r a r
'roo so r
o Ni t s at c s n toP t t t a n t e a r .d t ro im tsfu nr i a cr cd f e n ner eg r ei A ea o R a e t t t n mt e Dr o t e t R e M " 0 ea r l e n ipn Dg n Dg r ask a e u I r oat n o se d 1
- nm, qw le2 s c u s f
m ni r ni tot r u r u lorg oo oot ss t k e r E o l F et t i it it a ea it n e 4 ch e et n nt s a t t s t t e F t iein !si n o lar a o bG u el h c uis
.i n wp ym ww tnMe t
s t m T le n ba ct n f f i le n e _ t t y b mT _ r u r lo ic ol r a t m c r Mo emu n r,b e e ra DS DF Sf o GN u Sf u loin mr mv uep e cs ut r s em t si n r t wo
- o. h e Tti Inf son InHe N ) i
- f .a e( 1 2 3 4 5 . . R a b c. h4nI-
- i Cz[ g.NIAcn (Vf+r$7gVs7/4 TWINW)r%W. -
> 7O/WNWt4N
I s s! B 9 3e s
,O c 5 et
& 'i sL a O
A 3 3 i t i k2
~
- 5 2, e >
=
2-a c - .. 3 5 : e
.s e w *
[ . e e 5 2 5 5 s 2 s
, i .
e u 3S 5 li i C i o 2 e 8 ; e
- e. .s s e .=. C 2
8
- s I3
* =
s 2e o E 1 - w e9 W E
\ 2 I? 'e S
= -
5 s. E e 1
- e t. O i e HATCH - UNIT 1 3,2-47 K:\wp\techsp\h\lP3-2323. pro \323-0
J t f a-Table 4.2-14 ! b CHECK, FUNCTIONAL TEST, AND CALIBRATION MtNtMUM FREQUENCY FOR INSTRUMENTATION
,, . VotiCH ARMS THE LOW LOW SET S/RV SYSTEM
. ~
6 Z Ref. Instrument Check . Instrument Functional Test ' instrument Cai+bration No.I*I instrument Minsmum Frequenev . Momum Frequency" ' Mmimum Fre<rmy d
.]
1- Reactor Vessel Steam Dome Once/ shift Once/ quarter Onceiopeesting cycle ' l-
. Pressure
'2 Relief / Safety Valve Tastpipe N/A ' Once/ quarter (d) - Omeloperstmg cydete) l Pressure t W N
9 x to
. n a. The cofumn entitled "Ref. No." is only for converwence so that a one-tm relatuship can be established between stems in table 4.2-14 and items in table 3.2-14 F:
) b. Instrument functional tests are not required when the instruments a o not required to be operable or are tnpped.
- [ However, if functional tests are missed, they shall be performed prior to returrwng the mstrument to an operable
% status.
m
- y c. Cahbrations are not required when the instruments are not required to be operstde. However,if cal 4> rations y are missed, they shall be performed prior to returrwng the instrument to an operat4e status s
3 ~
- d. See section 4.6.H.1 e.1 for exceptions to itss pressure swoch functamat test frequency.
m W e. See section 4.6.H.1.e.2. i N t.n2 N W 1 O
/
Lal N W f < w i O W e au- % _w - -- . - . - - _ _ . _ - - - - - _ = - - - _ --_a - . . =-- u
,__ BAS [S FOR llM111NG COND1110NS FOR _0PERid10N 3,2 110lff,.llDLIN51RUMENTAT10N in addition to the Reactor. Protection System (RPS) instrumentation which in-itiates a reactor scram, protective instrumentation has been provided which initiates action to mitigate the consequences of accidents which are beyond i the operators ability to control, or terminates operator errors before they result..in serious consequences. This' set of. Specifications provides the lim-iting conditions for operation of the instrumentation:
(a) which initiates isolation, l (b) which initiates or controls the core and containment cooling systems, (c) which initiates control rod blocks. (d) which initiates protective action,
.(e) which monitors leakage-into the drywell and (f) which provides survell-lance information. The objectives of these specifications are (1) to. assure the effectiveness of the protective instrumentation when required by presery-ing its capability to tolerate a single f ailure of any component of such sys-tems even during periods when portions of such systems are out of service for maintenance, and (ii) to prescribe the trip settings required to assure ade-quate performance. When necessary, one channel may be removed from service for brief intervals to conduct required functional tests and calibrations, footnotes are provided in each LCO table (Tables 3.2-1 through 3.2-14) which
' dictate the allowable time interval. .One instrument channel may be considered inoperable for up to 6 huurs in order to perform required surveillances for this instrumentation, prior to entering other applicable actions.
A. Isolation Actuation instrumentation (Table 3.2-1) l , Isolation valves are installed in those lines which penetrate-the primary con- ; tainment and must be isolated during an accident. Actuation of these valves
-is initiated by instrumentation shown in Table 3.2-1 which senses the conditions for which isolation is required. Such instrumentation must be available whenever primary containment integrity is required. The objective is to isolate the primary containment so that the guidelines of 10 CFR 100 are not exceeded during an accident.
- 1. Reactor Yessel Water Level l
- a. Reactor Vessel Water level Low (Level 3) (Narrow Ranae) l l The reactor water level instrumentation is set to trip when reactor water level is approximately 14 feet above the top of the active fuel. This level.is referred to as Level 3 in the Technical Spect- ,
fications and corresponds to a reading of 0.0 inches on the Narrow Range. scale, This trip initiates Group 2 and 6 isolation but does not trip the recirculation pumps.
- b. Reactor Vessel Water Level Low Low (Level u The reactor water level instrumentation is set to trip when reactor water level is approximately 9 feet above the-top of the. active
, fuel. This level is referred to as Level 2 in the Technical Speci-l fications and corresponds to a reading of -47 incnes, This trip initiates Group 5 isolation,-starts the standby gas l treatment system,_-and initiates secondary containment isolation. I l l HATCH - UNIT 1 3.2-50 K:twp\techsp\h\2P3-2323. prot 323-173 i' 1 u__ , _ -
~
lieMS 6 0R tlMlllHG CONDITIONS FOR OPERATION 3.2.A.7. tRin Steam Line Tunnel Temperat ge Hiah (Con _tinueil with the resultant small release of radioactivity, gives isolation before the guidelines of 10 CfR 100 are exceeded. B. hKlar_b'ALCr Cleanuo System Dif fertatial Flow Hlah Cross leakage (pipe break) from the reactor water cleanup system is detected by measuring the difference of flow entering and leaving the system. The set point is low enough to ensure prompt isolation of the cleanup system in the event of such a break but, not so low that (purious isolation can occur due to normal system flow fluctuations and instrument noise. Time delay relays are used to prevent the isola-tion signal which might be generated from the initial flow surge when the cleanup system is started or when operational system adjustments are made which produce short term transients.
- 9. hactor Water Cleanup Area Temperatgg_1[igh and -
- 10. hactor Water Cleanuo Area Ventilation Dif ferential Temperature High Leakage in the high temperature process flow of the reactor water cleanup system external to the primary containment will be detected by temperature sensing elements. Temperature sensors are located in the inlet and outlet ventilation ducts to measure the temperature dif ference. Local ambient temperature sensors are located in the compartment containing equipment and piping for this system. An alarm in the main control room will be set to annunciate a temperature rise corresponding to a leakage within the identi-fled limit. In addition to annunciation, a high cleanup room tempsrature will actuate automatic isolation of the cleanup system.
- 11. On@nser Vacuum Low The Bases for Condenser Vacuum low are discussed in The Bases for Specifita-tion 2.1.A.7.
- 12. Drywell Radiation When drywell radiation reaches the setpoint (1 138 R/hr), the purge and vent valves are automatically closed, thus isolating the containment atmosphere from the outside environment.
- 13. HPCI Emeroency Area Cooler Ambient Temperature Hiah High ambient temperature in 'he t HPCI equipment room near the emergency area cooler could indicate a break in the HPCI system turbine steam line.
The automatic closure of the HPCI steam line vcives prevents the excessive loss of reactor coolant and the release of significant amounts of radioactive material from the nuclear system process barrier. The high temperature setting $ 169 F was selected to be far enough above
" anticipated normal HPCI system operational levels to avoid spurious isolation but low enough to provide timely detection of HPCI turbine steam line break.
HATCH - UtilT 1 3.2-52 K:\wp\techsp\h\2P3-2323. pro \323-121
- - . . -. _._ __m _ . _ _ _ . _ - - . . . -_ _ ~m_.- .m.__-..~ ___ ._ ~
i
~
BASES FOR LIMITING CONDITIONS FOR OPERATj0ji 3 . 2 .' A .14 . HPCI Steam-sucolv Pressure' tow Low pressure in the HPCI steam line could indicate a break in the HPCI steam line. Therefore, the HPCI steam line isolation valves are automatically closed. The steam line low pressure function is provided so
.in the event that a gross rupture of the HPCI steam line occurred upstream from the high flow sensing location, thus negating the high flow indicating function, isolation would be effected on low pressure. The allowable value of 2 100 psig is selected at a pressure sufficiently high enough'to prevent turbine stall.
- 15. HPCI Steam Line AP (Flow) Hioh
, : HPCI steam line high flow could indicate a break in the HPCI turbine steam line. ' The automatic closure of the HPCI steam line' isolation valves. e prevents the excessive loss of reactor coolant and the release of' significant amount of radioactive materials from the nuclear system process barrier. Upon detection of HPCI steam line high flow, the HPCI turbine steam line is isolated. The high steam flow trip setting of 303%
flow was selected high enough to avoid spurious isolation, i.e., above the . high steam flow rate encountered during turbine starts. The setting was selected low enough to provide timely detection of a HPCI turbine steam. line break. ,
- 16. g(I Turbine Exhaust Diaohracm Pressure Hiah High pressure in the HPCI turbine exhaust could indicate that the turbine -
rotor is not turning, thus allowing reactor pressure to act on the turbine exhaust line. The HPCI steam line isolation valves are automatically closed to prevent overpressurization of the turbine exhaust line. The turbine exhaust diaphragm pressure trtp setting of f 20 psig is selected' high enough to avoid isolation of the HPCI if the turbine is operating, yet low enough to effect isolation before the turbine exhaust line is unduly pressurized.
- 17. HPCI Sucoression Chamber Area Ambient Temnerature Hiah-A temperature of 169'f will initiate a timer to isolate the HPCI turbine steam line.
- 18. RCI Sucoression Chamber Area Differential Air Temperature Hlah A dif ferential air temperature greater than the trip setting of $ 42'F between the inlet and outlet-ducts which ventilate the suppression chanber area will initiate a timer to isolate the HPCI turbine steam line.
- 19. pCIC Emeroency Area Cooler Ambient Temocrature Hiah High ambient temperature in the RCIC equipment room near the emergency area. cooler could indicate a break in the RCIC system turbine steam line.
" The automatic closure of the RCIC steam line vsives prevents the excessive loss of reactor coolant and the release of significant amounts of radioactive material- from the nuclear system process barrier. The high temperature setting of s 169'F was selected to be far enough above anticipated normal RCIC system operational levels to avoid spurious isolation but' low enough to provide timely detection of a RCIC turbine steam line break.
HATCH - UNIT 1 3.2-52a K:\wp\techsp\h\2P3-2323. pro \323-121 l l _ _ - . ._. _ __ _._ _. , __ _ - ._ ._ _, _
BASES FOR tlM111NG CONDITIONS FOR OPERAll0N 3.2.A.20. RCIC Steam Sucolv Pressure tog-Low pressure in the RCIC steam supply could indicate a break in the RCIC steam line. .Therefore, the RCIC steam supply isolation valves are automatically. closed. The steam line low pressure function is 'provided so that in the event a gross rupture of the RClc steam line occurred upstream from the high flow sensing location, thus negating the high flow-indicating function, isolation would be effected on low pressure. .The isolation setpoint of 160 psig is chosen at a pressure below that at which the RCIC turbine can effectively operate.
- 21. RCIC Steam Line (APJ Flow High RCIC turbine high steam flow could indicate a break in the RCIC turbine steam line. The automatic closure of the RCIC steam line isolation valves-prevents the excessive loss of reactor coolant and the release of significant amounts of radioactive materials from the nuclear system process barrier, tipon detection of RCIC turbine.high steam flow the RCIC turbine ste n line is isolated. The high steam flow trip setting of 306%-
- flow was selected high enough to avoid spurious isolation, i.e. -above the
- high steam flow rate encountered during turbine starts. The setting was selected low enough to provide timely detection of a RCIC turbine steam
. line break. . ,
- 22. LCIC Turbine Exhaust Diaohraam Pressure Hioh High pressure in the RCIC turbine exhaust could indicate that the turbine rotor is not turning, thus_ allowing reactor pressure to act on the turbine-exhaust line. -The RCIC steam line isolation valves are automatically closed to prevent overpressurization of the turbine exhaust line. The turbine exhaust diaphragm pressure trip setting of 5 20 psig is selected high enough to avoid isolation of the RCIC if the turbine is operating, yet low enough to effect isolation before the turbine exhaust line is-unduly pressurized.
~
j 23. ElC_$.ucoression Chamber Area Ambient Temoerature Hiah L As in the RCIC equipment room, and for the same reason, a temperature of li s 169aF will initiate a timer to isolate the RCIC turbine steam line.
- 24. Suboression Chamber Area Differential Air Temperature Hioh A high differential air-. temperature between the h,let and outlet ducts which ventilate the suppression chamber' area will initiate a timer to .
isolate the RCIC turbine steam line. i 8, Instrumentation Which initiates or Controls HPCI (Table 3.2-2)
- 1. Reactor Vessel Water level low Low flevel 2)
# The reactor vessel water level instrumentation setpoint which initiates HPCI "
is a -47 inches. This level is approximately 9 feet above-the top of the active fuel and in the Technical Specifications-is refer-red to as Level 2. The- reactor vessel low water level setting for HPCI system initiation is selected high enough above the active fuel to start the HPCI system in time both'to prevent excessive fuel clad temperatures and to prevent more than a small fraction of the core from reaching the temperature - at which gross fuel failure occurs. The water level setting is far enough
- below normal levels that spurious.HPCI system startups 'are avoided.
- 2. Drywell Pressure Hiah The drywell pressure which initiates HPCI is s 2 psig. High drywell pressure could indicate a failure of the nuclear system process barrier. This pressure is selected.to be as low as possible without inducing spurious HPCI system startups. This instrumentation serves as a backup to the water level instrumentation described above.
HATCH - UNIT 1 3.2-52b K : \wp\ t ech s p \ h \ 2 P3- 2323. p ro \323 - 12 v - , - .# ...._s-__ s... - . ~, . * + , - .#%_. - m . -- ,,-
BASES FOR LIMillNG CONDillQf15 IOR OPERANON 3.2.B.3. HPCI Turbine Overseeed The HPCI turbine is automatically shut down by tripping the HPCI turbine stop valve closed when the E000 rpm setpoint on the mechanical governor is reached. A turbine overspeed trip is required to protect the physi-cal integrity of the turbine.
- 4. HPCI Turbine Exhtsst Pressure High the HPCI When turbineHPCI turbine exhaust is automatically shutpressure down byreaches trippingthe thesetpoint (s 146 HPCI stop psig)losed.
valve c HPCl turbine exhaust high pressure is indicative of a condition which threat-ens the physical integrity of the exhaust line.
- 5. HPCI Pumo Suction Pressure Low The pressure switch is used to detect low HPCI system pump suction pressure ~
and is set to trip the HPCI turbine at s 12.6 inches of mercury vacuum. This setpoint is chosen to prevent pump damage by cavitation.
- 6. EtAttor Vessel Water Level Hiah (Level 8)
A reactor water level of +56.5 inches is indicative that the HPCI system has performed satisfactorily in providing makeup water to the reactor vessel, lhe reactor . vessel high water level setting which trips the HPCI turbine is near the top of the steam separators and is suf ficient to prevent gross moisture carryover to the HPCI turbine. Two analog dif-ferential pressure transmitters trip to initiate a HPCI turbine shutdown.
- 7. HPCI Pumo Discharoe Flow Hioh To prevent damage by overheating at reduced HPCI system pump flow, a pump discharge minimum flow bypass is provided. The bypass is controlled by an automatic, D. C. motor-operated valve. A high flow signal from a flow meter downstream of the pump on the main HPCI line will cause the bypass valve to close. Two signals are required to open the valve: A HPCI pump discharge pressure transmitter high differential pressure signal must be received to act as a permissive to open the bypass v.! te in the presence of a low flow signal from the differential pressure transmitter.
Mlf.: - Because the steam supply line to the HPCI turbine is part of the nuclear system process barrier, the following con-ditions (8-13) automatically isolate this line, causing shutdown of the HPCI system turbine. B. Deleted HATCH - UNIT 1 3.2-53 Amendment No. 403, 121
-I BASES FOR LIMITING COND1110NS FOR OPERA 110N 3 - 2, B ,8.-
. Deleted E
- 9. Deleted n
- 10. Deleted
- 11. Deleted ,
1
- 12. . Deleted.
HATCH - UNIT I 3.2-54 K:\wp\techsp\h\2P3-2323. pro \323-121 l
. , ~
,, v . ,--- ~
BASES FOR tiMI11NG CONDIT10PS FOR OPERA 110N 3.2.B.13. Deleted
- 14. Condensate Storace Tank level low The CST is the preferred source of suction for HPCI. In order to provide ,
an adequate wate'r supply, an indication of low level in the CST automat- + ically switches the suction to the suppression chamber. A trip setting of 0 inches corresponds to 10,000 gallons of water remaining in the tank.
- 15. Sucoression Chamber Water Level Hinh-A high water level in the suppression chamber automatically switches i 'Cl suction to the suppression chamber from the CST.
- 16. HPC1 toaic Power f ailure Monitor The HPCI Logic Power failure Monitor monitors the availability of power to the logic system. In the event of loss of avallebility of power to the logic system, an alarm is annunciated in the control room.
C. Instrumentation Which Initiates or Controls RCIC (Table 3,2-31
, 1. Reactor Vessel Water level tow low (Level 21 The reactor vessel wa'ter level instrumentation setpoint which initiates RCIC is a -47 inches. This level is approximately 9 feet above the top of the active fuel and is referred to as level 2. This setpoint insures that RCIC is started in-time to preclude conditions which lead to inade-quate core cooling.
- 2. RCIC Turbine Oversneed The RCIC turbine is automatically shutdown by tripping the RCIC turbine stop valve closed when the 125% speed at rated flow setpoint on the mech-anical governor is reached. Turbine overspeed is indicative of a condi-tion which threatens the physical integrity of the system, An electrical tachometer trip setpoint of 110% also will trip the RCIC turbine stop valve closed.
- 3. RCIC Turbine Exhaust Pressure Hioh Wnen RCIC turbine exhaust pressure reaches the setpoint (s 45 psig),--the RCIC turbine is automatically shut down by tripping the RCIC turbine stop valve closed.- RCIC turbine exhaust high pressure is indicative of a con-dition which threatens the physical integrity of the exhaust line.
- 4. -RCIC Pumo Syction Pressure low One differential pressure transmitter is used to detect low RCIC system pump suction pressure and is set to trip the RCIC turbine at $ 12.6 inches of mer-cury vacuum.
HATCH - UNIT 1 .3.2-55 K:\wp\techsp\h\2P3-2323. pro \323-121 8
- . , . . m, - . .
IMSES FOR LIMITINQ CONDITIONS FOR OPERMION 3.2.C.5, Reactor VI ssel Wster level Hioh (Level 81 A high reactor water 'evel trip is indicative that the RCIC system has performed n tisfactorily in providing makeup water to the reactor vessel, lhe reactor vessel high water level setting which trips the RCIC turbine is near the top of the steam separators and sufficiently low to prevent gross meisture carryover to the RCIC turbine. Two differential pressure trans-mitters trip to initiate a RCIC turbine shutdown. Once tripped the system is capable of automatic reset af ter the water level drops below level 8. This automatic reset eliminates the need for manual reset of the system before the operator can take manual control to avoid fluctuating water levels.
- 6. RCIC pumo Discharae flow To prevent damage by overheating at reduced RCIC system purp flow, a pump discharge minimum flow bypass is provided. The bypass is controlled by an automatic, D. C. motor-operated valve. A high flow signal from a flow meter downstream of the pump on the main RCIC line will cause the bypass valve to close. Two signals are required to open the valve: A RCIC pump discharge pressure transmitter high differential pressure signal must be received to act as a permit.sive to open the bypass valve in the presence of a low flow signal from the differential pressure transmitter.
Note: Because the steam supply line to the RCIC turbine is part of the nuclear systam process barrier, the following conditions (7 - 13) automatically isc' ate this line, causing shutdown of the RCIC system turbine.
- 7. Deleted a
- 8. Deleted HATCH - UNIT 1 3.2-56 K:\wp\techsp\h\2P3-2323. pro \323-121 i
.-..._.a
i
, BASES FOR LIM 111NG CONDli10NS FOR OPERATION 3.2.C.9, Deleted 10.-Deleted
- 11. Deleted
- 12. Deleted
- 13. RCIC Locic Power Failure Monitor The RCIC Logic Power Failure Monitor monitors the availability'of power to the logic system. In the event of loss of availability of power to the logic system, an alarm is annunciated in the control room.
- 14. Condensate Storace Tank Level tow The low CST level signal transfers RCIC suction from the CST to the suppressitm pool. The setpoint was chosen to ensure an uninterrupted supply-of water.during suction transfer.
- 15. Sucoression Pool Water igyel Hiqh A high water level in the suppression chamber automatically switches RCIC suction from the CST to the suppression pool.
HATCH - UNIT 1 3.2-57 K:\wp\techsp\h\2P3-232. pro \323-121
t%Sts F OR .LlMITING (QHDITIONS FOR OPERA 110N
- 2. QDEU._P.freintre tiinh Primary containment high pressure could indicate a break in the nuclear system process barrier inside the drywell. The high drywell pressurt setpoint is selected to be high enough to avoid spurious starts but low enough to allow timely system initiation,
- 3. P_ tactor Vessel Steam Dome _Pniture low With an analytical limit of 2: 300 psig and a nominal trip setpoint of 370 psig, the recirculation discharge valve will close successfully during a LOCA condition.
Once the LPCI system is initiated, a reactor low pressure setpoint of 460 psig produces a signal which is used as a permissive to open the LPCI in-jection valves. The valves do not open, however, until reactor pressure
~
falls below the discharge head of LPCI. HATCH - UNIT 1 3.2-60 K:\wp\techsp\h\2P3-2323. pro \323-121 j
.. - - - -- ---._.---.. . - - - - . - . - - - - - . - - - - . - . _ . . .~.
BASES FOR iIMil.lbG CONDITIONS FOR OPERAll0N-4.2 PROTECTIVE INSTRUMENTATION I The instrumentation listed in Tables 4.2-1 through 4.2-13 will be functionally tested and calibrated at regularly scheduled intervals.1The minimum functional test frequencies and allowable outage times for selected instrumentation related to isolation actuation, ECCS and RCIC actuation, and control rod block have been-revised. The NRC-approved r911 ability-based methodology in References 1 through 4 provides
-a basis for these C.anges and is consistans with similar changes to RPS '
instrumentation. The frequency of functional testing and calibration for other instrumentation is based on historical methodology (Reference 5). A. Egferences
- 1. NfDC-30851P-A, "BWR Owners' Group Technical Specification improvement Analysis for BWR Reactor Protection System,* March 1988.
- 2. NEDC-31677P-A, " Technical Specification improvement Analysis for BWR
! solation Actuation instrumentation " July 1990.
NEDC-30936P-A, "BWR Dwners' Group Technical Specification improvement 3. Methodology (with Ocmonstration for BWR [CCS Actuation Instrumentation) Part 2,* June 1987.
- 4. NEDC-30851P-A, Supplement 1. " Technical-Specification Improvement Analysts for BWR Control Rod Block Instrumentation," October 1988.
- 5. kCRL-50111, " Improving Availability and-Readiness of Field Equipment Through Periodic Inspection," Benjamin Epstein. Albert Shiff, July 16, 1968, page 10. Equation (24), Lawerence Radiation Laboratory.
w. r HATCH - UNIT 1 3.2-69 K:\wp\techsp\h\2P3-2323. pro \232-103 v . ., ~ , . . - m n ,, ,-- , ~ - - . - - , w ,.n,, , - -- --,, , . --a w
_ BA$(LL(dLLIM111NG COND1110NS FOR OPERATION Deleted
' St 4 ')
HATCH'- UNii 1 3.2-70 e 5 , , v r ,.'.v. , E -- - - - .
t l
"" -1 IN.11d1)1[ds [JNUlUD4$__Jg pg g g Ocleted 1
I l l t i 9 r I t a o u .. ... s.. w,u u, ,, ,
-HATCH - UNJT j 3.2-71 1
I
> ' .i . .m - - _. , .. . . _ ....,..#..,-.~... .,...e .. _ , _ . . ,,....m-_...._,...--.e-.,'.-r . ._4. ..,-.. . , . _ . , , ,
e--- - - - - - - - - - . _ , - - - , ,, . , - _ . - - - - - ,_ , _ ___ _ _ ___,___ ___,_ _ _ ,__ _ i 4 b f!GURE 4.2-1 Deleted I i
- f
* YN' M I m , _ _ _ ,
15fl5U2Willm_jfL011MUEt ..'AtYlltLIMLLLWi!M!ill_ 3.5.H. MattduantnLH11tdluthane 4 . S at . titintratutnL1111e d . D i s c h a rse han Eini whenever the (5 system, LPC1, The following surveillance re-HPCI, or RCll are required quirethents shall be performed to be operabic, the discharge to assure that the discharge piping from the pump discharge piping of the CS system, LPCl, of these systems to the last HPCI, and RrlC are block valve shall be filled, filled when required: 1he suctice of the HPCI pumps shall le aligned to the conden- 1. (very month, the discharge
- s. ate storage tank, piping of the LPCI and CS systems shall be vented from the high point and *nter flow observed,
- 2. Following any period where the LPCI or C$ systems have not been required to be operable, or have been inoperable, the discharge piping of the system or sys-tems being returned to ser-vice shall be vented from the high point prior to re-turn of the system to service,
'- 3. k'honever the HPCI or RCIC system is lined up to take suction from the condensate storage tank, the discharge piping of the HPCI and RCIC shall be vented from the high point of the system and water flow observed on a monthly basis. 4 The level switches which monitor the discharge lines shall be calibrated every 3 months,
- 1. tiinim.am R1yer Lgygl
- 1. tiininum River level lhe water level as, measured
- 1. If the water ,evel, as in the pump well, and the rneasured in the pump well, level in the river
- shall is less than 61.2 ft MSL, be verified with the follow-the distbarge from t'ch plant ing frequencies:
service water (P5W) pump will be throttled such that each pump 1,1yrl (MSL) fr.t_qutg.y does not exceed 70(t gpm. 1, > 61.7 ft 01 weekly,
- 2. If the water leve es measured in the pump well, '":reases to 2. 5 61,7 ft [very 12 hrs, less than 60.7 ft t.t, or if the level in the riser
- drops to a level equival]nt to less
'Only pump well monitor.ug it required if a temporary weir is not in place, . HATCH - UNIT 1 3.5-11 k:\wp\techsp\3-5UI, pro \323-170 l
l
~
1DillDil.idiDll10N5 foR OPEPAT101 SURVllittML MQUIREMENis 3.6.H.l. frlte,ff, ably _YAhti 4 6 H.l. Felief/ Safety Valves
- a. Ww y nore relief / safety a. Ltd of Otuatim Cycle T "
%nown to be f ailed"* an or r Jown shall te initiated toprvximately one-half of all
% tor depressurtred to relief / safety valves shall to
.n d3 psig within t4 hours. henchchecLN or replaced with 0 reactor startup frorn a a temchttuked valve each re-w.. .ondition all relief /tafety fueling out ne. All 11 valves valves shall be operable."
will have toen checked or re-placed upon the cmpletion of every second operating cycle. ;
- b. With one or rore relief / safety b. [EhAE411tELCYClt valve (s) stuck open, place the reactor rnode switch in the shutdown position. Once durirg each ogerating cycle, at 4 itactor pitssurt
> 100 psig each rtlief calve shall te ranually opened until thenrocouples downstrvatn of the valve irdicate stern is flow-ing fmn the valve.
- c. With one or core safety / relief valve c. Intearity of Relief Vnlyg tailpipe pressure switches of a hells 1*
safety / relief valve declared ; inoperable and the associated The integrity of the relief valve safety / relief valve (s) otherwise tellows shall te continuously a indicated to be open, place the conttored aid the pressure > reactor trode switch in the Shut- Switch calibrated once per down position, operatirg cycle and the accu-nulators ard air piping shall te inspected for leakage once per operatirg cycle,
- d. With one safety / relief valve tailpipe d. Relief Valve Maintenage prrssurt switch of a safety / relief valve declarrd inoperable ard the asso. At least are relief valve shall ciatedsafety/reliefvalve(s)otherwise te disassort>1ed ud inspected irdicated to te closed, plant operation each operating cycle.
may continue. Pa ove the function of that pressure switch frmrn the low IN e. Otugbility of failDire set logic circuitry until the next COLD Pressure Switchel SIRDOWN. Upon C0lD SUTIDN. restore . thepressureswitch(es)toOPEPWILE The tailpipe pressure switch status tefore 51ARTUP. of each relief / safety valve sb:.ll te denonstrated opezable**** l
- e. With teth safety / relief valve tailp'ipe by perfonae ' a:
pressurv switchts of a safety / relief valve declared inoperable and the asso- 1. Functional Test: ciated safety /rtlief valve (s) otherwise indicated to be closed, restors at least 4. At least once per 92
,_L one inoperable switch in OPEPME status days, except that all within 14 days or te in at seast ICT portions of instnston-9f tlinN within the next 12 hours tation inside the pri-and in COLD SUTION within the mary contairvent may te follwing 24 hours, excluded fmn the functional test, and
*0oes not apply to two-stMe Target Pel SRVs "The Relief / Safety valves are not equired to te operable for perfonnance of inservice hydrostatic or pressure testing with reactor pressure girater than 113 psig and all control rods inserted. Overpressure protection will te provided as requited try A9E Code.
*"lhe failure or malfunction of any safety /rvisef valve shall te reported by telephore within 24 hours; confinmd by telegraph, mallgram, or facsimile transmission to the Director of the Regional Office or his designee re later than the first working day and a written followup report within 30 days. Tre written followirq thesnou followup report event;ld te cmpleted to accortance with 10 CFR 50.73 or other hoplicable recuinsmnts.
*"*0ne Instnrent channel may te inoperable for up to 6 hours to perfonn rrquired surveillances prior to entering other applicable actions.
HATCH - (NIT 1 3.6-9 k:\wp\techsp\h\3-6U1323. pro \323-149
i __LisfPG LLt011kl15 fM OHPAlhJ4 9E'ElillMi M(UlMMNis 4.6 H.l. Relief / Safety Valyn (Continued)
- e. Opfilh1111Y of Tail Pjpg
- Prvisure Switcheg
- 1. Functional Testt
- b. At each scheduled out-age greater than 72 hours during which ers try is made into the primary contilnment. ;
if not perfonted with-in the previous 92 l days.
- 2. Calibration and verifying the setpoint to be 85. 415.
-5 psig at least once per 10 months.
3.0,H,2. Iselief/h{g1Lyallts low LW 4.6,H.2. ltiiunction E9)ltflhillLlilV85LNLW hifunction During power operation startup, The low low set relief valve func-and hot standby the relief tion and the low low set function valve function and the low low pressure actu. tion instristenta-set function of the following tion shall be demonstrated OPLpABLE***l reactor coolant system safety / by perfomance of at relief valves shall be OPCMBLC with the following low low set a. OWNEL FUNCi10mL TEST. function lift settings: including calibration of the trip c.itt and the dedicated low Low Set Allowable Value (psig)* high steam dome pressure y31vefunction Ont0 Cl2lLg channels **. at least once low s 1005 s 857 Medium s 1020 b.
> s 872 OWNFL CAllDRATION. Logic Medium High $ 1035 s 887 System function Test, and High s 1045 i 897 simulated automatic operation of the entire system at least
- a. With the relief valve function and/or once per 18 months.
the low low set function of one of the atove required reactor' coolant systwn safety / relief valves inoper-able, restori the relief valve (tec- 5 tion and the low low set function to OPEPABLE status within 14 days or be in at least IDT SHlfiDOWN within the next 12 hours and COLD SitffDOWN within the following 24 hours, t
*the lif t setting pressure shall correspord to ambient conditions of the valves at nominal operating tenperatures and pressures.
**The setpoint for dedicated high steam dame pressure channels is 11054 psig.
***0ne instruttent channel may be inoperable for up to 6 hours to perfom required surveillances prior to entering other applicable actions.
HAICH - UNIT 1 3,6-94 k:\wp\techsp\h\3-601323. pro \323-103
- 9 6
- g. g--.,,9- ,,--y - . , + -,. y g-_ . - - , s - +-,.. .-
l 1flN!fintOnhf6 R41 OptflAl1(H SURVEllllML k[OUIRIMNii 4.9.A.6. DEntentL250 Yah.DC to f,00 Yah - AC Inverters (Continued)
- b. Once every scheduled refueling outage, the servency 250 volt LC/600 volt AC inverters shall te subjected to a load test to dononstrate operational readiness.
3.9. A.L Ltsic_$num 4.9.A.7. IngicSystom3 the following logic systems shall The logic systems shall to tested in be operable: the manner and frequency as follows:
- a. The cocoon accident signal a. Each division of the (.oncon I logic systta is operable, accident signal 1(9 1c system shall ,
le tested every scheduled refueling j outage to dmonstrate that it will < function on actuation of the core Spray systta to ptvvide an automatic start signal to all 3 diesel generators, t) . The undervoltage tilsys and b.l. Once every scheduled refueling supporting systta are operable, outage, the conditions under which the undervoltage logic systte is required shall te sinulated with an undervoltage on each start bus to denonstrate that the diesel generators will start. The testing of the undervoltage logic shall dmonstrate the operability of the 4160 volt load shedding and auto bus transfer circuits. Tte-sinulations shall test both the degraded voltage and the loss of off-site power vtleys.
- 2. Deleted l c.l. Once per operating cycle each diesel generator shall be d e onstrated operable by simulating -
toth a loss of off-site power and a degraded voltage condition in conjunctionwithanaccidenttest
- c. The conron accident signal logic signal and verifying:-
system, and undervoltage relays and supportif.9 system are operable.
. HAICH - (NIT 1 3.9-4 k:\wp\techsp\h\3-901323. pro \323-88
-n, -v's-ne-
INSTRUMENTATION fLAD10 ACTIVE L10VID EFFLUENT INSTRUMENTATION ! U MITING CONDITION FOR OPERATION 1 3.14.1 The radioactive liquid effluent monitoring . instrumentation channels shown in table 3.14.1-1 shall be ! OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.15.1 are not exceeded. The alarm / trip - setaoints of these channels shall be determined in accordance wit 1 the 0FFSITE DOSE CALCULATION MANUAL (ODCM). i APPLICABILITY ! As shown in table 3.14.1-1. bf11011
- a. With a radioactive liquid effluent monitoring -
instrumentation channel alarm / trip setpoint less 1 conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, declare the channel inoperable, or change to a conservative value.
- b. With the number of' channels OPERABLE
- 1ess than the_.
minimum channels required by table 3.14.1-1, take the l._ action shown in table 3.14.1-1.- .
- c. The provisions of Specification 6.9.1.13(b) are not applicable,
- d. When the ACTION statement or other requirements of this
-LCO cannot be met, steps need not be taken to change the Operational Mode of the Unit. Entry into an Operational Mode or other specified condition may be made if, as a minimum, the requirements of the ACTION Jtatement are -
satisfied. S.11RVEILLANCE RE0VIREMENTS 4.14.1 Each radioactive liquid effluent monitoring , instrumentation channel shall be demonstrated OPERABLE by l per'ormance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALABRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in table 4.14.1-1. L 1:
*0ne instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable actions.
HATCH-UNIT 1 3.14-1 k:\wp\techsp\h\3-14UI. pro \l10
,.,.-.......,._,._w, .n_..-., c,, ,_ . ~ . , , ,-,,_ _ ,.n-e , _ , , , , - , . _ 5,~_.,.__,m.
TABLE 3.14.2-1 (SHEET 3 Of 4;
!M010AC11VE CASEQMLEFfLUEfil M0fil10 RING INSTRUMENTAT10tl lable Notationi 4 Monitor must be capable of responding to a lower Limit of Detection of 1 x 10"' Ci/ml.
*During releases via this pathway.
**During main condenser offgas treatment system operation.
***During operation of the main condenser air ejector.
ACTION 104 - With the number of channels OPERABLE less than refutredbytheMinimumChannelsOPERADLErequirement efluentreleasesviathispathwaymaycontinue,provIded the flowrate is estimated at least once per 4 hours. if the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days an explanation of the circumstances shall be included in the next semi-annual effluent release report. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable actions. ACTION 105 - With the number of channels OPERABLE less than re effuiredbytheMinimumChannelsOPERABLErequirementluentreleasesviathispathwaymay grab samples are taken daily and analyzed daily for gross activity within 24 hours. With the number of main stack monitoring system channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, without delay suspend drywell purge, if the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for an explanation of the circumstances shall be over30 includeddays in {henextsemi-annualeffluentreleasereport. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable actions, - ACTION 106 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may continue provided: (a) Gas withsamples are collected in the ensuing once 4 hours, or per 4 hours and analyzed (b) Using a temporary hydrogen analyzer installed in the offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged every 4 hours. HATCH-Ulill 1 3.14-9 h:\wp\techsp\h\3-14VI. pro \l10
TABLE 3.14.2-1 (SHEE1 4 of 4) EA010 AClLYflAji[QM S E F f LU U{L110N 1 T OR 1 RD._(({1LRM[lil AJ1Q1{ Table Notations (Continued) If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable actions. ACTION 107 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided sampics are continuously collected with auxiliary sampling equipment for periods on the order of 7 days and analyzed within 48 hours after the end of the sampling period. If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.
^
One instrument channel may be inoperable for ut"to i 6 hours to perform required surveillances prior to entering other applicable actions. ACTION 108 - With the number'of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, release to the environment may continue for up to 72 hours provided:
- a. The offgas system is not bypassed, and
- b. The offgas post-treatment monitor (Dll-K615) or the main stack monitor (Dll-K600) is OPERABLE.
Otherwise, be in at least HOT STANDBY within 12 hours. If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable actions. 9 HATCH-UNIT 1 3.14-10 k:\wp\techsp\h\3-14UI. pro \l10 l
REACTIVITY CONTROL SYSTEMS Q!(TROL R0D SCRAM ACCUMULAIQEl Ll!il]J!(G CONDITION FOR OPERATION 3.1.3.5 All control rod scram accumulators shall be OPERABLE. APPLICABILLIX: CONDITIONS 1, 2 and 5*. ACllD!i:
- a. In CONDITION 1 or 2 with one control rod scram accumulator inoperable, the provisions of Specification 3.0.4 are not applicable and operation may continue, provided that within 8 hours:
- 1. The inoperable accumulator is restored to OPERABLE status, or '
- 2. The control rod associated with the inoperable accumulator l is declared inoperable and the requirements of l
Specification 3.1.3.1 are satisfied. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours,
- b. In CONDITION 5* with a withdrawn control rod scram accumulator inoperable, fully insert the affected control rod and electrically disarm the directional control valves or close the withdraw isolation valve within one hour. The provisions of Specification 3.0.3 are not applicable,
- c. One instrument channel may be inoperabic for up tii 6 hours to perform required surveillances prior to entering other applicable ACTIONS. ,
SURVEILLANCE RE0VIREMENTS 4.1.3.5 The control rod scram accumulators shall be determined OPERABLE: a, At least once per 7 days by verifying that the pressure and leak detectors are not in the alarmed condition, and
- b. At least once per 18 months by performance of a:
-1. CHANNEL FUNCTIONAL TEST of the leak detectors, and
- 2. CHANNEL CAllBRATION of the pressure detectors to alarm at: 940 psig.
l
*At least the accumulator associated with each withdrawn control rod.
I Not applicable to control rods removed per Specification 3.9.11.1 or 3.9.11.2. l HATCH - UNIT 2 3/4 1-8 k:\wp\techsp\h\3_412. pro \323-55 l
i 8{gilVITY C0fliROL SYSlfJili 800 BLOCK M0filTOR LIMITING CONDIT10ft FOR OPERAT10f4 3.1.4.3 Both Rod Block Monitor (RBM) channels shall be OPERABLE. APPLIC ABIL1H: C0fiDIT10N 1, when THERtiAL POWER is greater than or equal to 30% of RATED THERMAL POWER and when the MCER is less than i the value provided in the CORE OPERATING LIMITS REPORT. ; 1 l ACT10ft:
- a. With one RBM channel inoperable, POWER OPERAT1011 may continue provided that the inoperable RBM channel is restored to OPERABLE status within 24 hours; otherwise, trip at least one rod block ;
monitor channel within the next hour,
- b. With both RBM channels inoperable, trip at least one rod block monitor channel within one hour.
- c. One instrument channel may be inoperable for up to 6 hours ~to perform required surveillances prior to entering other applicable ACTIONS-SURVE1LLANCE REQUIREMENTS 4.1.4.3 a. With both RBM channels OPERABLE, surveillance requirements are given in Specification.4.3.5.
- b. With one RBM channel IN0PERABLE, the other channel shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST prior to withdrawal of control rods.
t HATCH-UNIT-2 3/4 1-17 k:\wp\techsp\h\3_412\l06. Pro 1
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PR01ECT10N SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2. Set points and interlocks are given in Table 2.2.1-1. APPllCABILITY: As shown in Table 3.3.1-1. A(ll@:
- a. With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place at least one inoperable channel in the tripped condition within 12 hours.
- b. With the requirements for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one inoperabic channel in at least one trip system
- in the tripped condition within I hour and take the ACTION required by Table 3.3.1-1.
- c. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS, provided at least one OPERABLE channel in the same trip system is monitor-ing that parameter._ _ -
- d. The provisions of Specification 3.0.3 are not applicable in OPERA- l TIONAL CONDITION 5.
SURVEllLANCE REQUIREMENTS 4.3.1-1. Each reactor arotection system instrumentation channel shall be demonstrated OPERABLE ay the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CAllBRATION operations during the OPERAIl0NAL l CONDITIONS and at the frequencies shown in Table 4.3.1-1. 4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18_ months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system. 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function of Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of. redundant channels in a l.. specific reactor trip function.
*1f both channels are inoperable _in one trip system, select at least one inoperable channel in that trip system to place in the tripped condition. l except when this could cause the Trip Function to occur.
HATCH - UNIT 2 3/4 3-1 techsp\h\3_432323. Pro \323-100
. . - - - - ._...................__s
TABLE L3.1-1 (Continued) i REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION 9 - In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHU1DOWN within 6 hours. in OPERATIONAL CONDITION 3 or 4, lock the reactor mode switch in the Shutdown position within I hour. In OPERATIONAL CONDITION 5, suspend all o)erations involving CORE ALTERATIONS or positive reactivity c1anges and fully insert all insertable control rods within I hour. TABLE NOTATIONS
- a. Deleted. l
- b. The " shorting links" shall be removed from the RPS circuitry during CORE ALTERATIONS and shutdown margin demonstrations performed in accordance with Specification 3.10.3.
- c. The IRM scrams are automatically bypassed when the reactor vessel mode switch is in the Run position and all APRM channels are OPERABLE and on scale.
- d. An APRM channel is inoaerable if there are less than 2 LPRM inputs per level or less than 11_PRM inputs to an APRM channel,
- e. These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed.
- f. This function is automatically bypassed when the reactor mode switch is in other than the Run position,
- g. This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
- h. With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.11.1 or 3.9.11.2.
- i. These functions are bypassed when turbine first stage pressure is $250*
psig, equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER. J. Within 24 hours prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full-power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level- and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen
- Initial setpoint. Final setpoint to be determined during startup testing.
HATCH - UNIT 2 3/4 3-5 techsp\h\3_432323. Pro \323-100
TABLE 3.3.1-1 (fontinued REACTOR PROTECT 10t1 SYSTEM lilSTRUMEf41 AT10_Il injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours of re-establishing normal radiation levels af ter completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power. HATCH - UtilT 2 3/4 3-5a techsp\h\3_432323. Pro \323-100
UlSTRVMERJAllflu 314.3.2- ISOLATION ACTUATION INSTRUMENTATION LIM 1 TING CONDIT10N FOR OPERAT10N l 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the i values shown in the Trip Setpoint column of Table 3.3.2-2 and with :
-lSOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3. ,
APPLICABillTY: As shown in Table 3.3.2-1. ACTION:
- a. With an isolation actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable and place the inoperable channel in the tripped condition
- until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
- b. With the number of OPERABLE channels less than required by the minimum OPERABLE channels per trip system requirement for one ,
trip system, either:
- 1. Place the inoperable channel (s) in the tripped condition
- within 12 hours OR
- 2. Take the ACTION required by Table 3.3.2-1.
The provisions of Specification 3.0.4 are not applicable.
- c. With the requirements for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one inoper-able channel in at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table t 3.3.2-1.
- With a design providing only one channel per trip system, an inoperable-channel need not be-placed in the tripped conditi.pn where this would cause the Trip-function-to occur. -In these cases', the inoperable channel shall be restored to OPERABLE status within 2 hours or the ACTION required by Table 3.3.2-1 for that Trip function shall be taken.
**1f both channels are-inoperable in one trip system, select at least one inoperable channel in that trip system to place in the tripped condition, except when that would cause the Trip function to ot. cur.-
HATCH - UNIT 2 3/4 3-0 '.1
. p techsp\h\3 1323?5. Pro \323-8 l
-- . . . . - - _ - ~ - - ~ - _ . _ . - .--_ . _ _. . , _ _ . _ _ _ . _ _ - - - . _ .
s t i LIMITIRG CONDITION FOR OPERAT1.ON {
- d. One instrument channel may be inoperable for up to 6 hours to perform !
required surveillances prior to entering other applicable- ACTIONS. l
- e. The provisions of Specification 3.0.3 are not applicable in l OPERATIONAL CONDITION 5. l SURVEILLANCE RE0VIR[HENTS f 4.3.2.1 Each isolation actuation instrumentation channel shall be .['
demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST AND CHANNEL CAllBRATION operations during the OPERATIONAL CONDlil0NS and at the-frequencies shown in Table 4.3.2-1. ;
- i i
t e i
.1 I
f s r j-i r-l t l- . HATCH --UNIT 2 3/4 3-9a k:\wp\techsp\h\3_432323. Pro \323-8
--.-.-.a--..-.-.-.__--.-.---.. ..-;--.-..---,_-...
l 1ABLf 3.3 J-1 (Continued)
]SblAT10N A.Clyal10N INSTRUMENTATION 6.CllDU AC110N 20 -
Be in at least HOT SHU100WN within 6 hours and in COLD SHUTDOWN within the next 30 hours. AC110N 21 - Be in at least STAR 1UP with the main steam line isolation valves i closed within 2 hours or be in at least HOT SHUT 00WN within 6 l hours and in COLC SHU100WN within the next 30 hours. l AC110N 22 - Be in at least STAR 10P within 2 hours. ' ACTION 23 - 00 in at least STARTUP With the Group 1 isolation valves closed I within 2 hours or in at least HOT SHUTOOWN within 6 hours. ACTION 24 - Establish SECONDARY CONTAINMENT IN1EGRlTY with the standby gas treatment system operating within one hour. ] ACTION 25 - 1solate the reactor water cicanup system. ACTION 26 - Close the affected system isolation valves and declare the affected system inoperable. ACTION 27 - Verify power availability to the bus at least once per 12 hours ; or close the affected system isolation valves and declare the
.affected system inoperable, l ACTION 28 -
Close the shutdown cooling supply and reactor vessel head spray isolation valves unless reactor steam dome pressure $ 145 psig, i AC110N 29 - Either close the affected isolation valves within 24 hours or be in HOT SHUTDOWN within the next 6 hours and in COLD SHUTOOWN ; within the next 30 hours.
~
l@lfdi Actuates the standby gas treatment m iem.
- When handling irradiated fuel 1n the secondary containment.
- When performing inservice hydrostatic or leak testing with the reactor coolant temperature above 212' F.
- When handling irradiated fuel 1n the secondary containment.
- a. See Specification 3.6.3. Table'3.6.3-1 for valves in each valve group.
- b. Deleted. l.
HATCH - UNIT 2 3/4 3-15 techsp\h\3_432323. Pro \323-91
.~.-.:---.-.=. -. - .- - .. .- . -- .-.-. _ _ .-. - .-_. .._ _ - - -
l TABLE 3.3.2-1 (Continued) ISOLATION ACTVATION INSTRUMENTATION
- c. With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall ,
be restored to OPERABLE status within 2 hours or the ACTION required by Table 3.3.2-1 for that Trip function shall be taken.
- d. Trips the mechanical vacuum pumps,
- e. A channel is OPERABLE if 2 of 4 instruments in that channel are OPERABLE.
- f. May t,e bypassed with all turbine stop valves closed.
- g. Closes only RWCV outlet isolation valve 2G31-F004.
- h. Alarm only,
- i. Adjustable up to 60 minutes.
J. 1solates containment purge and vent valves,
- k. Within 24 hours prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full-power radiation background level and associated trip setpoints may be
- changed based on a calculated value of the radiation level expected during :
the test. The background radiation level and associated trip setpoints may ' be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background , radiation level shall be determined and associated trip setpoints shall be set within 24 hours of re-establishing _ normal radiation levels after completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power. l; HATCH - UNIT 2 3/4 3-15a techsp\h\3_432323. Pro \323-91
- ._ __ _ _ . - _ . _ . _ . - _ . __._..a
T ABLE 4 3 2-1 [4 iSDL ATIO*J ACTU ATIO'1 I?fSTRUfM*JT ATION SURYULL AftCE RE QUtREfAErlTS i OPERATIOf4AL CH Aff.'E L CH ATJ'iLL COf404TIO*ts 174 WHtCH FUTJCTIONAL
~
5 T R!" FUNCTION CHAPCEL CHECK _ TEST C AlfE'4 8 TIO*4 SURVUtt ANCE PECbmED
" 1, PR!?AARY COtJT Alff*#ENT 1 SOL AT80N
- a. Reactcw Vessef Weer Level R 1, 2. 3 S Q
- 1. Low (Level 3) R 1, 2. 3 S O
- 2. Low Low (Levet 27 R 1, 2. 3 S Q 3 Low Low Low (Levd 1)
Q R 1.2.3 { 12 . Drywell Pressure - Hgh S c, fan Steam L ne W"* R 1,2.3 l
- 1. Rad.ation - Hgh S 1 fJA PJ A O
- 2. Pressure - Low R 1. 2, 3 S O
- 3. How - Kgh ,
W d. TW+n Steam Lme Tunnel R 1, 2. 3 l x S Q a Temperatu.e - Hgh 1, 2 *. 3' l w NA NA O CoewJenser Vecuurn - Low 4 e.
- f. Turtur.e Swung Area Temo. - R 1.2.3 l f4A C y
Hgh l R T . 2. 3 l S Q
- g. Drywell Radistoon - Hgh t
r / i c+ 2. SECONDARY CONT Ate fAENT fSOLAT'ON re n , 7 a. Reactor Sinbr g Exhaust 1. 2. 3, 5 erwi l Radiat.on - ngh S Q* R t
/ l 7 O R 1. 2. 3 S
'g b. Drywen Pressure - Hgb l
N
- c. Reactor Vessel Weter Level -
Low Low (Level 2) S Q R 1,2.3 l N ,
" 4. Refueling Floor Exhaust 1. 2. 3. S and l S NA O y Radiation - f+gh O
/
w N W *When handieng ertediated fuel in the secorw.fary conta.nrraeM. e y #fAay be bypassed with aG tuttine stop vaivas closed. (aHnstrument a6gnment usmg a starriard current source.
~ T ABLE 4.3.2 i (C&bn 3.-17 3 --A TSOLATION ACTU ATiON fNSTEU'*ENT AT!CN SURVDLL ANCE REQ 9tF!r TENTS CPERATiONAL e CHA NNEL FUNCT3ONAL C HA *.NE L CONDITKMS !M WH!CH CH A NNEL E CHECK TEST C At GA AT'ON SURVEtLLANCE FEC9 ED T RIP FUNCTION ]
3, FE ACTOR WATER CLEANUP SYSTEM fSOLATicti Q R 1. 2. 3 l A Fisw - H g5 S a. O R 1.2.3 l Area Tempera:t.<e - Rgh S b.
- c. Area Vent 4eteort A R T , 2. 3 l S O Tem;eature . H.gh R NA 1. 2. 3 SLCS 1%stum NA d.
1, 2. 3 S O R l
- e. Reactor Vessel Water Level -
Low Low (Level 2) W 4 HfGH FRESSURE COOLANT l'JJECTION N A SYSTEM iSOL ATION w Q R 1. 2. 3 l HPCI Steam Une now-Wah S a. N b. HPC1 Steam Supply Pressure- 1,2.3 l Q R S Low S Q R 1. 2. 3 l
- c. HPCi Tutbme Ed.aust 7
-- Diapbreg n Pressure - bgh I d. HPCI Pipe Penetreteen Room Temperature - Kgh S O R 1.2.3 l 3e+ e. Suppression Pool Area Arnbeent 1.2.3 l S Q R $ Temp. - Hgh Suppression Pool Area AT - l T
[ f. Mgh S O R 1. 2. 3 G g. Suppress.on Ps 4,.. Temp. R 1. 2. 3 NA SA
'g Timer Relays Ernergency Area Cooier Temp. -
I h. R 1, 2. 3 S O N Man Drywe8 Pressure - Kgh S O R 1.2.3 L R NA T. 2. 3
- j. Loge Power Morutor NA N
W 7 O
/
W N W t W SD
I TABLE 4.3 2 7 fCemet
.P
-4 O ISOLATION ACTU ATIO?J t*JSTRtr% TNT AT20+J SU4vtrLLae4CE PEQU!cEtfENTS
=
OPER A TIO?d A L t CHANNEL CHAMP?EL CO?JO4TIO*JS 1** wutCH C CHANNEL FUNCTIONAL SURVETLLaNCE mEc'.paEO l :;r TEST C AUBF A7 TON TRIP FUNCTtON CNECK I
- 5. FE ACTOR CORE ISOLAT'Of4 COOUtJG SYSTEM ISOLAT10tJ O R 1. 2. 3 RCIC Steam line FlowMgh S
- a. R T . 2. 3 S Q
- b. RCIC Steam Sugg.fy Pressure-toa O R 1. 2. 3 l RC'c Turtwr:* Enhws1 S c.
Dighteyn Presuse-Ng5 R 1. 2. 3 { S C
- d. Em;;*ncy Area Cootet l Tm. rerature - Rgh R 1. 2. 3 l l
~S O
- e. Supp-esven Poc4 Area Af-duent Terrverature-Hegb R 1. 2. 3 l S C
- f. Stwessort Pool Area AT-K ph
- g. Surfres5*on Pool Area R 1. 2. 3 NA SA
- W Temp. Terne, Relays R 1. 2. 3 l
% $ Q a h. CryweU Pressure - Hg5 fiA 1. 2. 3 NA R g i Logic Power Morvtor N
w G. SHUTDOWTJ COOLftJG SYSTEM iSOL ATicN I, G R 3.4.5 Reactue Vesset Water Level- S y a.
+- Low (Level 3) s 1. 2. 3 l
- E S C R
- b. Reactor Steam Dome 3e Pressure - Hg5 o
O 3' w 7 w W I a W N W N W O
/
Cat N (48 0 (a) to
1!1ST RUMENTAT10N 3/4.3.3 EMERGE!4CY CORE C00Lil10 SYSTEM ACTUATION INSTRUM!11MIEi tIMITING CONDITION FOR OPERATION 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2 and with EMERGEllCY CORE COOLING SYSTEM RESPONSE TIME as shown in Table 3.3.3-3. AR11CABillTY: As shown in Table 3.3.3-1. ACTION:
- a. With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable and place the inoperable channel in the tripped condition until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
- b. With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place the inoperable channel in the triaped condition or declare the associated ECCS inoperable within 12 1ours. l
- c. With the requirements for the minimum number of OPERABLE channelt not satisfied for both trip systems, declare the associated ECCS inoperable within one hour,
- d. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
- e. The provisions of Specification 3.0.3 are not applicabic in l OPERATIONAL CONDITION S.
51!!LVfdLLANCE REOUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CAllBRATION operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3-1, 4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary fcr proper functioning of the trip system. HATCH - UNIT 2 3/4 3-24 k:\wp\techsp\h\3_432323. Pro
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44 4 4 4,4 4 4 - T S C I 33 33 3 3 3 3233 ANN 22
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E L N t TE AOT O Q O QQ NR 3 B O HN m x A T CJFt t T A a U ic _ T d C e A e _ _ p . M S .- E M E r e _ T p S T Y - S E _ S L ' Y L E S 8 -_ G 4 K f t A M NC SS A 4 S S S AA R _ f L A E SN 5 R SS NM E P - O HH # O O CC C er C _ E E a . R C s . O O C M m e . w t s . Y N o y C O L ve s l b . N I T e u E e rR ._ G - C s . E t e uy y R E le v7 J N le v v e se st e r M e 1 eI L l ee p L % hL PrD s E r e leg e r T N ge eud' l e . e r e t a e vRmo o A Ntev a lhee o m . imoa t e - t c L - o . T v
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3/4.3.4 REACTOR CORE IS.01AT10N CDQLl@,. SYSTEM ACTUATION lNSTRUMENTATION LJ11]11NG CONDITION TOR OPERATION 3.3.4 Thereactorcoreisolationcooling(RCIC)systemactuationinstru-mentation shown in Table 3.3.4-1 shall be OPERABLE with their trip set-points set consistent with the values shown in the Trip Setpoint column of Table 3.3.4-2. EptICABillTY: CONDITIONS 1, 2 and 3 with reactor steam domo pressure
> 150 psig.
Ell @
- a. With a RCIC system actuation instrumentation channel trip set-point less conservative than the value shown in the Allowable Values column of Table 3.3.4-2, declare the channel inoperable and place the inoperable channel in the tripped condition until 1 the channel is restored to OPERABLE status with its trip Set-point adjusted consistent with the Trip Sotpoint value. 1 b, With the requirements for the minimum number of OPERABLE -
channels not satisfied for one trip system, place the in- ; operable channel in the trip)ed condition or declare the RCIC system inoperable within 12 Tours.. _._- L ;
- e. With the requirements for the minimum number of OPERABLE i
- hannels not satisfied for both trip systems, declare the RCIC system inopera'ble within one hour,
- d. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS..
SVRVEILLANCE REQUIREtlENTS _ 4.3.4.1 fach RCIC system actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL C;1ECK, CHANNEL.
-FUNCTIONAL TEST and CHANNEL CAllBRATION at the frequencies shown in Table 4.3.4-1.
4.3.4.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system. HATCH - UNIT 2 - 3/4 3-33 k:\wp\techsp\h\3,_432323. Pro
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i I INSTRUMENTATION 3/4.3.5 CONTROL ROD W11HDRAWAl BLOCK INSTRUMENTATION f LJjilIB$_(DliDLUON FOR OPERATION 3.3.5 The control rod withdrawal block instrumentation shown in Table 3.3.5-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.5-2. APPLICABillTY? As shown in Table 3.3.5-1. ACTION:
- a. With a control rod withdrawal block instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.5-2, declare the channel ino)erable until the channel is restored to OPERABLE status wit 1 its trip setpoint adjusted consistent with the Trip :
Setpoint value.
- b. With the requirements for the minimum number of OPERABLE channels not satisfied for any trip function, place that trip function in the tripped condition within one hour.
- c. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other .
applicable ACTIONS. '
- d. The provisions of Specification 3.0.3 are not applicabic _- -_ , .l .
in OPERATIONAL CONDITION 5. - SVRVEllLANCE RE0VIREMENTS 4.3.5 Each of the above required control rod withdrawal block instrumen-tation channels shall be demonstrated OPERABLE by the performance of the' CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION oaerations during the OPERATIONAL CONDITIONS and at the frequencies slown in Table 4.3.5-1. 1 L HATCH - UNIT 2 3/4 3-37 k:\wp\techsp\h\3_432323. Pro
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$ . CONTRot. ROD W1THDR AWAL BLOCK INSTRUMENT ATION
' MINtMUM NUMBER OF APPLICABLE 2- OFERABLE CH ANNELS OPERATIONAL
~[-
. TR!P PJNCTION : PER TRIP (UNCTION CONDITIONS '
- 1. APRM 12C51-K505 A. B, C. D, El F)
. . . i l ac Flow Referenced Shnulated Thermal 4 1
- Power- Upscale .
- b. Inoperative 4 1. 2. S - 1
- c. Do wnscale , .
4 1
' d. Neutron Flux - High.12% 4 2. 5 .
I
-2. ROD BLOCK MONITOR (2C51-K605 RBM A And B) [
- a. Upscale 1 8
1 *1
.. b . Ineperative 1 18 *'
- c. Dawnseale 1- .1 8*3
- W . 3. SOLCCE R ANGE MONITORS (2C51-K600 A, B, C, D) '
A ~ r w a. Detector not fullinM -3 2 2 5
$' b. ' Upscate ICI
.3 2 2 5 ,
y c. InaperativeM 3 2 .[
.* 2 5 :
T d. DownsceleN 3 2 D, 2 5 c+ 7 4.- INTERMEO! ATE RANGE MONITORSM 'j (2C51-K601 A. B. C, D E, F, G, H) ' n
'y a. Detector foot fullin I*I 6 2. S
'g b. Upscale 6 2. S 3
I c. Inoperative 6 2, S w" d. DownsceleI *I 6 2 N W N 5. SCR AM O!SCHARGE VOLUME (2C11-N013E) ' W
- e. Water Level-Kgh 148 1,2.S M l-O p ..
W N W
.i S
i y , ..J-- ,- . _ ~ . , , ...v . , ,. . ..
TABLE 3.3.5-1 (Continued) CONTROL ROD WITHDRAWAL BLOCK INSTRVHENTATION
- ILQlf,
- a. When the limiting condition defined in section 3.1.4.3 exists,
- b. This function is bypassed if detector is reading > 100 cps or the IRM channels are on range 3 or higher.
- c. This function is bypassed when the associated IRM channels are on range 8 or hicher.
- d. A total of 61RM instruments must be OPERABLE.
- e. This function is bypassed when the IRM chunnals are on range 1.
- f. With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.11.1 or 3.9.11.2.
9, Witiidr6wal of control rods is not permitted during required surveillance testing. HATCH - UNIT 2 3/4 3-39 techsp\h\3 432323. Pro \323-106
r r TABLE 4.3.5-1
. . --4
? CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLAMCE REQUtREMENTS '
CHANikEL OPERATIONAL E' CHANNEL ~ FUNCTIONAL - CHANNEL CONDITIONS IN WHICH
~
TRfP FUNCTION CHECK ' TEST CAllBRAT10NI *l SURVEILLANCE REQtAMED '.
'1' . APRM:
- a. Flow Referenced Swnulated Thermal Power-Upscale NA- - SNM,Q . R 1
- b. Inoperative ' NA. . S!UM,0 -- NA 1,2,5
- c. Downscale NA ' S/UM.O 'R 1 !
- d. Neutron Flum - High,12% ,NA ' S/UM,0 R 2, 5
- 2. Rod Block Morwtor:
- s. Upsca!e NA 5/UM, O R :1M
- b. Inoperative NA S/UM,O NA '1M
- c. Downscale NA S/UM, O R. 18 i W 3. Source Range Morntors: l An y a. Detector not futt in NA $/UM.W NA . 2, 5 4
8-
- b. Upscale NA SfUM.W R 2. 5 ,!
NA
- c. Inoperative 'NA S/UM.W 2, 5
- c. Downseale 'NA S/UM,W R 2, 5 .
.T . / 4. . Intermediate Rare Monitors: .
9
- E V i
%- a. ' Detector not fuit in NA S/UM.WM NA 2, 5 to b Upscale NA' S/UM.WM' R 2, 5 0
- 7 c. Inoperative NA S/UMWM NA 2, 5 y d. Downscale NA S/UM,WM R 2, 5 ;
/
3W S. - Scram Descharge Volume: , 1,2 S M l , Jb e. Water Level 44igh ' NA O R sa N W
'N W
"5
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/
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INSTRUMENTATION 3/4.3.6 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LlHITING CONDITION FOR OPERATION 3.3.6.1 The radiation monitoring instrumentation channels shown in Table 3.3.6.1-1 shall be OPERABLE with their alarm / trip setpoints within the-specified limits. APPLICABILITY: As shown - in Table 3.3.6.1-1. ACTION:
- a. With a radiation monitoring instrumentation channel alarm / trip-setpoint exceeding the value shown in Table 3.3.6.1-1, adjust the setpoint to within the limit within-4 hours or declare the channel inoperable.
- b. With one or more of the above required radiation monitoring instrumentation channels inoperable, take the ACTION required by Table 3.3.6.1-1. '
- c. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
- d. The provisions of Specifications 3.0.3 and 3.0.4 are not - l applicable.
SyRVEILLANCE RE0VIREMENTS 4.3.6.1 Each of the above required radiation monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.6.1-1. HATCH - UNIT 2 3/4 3-43 k:\wp\techps\h\3_432323. Pro
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.2 The seismic monitoring instrumentation shown in Table 3.3.6.2-1 shall be OPERABLE. APPLICABILITY: At all times. ACTION:
- a. With one or more of the above required seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission within the next 10 days outlining the cause of the malfunction and the plans for restoring-the instrument (s) to OPERABLE status.
- b. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not !
applicable. SURVEILLANCE REQUIREMENTS 4.3.6.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the fre-quencies shown in Table 4.3.6.2-1. 4.3.6.2.2 Each of the above required seismic monitoring instruments actuated _during a seismic event shall be restored to OPERABLE status within 24 hours and a CHANNEL CALIBRATION performed within 30 days following'the seismic _ event. Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specificatinn 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety. HATCH - UNIT 2 3/4 3-47 techsp\h\3_432323. Pro \323-86
INSTRL1 MENTATION EfMOTE SHUTDOWN MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.3 The remote shutdown monitoring instrumentation channels shown in Table 3.3.6.3-1 shall be OPERABLE with readouts displayed external to the control room. APPllCABILITY: CONDITIONS 1, 2 and 3. ACTION:
- a. With one or more of the above required remote shutdown monitoring instrumentation channels inoperable, either restore the inoperable channel (s) to OPERABLE status within 30 days or be in at least HOT ,
SHb!DOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
~
- b. One instrument channel may be inoperable for up to 6 hours ~~ to perform required surveillances prior to entering other applicable ACTIONS.
~
- c. The provisions of Specification 3.0.4 are not applicable. l 1
SURVEIL (ANCE REQUIREMENTS 4.3.6.3 Each of the above required remote shutdown monitoring instrumen-tation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.6.3-1. HATCH - UNIT 2 3/4 3-50 k:\wp\techsp\h\3_432323. Pro
.lNSTRUMENTATION POST-ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.4 The post-accident monitoring instrumentation channels shown in Table 3.3.6.4-1 shall be OPERABLE.
APPL!CABillTY: CONDITIONS 1, 2, and 3*. ACTLON:
- a. With one or more of the.above required post-accident monitoring channels inoperable, either restore the inoperable channel (s) to OPERABLE status within 30 days or be in at least H0T SHVTDOWN within the next 12 hours,
- b. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
- c. The provisions of Specification 3.0.4 are not applicable. l SURVEllLANCE REQUIREMENTS l
{ l
'4.3.6.4 Each of the above required post-accident monitoring instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL-CAllBRATION operations at the frequencies - shown in Table 4.3.6.4-1.
i
- Condition 3 is. applicable only to Items 12, 13, and 14 of Table 3.3.6.4-1.
HATCH - UNIT 2 3/4 3-53 techsp\h\3_432323. Pro \323-45
TABLE 3.3.6 4-1 ['t>
--4 h PO3~.-AC(PENT MONTTORING INSTRUMEf4TATIOfJ e
MitJiMUM E CH AtJtJ%"2
-4 OPERAiQ INSTRUMENT ro 2
- 1. Reactor Vessel Pressure (2B21-RS23 A. B) 2 l 2 Reactor Vessel Shroud Water Level (2B21-R610, 2821 R615l 2
- 3. Suppession Chamber Water Level (2T48 RS22 A, El 2
- 4. Suppresuon Chamber Water Temperature (2T47-R626, 2T47-R6271 2
- 5. Sug pression Chamber Pressure (2T48 R609,2748 R609) 2
- 6. Drywell Pressure (2T48-R6C9, 2T48-REO3) 2
- 7. Drywell Temperatur e (2T47-R626, 2T47-R627) 2
- 8. Post LOCA Gamma Radiation (2011-8(622 A, E C. D) w 2*
g 9. Drywe!! H2 42 Analyzer (2P33-R601 A, B) tal [ 10.a) Saf ety! Relief Valve Positiori Prwnery Indicator (2821-tJ301 A-H and K-M) us (a) b) Safety / Relief Valve Position Secoexiary indicator (2821 NOO4 A-H and K-M) 2
- 11. Drywc!I High Range Pressure (2T48-R601 A,8) 2(bl
- 12. Drywell High Range Radiation (2D11-K621 A. 8, 2T48-R601 A, B) g
} 1 tb)(c)
- 13. Main Stack Post Accident Efftuent Morwtor (D11-R6311 f
N to 14. Reactor Building Vent Plenum Post-Accident Effluent Morstor (2D11-R631) 1 (b)(ci n
- r E
s h w 1, *The Drywell H 20, Analyzeu shall be operable with continuous sampling capabi!.ty wittsn 30 minutes W of an ECCS actuation during a LOCA.
~
w O 'w a,
~
IBjTRUMENTATION SOURCE RANGE M0filTORS LIMITING CONDIT10tl FOR OPERATION 3.3.6.5 Three source range monitors shall be OPERABLE. eP?llCABillTY: CONDITIONS 2*, 3 and 4. ACTIOil:
- a. in CONDIT10tl 2* with one of the above required source range monitors inoperable, restore 3 source range monitors to OPERABLE status __
within 4 hours or be in at least HOT SHUTDOWN within the next 6 hours, b, in CONDITION 3 or 4, with two or more of the above required source range monitors inoperable, verify all control rods to be fully inserted in the core and lock the reactor mode switch in the Shutdown position within one hour,
- c. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
SURVEllLANCE RE0VIREMENTS 4.3.6.5 Each of the above required source range monitors shall be demon-strated OPERABLE by:
- a. Performance of a:
- l. CHANNEL CHECK at least once per:
(a) 12 hours in CONDITION 2*, and (b) 24 hours in CONDI110N 3 or 4.
- 2. CHANNEL CAllBRATION** at least once per 18 months,
- b. Perf'rmance o of a CHANNEL FUNCTIONAL TEST:
- 1. Within 24 hours prior to moving the reactor mode switch from the Shutdown position if not performed within the previous 7 days, and
- 2. At least once per 31 days.
*With IRMs on range 2 or below.
**May exclude neutron detectors.
HATCH-UNIT 2 3/4 3-56 k:\wp\techsp\h\3_432323. Pro
. . . _ . . . - .- . - - . - . . . . - . . . . . = . . , - , ~ - . - , . -.-
t INSTRUMENTATION-r
.l.IMITING-CONDITION FOR OPERATION (Continued)
- c. .Nerifying, prior to withdrawal. of control rods, that the SRM count
. rate-is at least 3 cps with the detector fully inserted.
\ 4 f i-i l l l> [:
-HATCH-UNIT'2 3/4 3-56a k:\wp\techsp\h\3_432323. Pro-
__ u._ _ :.
INSTRUMENTATION '
-MAIN CONTROL-ROOM ENVIRONMENTAL CONTROL SYSTEM (MCRECS) ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION __
3.3.6.7 The MCRECS actuation instrumentation channels shown in Table ,
- 3.3.6.7-1 shall be OPERABLE, with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6.7-2.
APPLICABILITY: As shown in Table 3.3.6.7-1. ACTION:
; a. As shown in Table 3.3.6.7-1, l
- b. One-instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
o SURVEILLANCE RE0VIREMENTS IL 4.3.6.7 Each MCRECS actuati6n channel shall be demonstrated OPERABLE'by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CAllBRATION operations during the OPERATIONAL CONDITION and at the frequencies shown in Table 4.3.6.7-1. lI l' HATCH - UNIT 2 3/4 3-58 techsp\h\3_432323. Pro \323-71
TABLE 3.3.6.7-1 (SHEET 2 0F 2) MCRECS ACTUATION INSTRUMENTATION ACTION ACTION 52 - Take the ACTION required by Specification 3.3.3. ACTION 53 - Take the ACTION required by Specification 3.3.2. ACTION 54 -
- a. With one of the required radiation monitors inoperable, restore the monitor to OPERABLE status within 7 days or, within the next 6 hours, initiate and maintain operation of the MCRECS in the pressurization mode'of operation,
- b. With no radiation monitors OPERABLE, within 1 hour initiate and maintain operation of the MCRECS in the pressurization mode of operation.
- c. The provisions of Specification 3.0.4 are not applicable.
tLQLF1
- When handling irradiated fuel in secondary containment.
- a. (Deleted) l
- b. With a design providing'only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 12 hours or the l ACTION required by Table 3.3.6.7-1 for that Trip Function shall be taken.
- c. Actuates the MCRECS in the control room pressurization mode.
- d. (Deleted)
- e. Within 24 hours prior to the planned start of the hydrogen injection test with the reactor power at greater than 20-percent rated power, the normal full-power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the fest. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours of re-establishing-normal radiation levels af ter completion of hydrogen injection and prior to establishing reactor power levels below 20-percent rated power.
HATCH - UNIT 2 3/4 3-58b techsp\h\3 432323. Pro'323-96
X
^
i ^ g TABLE 4.3.6.7+1 , --e . O ' MCRECS ACTLfATION INSTRUMENTATION SURVEfLL ANCE REQUIREMENTS 8 , . CHANNEL OPERATIONAL c CHANNEL - FUNCTIONAL CHANNEL CONDITIONS IN WHtCH 3
-4
, TR!P FUNCTION CHECK TEST - C AUBR ATION ' SURVEILLANCE REQUtRED l i
.y 1. Reactor Vessel Water Level- S O R' 1, 2. 3 - l ..
, Low Low Low (Level 1) 2.' Crywell Pressure - High S Q R 1,2,3 l
- - 3. Main Steam Une Radiation - H+gh ~S V/ *' 'R 1.2,3 -l' 4 Min Steam Une Flow -High -S Q R. 1.2,3 l S. Refueling floor Area Radiation - S O - Q 1.2.3,5 *' l High 6 Control Room Asr Irdet NA O'**
R 1, 2, 3, 5.'
- f Radiation - High w
- N i A w
a m i' CD CL W
/
- C 4
m
/
4 @ m Q
- When hanchng irradiated fuelin the secondary sontainment.
- a. Instrument ahanment using a standard current source.
- 3- '!
W I A M N W N 2 .M
-1 O /
W
- N W
i e .- O
INSTRUMJNTATION RADI0 ACTIVE L10VID EFFlVENT INSTRUMENTATION llMITING CONDITION FOR OPERATION . 3.3.6.9 The radioactive liquid effluent monitoring instrumentation channels shown in table 3.3.6.9-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (0DCM). APPllCABILITY As shown in table 3.3.6.9-1.- ACTION
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less /
conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, declare the channel inoperable, or change to a conservative value,
- b. With the number of channels OPERABLE less than the minimum channels required by table 3.3.6.9-1, take the ACTION shown in table 3.3.6.9-1.
- c. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
- d. The provisions of Specifications 3.0.3, 3.0.4, and l 6.9.1.13(b) are not applicable. _
SURVEILLANCE REQUIREMENTS 4.3.6.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in table 4.3.6.9-1. I HATCH - UNIT 2 3/4 3-60a techsp\h\3_432323. Pro \323-48 i
INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT INSTB9MENTAT10N LIMITING CONDITION FOR OPERATION 3.3.6.10 The radioactive gaseous effluent monitoring instrumentation channels shown in table 3.3.6.10-1 shall be CPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.ll.2.l(a) are not exceeded. The alarm / trip setpoints of these channels shall be determined in ac,ridance with the ODCM. ApPLICAClllli As shown in table 3.3.6.10-1; ACTION
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value that will ensure that the limits of 3.ll.2.l(a) are met, without delay restore the setpoint to a value that will ensure that the limits of Specification 3.ll.2.1(a) are met or declare the channel inoperable,
- b. With the number of channels OPERABLE less than the minimum channels required by table 3.3.6.10-1, take the ACTION shown in table 3.3.5.10-1,
- c. One instrument channel may be inoperable for up to'6 hours to perform required surveillances prior to entering other applicable ACTIONS.
- d. The provisions of Specifications 3.0.3, 3.0.4, and l 6.9.1.13(b) are not applicable.
SVRVEILLANCE RE0VIREMENTS i 4.3.6.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in table 4.3.6.10-1. I HATCH - UNIT 2 3/4 3-60f techsp\h\3_432323. Pro \323-48 l
INSTRUMENTATIQN 3/4.3.8 DEQftADED STATION V0LTAGE PROTECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.8 The de raded station voltage relay channels shown in Table 3.3.8-1 shall be OPER BLE. APPLICABillTY: CONDITIONS 1, 2, and 3. ACTION:
- a. With the number of OPERABLE channels one less than the required OPEPABLE l channels, operation may proceed until performance of the next scheduled instrument functional test-provided a trip signal is placed in the LOSP lock-out relay logic for the applicable inoperable channel,
- b. One-instrument channel may be inoperable for up to 6 hours to perform required surveillances prior-to entering other applicable ACTIONS.
EURVE!LLANCE DE0VIREMENTS _ 4.3.8 Each of the above required degraded station voltage relay channels shall be demonstrated OPERABLE by performance of the CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operation at the frequencies shown in Table 4.3.8-1. HATCH-UNIT 2 3/4 3-63 techsp\h\3_432323. Pro \323-27
INSTRUMENTATION 3/4,3.9 RECIRCVLATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITING CONDIT10' FOR OPERATION 3.3.9.1 The anticipated transient without scram recirculation pump trip (ATWS-RPT system instrumentation channels shown in Table 3.3.9.1-1 shall be OPERABLE w)ith their trip setpoints set consistent with values shown in the Trip Setpoint column of Table 3.3.9.1-2. APPL 1CABILITY: OPERAT10NAL CONDITION 1. ACTION:
- a. With an ATWS recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.9.1-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel trip setpoint adjusted consistent with the Trip Setpoint value,
- b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel in the tripped condition within 12 hours. l
- c. With the number of OPERABLE channels two less than reciuired by the Minimum OPERABLE Channels per Trip System requirement for one trip system and,
- 1. If the inoperable channels consist of one reactor vessel water level channel and one reactor vessel pressure channelinoperablechannelsinthe lours.1
- 2. If the inoperable channels include two reactor vessel water level channels or two reactor vessel pressure channels, declare the '
trip system inoperable.
- d. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 14 days or be in at least STARTUP within the next 6 hours.
- c. With both trip systems inoperable, restore at least one trip system to OPERABLE status within I hour or be in at least STARTUP within the next 6 hours.
~
- f. One instrument channel may be inoperable for up to 6 hours to perform i required surveillances prior to entering other applicable ACTIONS.
HATCH - UNIT 2 3/4 3-66 techsp\h\3 432323. Pro \323-110
SURVEILLANCE RE0!jjREMENTS ~
-4.3-.9.1.1 Each ATWS recirculation ) ump- trip system instrumentation channel shall- be demonstrated OPERABLE by tie performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL. TEST shown in: Table 4.3.9.1-l.and CHANNEL CALIBRATION operations at the frequencies .
9 4.3.9.1.2 LOGIC SYSTEM FUNCTIONAL-TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
-. HATCH - UNIT 2- 3/4 3-66a techsp\h\3_432323. Pro \323-110 l
l!iSTRUMENTATION END-0F-CYCLL81CIRCULA110N PUMP TRIP SYSTEM INSTRUMEt1TATION LIMITING CONDITION FOR OPERATION 3.3.9.2 The end-of-cycle recirculation pump trip (E0C-RPT) system instrumentation channels shown in Table 3.3.9.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.9.2-2 and with the END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.9.2-3. APPLICABillTY: OPERATIONAL CONDITION 1, when THERMAL POWER is 9reater than or equal to 30% of RATED THERMAL POWER. ACTION:
- a. With an end-of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable values column of Table 3.3.9.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value,
- b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition within 12 hours. l
- c. With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:
- 1. If the inoperable channels consist of one turbine control valve channel and one turbine stop valve channel place both inoperable channelsinthetrippedconditionwithinIkhours. l
- 2. If the inoperable channels include two turbine control valve channels or two turbine stop valve channels, declare the trip system inoperable.
- d. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours or reduce THEMAL POWER to less than 30% of RATED THERMAL POWER within the next 6 hours,
- e. With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or reduce THERMAL POWER to less than 30% of RATED THERMAL POWER within the next 6 hours,
- f. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
HATCH - UNIT 2 3/4 3-70 techsp\h\3_432323. Pro \323-69
TABLE 3.3 9.21 h H O EfiO OF-CYCLE RECTRCULATIOfJ PUMP TfitP SYSTEM 1NGTRUMEFJTATION I i MiNtMUM C OPERABLE CHANNELS PER TPl? SYSTEM N TRIP FUNCTtON N 2
- 1. Turbine Stop Valve - Closure 2"
2 Turbine Controf VAe Fast Closure 6 w N 4 w e w N X.
/
t v \
/
l r+ CD n r en t
/ =r /
w I I*IDe!ef ed. w y
"This function shall be automatically bypassed when turbine first stage pressure is less than or equal to 250 psi 0, equivalent to THERMAL POWER y tess than 30% cf RATED THERMAL POWER.
o
/
w N w t G C
y TABLE 4.3.9.2.1-1
--4 Q END-OF-CYCLE REClRCUL ATION PUMP TRIP SYSTEM SURVEttt ANCE REQUIREMENTS c CHANNEL H
3 ' TRIP FUNCT!ON FUNCTIONAL TEST CHANNEL CAllBRATION N
- 1. Turbine Stop Valve . Closure Q'- R' l
- 2. Turbine Control Valve - Fast Closure Q* R l w
N w I N L11 W s t t
/
c+ O > r1 ' 7 m t
/
7
/
W l 4 w N *The Recirculation Pump Breakers need not be tripped on part of the Channel Functional Test. All channel alarm functions and only that portion of the W trip functions which can be tested without causing a trip of the Breakers tend Recirculation Pumps) need be tested during the Channel Functional Test.
~1 O /
W N W , e f m to
f1AC103 COOLANT SYSTEM 3/4.4.2 SAFETY /REllEf VALV[j LIMITING CONDITION FOR OPERAT10N 3.4.2.1 The safety valvo function of the following reactor coolant system safety / relief valves shall be OPERABLE with the mechanical lift settings within + 1% of the indicated pressures *, 4 !iafety-relief valves @ 1090 psig. 4 Safety-relief valves @ 1100 psig**. 3 Safety-relief valves @ 1110 psig**, APPllCABillTY: CONDITIONS 1, 2 and 3. AC110N:
- a. For low-low set valves, take the action required by Specification 3.4.2.2. For ADS valves, take the action required by Specification 3.5.2.
- b. With one or more safety / relief valves stuck open, place the reactor mode switch in the Shutdown position,
- c. With one or more S/,RV tailpipe pressure switches of an S/RV deciared inoperable and the associated S/RV place the reactor mode switch in th(s) otherwiseposition, e shutdown indicated to be open,
- d. With one S/RV tailpipe pressure switch of an S/RV declared inoperable and the associated S/RV(s) otherwise indicated to t'e closed, plant operation may continue. Remove the function of that pressure switch from the low low set logic circuitry until the next COLD SHUTDOWN.
Upon COLD SHUT 00WN, restore the pressure switch (s) to OPERABLE status before STARTUP.
- e. With both S/RV tailpipe pressure switches of an S/RV declared inop-erable and the associated S/RV(s) otherwise indicated to be closed, restore at least one inoperable switch to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
- f. The failure or malfunction of any saf ety/ relief valve shall be reported b mailgram, y telephone within 24 hours; confirmed by telegraph,or facsimile transmission to th Office, or his designee no later than the first working day following the event; and a written followup report within 30 days, lhe written followup report should be completed in accordance with 10 CFR 50.73 or other applicable requirements,
- g. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
SURVEILLANCE RE0VlREMENTS 4.4.2.1 The tail-pipe pressure switches of each safety / relief valve shall be demonstrated OPERABLE by performance of: l
- a. CHANNEL FUNCTIONAL TEST:
- 1. At least ente per quarter, except that all portions of the l channel inside the primary containment may be excluded from the CHANNEL FUNCTIONAL TEST, and
- 2. At each scheduled outage of greater than 72 hours during which entry is made into the primary containment, if not performed within the previous quarter. l
- b. CHANNEL CALIBRATION and verifying the setpoint to be 85 psig, with an allowable tolerance of +15 psig and -5 psig, at least once per 18 months.
- The lif t setting pressure shall correspond to ambient conditions of the valves at nominal operating temperature and pressure. >
** Up to two inoperable valves may ha replaced with spare OPERABLE valves with lower setpoints of 1090 and 110v gig, respectively, until the next refueling outage.
HATCH - UNIT 2 3/4 4-4 techsp\h\3 442323. Pro \323-86
Rff1CTOR COOLANT SYSTEM SAFETY /REllEF VALVES LOW-l0W SET FUNCTION LIMITING CONDITION FOR OPERATION e 3.4.2.2 ifs r elief valve function and the low-low set function of the following reactor esolant system safety / relief valves shall be OPERABLE with the following
'l ow- i ur set function lift settings:
Low Low Set Allowable Value (osial* Valve Function Qngn C1050 Low 1 1010 $ 860 Medium Low s 1025 s 875 Medium High s 1040 $ 890 High 5 1050 s 900 APPL IC ABILITY: OPERATIONAL CONDITIONS 1, 2 and 3 ACTION:
- a. With the relief valve function and/or the low-low set function of one of the above required reactor coolant system safety / relief valves inoperable, restore the inoperable relief valve function and low-low set function to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTOOWN within the following 24 hours.
- b. With the relief valve function and/or the low-low set function of more than one of the above required reactor coolant system safety / relief valves inoperable, be in at least H0T SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours,
- c. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
SURVEILLANCE REOUIREMENTS 4.4.2.2 The low-low set relief valve function and the low-low set function pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:
- a. CHANNEL FUNCTIONAL TEST, including calibration of the trip unit and the dedicated high steam dome pressure channels **, at least once per quarter. l
- b. CHANNEL CAllBRATION, LOGIC SYSTEM FUNCTIONAL TEST and simulated automatic operation of the entire system at least once per refueling outage.
*The lift setting pressure of the valves is defined in subsection 3/4 3.4.2.1.
The accuracy of the low-low set setpoints is defined to be the accuracy of the instrumentation controlling the setpoints of the low-low set valves.
**The setpoint for dedicated high steam dome pressure channels is less than or equal to 1054 psig. ,
HATCH - UNIT 2 3/4 4-4a techsp\h\3_442323. Pro \323-33
REACTOR COOLA.NT SYSTEM 3/4.4.3' REACTOR COOLANT SYSTEM LEAKAGE LLAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:
- a. The primary containment atmosphere particulate radioactivity monitoring system,
- b. The primary containment floor-drain and equipment sump level and flow monitoring systems, and
- c. The primary containment gaseous radioactivity monitoring system.
APPLICABILITY: CONDITIONS 1, 2 and 3. ACT10ti:
- a. With either the primary containment atmosphere particulate radioactivity monitoring system or the primary containment gaseous radioactivity monitoring system inoperable, operation may continue for 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 8 hours;
- b. With at least one leakage monitoring instrument OPERABLE for both the primary containment floor drain sump and the equipment sump, operation may continue for 30 days;
- c. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours,
- d. ._0ne instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
SURVEILLANCE RE0VIREMENTS 4.4.3.1 The leakage detection systems shall be demonstrated OPERABLE by:
- a. Primary containment atmosphere gaseous and particulate monitor-ing system-performance of a CHANNEL CHECK at least once per 8 hours, a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
- b. Primary containment sump level and flow monitoring system-performance of a sensor check at least once per 8 hours, CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.
HATCH - UNIT 2 3/4 4-5 techsp\h\3_442323. Pro \323-ll7
EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 LQW PRESSURE CORE COOLING SYSTEMS LQRE SPRAY SYSTEM WILTING CONDITION FOR OPERATION 3.5.3.1 Two independent Core Spray System (CSS) subsystems shall be OPERABLE with each subsystem comprised of:
- a. One OPERABLE CSS pump, and
- b. An OPERABLE flow path capable of taking suction from at least one of the following OPERABLE sources and transferring the water through the spray sparger to the reactor vessel;
- 1. In CONDITION 1, 2 or 3, from the suppression pool.
- 2. In CONDITION 4 or 5*;
a) From the suppression pool, or b) When the suppression pool is being drained, from the condensate storage tank containing at least 150,000 gallons of water. AEPLICAB[Lill: CONDITIONS 1, 2, 3, 4, and 5*. ACTION
- a. In CONDITION 1, 2 or 3;
- 1. With ont CSS subsystem inoperable, POWER OPERATION may continue provided both LPCI subsystems are OPERABLE; restore the inoperable CSS subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
- 2. With both CSS subsystems inoperable, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours.
- 3. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
- The co.c spray system and the suppression chamber are not required to be OPERABLE provided that the reactor vessel head is removed and the cavity is flooded, the spent fuel pool gates are removed, and the water level is maintained within the limits of Specification 3.9.9 and 3.9.10.
HATCH - UNIT 2 3/4 5-4 techsp\h\3_452324. Pro \324-86
[dfRGENCY CORE C09 LING SYSTEMS LJMITING CONDITION FOR OPERATION (Continued) ACTION: (Continued)
- c. With one suppression chamber water level instrumentation channel inoperable, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours and verify the suppressien chamber water level to be 112'2" at least once per 12 hours,
- d. With both suppression chamber water level instrumentation channels inoperable, restore at least one inoperable channel .
to OPERABLE status within 6 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTOOWN within the followina 24 hours and verify the suppression chamber water level to be 2 12'2" at least once per hour.
- e. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
EURVEILLANCE RE0VIREMEN"S 4.5.4.1 The suppression chamber shall be determined OPERABLE by verifying:
- a. The water level to be 112'2" at least once per 24 hours.
- b. Two suppression chamber water level intirumentation channels (2T48-R607A,B) OPERABLE by performance of a:
- 1. CHANNEL CHECK at least once per 24 hours,
- 2. CHANNEL FUNCTIONAL TEST at least once per 31 days, and
- 3. CHANNEL CALIBRATION at least once per 6 months.
4.5.4.2 The conditions of Specification 3.5.4.b.2 shall be verified to be satisfied prior to draining the suppression pool and at least once per 12 hours thereafter while the suppression pool is drained. HATCH - UNIT 2 3/4 5-10 techsp\h\3_452324. Pro \324-6
CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) ACT10Ni (Continued)
- d. In OPERATIONAL CONDITION 1 or 2 with THERMAL POWER > 1 percent of RATED THERMAL POWER and the average suppression chamber water temperature > 110'F, place the reactor mode switch in the Shutdown position,
- e. With the average suppression chamber water temperature > 120af and the main steam isolation valves closed following a scram from OPERATIONAL CONDITION 1 or 2, depressurize the reactor pressure vessel to < 200 psig at normal cooldown rates.
- f. With one suppression chamber water level instrumentation channel ino)erable, restore the inoperable channel to OPERABLE status wit 11n 30 days or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
- g. With both suppression chamber water level instrumentation channels inoperable, restore at least one inoperable-channel to OPERABLE status within 6 hours or be in at-least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the follow-ing 24 hours.
- h. One instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS.
SVRVEILLANCE RE0VIREMENTS 4.6.2.1 The- suppression chamber shall be demonstrated OPERABLE:
- a. By verifying the suppression chamber water volume to be between 12 ft-2 in. and 12 ft-6 in. at least once per-24 hours
- b. At least once per 24. hours in OPERATIONAL CONDITION 1 or 2 by I
verifying the average
- suppression chamber water temperature to be s 100*F.
- c. - At least once per 5 minutes 'in OPERATIONAL CONDITION 1 or 2 during testing which adds heat to the suppression chamber, by verifying the average
- suppression chamber water temperature s 105 F.
- d. At least once per 60 minutes when THERMAL POWER > 1 3ercent of RATED THERMAL POWER and average
- suppression chamaer water temperature > 100 F, by verifying average
- suppression chamber water temperature < 110 F.
*The average suppression chamber water temperature shall be determined using a_ weighted average of the suppression pool temperature sensors, as described -
in BASES subsection 3/4.6.2. HATCH - UNIT 2 3/4 6-12 techsp\h\3_462324. Pro \324-ll4
REFUELING OPERATIONS 3/4.9.2' INSTRUMENTATIQH LIMITING CONDITION FOR OPERATION 3.9.2 At least 2 source range monitor * (SRM) channels shall be OPERABLE and inserted to the normal operating level:
- a. Each with continuous visual indication in the control room,
- b. At least one with an audible alarm in the control room, 'I
- c. One of the SP.M detectors located in the quadrant where CORE ALTERATIONS are being performed and the other SRM detector located in an adjacent quadrant, and ]
- d. The " shorting links" removed from the RPS circuity during CORE l
ALTERATIONS and shutdown _ margin demonstrations. APPLICABILITY: CONDITION 5. ACTION:
- a. With the requirements of the above specification not satisfied, immediately l suspend all operations involving CORE ALTERATIONS ** or positive reactivity changes and actuate the manual scram. The provisions of Specification 3.0.3 are not applicable,
- b. One' instrument channel may be inoperable for up to 6 hours to perform required surveillances prior to entering other applicable ACTIONS._ __ ,
SURVElktANCE RE0VIREMENTS 4.9.2 Eact. he above required SRM channels shall be demonstrated OPERABLE by,
- a. At ' east once per 12 hours;
- 1. Performance of a CHANNEL CHECK,
- 2. Verifying the detectors are inserted to the normal operating level,
- 3. During CORE ALTERATIONS, verifying that the detector of an OPERABLE SRM channel is located in the core quadrant where CORE ALTERATIONS are being performed and one is located in the adjacent quadrant.
*The use of special movable detectors during CORE ALTERATIONS in place of the normal SRM nuclear detectors is permissible as long as these special detectors are connected to the normal SRM circuits. **Except riovement of SRM or special movsble detectors.
HATCH - UNIT 2 3/4 9-3 techsp\h\3_492324. Pro \324
' l 3/4.3 INS 1P9MLt{T A110]J , i l MS15__._ . [ It is permissibl9 to remove a channel from service for a brief ihterval to !
';onduct required surveillance testing. Notes that dictalJ the allowable time interval are provided in each ACTION section. An instrument channel that is removed from service for required surveillance testing may be l considered inoperable for up to 6 hours in order to perform the required '
w rveillances, prior to entering other applicable ACTIONS. 3/4.3.1 RffefJn PP0TECTION SYSTEM INSTRUMENTATION The reactor protection system automatically initiates a reactor scram to: a, preserve the integrity of the fuel cladding. l
- b. Preserve the integrity of the reactor coolant system,
- c. Minimize the energy which must he cdsorbed following a loss-of- i coolant accident, and
- d. Prevent inadvertent criticality.
1his specification provides the limiting conditions for operation necessary to preserve the ability of the system to perform its intended ; function even durint periods when instrument channels may be out of service because of ..aintenance. When necessary, one channel may be made inoperable for brief intervals to conduct the required surveillance tests. ( The reactor protection system is made up of two independent trip systems. There are usually four channels to monitor each parameter with two channels in each trip system. The out)uts of the channels in a trip system are combined in a logic so that etiler channel will trip that trip system. The tripping of both trip systems will produce a reactor
- scram. The system meets the intent of IEEE-279 for nuclear power plant protection systems. The bases for the trip settings of the RPS are discossed in the bases for Specification 2.2.1.
The meaurement of response time at the specified frequencies provides assurance that the protective functions associated with each r.hannel are completed within the time-limit assumed in the accident analysis. No credit wts taken for those channels with response times indicated >$ not , applicable. Response time may be demonstratec sy any series of sequential, overlapping or total channel test measurements, provided such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either: (1) inplace, onsite or offsite test measurements, or (2) utilizing replacement sensors with certified response times. HATCH - UNIT 2 B.3/4 3-1 techsp\h\B3_432324. Pro \324 r,,,.- ,-,-e,, --,,,g,--, - , - , - ,-n~- - + - ~ , - - - w r,
Marked Up Copy of Current 15 Pages
1 . L e t TABLE OF CONTEWT5 [ Page ; 5ection *$ection , 1.0 DEFINITIONS 1. 051 5AFLTY LIMIT 5 "IIMITING 5AFLIY SYSTLM bL111NG5 1.1. FUEL CLADDING INTEGRITY 2.1. FUEL CLADDING INTEGRITY 1.1 1 A. Reactor Pressure >800 psia A. Trip Settings 1.1 )- and Core Flow >101 of Rated
.B. Core Thermal Power Limit (Reactor 1.1-1 1 l
Pressure 1 800 psia l C. Power Transient 1.1-1 D. Reactor Water Level (Hot or Cold 1.1-2 Shutdown Condition)
- 8. Reactor Water Levet Trip Settings 1.1 5 :
Which Initiate Core Standby . Cooling Systems (CSCS) ( 2.2. REACTOR COOLANT SYSTEM INTEGRITY 2.2 1 1.2. REACTOR COOLANT SYSTEM INTEGRITY SURVLILLANCE REQUIREMENT 5 LIMITING CONDITIO!Q_FOR OPERATION 3.1. REACTOR PROTECTION SYSTEM 4.1. RCACTOR PROTECTION SYSTEM 3.1 1 A.- Sources of a Trip Signal Which A. Test and Calibration Requirements. 3.1 -1 Initiate a Reactor Scras , for the RPS-
- 9. RPS Response Time B. Maximus Total Peaking Factor -3.1 2 (MTPF)
-3.2. PROTECTIVE INSTRUMENTATION 4.2.- PROTECTIVE INSTRUMENTATION 3.2 1
(- C.ScttHcrs AchtedforGw4muserdatten A. q'I ns trumenta t i on -Whi c h--I n i ti a te s - - A. (Instrianentation-Whieh-Initiates. TwhHm Ae4ucsonLAtument<dius 3.2-1 Seacter-Vessel-end-Primary- Aeactor-Vessel-end Primary-Containment-Isoletten. -Centainment-Isolatten. , B. Instrumentation Which Initiates B. Instrumentation Which Initiates 3.2 1 c.~ or Controls HPCI or Controls HPCI " k~ C.
- Instrumentation Which Initiates 3.2-1 C. Instrumentation Which Initiates .
or Controls RCIC or Controls RCIC . Instrumentation Which Initiates D. Instrumentation Which Initiates 3.2-1 L D. L. -ot' Controls ADS or Controls ADS
.i ,
u HATCH - Uh!T 1- i , Amendment No. 27
=
L :-
i LIST OF TABLES k, m.a . tan na
. 1.1 - Frequency Notations ,
1.0-11
/7 3.1 -1 Reactor Protection System (R'PS) Instrumentation 3.1 -3
\. Requirements 4 .1 -1 Reactor Protection System (PRS) Instrumentation 3.1 -7
. Functional Test, Functional Test Minimum Frequency, and Calibration Minimum Frequency
~I't.ota&n Ac4 tut &n insirtwnittHew
{
- 3. 2 -1 i n s temmen ta t ion- Whi c h -Ini t i a t e s-R ea c ter- Ve s s el-- 3.2-2 and-P rima ry-Con ta i nmen t-I s ol a ti on-3.2-2 Instrumentation Which Initiates or Controls 3.2-5 HPCI 3.2-3 Instrumentation Which Initiates or Controls 3.2-8 RCIC 3.2-4 Instrumentation Which Initiates or Controls 3.2-10 ADS ,
3.2-5 Instrumentation Which Initiates or Controls 3.2-11 tna LPCI Mode of RHR -
. 3.2-6 Instrumentation Which Initiates or Controls 3.2-14 Core Spray
- 3. 2 -7 Neutron Monitoring Instrumentation Which 3.2-15 Initiates Control Rod Blocks 3.2-8 Radiation Monitoring Systems Which Limit 3.2-18
'- Radioactivity Release 3.2-g Instrumentation Which Initiates Recirculation 3.2-20 Pump 7 rip 3.2-10 Instrumentation Which Monitors Leakage into 3.2-21
( the Drywell 3.2-11 Instrumentation Which Provides Surveillance 3.2-22 Information 3.2-12 Instrumentation Which Initiates the 3.2-23a
! Disconnection of Of fsite Power Sources 3.2-13 Instrumentation Which Initiates Energization 3.2-23b of Onsite Power
- Sources l
- ( .
HkTCH - UNIT 1 vii Amendment No. II, 88, 110 m e J
'.D;cicdic n AcriticdIC a LIST OF TABLES I,wArtuve Hrdtn dtttNeUktnde, (Continued) rec ruwe p 1< Title EgSLt 4.2-1 Check,-Functional-Test,-and Calth atton-Minimum- 3.2-24 F requenc y - f or- I n st rumenta tion - Whic h- Ini t ia te s -
Reactor Vessel-and-Primary-Containment-Isolation- ) 4.2-2 Check, Functional Tast, and Calibration Minimum 3.2-27 Frequency for Instrumentation Which Initiates or Controls HPCI 4.2-3 Check, Functional Test, and Calibration Minimum 3.2-30 Frequency for Instrumentation Which Initiates or Controls RCIC 4.2-4 Check, Functional Test, and Calibration Minimum 3.2-33 Frequency for Instrumentation Which Initiates
- or Controls ADS 4.2-5 Check, Functional Test, and Calibration Minimum 3.2-35 Frequency for Instrumentation Which Initiates or Controls the LPCI Mode of RHR 4.2-6 Check, Functional Te'st, and Calibration Minimum 3.2-30 Frequency for Instrumentation Which Initiates
. or Controls Core Spray )
4.2-7 Check, Functional Test, and Calibration Minimum 3.2-40 Frequency for Neutron Monitoring Instrumentation Which Initiates Control Rod Blocks 4.2-8 Check, Functional Test, and Calibratioh Minimum 3.2-42 Frequency for Radiation Monitoring Systems Which Limit Radioactivity Release-4.2-9 Check and Calibration Minimum Frequency for 3.2-45 Instrumentation Which Initiates Recirculation Pump Trip
~
4.2-10 Check, Functional Test, and Calibration Minimum 3.2-46 i Frequency for Instrumentation Which Monitors Leakage into the Drywell ! 4.2-11 Check and Calibration Minimum Frequency for 3.2-48 Instrumentation Which Provides Surveillance Information ) 4.2-12 Instrumentation Which Initiates the 3. 2-49 a Disconnection of Offsite Power Sources 4.2-13 Instrumentation Which Initiates Energization 3. 2-49b by Onsite Power Sources HATCH - UNIT 1 viii Amendment No. If, 50, fi, 88, 110 , 9
4 TcDlo 3.1-1 (Cont'd) x
!M n Scram Source of Scram Trip Signal Ope ra ble Channels Scram Trip Setting Source of Scram L.gnal is Mumber Required to be Operable
% Required Per 4
(a) Trip System . Except as indicated Below e c_ (b) i z
*-* 12 Turbine Stop Valve to 510% valve closure Automatically b passed when ' - Closure from full open turbine steam flow is below Tech Spec 2.1.A.3. that corresponding to 30% of rated therwil power as measured by turbine first staga pressure.
Notes for' Table 3.1-1
- c. The column entitled " Scram Mumber" is for convenience so that a one-to-one relationship can be established between items In Table 3.1-1 and items in Table 4.1-1.
- b. l. The re sha l l be two operable or tripped trip systems fer each potentis t sc ram s i gna l . If the number of operable chanseets cannot be met for one of the trip systems, that trip system shall be tripped. "c_ .;r,-
-ene-t r!; c 5 ;;n: 5 ch:rn:!wf-a-t-r4p-+yetaaHaay-be-inoperable-for-op- to-two -{ 2 )-houre-der: g ; r4eds-er-required-
-surve444ence-t-- t ? ~; "! theut - tr-4ppin9-the-associated-tr4p-systee r-provided--tha t-the et* e r .n z '-'r.g chc rr:4(of-eeni tering- tha t-parameter-w4 th in-tha 4-tr4 p-sy44ee-4 s-(4 re )-opersb 4 er.
- c. Within 24 hours prior to the planned start of the hydrogen injection test with the reactor power at greater than F 20% rated power. the normal fulI power radiation bacI= ground level and associated trip setpoints may te changed based on a calculated value of the radiation level expected during the test. The background radiation Sevel and
- associated trip setpoints may be adjusted during the test based on either calculations or measurements cf actual
- radiation tevels r3sulting f rom hydrogen injection. The background radiation level shaft be datermined and associated trip setpoints thatI be set within 2ts hours of re-establishing normal radia tion levels af ter completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.
-bl. Crc ir\fdT-urnefh dfLGIT3 r-VCf b W% DO bF L O k b" hY U Q k Mrkr TG '
l hequired suneHtances Mc- 4e en4em oc; cuer og,;cc6;e ;mng prhaed a+ teas + ene iperraae chcmnen in &c Ab.x w p,y [ e roc nH t t,nq erde pararnever-. I a 'J , b o l ct 2 l
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( BASES FOR $URVilllaNCE RIOyjRfMENIS __ 4.1 REACTOR PR01LC110N SYSTEM (RPS) g f~ddd n~LnMtd dn
- A. Hst[4nd CaMbrition Reauirements f or the. RPS / ,
{he_ minimum functionaktesting.f reouancy-used n.this-specification-is-based + on a reliability analysis using the concepts developed in Reference 1 and the suheillance f requencies for ATTS equipment approved by the NRC in Ref erence
- 2. These concepts were specifically adapted to the one out of two taken' twice\ logic of the reactor protection system. The analysis shows that,the sensor $\are primarily responsible for the reliability of the reactor,protec-tion system. This analysis makes use of unsafe failure rate experience at conventional and nuclear power plants in a reliability model for the system.
An unsafe failure is defined as one which negates channel operabliity and s which, due
, tested to its nature, or attempts is revealed to respond to aonly realwhen the Failures signal. c h nnel is'as suchblownfunctionally fuses, ruptured bourdon tubes, faulted amplifiers, faulted gables, etc.,
which result in u> scale or downstale readings on the reactor instrumentation are saf e and will be easily recognized by the operators during operation be-cause they are revealed by an alarm or a scram. /
\ /
The channels listed in Table 4.1-1 are divided into four groups for l functional testing. These are: ' Group A. On-Of f Sensor,s that provide a Sgram trip f unction. Group B. Analog devices coupled with birstable trips that provide I a scram f unction. /
\
Group C. Devices which ony serve a useful function during some restricted mode ofsoperatjon, such as startup or shutdown, or f or which the only practical test is one that can be perf ormed at shutdown, / Group D. Analog transmitters apli trip units that provide a scram trip function.
/
7' The sensors that make up Group A ire speci (cally selected f rom among the whole f amily of industrial on-of f sensors that have earned an excellent reputation for reliable operation. j Duringdet(gn,agoalof 0.99999 probability of success at the 50% confiv ce level was adopted to assure that a balanced and adequate' design is achieved.\The probability of success is primarily a funt! tion of the sensor f silure rate and the test interval. A three-fnontt / test interval was plaoned fqr Group A sensors. This is in keeping with; good sperating practices, andssatisfies the design ( goal for the logic configuration utilized in the React protection System. To satisfy the lon term objective of maintaining an adequgte level of safe-ty throughout the' plant lifetime, a minimum goal of 0.9999 at the 95% conft-dencelevelisgroposed. Withtheoneoutoftwotakentwithlogic,this requires that ftach sensor have an availability of 0.993 at the\95% confidence (- level. This/ level of availability may be maintained by adjustis interval af a function of the observed failure history (Ref. 1) .h \)the test o facili-tate the,4mplementation of this technique, Figure 4.1-1 is provide 6sto indi-cate anglippropriate trend in test interval. The procedure is as follows:
- 1. Like sensors are pooled into one group f or the purpose of data
,/ acquisition.
[r-The-f at tor-M-it-the-exposure hours-and-is-equal-te-themumber-ef-Sensort HATCH - UNIT 1 3.1-15 Amendment No.103
Insert A (to P. 3.1-15) i The minimum functional test frequency and allowable outage time specified for , RPS instrumentation are based on the NRC a) proved reliability analyses performed in Reference 1. The analyses considered t1e } latch-specific design, including ' the ATTS equipment discussed in References 2 and 3. Included in the Reference 1 analyses is justification for one instrument channel to be inoperable for up to 6 hours to perform required surveillances, provided at least one operable channel in the same trip system is monitoring that parameter, prior to entering other applicable Actions. 4 i I 1 5 P- [
..wm- --____--_____--u - _ _ _ _ _ _ _ . - _ - _ _ _ _ _ _ . _ _ _ _ -_ _ _ ___-___-_---m_ . - _ _ . _ . . _ - ---____------m_ ___-*+--e_er,--wv= --s- -w ==.-e --a.-
[ \ (N,Tedt4e BASES FOR BLRVilLL ANCE R(QpjR,{y[ 4th Aar-Test-and-Calibration-Reautrement s for-th_t;21:-(Continued)----
\ /
\ in a group, n, times the elapsed time T, therefore M = n T. '.
- 3. The accumulated number of unsafe f ailures is plotted as an ordine e
\ against M as an abscissa on Figure 4.1-1.
- 4. Astest interval of one result will be used initially until aftrend is established.
After a trend is established, the appropriate test inter #al to satisfy
^
5. the goal will be the test interval to the left of the iotted points. Group B devices utiltre an analog sensor followed by an mplifier and a bistable trip circuit.y The sensor and amplifier are aptive components and a failure ;s almost always accompanied by an alarm and an indication of the source of trouble.An In the event of failure
'as-is' failure is one d, fepair or mid-scale substitution I
at sticks l can start inrnediatelb'9oing either up or down and is not capable of esponse to an out-of-limits in/(is a rar in-put. This type of failure for analog device e occurrence and is ! detectable by an operator'vho observes that ons signal does not track the other three. For purposes bf analysis, it 1)' assumed that this failure will be detected within two hours. / .
/ \
s a part of the Group B devices can sustain The bi-stable trip circuit whic unsaf e f ailures which are reveale gonly'on test. Therefore, it is necessary ) to test them periodically. /
/
l A study was conducted of the instrulnen etion ci.annels included in the Group
- B devices to calculate their 'unsa'fe' f ai}ure rates. The analog devices (sensors and amplifiers) are predicted to have an unsafe f ailure rate of less than 20 x 10-* f ailures/he'ur. The bi 'itable trip circuits are pre- t dicted to have unsafe f ailure' rate of less thip 2 x 10** f ailures/ hour.
- Considering the two hour monitoring interval f6r the analog devices as assumed above, and a week)p test interval for thhbi-stable trip circuits, the design reliability goal of 0.99999 is attainedswith ample margin.
The bi-stable devicesj e monitored duririg plant ope ton to record their failure history and establish a test interval using thexcurve of Figsre 4.1-1. Therearetdmerousidenticalbi-stabledevicesuhdthroughout the plant's instrumentation system. Therefore, signifhan data on the f ailure rates for' the bi-stable devices should be accumula(te rapidly.
/
The frequency'of calibration of the APRM Flow Referencing Network has been established <as once per operating cycle. Thereareseveralinsthmentswhich must be calibrated and it will take several hours to perform the chlibration of the entire network. While the calibration is being performed, a\ero flowsignalwillbesenttohalfoftheAPRM'sresultinginahalfschm n ! and red block condition. Thus, if the calibration were performed durin F
- operation, flux shaping would not be possible. Based on experience at othsr generating stations, drif t of instruments, such as those in the Flow l Ref erencing Network, is not significant and therefore, to avoid spurious (sramsv-a-cal 4bratlon-f requeney-of-ons+-See-operat4et-eye 4e-4s-estaM4theti.
i HATCH - UNIT 1 , 3.1-16 l
Dd6b ,
- SAst$ FOR $URytlLLANCE Rt0VIREMENTS Th A ri e s t -end -t a 14 bee t 40*-Reev i cemen t s -4 *F t 4 A pS-( Con t i nued )
Group C devices are active only during a given portion of the operation , , f' % cycle. For example, the IRM is active during startup and inactive durJfig (~ iull-power s operation. Thus, the only test that is meaningful is theA ne po(f ormed just prior to shutdown or startupt i.e., the tests that pte per-formed just prior to use of the instrument. Calibration f requency of the instrument channel is divided i t'o two cate-goriest ey are as follows:
- 1. Passive type indicating devices that can be compared with like !
units on a to,ntinuous n reference. ,
- 11. Vacuum tube or seiniconductor devices and dete tors that drif t or lose sensitivity Experiencewithpassive\ typg instruments in enerating stations and substa-tions indicates that the speQfied calibrati(ons are adequate.For those devices which employ amplifiers, etc., drif t specifications ca11 for drif t to be less than 0.45/ month: 1.e.) in ths period of a month a drift of 45 could occur and still provide r' adequate margin. For the APRM system, i drif t of electronic apparatur is not the only consideration in determining a calibration frequency. ChangeA n po% r distribution and loss of chamber' sensitivity dictate a calibration every Kven (7) days. Calibration on this frequency assures-plant j dperation at below thennel limits.
ThesensitivityofLPRMde(ettorsdecreaseswi exposure to neutron flux -i at a slow and approximately constant rate. This (s compensated for in the , APRM system by calibrating twice a week using heat %alance data and by calibrating individui1 LPRM's every 1000 ef f ective f h power hours using TIP traverse data / ; Group D devic onsist of analog transmitters, master tri sunitt, slave trip units nd other accessories. ' The general description Ofs the ATis , devices provided in Reference 3. AsevidencedbyNE00-21617%,the - NRC ha pproved the.following surveillance f requencies for ATTS
- utpments :
- 1. nce per shift for-channel check _
2 Once per month for channel functional test _ 3 - Once per operating cycle for channel calibration a ' {-
)f. Maximum Fraction of Limitino Power Density (MFLPD) -
f 34s-seetten-deleted, , J . HATCH UNIT 1 3.1-17 Amendment No. 73, 193, 105 ;
,e- v e- , ve u e we 'r e ervrw, v-,-er-w--w e r- ve- e evv*- --e-w+--, * , -,-w<-- u- .c n am-+---u r>e+-- <,-t- e- w- wms----- - p--v = n e mee,-, -i r, e g
- BASE $ FOR $URVEILLANCE REQUIREMENTS )
4.1.C. References ir- Iv- M r-Jac obs r' Aelia bi li t y- of-ing inee red -Sa f e t y- Fea t ure s -a s -a -f unc t ion- of-T es t ing 4 requenc y. L Nuc lea r- Sa f et y,-Volume-9 r-Wo r4 rJuly-Augus t r1969;-- pp-303-31Pr-
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- 2. N[DO-21617-A, ' Analog Transmitter / Trip Unit System for Engineered Saf e-guard $ensor Trip Inputs.'
- 3. NED[-22154-1, ' Analog Trip system for Engineered Saleguard Sensor Trip Inputs - Edwin 1. Hatch Nuclear Plant Units 1 and 2.'
- l. IdEDC -?025l P- A s "Thchnico) EspeciViccdicn Lprovemad Anatpes 9er svnt ~Praec+ ion Sy.sht " Mcus 19W.
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HAICH - UNIT 1 3.1-18 Amendment No. 103
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- NUM8tR OF IDENTIC AL COMPONENTS T
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t1M111NG COH01110NS FOR OPE RATION SURvt1LLANCE REQUIREMEN15 3.2 P.ROTEC11vt INSTCUMENTA110N 4.2 PR01tC11VI INSTRUMENT A110N Applicability Appiitability 1he Limiting Conditions for Operation 1he Surveillance Requirements (- apply to the plant instrumentation apply to the instrumentation which perforns a protective which perf orms a protective f unction, function. Objective Obiettive
! The objective of the limiting Condi- The objective of the Surveillance ,
tions for Operation is to assure the Requirements is to specify the type operability of protective instrumen- and f requency of surveillance to tation, be applied to protective instru-mentation. SpeciHeations Specificatie,i The Limiting Conditions for Operation The check, functional test, and of the protective instrumentation af- calibration minimum f requency for fecting each of the following protec- orotective Snstrumentatinn affect-tive actions shall be as indicated in ing each of the following protec-the er ,esponding LCO table. tive actions shall be as indicated in the corresponding SR table. Protective Action LCO Table SR Table A. Initiates Reacto M essel- 3.2-1 4.2-1 and-Centainment 1solat. ion MitrdicA B. Initiates or Controls HPCI 3.2-2 4.2-2 C. Initiates or Controls RCIC 3.2-3 4.2-3
- b. Initiates or Controis ADS -
- 3. 2-4 4.2-4 E. Initiates or Controls the 3.2-5 4.2-5 LPCI Mode of RHR F. Initiates or Controls Core 3.2-6 4.2-6 Spray G. Initiates Control Rod Blocks 3.2-1 4.2-1 H. Limits Radioactivity Release 3.2-8 4.2-0
- 1. Initiates Recirculation Pump 3.2-9 .4.2-9 1 rip J. Monitors Leakage into the 3.2-10 4.2-10 Drywell K. Provides Surveillance 3.2-11 4.2-11 Information L. Initiates Disconnection of 3.2-12 4.2-12 Offsite Power Sources i M. Initiates Energitation by 3.2-13 4.2-13 Onsite Power Sources '
H. ' Arms the Low Low Set S/RV 3.2-14 4.2-14 System HA1CH - UN11 1 3.2-1 Amendment No. BF.103 _._~._.m_____._ ._____
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'Def. - Conditlen per Trip t fd1 sesteen fri me. mmmenclat ure instem (b) fris Settles 1astrummet
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' 21 ' '
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- Z' eCIC tertiae.
L .Z. G eses Isetation i t1- ' 529 psig Close WCIC isoletlen valves in actC
~
22 WCIC Tertiae Mip f waives and declare-
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twheest RCIC terbine. Diaphraya Pressere . i D ese WCIC lseistfee Clews isolation , EXC Seppression Mip I 1169'T waives and declare valves in SCIC 23 system, trips Chamber Aree WCIC inoperable.
' Ambient Temperatore aCIC tertice.
G ese DCIC isolatie. Gews isolettee ! 9CIC Seepression Mid . i 342*r waives and declare waives in SCIC 24 ' srstee. trips ' Chamber Area aCIC ineserabic. WCIC tertise. w Diftercatlet ~ i
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Insert B to Table 3.2 1 Add to Note c.1:
"With the number of operable channels less than required by the Minimum Operable Channels per Trip System requirement for one trip system, either
- 1. ) lace the inoperable channel (s) in the tripped condition
- within 12 Tours OR
- 2. take the ACTION required by Table 3.21. i
- With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip function to occur, in these cases, the inoperable channel shall be restored to operable status within 2 hours cr the ACTION required by Table 3.21 for that Trip function shall be taken".
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/c nrcW i etir b We o rm a
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- ; e s araeriob c r.p r oleo' ra - - r r to vod a qH I
ys eeed - r i t p snne ast l m brse s cs rh t ol srrs p n ue l s ne ot l eec se i iset tel a ec r e wo u de r ehdnodo r ee s i l hvx at e y t avb' a* 4~ :! t4 1 G nteoinho n, situ t l es nc id h r i t srra a ataot i n nn ".a n snoo ett r g ooe r t p'* ~ n gm g h n c pe l rbal iug o r2r ne oa o1 twat yh c e t dcot ya r e r! a e ;! er a e eoeal wddckni cir a c Glde N-f3 2 i r ,ern gl eaes o i n t heo" e c rwc
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.e n9 ve 2ttttnto t ir ep i i u ne in rt2d n aessenr ne l n year oe rs u cew aoFs.
ru pf ea prl r ee e h ;el d e- d e a n e i l v ir s e ttooy e gi d r ph tn dnL ec n p v '"a nh t p! e hgp Cre mp st Cr et i r '2 e s eme P-e ee h e e t itrhhyef ieedt he ru1 re ha heLe P p2 pt We : tpe T Wattthso Tb . 2 . L 4 c
. 2c ,
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, 4
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- Table 3.2-2 h-
- t INSTRUMENTATION WHICH INITIATES OR CC1TROLS HPCI Trip Setting Jtema rks 9 R3r. Mo.
Instrtment Trip-
' Condition Required Ope rable (o) temenclature Channels c per Trip 2 System (b)
U
*~~
- 1. Reactor Vessel Water Level Low Low 2 2-8s7 Inches inittstes HPCI: Also Initiates g (Level 2) RCic.
Drywel l ?ressure High 2 5 1.92 psig Inittstes **PCl; Also Inittstes l 2. LPCI and Core Spray and pro-vides e perialssive signal to ADS.
- 3. HPCI Turbine Overspeed Hechanical 1 5 5000 rpm Trips HPCI turble
- 4. IIPCI Turbine Exhaust Pressure High 1 5 II:6 psig Trips HPCI'tterbine g Low 5 12.6 inches Trips HPCI turbine {
- 5. HPCI Pump Suction Pressure 1 Hg vacute
- 6. Reactor Vessel Water level High 2 5 +56.5 inches Trips HPCI turbine w _
(Level 8)
- 7. HPCI Pump Discharge Flow High 1 2 870 gpm Closes HPCI minimwe flow bypass h,
u ( 2 9 . 01: Inches) line to suppression chamber. Low 1 5 605 gem Opens HPCI minisntn r:ow bypass 4 (s 4.36 inches) line ir pressure p-raisslve is present. l . _ _ ~ HPCIEdencyjAres[ / Hj h [ / 1
/ 5 169'I Closes Isol'etion v/tves in ,
y (\ 8.
,,[ Cooler Ambient Temperature / / ifPCI system, trfpsHPCI[ / {
I
- ' ,/ .[ !
/
purbine.; y g 3' : i ,
$. *8ck a
n E O u- . 4 0 p 9.'De%ed. w
~ 10. Teleied. - .
o
~ Il. T ele M .
w e h6 .
. b. . ', ro.
h
--4 Table 3.2-2 (Cont.) $ Required Operable , 3g $ Trip Channets C
Re f". No.
- 7. v 4endition per Trip 5 (s)
-4 Instrument
[ ./ g' Mosene t s ture System (b) Trip Setting Rema rks
, f . *T 9 / HPCI Steam Supply Pressure /
l<ow ,,- f I 2100 psig j< Closes isolation volves In I
]
/ / / ,
j/ / HPCI systest, trips HtCI / l ,-
/ / ' / y '/ turbine./ /
e _/ / / . .
/ /
{ t0. jhPCI Stess Line AP (Flow) Hlyh / 1 5303% rated / Close isolation volves in
/ ' / t't ow f HPCt system, s MPCI trip /
- / y
/ / '
s'
- / turbine.
, / /
/
S20 psig /
/.. /
Close Isoletion isives in I 11 / HPCI Turbine Exhaust , itigh , 1 HPCI system, trips HPCI / DIsph mgm Pressure / / /
/ /
/ / turbine. /
/ 7
/ "'
/ -
/ ; / / ;
- 12. '
Suppression Chamber Ares High / 1 5169*F ' Close Isolation valves'in i Amb i ent T eepe ra tu re, -
/ / HPCI system, trips HPCI l i l
/ l l turbine. / /
/ / / / / l
,13 . Suppression Cheeber Ares .Migh / 1 ' Si2'F / Close isoletion valves in 3
/ HPCt system, trips HPCI P
to /-
/ Di rre rent is t Ai r Tewpe ra ture l
/
/ j'/ turt> lne. / /- \
s
- Condensate Storage isnk Low 2 20 Inches Autoestic interlock switches lit.
Level suction from CST to suppression chsaber.
- 13. Suppression Chestber Water High 2 513ts.2 Inchas Autoestle Interlock svltches Level with respect to suction from CST to torus invert suppression chseber.
1 Mot AppIlcable geonitors svaltabittty or
- 16. HPCI Logic Power Fallure power to logic systm.
Monitor
- s. The column entitled "Ref. Mc.* Is ofdy for convenience so that e one-to-one reistionship can be estabi t sbed
{ between items In Tebte 3.2-2 and items in Toble is.2-2. 53 rn 3 e+ 2 P m N e N G w e W N Y _ m _ . _ . . _
.- m' a _. .%
O O
- m thstes f oe Table -2 Kent.)
x b.1. When any CCES subsystem is required te be operable by Sed io 15, there stulf be two eperabic
> trip systews. If the required mseber of operable thannels t#anet tw met for eae of the trip sysicers.
N place the inoperable thannel in the tripped tenditica er dettere the essociated CCCS inoperable I within. If the required number of eperat>'4e tha mals taaaet t=e met ter both trip systeers.
. declare he associated CCES inoperable within 1 beve.
c 12. heur-s. x
--4 - b.z. Cre inehurnent channd may be;intpernWe b op 4 G kcurs b pech recpired surveillances pr-ice b eixbering c Aer appUwe 'gm c, *J 31 en =
CL - r+ 2
,o o
I i
I Table 3.2-1 X n
-tMSTRUf1EllTATIOM milch IMtitATES OR CO$tTROLS RCIC I fte r. Instrument Trip Raquired Trip setting Reeseks e Mo. Condition Operable Mooanctature Cha m ts E (s) per Trip System (b)
W
- 1. Reactor Vessel Water Levet low Lew 2 2-47 inchas inittstes RCIC; also inittstes g (Level 2) MFCI.
- 2. RCIC Turbine Overspeed Electrical 1 5110% rated Trips RCIC turbine.
Nachenicst 1 5123% rated Trips RCIC turbim .
- 3. RCIC Turbine Exhaust High 1 5*k's psig Trips PCIC tJrbine. l Pressure is . RCIC Pump Suction Pressure Low 1 512.6 inchas Trips RCIC turbine.
Hg VactRam l
- 5. Reactor Vessel Water level High 2 5*56.3 Inches Trips RCIC; *istematically resets (Levet B) when water drops b* low level 8, systes steicestice s ty restarts et w IeveI 2.
N 6. RCIC Pump Discharge Flow High 1 >87 gre Closes 8tCIC ministam riew cn (2 10.6 Inches) bypass tine to stwression chamber.
, low 1 553 gre Opens RCIC plaimine rtow y (S 3.87 inches) b>srass t Ine Ir pressore
[ T g~ M L permissive is present. l
/RCic EmaEjency Aree'
~
y!7. . High 1 5169'r closes isoletion valves la
<D
/ Cooler Ambient Tempereture '
',RCIC system, trips FCIC
$ -. r.~. . - J --- _-. l_. __-. i _.. .. l. __ _J _ - ., _ j_ _ - n _-. _.w _ l '
tu r*J i nei ; ,_ _ , a en 3C j .
=
0 , , , I
~*
M((df3kb . w N e-aj ( -
~ ir ~ ,
5 * .$ 4 ,y W i {- % r vetewed. e o fd. ' i t. . N w
'uetudP w
_ . _ _ _ _ - _ _ _ _ _ _ _ -m
, . . . m ;
" Table 3.2-3 (Continued).
k Required j-4 [y' Trip operable Citannels Rer. - Condition per Trip
- Q teo. Remmeks 8
(s) Instrtment / W isture System (b) Trip Setting s c- b. kCIC Steam Sceply fressure ~ Low 2. ' 260 psig / Closes RCIC system, trips RCic Jsolation v3Tves in/ i I g
- z
~ /-
/ / turbibe. f
* / /
/- / /
RCIC4tess Line AP,(flow) 1/,- S306% yate1f Closes isoistion waives in y9 '. High a / ,e flow ,PCtc system, t ri pottCIC l /,/
/ /
/ /,/ turbine. j f
/ 520 psig / Closes isolstfon ystwes in 10.
,[/
RCIC Turbine'/ Exhaust Ofsphrsget Pressure / High
/
1
/ f RCIC system,/ trips RCIC [ ;j g turbine. ,/
- 1. Supptession Chamber, Area High , 1, 116g*F Closes,(sotation volves,4n ;
l Arbient Temperature / / RCIC system, trips RCIC l l l / A / ,! 'Y " l ,
~12. Suppression Chamber Ares ,4tigh / 1 sas2'r closes Isotstgen ystwes In l l
Different(sl Air '
/ tr s RCIC 3 Tempers taire __ / /'/ RCIC turbine. systee, *
[ b2 13. RCIC logic Power Failure 1 Not Applicable Monitors svsitsbility of g Monitor power to logic system. m 1 13 . Condensate Storage Tank Low 2 20" Transfers suction tree CST g Water level to suppression pool.
- 13. Suppression Pool Water High 2 50" Transfers suction f m MT g Level to suppression pool.
g . R E 0 E 5 %... , .. . . . - __ .__ . -m __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . . . _ _ _ . _ _ _
NOTES FOR TABl.E 3.2-3 l
'l
- 4. The column entitled "Ref. No." is only for convenience so_that a one-to-one relationship can be established between items in Table 3.2-3 and items in Table 4.2-3.
b.l. When any CCCS subsystem is required to be operable by Section 3.5. there shall be two operable trip systems. If the required number of operable channels cannot be rnet for one of the trip systems, place the inoperable l charinel in the tripped condition or declare the associated CCCS inoperable within -hour. If the required number of operable channels cannot be met for both trip systems, declare the associated CCCS inoperable within I hour. I'l ly ur$. ) h ,i (_rg- i g lt t y t y y } O V lj u M :] h t( u / i Hi%I C I
'4h (p c w s k p r'? n o r u g u cc d ' hi W U U " C C
t P h' I ( en\ enL {1, CM L r ( q4)u:yMk .\0k-ic6Yc'>. J I h _ c1Ce.ohl11 - 3.2-,a smenemen1 No. rer. >>o ,
( ,
, . . ~ . .
..-...._ - . .m. ; ,. , ny;. .
A $ , f .. 6 ( -
* ./
g I"yNa - Tatie 3J-4 ' { a J ~ [
$ 905TRUmEITTATlost WHID4 WNTIATES OR C00fTROLS ADS
~ ~
Ref. nosensmont Tsip heesked Tsey settig t.
- f. E No. ~
Casiesen Operette Amnesshe . ' , s ; Q les 8hensas8=es* Ch=aa='s ~ i l' '~ per Trip a ! e
.,_ Susamn R$
~ !
- 1. Reeeest Vessel W eemt Lessi Law 5. east 38 1 302 businne Cenemas leer lessi. ADS pasadeshe ; { ,
Roemeer Vemmet Weent Level Leur Low Leur 2 ( h m.113 bishoe houdmatue olyset to ADS ener t Smeet 1) 8 . i ,
- 2. Dryumes Pessomso Mali 2 s122 puis Pesadadesslyufse ADSshuar -
s ,
!- 3. MHR Ptmosp F "_
t Mgh 2 - 3112 peig * ' Pusudentes slyed to ADS meer [ f . g 4. CSPtsnipr " % Mgh l- _ m 2 m137 pela pesadescue etyuf to AOS ease
.
- Premesse -
h3 ,
.* e - i g S. Auto r _"- 2 sta sudsuseme Depeans Idges dryuus asummuse
., Lew Weemr Level Tbner
;r pensessees apen omsessmed Lowel 1 .
.. S. ' Assen-- 1
- i Timer 1 130 t 12 asesude 100uh Lemos 3 and Level 1 and 9dsh j
dryuse psamouse asus CS er IW4R pemeup - l3* 7 . et possanne, musse sogneuse . 1 begbus. If the ADS ener le samt t
/' 7. Aseeniede EBewdown Centret
-e = = h ee A.S. .
;l 1 Met appEestie Perwar Fesure teenleer hemsdesse esammhe.,of poseer to lugle eyeemm
)
i
- s. T he co s tuun enti tled "Re f.
8tems in Table 3.2-4 and items in Table 4.2-4No." is only for cortvanlence so that e one-to-one relationship can Ipe established betweese , R { vo b.j. IJhen any CCCS subsystem ' { trip systems. is reqtsf red to be operable by section 3.5. there she s I be two operable a n* piece the Inoperable If the channel required rresuber of' operable channels cannot be met for onw or the trip systees i wi thin 4,-JoseA in the tripped condition or dectore tM sssocInted CCCS Inoperable ,
$ declare he associated CCCS Irioperable within 1 hour.if the required number of operable channels cannot be met for both trip syst z
O 12. hours. - i I (~ bz On6 i'eFrurnent channej may be incperable b j g 6 mm yired Surveinances prior- % enwftng g Q M M
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s> t, 10 _D . hil d A fi d i h HATCH - UNIT 1 3.2-11 Amendment No. EJ. EZ. 92. 103. 1El 9
[ ' [t I p ;' ,.) ; {i {t , i ,' i.' t, !e !I; * ;I ; tf> . 0r Q, s m e t s s r ue e yes b est m t he t n c a bpst sirs rrey h 4eh etps i p v o oenp k C h hii s ot r n w St i t o s tfC oCh e Ct be o
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o ! e +o - e - 3nrn eaa r l t7 c Mi b a nal c T a hi s t i occ es r e tsdl R r o ol sb eern cl e p p f
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e c nn bhocr' yanh . isen t lei e ci u o teo bccna i M s m l e8 l h wt oi e bl4b ab ia1 ra er v.d pe ercen pi n o pd o h l ra o f! br po w ' e oepri t qle i o oirre n ly R. n3 trtel e bb~ n o dbema . sl ib e emhur a u ndo rutne p in dudsn 3 qd i e n
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on NI
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ee erh rrli iqneC ieuS sunqC earC hdo- i eM r e Rt
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fable 3.2-6
$ -4 INSTRUMLMTAT IOM WHICII 1911 Ti ATES OR COM1ROLS CORE SD O
^
Re f'. Instrument Trip Regtei red TRIP SattIng Rees r fr s Mo. Condition Operabte 8 (a} MomencIsttfre Chsof*Is c- pe r T ri p Sys ten _Lb1
.Z _
-4
1. Re&ctor Vessel Water tevel (cw t ow tow 2-113 incM t Inittst*S C3.
(Level 1) 2
- 2. Drywe*1 Pressure 71 19h 2 51.?? psig Initiates CS. Afsn Inittstes 94PCI and trCI mode or R$4R sad provides s p* missive Sionst to ADS.
- 3. Reactor vessel Steam Dome Low 2 2422 psiq* rerwissive to w CS Pressure injact8on vsIves.
- 4. Core Sprsy Sparger l S 3.1 psid 9%nitors Integrity of CS Dirrerential Pressure greater { tess piping inside vessel (betw**n ne1stivel then the nozzle end core shrotaf).
the norass indicated P at ro ra ted co re powe r and rIow. 5 5. CS Ptrop Di scha rge r low Low 1 2610 gre M in s amem riow bypess tin
- ts closed when few rlow sitpist (2 4.13 Inchas) is not present.
y en
- 6. Core Spray togle l'ower ra f store Monitor i Mot Applicable tenitors availability er power to logic system.
3 a
- 3 rp *Inis trip runction shall be 5500 psitJ.
3
- s. The re t umn ent i t led "Ref. No." is only r3r convenience so that a on*-to-one relationship can be estabt ished Z between items in Table 3.2-6 and items In Table 4.2-6.
- b. L When any CCCS st:bsystem is required to be operable by Section 3.3, there shalI be two opershte y w trly systems. f r the regest red number or operable channels cannot be spat for one of the trip systems.
a 13 place the Inoperable channet i n the t r i pped cond i t i on o r d*c l a re the a s soc i a ted CCCS B rioperable ON within * "m 3 r the regtnited ntsmber or operable channels cannot be mat for both trip systems, w4 declare {the associated CCCS inoperable within 1 hour. IL hm. Z
- c. Alarm only. When inoperable, verity that the core spray dirrerentis t pressure is within fielts et lesst once per 12 hours or, declare the associated core spray toop inepareble, w
- b. b Pd $D moi O TM C NW O d O UTQ recp6ced 6urveinances p. rice 4e en+eriaq c+er oppHcaWe pagm ,
;; ~
-. e w _
_ w v
M "m t i D i .,
- f 1 (
i Table 3.2-7 (Continteed) ~ Reqasi red x ' Ope rab l e Trip Channels N> Re r. per Trip Remarks Condition Trip Setting x f40 '. Namencla ttere System
' (a) Instriement RBM, Upscale 7t e ll f~ i c
44
$117/125 of full scale There are three tepscale P!p levels.
Low?"r Only one is er 95 led over a specified 3
--4 Sets, M .c (t_ TSP) ope ra t ing core tfw rata l ge t - tange.
- Att RBM trips are atetematically by-
. Intermediate Trip- $111.2/125 or ruil scale 9;ssed below the low power se.tpoint.
Setpoint (ITSP) flee itpscaie LTSP is app t ied 12etween .i 5107.ts/125 or rulI seale the lov cower and the inte reedi a te
; liigh Trip power setpoints. The nepscale itSP 4
Setpoint (lliST ) is applied between the intere diate j power setpoint and the high power setpoint. The etpscale HISP is applied above the high power set-point. Power Range Not^ Se tpo i r.t s ape..ce5'fe 53G% rated core thermal Power range setpoints control tfm Low Power . power enforcement of the appropriate tep-
- i w
* 'Setpoint (LPSP) scale trips over the proper core p, thermal power ranges. The power e
I nt e rmed i a te Powe r 565". ra ted co re the rata l signet to the RBM is provided by Se; point (: PSP) power the APRM.
@ 585% rated core therma t liigh Power power Setpoint ( flPSP) 52.0 seccMe RCM bypass time delay is set low Dypass Time Not enotegh to assure minimtem rod move-Delay ( tds ) applicable ment while tipscale trips are Dy-pa m d.
1(g)(h') 518 gallons Sc ram fligh Water i 5. Levet , Di scha rge, 4
}
i 8 vo l time h i i
=
a E3 . m et 2 O . M O - Ut
~
" ~ N m Notes for Table 3.2-7 e
- x
--4 is only for convenience so that a one-to-one relationship can be established 9 a. The coltimo entitled "Ref. No." between items in Table 3.2-7 and items in Tab *e 4.2-7.
, t he re sha l l be two operable or tripped systems c b. l. For the START & Hot STANDBY position of the Mode Switch,f r the regtsirements established by the column cannot be met for one 2 for each potentlaf trip condition. for sep to seven days provided that during that time Z or the two trip systems, the condition may exist immediatefy and daily thereaf ter- if this condition lasts longer the operable system is functionally tested E r the requirements established by this column cannot be " than seven days, the system shall be tripped.
met for both trip systems, the sy9tems shall be tripped,
- c. One of the four SRM inputs may be bypassed.
This function is bypassed when the 74ede d. The SRH and IRM blocks need not be operable in the Run Mot *e. Switch as placed in the RUN position. 12% APRM Rod Ofock), e. The APRM and RDM rod blocks need not be Operable in the S* art & Hot Standby Mode (rweept in Section f. The RBM is only required when core thermal powsr is 2307, and the limiting condition defined 3.3.f' exists, and Refuel Mode when any ec *rof rod is This trip is Operable in Power Operation and flot Standby Mode, g. wi thd rawn. Not applicable to control rod s removed pe r Speci f ica t ion 3.10.E. i: cel
- h. WHhdratcal c4 conht rods is nc+ Perm &ci during O c
g surveilkmee. +es+ing .
?.
- 4c 4 chann el WW be incpemble. 4br- up 4c 6 Eo -
.-b.2~ One in.drurnen pc% re9 d red dv.rveillances prior 4e ederinc' quede AcMons-k a
a E O cn
R R' N $ p.
' Table 3.2-8'(cont.)
1 3 Re f. Instrument Trip Required: Trip Setting Action to be taken if itema rks n 10 0 . Condition Operable there are not two operable I (a) Ilomencla- Channels or tripped trip systems a ture per Trip L System (b) e 2- i --a w
- 5. Main Steam f.ine Hi 2 S3 times ~ Isolate the mechanical One trip per trip Radiation Monitor noriaal full vacuum pump and the logic system will power background . gland seal condenser isolate the.
**8 exhauster mechanical vacuum l.
pump and the gIand seal condense r exhauster,
- s. The coluem entitled "Ref. Ilo." is only for convenience so that a one-to-one relationship can be established between items in Table 3.2-8 and items in Table as.2-8.
b.l. Whenever the systees are required to be nperable, there shall be two operable or tripped trip systems. fr this cannot be met, the indicated action shall be taken. F In the event that both off-gas post treatment' radiation monitors become inoperable, the reactor shall be placed in the Cold Shutdown within 24s hours unless one monitor is sooner made operable, or adequate alternative to 8 monitoring racilities are available, e
- d. From and after the date that one or the two off-gas post treatment radiation monitors is made or round to be inoperable, continued reactor power operation is permissible during the next fourteen days (the allowable' repair time), provided that the inoperable monitor is tripped in the downscale position.
~
- e. Within 2ts hours prior to the planned start or the hydrugen injection test with the reactor power at greater than 20% rated power, the normal rull power radiation beckground level and assoc!sted trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual rad ia tion levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 2ts hours or re-establishing normal radiation levels after completion or hydrogen injection and prior to establishing reactor power levels below 20% rated power.
be inoperable %r un +c G hours % w f -b. Lone indrtuwen+ th cqp\icctbb ACMons. vel lcances channel mper7ct-vnpHee -to eneq chr-repred 4 a 2 _ g e
y ~~ 6 Table 3.2-9 E INSTRUMENTATION WHICH INITIATES RECIRCULATION PtMP TRIP
-f, Remarks Z g Ref. Instrument Trip Required Trip Setting No. Condition Operable e
Nomenciature Channels c (a) per Trip z Systee
-4 e*
- 1. Rea: tor Vessel Water tevel tow (Level 2) 2'*' 2~47 inches H,0 Power must be redused and the l mode switch placed in a mode (ATWS RPf)" ' other than the RUN Mode.
High 2' 1 8095 psig Power must be reduced and the l
- 2. Reactor Pressure mode switch placed in a mode (ATWS RPT) other than the RtM Mode.
- 1. Turbine Stop 2' l. Stop Valve Trips recirculation pumps on ^
- 3. EOC - RPI 190% open turbine control valve fast Valve Closure closure or stop valve closure
- 2. Turbine Control 2. Control Valve Valve Fast Hydraulic when reactor is > 30%.
Closure Press Trip Point Y
'? Ihe column entitled "Ref. No." 11 only for convenience so that a one-to-one relationship can be established N (a) between items in Table 3.2-9 and items in table 4.2-9.
(b)l.Whenever the reactor is in the RUN Mode, there shall be two operable trip systems for each parameter for each operating recirculation pump. If the required ntenber of operable channeis cannot be met for one of the trip systems, place the inoperable channel in the tripped condition or take the indicated action within 14 days. If the required number of operable channels cannot be met for both trip systees, take the indicated action within I hour.
-aw-k" (c) Anticipated Transients Without Scram - Recirculation p ump Trip _
ct a (d) End of Cycle - Recirculation Pump Trip cu 5 (e) Either of these two EOC - RPT systems can trip both recirculation pumps. Each EOC - RPI system will trip if 2-out-of-2 fast closure signals or 2-out-of-2 stop valve signais are received. 2 o (f)l,Therequirementfor'thesechannelsappliesfreeEOC-2000 MWD /ttoEOC. The RPT system may be placed in an inoperable N status for up to 2 hours to provide the required monthly surveillance. If one EOC-RPT system is inoperable for 7 longer than 72 hours or if both EOC-RPT systems are simultaneously inoperable, an orderly power reduction will be immediately initiated and reactor power will be c301 within the nemt 6 hours. 7 g - ra y (g) Either of these two ATWS-RPT systems can trip both recirculation pumps. Each ATWS-RPT system will trip if 2-out-of-2 b.: reactor low water level signals or 2-out-of-2 reactor high pressure signais are received. )
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-4 NOTES FOR TABLE 3.2-11
- s. r": '
i ' :I: . .
,! , s. . The column entitled *Ref. No." is ordy for c::.u -.c.e so that a one-to-one relationsrup can be
- j. estabEshed between items in Table 3.2-11 and items in Table 4.2-11.
2:
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- b. Limitine Conditions for Operation for the Neutron Mord. ring System are Ested in Table 3.2-7.
- c. l. With one or tr' ' M the rnonitoring channele inoperable, either restore the inoperable channeNel to OPERABLE statue within 30 deve or be in et least ff0T SHUT [.OWN within the next 12 hours.
Continued operst"on is permissibio for seven days from and efter the date that one of these parametere is not indicated in the control room. Surveillance of local pensis wiR be subsetuted for i+% in the -
- l. /! control room during the seven doye.
, d. Drywee and Suppression Char 4er Pressure are each recorded on the same recordere. Each output channel hee
, its own recorder.
, Drywes and Suppression Chamber air terriperature and sagpression chamber water temperature are a4 recorded .
,j on the same recordere. Each output channed has its own recorder. Each recorder tal6ee input from several
, temperature elements.
t Hydrogen and Oxygen are indicated on one recorder. The recorder has two pene, one pen for sech parameter. 4 7 Each channel of the post LOCA rednetson monitoring eyesem includes two detectore: one laceted in the
]
8 drywell swuf the other in the suppreesien chamber. Each detector feede a signal to a separate los count rate rneter. The meter output goes to a twe pen escorder. One high tecketion level alarm is provided per channel erwi annunciation of alarm is provided in the control room. -
- F n,gh Range o,yws. p,eesure and wigh aang. o,yweii Radiation are reco,d.d on the sam. cocordere. tach .
,i cL output channel has its own recorder.
i a e 4D e.1. In the event that aN indications of this parameter is disabled and such indication cannot be restored in 5 eim (6) hours, en orderly shutdown shst be initinted end %e reactor shaN be in a Hot Shutdown condition 2 in six (6) hours and a Co?d Shutdcwn condition in the fo6 wing eighteen (18) hours. i o - A
- f. L If either the pnmery or secondery indice6cn is inoperatde, the tonte temperature wig be monitored et p least once per shift to observe any unexplained terrrerature increase which might be indH:strve of an open SRV. With both the primary and secondary monitoring channele of two or more SRVs inoperable either p restore sufficient inoperable chenr. ele such that no more then one SRV hee both pnmery and secondary e
- channele inoperable within 7 deye or be in er tenet hot shutdown within the next 12 hours. -
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i NOTES FOR TABLE 3.2-11 (Continued) h or hot shutdown conditior and with the noseber of n g.].With the plant in the power operation, startup, initiate the preplanned alternata C operable channels less than the required operable channels, method of monitoring the appropriate parameter within 72 hours and: or af. either restore the inoperable channel (s) to operable status wit!..; 7 days of the event, w
-4 b2'. prepare and submit a special report to the NRC pursuant to Specification 6.9.2, within til days following the event outlining the action taken, the cause of the Inoperability, and the plans g
and schedule for restoring the system to operable status,
- h. A channel contains two detectors: one for mid-range noble gas, and one for high range noble gas.
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;j Minimum ~ Frequency Minimum Frequency. ' Minimum Frequency Mo. Instrument r
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. Once/ operating cycle Once/ month- cgaCtr4 t h '
-4 1 Reactor Vessel Water Level "Once/ shift ,
i
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{ b , 2 Reactor. Vessei Steen Dome ~ 'Once/ shift Once/montA W 4 Once/operstIng cycle .
. l.
' Pressure -( Shutdown Cooling.
Mode) 3 Drywell Pres su re ' Once/ shirt 'Once/menth. fif4'~ Once/ operating cycle. l' f is - Maln Steam Line Mone Once/ week (e) - Every 3 months ( f) ; ' Radiation Every 3 months 5 Main Steam Line. Mone '(d r A1/A Pressure 6 -Main' Steam Line Flow- once/ shirt. 'once/ sooth- W .. Once/ operating . cycle 7 Male Steam Line Tunnel
' Temperature
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y '8 Reactor Water Clennup System Differential Mone 4dP/d[A Every 3 months m }
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4 9 ' Reactor Weter Cleanup :Once/ shift l :Once/ month- F Once/ operating cycle , Area - Tempe ra ture i t
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l. Table is.2-1 ( Cont' d ) ' Instrtent ' F metional Test inst rumen*,' Ca l ib ra tion g Ne f. . 'Instrtsment Check ~ t Minimum Frequency
' Minimum' Frequency. Minimum Frequency g No. Instrument lbi' - ic1' g 'la_1 Once/ operating cycle .
' Once/mem4A-girtdS P -'
10 Peactor Water Cleanup -lOnce/ shirt-p e Area Ventilation -
. g -- . DifTerential Temperature Every.3 months
1JdQ[A 2 N 11 . Condenser Vecuum . None. Once/dey-Shi% Once/ M Once/operatind cycle - ' f. 52 . Drywel I - Rad iation
-Add F" l Notes' for Table 4.2-1
, 7pg g# ' A. The column entitled "Ref. No." is only for' convenience so that' a one-to-one relationship can be established between items in Table is.2-1 and items' in Table;3.2-1.
- b. Instrument functional tests are not required when the Instruments are not required ' to be operable o#-
a re tripped. Howeve r,' If functional tests-are missed, they shall be performed prior to returning .the ' instrument to .an operable - Status. C. Calibrations are not. required when the instruments are not required to be operable. However,.ir' b calibrations 'are missed, they shall be performed prior to returning the Instrument to an operable
~
status. ith an Intprval or not less the one mon nor II. In {ially once,pdr month. or. accor ing to rigdre 84.1-1 . re th,n thre months The'co :latlono[Instrume faifure te'date Include' sta obts,ned
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'20 RCIC Steam Supply Once/ shift Once/ quarter Once/ operating cycle Pressure 21 RCIC Steam Line Once/ shift Once/ quarter Once/ operating cycle
- AP (Flow) 22 RCIC Turbine Exhaust Once/ shift Once/ quarter Onra/operatingcycle Diaphragm Pressure 23 RCIC Suppression Once/ shift Once/ quarter Once/ operating cycle Chamber Area Ambient Temperature 24 RCIC Suppression Once/ shift Once/ quarter Once/ operating ~ cycle Chamber Area Differential Air Temperature
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d e m c r o r j e p e t l a s e e g i m l e t m t f n h c u v r l s a s i c n n l l a a y u d i o i a s o h h s m e r h s V e s r c s e / t o w ed v ev nt s p n : s i h t t/ a a p m e s e m t d a d n a o a it V a l l o C s D t s t r - f i d x i s V e p e c e s u e s a in e v m t e i, e n b t l e v l u h h t o e s o a l l a S l t w r rd.n si a n c c r u l l a t e I s r D m V p a a V g t n o a n r i e e o l l o h s l a e e n n S n n e m t i og rs t [r niis t a w t e n o iL i.t r io e t il o p c i n u u n in n c a oC
'R W r u i le a c t
n s e r e et r ru o t i t c g a mm a a W os t l y a E q f i o - s m n et e r n 'i m e c t u u s u p n iw SS w t I l t 7e e non i t r l a c n f o o t - d o S l e t s u n s i d o m n c t d w y f h t n t r i e l l in i a R u a y s o .dm- io a t t o a a e H h e r r S H D icg oep i 1 t d a s y f MM R R
- e s n i .
r n a d s e o rp oG i. cu h . . r h t a . . . . r T f S r i c t 1 2 3 4 S 6 7 l g r e r
. o or h o e r. _ L T r i
gg . c2
".rym o 1 1 l
.+ ,+ -m ^ -
/m p Table 4.2-2 5 Ched,' Functional Test, and Caiibration Minimum Frequency for Instrumentation Nr Which Ir.itiates or Controls HPCI
, Ref. Instrument Chec.k Instrument functi sal Test Instrument Calibration No. Instrument Minimum Frequency Minimum Frequency Minimum Frequency E 1A1 (b) ' (c) 1 Reactor Vessel Water Level Once/ shift Once/ mea %. +
Once/ operating cycle
- (Level 2) 2 Drywell Pressure Once/ shift Once/ mea u- p v W Once/ operating' cycle 3 HPCI Turbine Overspeed None N/A Once/ operating cycle 4 HPCI Turbine Enhaust Once/ shift Once/menth-
- Once/ operating cycle Prrssure c 5 HPCI Pump Suction Once/ shift Once/meath M Once/ operating cycle Pressure 6 Reactor Vessel Water tevel Once/ shift Once/mentA Q,ta M Once/ operating cycle g (Level 8) #
i y 7 HPCI Pump Discharge Flow Once/ shift once/ mea %. UCth Once/ operating cycle m N / HPCI dmergent f Area [ Mnte/ shift nCe/ month / Once' / operating cycli
/ Coo er Ambie Yemperaturie /
9 / HP,CI Steam upply Pressere Once/shvi Once/mo, h [ ,/ 04ce/opey#ating cy'cle
- 2. ' Dele 4ed.
- 9. Dele +ed y 10. 'Deleked.
C3. !k, D * *
?.
5A tz. M ehed. E
- 13. }eledtd.
m to M
.2
__ _ - ~ _ _ _ _ - _ _ - _ _ - _ _ _ - - - . - . - _ _ _ -
. . , ,j f ' ; ; l :, ij r
!1 ![ :! I tt( .! , t >!
3i l l ! . n o
,t i
t~ e" t o l e l e l e'
'l , ary cy cy cy bc c' - c in .
l e g- g g s g Cq au i n" i n i n i h t i n . e t t t t n t tr) a a a a o a nFc r r r r m r e ( e ep e p e p ep me p 3 t t o o o o y o . rs / '/ e
/
e
/ -
e r
/
e e ti e sn c c c c e c n ni- n n n n v n o - iM- d / O O O E O N e b n - a t' c M. s- p e-T' "
~ ih l r s a C e n n I o .
o # i c y i t iy=- f tc ne c a cn l n uu e" f g e r F ql oE nt i e eb - trI h h h h
- a n nF t t t t t r
- o e . n n n n e -
mm, o o o o /A p o
)
d u u-rm. / m
/
m
/
m
/
m N / m / o- t ti e e e e y e e e
't sn c c c c c c n C
( n o I ni. M, O n O n O n O n Mo n O n o. a-2 2, [ ~ t
- 2. 2 a3
- h . -
2 2 te. . l a s y. 4 ob . kc. sa e l e cn ee l e T h t h u. t t t t t b cn a Cq f f f f r a ni T e i i i i i T. e
'tr h h h h h s r nm is nF s s s s e / / / /' / o ee ms e e e e 'e e e f vt uu rm. 6 c c n
c n c' n n o c n n o s o ni ti.. 0 O O O N O N e cd t n sn. ni o r a N o iM f2 y2 l gf nfa o e sl ib _ a s a t r e r- ".T A^ A on Ni s r r [ ue ar eb r ~ bt ' e g b e . rm.
.s a m ee e
hu mt xs aa a/p r a re 'r Rt n Es hr h - r o h wo. " i. . i e Ce C u t C ot L er. p lt S Pt dn. nP nm naa ~-' nl n ee ltwe t. n. e. 6) m ew rg s be_ oe ite i iT oir snp el te iv av se oe Ico g M . it m to e Jr en ere st sem se sL Lr oe. te nb. t Sl nL e rr e r F pre ret e u t I( I p i pr dk pe lf d s C .Ca b prr nn pt Ci ne
- n. PP Pi m ii na ue Pa . mh HA HD SA A CT SW HF us I
5p/ lI ot
. cb a
et . hs Te ' f .y - eo, 4 5 6 . RNg 0-1 1 1 p3 1 1 1 1 a TMgx s gE g.to8,, 9 >b= e3+r 2O* NSf o tM j l !1 : , T
w-+,. ,..
-m
*O h, . ,Og h O, ,
Notes for Table 4.2-2 (tont'd) regttired when the Instruments are not rentsf red to be operabis or h b.t Instrteent rtenctional tests are not
--t a re tripped. However, i r rtenct iona l t.ests a re missed, they shall be verform**d prior to returning Q ' the Instrtament to an operable status. However, If C Instruments are not required to be operable.
- c. Ca l i b ra t ions a re not required when the
-4 calibrations are missed, they shall be performed prior to returning the Instrument to an operable
< j status, / /
r7- igure 4.1-1 dith an Interval or not less than one month
/ }
' Initlilly once per month or adcording to. /
/
'l f.. / / / rate data ma/ Incittde date'obtained
- inst lutmer,' ' fa i t ters/ / )
f t no/r/neore than / ihree months.'/ The p / compilaition i ns t rumen t ofra te s f ri an environevnt
<>i-e similar tolthat l l
I r/om other DWR's for whicff the same dysign / / / f j
/
/ data must'be /
l of IINP-1.
//The failure rate reviewed and approved Dy the AEC prpor to any change in the j
} ,
i/ oncr-a-mdnth f reqtrency. f Cl. D '?M C N CI. tests and simulated automat.f c ac+- e clon shall be performed once each operating . l_ogic system ronctional cycle for the following:
" 3. Diesel Generator initiation
- 1. HPCI Subsystem
- 4. Area Cooling for Engineered to
- 2. HPCI Sttbsystem Atito Isolation Safeguard Systems b
to incitede a calibratlon or time relays and timers necessary for lhe logic system functional tests shall proper l'tenctioning of the trip systems.
. ,a >
O r
Table is.2-3 r Check, functional Test, and Calibration Miniseum Trequency for instrumentation -
> ' Which initiates or controls RCIC O Ref. Instnsment Check Instrument Functional Test instrument 4 allbration Minimuis f requency Minimum Frequency Minimum Fr- v ency
, No. Instrument (c)
Ibl c [stl 3 1 Reactc r Vessel Water Level Once/shlft Orrs/montA dtr-[o# Once/ operating cycle
--4 (Level 2) 2 RCIC Turbine Overspeed Mo*ie N/A Once/ operating cycle Electrical / Once/ operating cycle Mechanical None N/A 3 RCIC Turbine Exhaust Once/ shirt Once/ operating cycle l Pressure Once/mentit- Q[L4GJ- k r 14 RCIC Pump suction Once/ shift Once/mont*e- M r once/ operating cycfe l Pressure g 5 Reactor Vessel Water Level Once/shCft Once/ - a+h Q4td. N r once/ operating cycle (Level 8) (
Once/ operating cycIe 6 RCIC Pump Ofscharge Fiow Once/ shirt OncefoontA g g d e
- Once/ opera ting 1Eycle .
7/ '/ RCICdmergengAres / Once/8hift
- once/ month Copler AmbientTemperdture / / / / ,/ /
/ / /
w
/l/
a
/ /
nciC stysm suppiy/ressure P -
/
- 0. nee / shirt Ode'/.onth / / Once/ ope re s s e., c3r/
cle t
~
t ,C v. O
- 7. 'b ele +ed .
% beleferl M
9 beJefed-
"g to ' Dele +e4.
m It 'beie+ect O . b a N
- - v m
_ .____ _ m _
.m an. .-= ===
c' < ) -
- N ?
.E,t _
e _r _r _C ro ., C=@ u a o o C C a b b ! k k T r hf o .. . , n . . EA w a u_ a m M
- * * = Q O O O 7
p= % % N h h e 9 t e L L
/'-
.C. u==C o C
'\W- -
c C e e gn C K O O E W W = N, SE
. G DC t D nM eb L-y
( Ql U C e a OO c
-. t .a. 46 L C 1, D. l m
f W .. C ML 1
.G. ~
~;
O g 1
.h W t J Q ,k'_ 5- e .L pC -Q -
a- a
~
=
r b s 9 2 f.r so 1 C @ ed .s
@ LL
-6 g 4 z e d- .J C e nke a L O aa a
C D O w C 9 C 0 a\e C 9 C D a h 1 1 I O i o CD 9 d= a E. H O *+ & A 9 ed % % mi N Na' \ N J$ e e 3 CO= @ e @ e e e e L == C ~CC U U ' O U C m= 1 I
= 3= C C C C O O
- O
& 6E O O '
O O 4 m er
@ N "$ y" U
\ d
- yn @y h
(. ,. N h
~ -
e
-1 Om e CD a
e x8 v se
~ N.
a e m ,e- -ee M &D M 9 6 e OC Om a ue w e u . C-e _ _ _m _ - . t =.
< 2 e em e e a - . ,
C@ e Cw 'm. e e JJ 3
.9 ss. s.
Q N. U C C C e L
.C .E
>- cm C=
eu 3 C C C O O O O O e a= WC O %'Nh O z z z w on ts a C b C= m L. Ei m.
%w ~
- O 8m. w- 5" Ca
. [$. Om i
x N) \
~N N
\
m=
== A
. C" coe CW WN e se e #3m g sg Lb
< < N $C b
, a 4 L
x- mba M C m Le .m u .e o sc &L m o 6 g mL as a en La ole As Ea E6 .L e - et +a e a i L i@ Xe ee e- L L O E& .
>0 M LC We 4L K< 0 0 0 8 - -O m e Qc y a *a 8. s C C .J -
@G a =. - to VC C e
= CA CE CeO C C= . DO O
- E =
O@ C=6 00 C= 00 =@ = 0 em DE p= ~93 ~K MG => M) M S as C O mW O *
. m'No.&.
@ Cn u3 m O e .>
m ma =o d. Co. t m- .=L
-L e si. .s2 Ce mec
= .C s 26 m o EC. Lee ., w a.
u as a u- mx aa ,e ae
-u a-o
.a no awa om ze ==. -o= . C O C. se e.
ac --E CL {- E< EQ W< 60 0 W E6 UN M 3: 3 _m gWW N 82 2** d
=n N cm 3 "". CLt
&G =OS
*n Ch O **
N \ M *
.r a * *
,O e - - - - - a n HATCH - UNIT 1 3.2-31 ' Amendment No. 101, 121
31 M ? " or m m * ~
*~' "., .m Table 4.2-13 % 4 Check, Functional Test, and Calibration Minimum Frequency for in67..'tWtJtion Q Which initiates or Controls ADS Instrument Functional Test Instrument Calibration Instrument Check Minimust Frequency Minimum Frequency C Ref.
Instrument Minimum f requency Ibl (c) 2 No. Q Lal Once/ operating cycle Once/ shift once/ mons!w
~ 1 e r essel Water Level Once/opersting cycle Once/ shirt once/montb Reactor Vessel Water Level (Level 1) Once/ operating cycle Once/ shift Once/=aa*h 2 Drywell Pressure Once/ operating cycle Once/ shirt Once/monttu 3 RHR Pump Discharge t Once/ operating cycle is Pressure CS Pump Discharge Once/shfft once/=aa+h gM M y
Pressure Once/ operating cycle None N/A 5 Auto Depressurl2ntion Lov Water Level T imer Once/operetIng cycIe Hof e N/A 6 Auto DepreasurIzatIon . Timer None w Notre Once/ operating cycle g 7 Automatic Blowdown e Control Powe r F a i lure W Monitor w Notes for Table 4.2-4
- s. The column entitled "Rer. No." is only for co tvenience so that a one-to-one relationship can be established between items in Table ts.2-te and items in Table 3.2-13.
O. a to 3 c+ 2
.O N
be N
~
.- .+
4
,.M %. % d ;-
. ti I'
O, , yy .
.~ .
e p- - .
' l r
Table 4.2 'N Check, Functional Test, ' e nti Calibration Minimum Frequency for Instrumentation .
. Which -Init.f ates or Controls .the LPCI Mode of RilR
.j .
~
Instrtement . Cal t hrstion
- . ; Instrument Famctional Test Re r. Instrtunent Check -
Mlnfmum frequency Mo. Instrument- . Minlansa Frequency ~ Minimum Trequency
.c (b) tel' laj .
. 2 R ac r essel Water Level Once/ shift l.Once/ month- Once/ operating cycle.-
1 L2 DryweI I - Pres sure . Once/ shift Once/meath- r~- 'Once/operntIng cycle' g . 3 c3, Reactor Vessel Steam Once/ shift
~
Once/ month- u
@ .F Once/ operating cycle '
Dome Pressure
-->= P' Reactor Shroud Water Level 'Onse/ shift Once/ : d Onc ;/ operating cycle .
as (Level 0) Once/ Operating cycle Mone, 5 LPCI Cross Connect valve- None. Open Anntenciator ; < . k RHR (LPCI) Pump Flow' One:e/shi rt Once/;;.-2 # Once/ operating cycle 6 RHR (LPCI) Pump None N/A Once/ operating cycle La 7 m Start Timers Valve Selection Timers N/A Once/ operating cycle 'g
, h 8 Mone .
t 9 RHR Relay Logle Power Moete Once/ operating cycle Mone- , . . , . f allure Monitor - . e
-b. TheVesej 6+ earn Deme Pnewure.
on(EAMW Once/p
- Once/opern4i*} qcle .
j g e
- i t
C v
.(*
2 l . b
.N ?
e. r 2
- l>
sS . Lt N ..' 6* >
. I
) . j
- - - , _ . , _ u. . _ , .
.- . - . - , . . .u 2 - - . .
- 4 Table'4.2-6 E- g Check,' Functional Test, and Calibration Minimus Frequency for instrtsmentation -
d n which initiates or Controls core Sprey. I Ref. Instrtteent Check ~ Instrument-Functionel Test - Instrtunent Calibration - e Mo. Instrument Minimum Trequency' ' Minimum Frequency. Minizian Frequency c lal fbl Id 1 .Re r esse t " Wa ter Level . Once/ shirt .Once/ month- M - Once/opersting cycle
*w W
2 Dryve 11. Pressure Once/ shirt' Once/ month- Once/operstIng cycle . l, 3 - Reactor Vessel Steam Dome Once/ shift' ~ Once/ month-cZtA M ' Once/ operating cycle - , Pressure f- . Is " Core Spray Sperger Once/ day' M/A ;. (- Once/ operating cycle Di f ferent ia l Pressure 5 CS Ptep Discharge Flow Once/ shift ' Once/montb- (fa & Oncv/ operating cycle 6 Core Spray Logic Power More- Once/ operating cycle Mone , Failure Monitor
- i. .
Notes for Table 4.2-6 I F s. The column entltled "Ref. No." is only for cenvenience so that a one-to-one relationship can be i N [, established between items In Table 4.2-6 and items In Table 3.2-6. m ., t g .
. o 4 O.
i # ' 4 2 5' O
~
G W N i . a
- - _. , - a .
9 y 1 4r*-y,,v-r w w. + - gi-L .We - ogr.e xe
i, 7-Table 4.2-7. , Check, Functie.nal Test, and Calibration Miniane Frequency -for
'h Neutron Moritoring Instrumentation Which initiates
'y
- I; Control Rod Blocks 8
Pe r. _ .Insteoment check Instrument f~unetione1- Test ' Instruertnt CaIIbratIon .. c-- No. . MInieta Trequency Minime.m Frequency Minimun Frequency , j; 2 lal instrument (b1 "fel id) 1 - SOURCE RANGE MONITORS
. W.
a.- Detector not full in iNA 'S/U, W- MA-
- b . '- Upscale- NA- : S/U' ' ', . W R
- c. . . Inopera tive -NA :S/U, W NA -
" d. Downscale NA- S/U, W R 2 INTERMEDIATE RANCE MONITORS
- a. Detector not fulI in .NA S/U8, W' . MA
- b. . Upscale NA S/U, Wi=8 R
- c. Inoperati ve NA S/U nA'
- d. Downscale 'NA S/U, W
, W' R 3 -APRM a .' Ficw Referenced Simulated .
, . Thermal Power-Upscale MA- S/U', Q R N b. Inope ra t ive NA S/U 8 , Q MA 1, ' c. Downscale .- "NA S/U, F Q R o d. Neutron Flux:- High,.127, NA S/U, Q. R !. 4 ROD BLOCK MONITOR.
- a. Upscale: NA. ~
S/U, Q R-
- b. Inope ra t ive MA S/U Q MA ..
- c. Downscale .NA S/U' ' ',, Q R 1
5 SCRAM DISCHARGE VOLUME
- a. Water Level-High NA Q R R.
3 C1.
$ Motes for Table 4.2-7 3
r+ 2 a. The column titled "Rer. No." is only for convenience so that a ore-to-one relationship can be established o between items in Table is.2-7 and items in Table '3.2-7. - b se
- b. Deleted.
. II e
n w v- w w' ..w- V, v.
- u .~ - .+. , , ,. -. - .- -:----__v_.-.__.
C O Wh m ) e n .t!
~3 &
C C & C
= tr a e a a se '
gg C C C C C "I
-E R R 8 8 8 %-
Cg M M es M M
!5C D.
D
. D. D. D. )
W~ > > > > > WE W W W W W C
= @
e 6 e C @ 3 #
-[
- e c 3 a
- E i
= o. 3 e 9 a . w Dt > = D G b E e k 6m -h a G Oe aU C D O be CC a O a w
~ ON b = 0 p@ =3 w w L vE dU e O O C UG X - b =
@h CL e m L
6 3 ed 3 6 *= = = = == m O 4 p-9>
- e. O w
b w b w w w b w %
) e w
t b= 4 i , , t 9 C V e w sa C em m me w O g g i O O- G G e $ e 6 6 ga gC w w w w 0 - O
=0 b d 3 w i E- gx 4.-
[e y}
.. e a w .
=D d } 4-:
C e e e I Ce W G. C b a '
-E C 74 cd 4 c o e c E - C kJ e c & O
- 1 e
N C-W % y . .,g: ~m s sh. N. eg e N C O a
- OE A s
[ 2 9 s n ~~w =J - > ?l4 9) a m e 6 . i; e a AJ d y d.h-O 4
-
- e e .m eg
~ un D DU Xh
. U- .Q D e O D e m ~- UU s= @ e a h
& -G *@ QC & C o MA L c e 4 U ..O3 0 0 C g w e 7 s C = VE +8 e >n . >a h h U
- Ce Cbe a es e a m = .Cw .a g e ed C6C V T U V e C E . m e
# B-w % % % % & @ @ C e
+J M w
Cb- h C O C C C O O e E ad E am CS = 0 0 C C E o V e eC CC b C e m6
..a== su
=b Z O d e ao 6 e Cw e. C e O- A N. g 4
-C - u
*a 0 C 2 ) @
uz O z C G% U a e - ai .. w - a G a se d e - C 3
. +8 W m et > 3 q) *a X d WL 3L s. y a en .
O C 0 e O C e ~ ad i e a w -- 4 Oa E s== 6 C e c I m= x- e s . O da XC WC 4W W = W *a e e eL WO O se 6 6 6 C -
@0 b *a L E CsE C
*a o C *a cw o
E e E O C - A no
>= 0C =C -= C= 3 = g h 6 C OO Do C -C k. ~ G JO -= == EO IO V C e a eZ 6 *a -e OE E o e b
. O d C e 3e O E - O #
C &C @= c- EC eC +4 ) M JC U S
> e C
n
@ O CV D 0 00 -
E a= =m L es = = = 4- +J e c e 3 eW -K O *J M *& C 4 4 p
)
.O 6 pe e .C4 E 6e a p 0 a
. *J e *= *W QM .a = C- V Z W bV hC eC CV =T C @ *J M C be &O eO O es e5 e E 4 C C
- QE E> E> QE %E 3 W @ * @
= g V E o ae aC a s a3 0
=O -
e na e -a m I # C L C g e 9 == & = , b .= 30e ** N m 2 an *
- E E m= en D HATCH - UNIT 1 3.2=42
,R 7 D &
flotes for Osbie 28.2-8 (Cnnt'd) I c. Instrument rttnctional tests att not regteired when the instrtiments are fvot reqtif red to be operable or a re t r i pped . Iloweve r, ir instrument rimetiona2 tests are missed, thsy shall be performed prior Nx 3 to returning the instrument to an operable star.us. I ns t rument ca l i b ra t ions a re no t required when the instrtments a re stot regteired to be operable or are E d. tripped. 110weve r, ir instrument calibrations Are missed, they shall be performed prior to return- I ing thee instrttment to an operable stattes.
)
d initially once per month or sedrding to rigtar5[ts.1-1 with an int al or not les than one
/ The compi/at. ion or instrumen railure rate da a may include month nor . ore than three mo#ths. /
/ e s-eme design ins essent operates n an environmen data ob,tained f rom other " JR's for which /
ed by the AEC rio r r to that of'ifNP- . The rallure r te date stest be releved / and app sim/i t ri ar'd_ Change in the nee-a-monMLIIC2L'CDCY This instrtmient f. This instrtementation is exempted from the i ns t rtunent reinctional test definition. O.MC
- f ttoc t i ona l test will consist or injecting a slettlated electrical signal into the measterement channels, Calibration sesing a
- q. Standard ctarrent source used which provides an instrtement channel a l igrimen t.
radiation source shall be made once per operatlng cycle. n w togic system f'unctional tests and simulated sittomatic actuation shall be performed once each operating cycle for the followins:
- 1. Secondary Containment Actuation 1
1 O f y-
~
Q. _O . [R _ l l l Table 4.2-9 r I 3c> CHECK ADO CAtlBRAf t04 MINipRNt TREQUENCY TOR IN$iRtf(NTATION '- WICH INITIATES RECIRCIA.ATION PtMP Trip i x 6
.e Ref. InstrumeFt (heck Instrument Functional Test Instessment Calibration
.c No. Instrument Ninimum Trecisency Ninimum freq.sency Minimien fregasency z fal M
1 Reactor Vessel Water tevel .Once/ shift Once/ month-- Li F M r~ Once/ operating cycle - l
.(ATWS RPT)'** -
~
2 Reactor pressure Onces hift' Once/ mon 4A-- Q44dr-ff f' Once/ operating cycle (AiwS RPT) (
~
) nta og'togic. None Oncefx1"i None b) Breabers None Once/operatindcycle Non c) Response Time , None None Once/ operating cycle RPT . logic + Breaters"'
Y
?as Notes for Table 4.2-9 v'
(a) The column entitled "Ref. No." is only for ConveilieCe so that a one-to-one relationship Can be established between items in Table 3.2-9 and itees in Table 4.2-9 (b) An Afw5 recirculation pump trip logic syst
- functional test shall be performed cace per operating cycle.
(c) The EOC-RPT System Response Time shall be tha. time interval from initial signal generation by the associated turbine stop valve limit switch or from when' tne turbine control valve hydraulic control oil pressure drops below the pressure switch setpoint to templete suppression of the electric arc between the . fully-open contacts of the recirculation pump circeit breaker. The response time may be measured by f 3 any series of sequential. overlapping. or total ste'ps such that the entire response time is ca. measured. Each test shall include at least the loqic of one type of channel input, turbine control Q valve fast closure or turbine stop valve closure, t.uch that both types of channel inputs are tested s at least once per 36 months. . The EOC-RPT System Retsponse Time acceptance criteria associated with r+ turbine stop valve c10sure shall be K 155 millisecteds; the EOC-RPT System Response Time acceptance , 2 criteria associated with the turbine control valve fast closure shall be K 175 milliseconds.
?
~
Th 1 hM tha
. ~w
~
e$ On 43 g..
T 4 Tcblo 4.2 2 Check, functiona l . Test,.' and T* Ilbra tion Minimum Frequency for instrumentation - 3m - Which Mon 1rs Leakage into the DrywetI' E ' Instrument Check' Instrument Functional Test Instrument Calibration; '
' Rer. No. . Minis' tem frequency Minimum Frequency Minimum Frequency:
ta) Ins t rument tbl fel idl c
$ g 1 Orywell Equipment Drain
. Sump Flow integrator Occe/ day top C 1ce/ mon 4h 'Every 3 months 2-i Dryweli Floor IPs 8n %sep Flow Integrator Once/ day (9) % m ot 1 Every 3 months 3- Scintillation Deteetor Orce/ day .(e) hvi M 'I Every 6 months for Monitoring Air Partic-lates 4 Scintil tretion Detector .
for monitoring Radiciodine Occe/ day .(a) b MO t , Every 6 months i 5 CM Tubes for Monitoring Noble Cases Occe/ day (t) bWlGfMCtM . .Every 6 months l Notes ' for Table 4.2-10 i I
- a. The - coltten ent i tled "Ref. No." is only for convenierce so that a one-to-one relationship can be established betweto
' items ir Table 4.2-10 and items in Table 3.2-10.
eu b. Instrument checks are not required when these instruments are not required to be operable or are tripped. However, E i f' instrument checks are missed . they shall be perfor1med prior to returning the ' instrtement to an operable status. ' m
- c. Instrument functional tests are not required 'when the instruments are not requi red to be . ope rab le or a re t ripped. - I Howeve r, en operable status.
if instrument functional tests are missed, they shall be performed prior to returning the instrent to
- i l
t i [ t t l $ \ . O. . a t et r . I O i-l 'Jh 'I ro I [ v - _ v V
._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _______ _ s
~- ;m, p
~~
Notes for Table ts.2-10 (Cont'd)
% d. Instrument calibrations are not required when the instruments are not required to be operable or N' a re tripped. However, if instrument calibrations are missed, they shall be performed prior to I
returning the instrument to an operable status. ing to Figure 1.1-1 with an interval or t less than 8ne month a 8 [ Initia ly once per onth or acco H re than thrtye months. Th compilation or instrtement railure rate d ta may include data nor ; ostAned < rom oder own's ror,unich the sa design instri nt operates n an enviro [nt similar f or to any t tha t o f HNP . The failure rate data artst be reviewed and approved by the AEC p j
/ change in thy once-a-month f requency.
e w e+ea. N I s 4
Table 4.2-14 . CHECR, FUNCTIONAL TEST, AND CAllDRATION HINIHUM FREQUENCY FOR INSTRUMENT AT IOff T WHICH ARMS THE LOW LOW SET S/RV SYSTEM - n T lestrtement Functional Test ins t rument Ca l ibra t ion Raf. Instritment Check Minimum f requencyt
- 8 Minimaem F requency* * *
, Minimum f requency No.1*8 Inst rtement Once/ operating cycle c
Reactor Vessel Steam Dome Once/ shift Once/mont4- mt -ICr 3
-4 1
Pressure Once/ operating cycle (e) Relier/ Safety Valve Tailpipe N/A Once/ month (d) QUDLhNCF l 2 h Pre s su re . e is only for convenience so that a one-to-one relationship can be estabilshed between
- n. The column entitled "Ref. No."
items in table 4.2-14 and items in table *.2-14. b. Instrument functional tests are not requered when the instruments are not required to beinstrirmentoperable or to are tripped. an operable 63 However, if functional tests a re al ssed, they shall be performed prior to returning the
- status, If cellbrations Jn a
- c. Calibrations a re not required when the instrtements are not required to be operable. Howeve r, g a re missed, they shall be performed prior to reiturning the instrument to en operable status.
d. See section ti.6.H.1.e.1 for exceptions to this pressure switch functional test frequency.
- e. See section 4.6.H.1.e.2. .
S m CL 9 o i 3 i et
- 2* ,
i O t a O* O.9 M V y v-
Vy )fk
.Y nh.
dt g o M$l$ f ek LIM 111M cDND111DNi IOR OPIM11DN 3.2 $01[CT10N,,1M51RLMENTAT10N e in addit,on to the Reactr.r Protection System (RP5) instrumentattor which in- [ ' ,Hf f et4 tttates a reactor scrat, protective instrumentation has been provided wntch
' d o)*' E 9 4
6 inttlates action to sittgate the conseguences uf accidents which are beyond the operators ability to control, or teretnates operator errors before they , result in serious conseguonces, lhts set of Spectitcations provides the lip.
,h..!2J I , r( 3 & .y 3J iting conditions for operation of the instrumentation which initiates react m ea6et-en: FWy astetweent isolation, l # 0 (a d k (b wttch initiates or controls the core and containment cooling systems, which intilates contest rod blocks, (d) which initiates pr$tective action.
f,j8 d <$
$d (c
Le which snonitors leakage into the drywell and (f) which provides survet).
!+E -Ia2
- d. Lance inforsation. Ire objectives of these specifications are (t) to assure the effectiveness of the protective instrumentation when required by preserv-0 Ibov .3 - ing its cepability to tolerate a single failure of any component of ruch sys-l } $
- j 'Lm test evte during pertocs when portions of such systems are out of strytce for aetntenute, and (11) to piestribe the trip setttngs required to assure ade- -
gg 3 Quate pen orsance. When necessary, one thannel may be made 1.W ie for IL),j ')j 3 ,,o brief intervals to conduct required fur.ctic v l test? l w"
- L 6 -
wv t o m m%. I A. MLent.D181DL.VAltidfdlittiLbeter Vusek,r, Containmed '.d calibrations. i # o1 f7 4 y h u a... M M .u. d' - Primary 1I k I \i'-t ,j j y { % liolation (lable Lhil d 41 , Isolation valves are insta.lled in thute lines which penetrate'the primary con-s tainment and must be isolated during a lost--of-coolant accident.60 that tha-s .1) vj .f l u dtation dose limits are not-exceeded during an accident cone ttr% Actud _l+).T
.- i v ! tion of these valves is initiated by protective instrumentation shown in Table a l 3.2 1 which senses the conditions for which isolation is required. Such in-strumentation must be evallable wheneer primary containment integrity is re- ,dj g yJpe[,, %t C
f quired. The objective is to isolate the primary containment so that the guidelines of 10 CFR 100 are not exceeded during an accident. The events- [ $ *' )c, J, when_isolettennis required are discussed in Appendia G of the f 6AReihe-dg 4 tastrumentation which-inttistes pris.ary-syssee-tsolation-ts connected in-4
) J t k 4 vel-bus- arrangement ,
s ,0 J O T 1. Featter YesstLygtr..Leve}
}* 9J Lhe g p i "
- 4. Etitignyyggl,,yger level low flevel 3) (Harrow Ranoei l- The reactor water level instrumentation is set to trip when reactor water level is approximately 14 feet above thL too of the active fuel. This level is referred to as Level 3 in the Technical Speci-fications and corresponds to a reading of 0.0 inches on the Harrow l Range scale. This trip initiates Group 2 and 6 isolation but does not trip the recirculation pumps.
- b. Et.tdor Yessel Water Level low tt.w flevel 2) 1he reactor water level instrumentation is set to' trip when re. ..wr
< water level is eeproxtmately 9 feet above tt.e top of the active fuel, this leveI is referred to as Level 2 in the Technical Spect-fications and corresponds to a retiing of -47 inches.
. This trip initiates Group 5 isolation, starts the standby gas treatment system, and inittJ ss secondary containment isolation.
~
r V O I ' i HATCH - UNIT 1 3.2-50 Amendment k i. " 4G), 424, !?3 i
e BASES FOR tlMITING C0901110NS FOR OPERA 110N 3.2.A.7. Main Steam 8,ine funnel Temperate
- Hiah (Continued) .
vith the - int small release of radioactivity, gives isolation before the guidel' n 11 s0 CFR 100 are exceeded.
- 8. Iteacto. .datur Clean _go System Dif f erential Flow Hich 1 *
)
Gross leakage (pipe break) from the reactor watgr' cleanup system is detected by measuring the dif f orence of flow entering and leaving the system. The set point is low enough to ensure prompt isolation of the cleanup system in the event of such a break but, not 50 low that spurious isolation ran occur due to normal system flow fluctuations and instrument noise. Time delay relays are used to prevent the isola- , tion signal which might be generated f rom the initial flow surge when the cleanup system is started or when operational system adjustments are made which produce short tern transients.
- g. Rt E. lor Water Cleanuo Area Temocrature Hioh and 10 !LtE.1Art Water Cleanuo Area Ventilation Differential Temocrature Hioh Lenkage in the high temperature process flow of the reactor water cleanup syswe external to the primary containment will be detected by temperature sensing elements. Temperature sensors are located in the inlet and outlet ventilation ducts to measure the temperature difference. Local ambient temperature sensors are located in the compartment containing equipment and piping for this system. An alarm in the main control room will be set to annunciate a temperature rise corresponding to a leakage within the identi-fied limit. In addition to annunciation, a high cleanup room temperature will actuate automatit -isolation of the cleanup system.
- 11. Condenser Vacuum low The Bases for Condenser Vacuum Low are discussed in loe Bases for Spec.i .ca-gd tion 2.1.A.7.
yQ B. Instrumentation Which Initiates of Controls HPCI (Table 3,2-2)
- 1. Reactor Vessel Water level Low low (level 2)
The reactor vessel water level instrumentation setpoint which initiates HPCI is t -47 inches. This level is approximately 9 feet above l the top of the active fuel and in the Technical Specifications is refer- ) red to as level 2. The reactor vessel low water level setting for HPCI system initiation is selected high enough above the active fuel to start the HPCI system in time both to prevent excessive fuel rud temperatures and to pre-vent more than a small fraction of the core f roa. . hing the temperature at which gross f uel f ailure occurs. The water levei +" 4 aa **8" snough belev normal levels that spurious HPCI system startups are avutoed.
)
- 2. Drywell Pressure Hiah The drywell pressure which initiates HPCI is 1 2 psig. High drywell pressure could indicate a f ailure of the nuclear system process barrier. This pressure is selected to be as low as possible wMhout inducing spurious HPCI system startups. This instrumentation ser- I ves as a backup to the water level instrumentation described above.
Amendment No. JJ, /M 121 HATCH - UNIT 1 3.2-52 l
" als/st4.T b" l1. Dr.g iin EAdieMon , ssihtm bespwL Il (* 0 e 4. es r'es s ket k-hf Js4 p e,s% (b l\1 A/ [h, l P er}t
- e I v t* % A lvt3 W A d**** kt'd) 8.f tlf k bl M*Im% !
4,tg c%4..memt am bup W fr* a. kN
- J 4* 4 4A . t w.ew a cM ,
f), t', etPtf taereenev Area teeler &dient Tsentrature L: inh , l Migh adtent teasereture in the NPCI eevipment team near the emergency a*ea teeler tev18 indicate a break in the NPCI system tur$1he steam 11pe. The auteestic closun of the NPCI steam line valves prevents the on-tessive less of reatter teclant and the release of significant amouets of
- radioactive esterial from the noclear system process barrier. The hiph temperature setting i 161'F was selected to be far enough above enti-tipated normal MPCI system operetten41 levels to aveld spurious isolation but Iw enough to provide timely detettien of MPCI turbine steam line brook.
lj p.' MPti steam Sunely Pressure L2r tw pressure in the NPCI stetis line seuld indicate a break in the NPCI l steam line. Therefore, the NPCI steam line isolation valves are auto- l natically closed. The steam line low pressure function is provided 80 in the event that a gross ' rupture of the NPCI steam line occurnd up-stream from the high flow sensing location, thus negating *.no high flow .' indicating function, isolation would be of fetted on low pressure. The alloweble value of t,100 psig is selected at a pnssure auf ficiently
*~
higfienough to prevent turbine stall. 45 W. NPCI Steam Line AP (Flow) Hieh HPCI steen line high f1w sould indicate a snak in the MPCI turbine l steam line. The automatic closure of the NPCI steam line isolation valves prevents the excessive less of Matter coelent and the M1 ease of signi-ficant amount of radioactive asterials from the nuclear systes process t,a rrier. Upon detection of HPCI steam line high f1w the NPCI tureine steam line is isolated. The high steam flow trip setting of 3035 f1w was selected high enough to avoid spurious isolation, i.e., above the high steam flow rate eitpuntend during turbine starts. The setting was selected low enough to provice tiegly detettien of an HPCI turbine steam line break. II,49'. MPtf Tuttine tuhaust Dianbraem Pretture Hinh High pressure in the NPCI turbine e haust could indicate that the turtiine retor is not turning, thus allowing reactor pressure to att on the turbine enhaust line. The NPCI steam line isolation valves AM sutenatically tiesed to prevent everpressurization of the turtiine eaaust line. The tuttine on-haust diaphragm pressure trip setting et < 20 psig is selected high enough 9 to avoid isolation of the NPCI if the turfine is operating. yet low enough
- to of feet isolation before the turbine exhaust line is unduly pret. urised.
Sueoression than6er Aree Ambient Temperature Hinh , A temperature of 16t'F will initiate a timer to isolate the NPCI tur$ine steam line. . o s
# ' - - * .---m ..w-- m. _ , . ,
,m
_ ~ . l . .. . Z W 3 N X Y (J o 't.) e 3.3. .h. I erettien Chasser area tif f enettai sie fencerature Wish A dif f orential air teaterature greater than the trip setting of g AP'T i between the inist and outlet ducts which ventilate the suppression Chamber i i area wi)) initiate a timer to isolate the NPCI turtlee Steen line, ,
/*ld Stit toertenev Area teoier Ambient Teneerature With High ambient temperature in the RCIC equipment rose meer the energency area tooler tou)d indicate a break in the RCIC systes turtine steam line.
The automatic closurt of the RCit steam )ine valves prevents the estes-sive less of reatter toolant and the rtlesse of significant amounts of radioactive material f rem the nuclear systen prettst barrier. The high
- temperature setting of 1169'F w.9s selected to be 'er enough above anti.
cipated norm) RCit system operational levels to avoM spurious isolation but tw enough to provide timely detection of a RCIC turMoe steam line break.
- 2 44' Rtit steam Sueciv pressure tw Lw pressurt in the RCIC steas supply top 1d indicate a break in the RCIC steam line. Therefore, the RCIC steam supply isolation valves are auto.
matica11y closed. The steam line tw yessure function is provided so that in the event a gross rupture of the RCit steam line occurred up-stream f ree the high flow sensing location, thus negating the high flow indicating function, isolation would be effected on low pressure. The iso-lation setpoint of 3,60 psig is chosen at a pressure betw that at which the RCIC turbine can effectively operate. , CI., Rett steam time f Ap) rios With RtlC steam line. turbine high steam f1w could indicate a break in the RCIC
. prevents the excessive loss of reactor toelant and the release of signifi-cant barrier.
amounts of radioactive materials f ree the nuclear syste The high steam f1w trip setting af 3065 f1w steam line is isolated.
- was selected high enough to avoid spurious isolation, i.e., above theThe setting was high steem (1w rate encountered during turtine starts.
selected tw enough to provide timely detection of an RCIC tuttine steam line break. N. Bt1C Tnebine tuhaat Dinebrao* pressun Nish High pressure in the RCIC turbine exhaust could indica The RCIC steam line isolation valves are automatically The tur-exhaust line. closed to prevent overpressuritation of the turtine exhaust enough to avoid isolation of the RCit if the turbine is operating,ly pres-enough to of fett isolation before the tur$1ne exhaust line is undu surited. p
, 11 11 yn ts_ssion'thamber Area Ap+1ent Teeeratur M L ,h 6.. -
115g'f will initiate a timer to isolate the RCIC turbIn N. Sueeression Chamber Area Dif ferential air Towerature Wish l-whitt, vent 11ste the suppression chamber area wil) initate isoiste the RCit turtine stata line.
-~.; - ~ , , - . - - , . . - - - -r, .-rw,- .-,n,-
BASES FOR LIMITING COND1110NS FOR OPERATION - ( 3.2.B.3, HPCI Turbine Overtpfff The HPCI turbine is automatically shut down by tripping the HPCI turbine , stop valve closed when the 5000 rpm setpoint on the mechanicel governor is reached. A turbine overspeed trip is required to protect the physi-cal integrity of the turbine.
- 4. }LPSI P Turbine tyhaust Pressure Hich ,
When HPCI turbine exhaust pressure reaches the setpoint (i 146 psig) the HPCI l turbine is automatically thut down by tripping the HPCI stop valve closed. HPCI turbine exhaust hijni pressure is indicative of a condition which threat-ens the physical integrity of the exhaust line.
- 5. HPC1 Pumo Suction Pressure Low The pressure switch is used to ottect low HPCI system pump suction pressure and is set to trip the Hs! turbine at 112.6 inches of mercury vacuu. l This setpoint is chosen to prevent pump damage by cavitation.
- 6. Reactor Vessel Water level HiQ (Level 8)
A reactor water level of +56.5 inches is indicative that the HPCI system has performed satisf actorily in providing makeup water to the reactor vessel. The reactor vessel high water level setting which trips the HPCI turbine is near the top of the steam separators and is sufficient to
, prevent gross moisture carryover to the HPCI turbine. Two analog dif-
,f ferential pressure transmitters trip to initiate a HPCI turbine shutdown.
' HPCI PumD Discharge Flow Hiah l 7.
To prevent damage by overheating at reduced HPCI system pump flow, a pump discharge minimum flow bypass is provided. The bypass is controlled by an automatic, D. C. motor-operated valve. A high flow signal from a flow meter downstream of the pump on the main HPCI line will cause the bypass valve to close. Two signals are required to open the valve: A HPCI pump discharge pressure transmittar high dif forential pressure signal must be l received to act as a permissive to open the bypass valve in the presence of a low flow signal from the differential pressure transmitter. I ff9.lO
- Because the steam supply line to the HPCI turbine is part I,
of the nuclear system process barrier, the following con-ditions (8-13) automatically isolate this line, causing shutdown of the HPCI system turbine. lM,
*P. E=: cenet 4: C: he-Ambient-Temperatur+-Hieh-
- 8. 'Dp!- l HitHmbient-temperature-in-the-HpCI-equipment-room-a+4r th: :- ~;;^r y teta-eeeler-tould-4ndicate4-break *a the uPCI t ytt- wre4ae4t+6m.11ae.
The-estemat4e-+4e:gr: Of th: "PCI :t:: ' h: v:h:: ; : :nt: th: ::- tet*4+e-les: Of rea:t:r-Mo44nt :nd 05: r:h::: Of-64;nh:nt := .t: Of-
+444+4et b; :t:r1:1-feem-the-nut 44ar-+ystem-prete5S-beer (ee,---The-h4th -
{ 3.2-53 Amendment No. IM , 121 HATCH - UNIT 1
a. BASES FOR LIMITING CONDITIONS FOR OPERATION T> ele 4ccl . ) 3.2.B.8. WM4-4meetenev "u - C004+e4mb4+nt-T+mpuetur+-444eh4&ent 4*oedh I t empe ra t u re-s e t t i ng-6-1698f-wa s -s e l ec t ed-t o-be-f e e-e nough-e bove-e n t i-
+4pate4-norma 44#41-system-operational-4+vels-to-avo44-spsr40us 4 solation-
+vt-low-e nough-t 0-pr+v 4 de-t 4 me ly-4 e t e t t (on-of-H pC l-tu rb 4 nea team-14ae4re a k, ,
)
j l
'pe1
- 9. HM4 el-ecd .
Steem-Gueelv-Pressuee-t+w-t+w-pre s s u re-4 n -the-NPC l4 t eam-44ne-could 4 nd ic a t e-44 r+a k-4n4he-HpGi-s t ea m -l i ne r---T h ere f o re rt he-HPGl-s t e 3 m-14 ne-4 sol a t 4en-va lve t-a r+-4uto- ] me t ic a ll y-c l o s e d ,--The - s team 44 ae-4 ew-pre s su re-f unet t on-45-p rov id ed in4he-event-that-4-9ros5-rupture-o(-the-MPCI-steam 44ne4ccurred-up -
+tream4 rem-the-high-flow-sens4ng-locationr -thus-+egating-the-high44ew-4ndicating funct4 car 4 &o44 tion-would4e-e f4+c ted-on 40w-p re s s u rer--The-e44ewable-value-of-t400-pt49-45-seleeted-4t-49resture-suff(c 4ent4y Mg h40-prevent 4urbineatall .
- 10. HPCI-6 team 44ne-ep4flowH44eh-MPCI-steam-14ne-high410w-could indicate-4-break 4n4he HPCI-turbine s t eam-14 ner--The-e ut oma t4 c-closure-o f-the-HpC4-s t eam-44 ee-4 s ola t i on-va l ve s-p re v e nt s -th e-e x c e s s i v e 40 s s-o f-rea c t o rd oola nt-a nd-t he -re lea s e-o f-s i g n b f i c a n t-emou n t-o f-rad 40a c t 4 v e-ea t e r i a ll-f rom-t he-nucle a r-s ys t em-p roce s s-ba re4 er,-Upon-detec t ion-of-NPC I-s t eam -14ne44gh-f 4ew-the-NPCI-tu rbine-
, s t eam -44 ne-45-4501 a ted r---The44 g h-s t e am 440w-t r4 p-s e t t4 ng -o f-403 bf4 ow-was-selected 44gh-enough-to-avoid-spur 40us 4so34 tion v 4,en-4bove-the -
high-steam-flow-ra te-+ncoun t e red-d uring-t u rbi ne-s t a rt s ,-The-s e t t ing wa s-s ele cted 4 ow-e noug h-to-pro vide-timely-d e tection-of-a n494bturb4 ne-steam 44ne4reakr 1$. du sEnhaust-MaphragmJressure H4ch-H i g h- pre s s u re-in-t he-HpCI -t u rbi n e-e n he u s t-cou l d-i ndica te-t ha t-the-tu rbi n e re t or-45-+0t-t u rn ing ethus-4440 wing-reactor-pre s s ar4404c t-on4he-turbine-e x h a u s t-14 ne r-The - HPGl-s t e am 44 ae-4 s c4444 en-valves-a re-e v t oma t 4 ci,44 y-cl o s ed - to-prevent-overpressur4 rat 40n-of-the-turbine-exhaust-44eer--The rurbine-ex-houst-diaphragm-pressure 4r49-sett4ag-of-6-30-ps49-4s-selected 44gh-enoughs l to-avoid-45014t4on-of-the-WpCl-41-the-turbine 4s-operating,-yet low enough-to-offect-4so44 tion-before4ho4 urb 4Ao 4xhaust line-45-unduly-pressur4 zed,- ) b elel-(d .
- 12. Gopere554on-Chamber-Aree4mbient-Temper 4ture H44 A-temperature-of M9"li" 4 4tiete e-timer--te 4so14tedheJPCbturbine= steams '
Heer-
)
)
HATCH - UNIT 1 3.2-$4 Atendment No. $3, 70s,121 *
.. BA$l5'FOR LIMITlhG CMITIONS FOR OPERATION T>cde 4 e d.
( 3.2.B.13. frtloor+s54on-Chen%r-Ares 444+r+nt441 M r seweratur+Jteh-A-444erent464-44r-tower 4turegreater-than-the-tr.4p-setting-of-s 421F 4t twe en-t he-4 n 4 e t-e nd -ou t h t-4v e t s-wh 4 th-vent i4 e t t-t hers uppret ti on-t hemb er-- ar44-wt44 initiate-a-t4m-to-45014te-the--@Cl-49tbine-steam-44Ae. (' 14. Condensate Storace Tank Level low The CST is the preferred source of suction for HPCI. In order to provide an adequate water supply, an indication of low level in the C$T automat-ically switches the suction to the suppression chamber. A trip setting of 0 inches corresponds to 10,000 gallons of water remaining in the tank. ( 15. Suppression Chamber Water level Hioh A high water level in the suppression chamber automatically switches HPCI suction to the suppression chamber f rom the CST.
- 16. HPC1 Locic Power Failure Monitor The HPCI Logic Power Failure Monitor monitors,the availability of power to the logic system, in the event of loss of availability of power to the logic system, an alarm is annunciated in the control room.
C. inj1rgmfetation Which initiates or Cortrols RCIC (Table 3.2-3) 9
- 1. _ Reactor Vessel Water Level Low Low (Level 2)
The reactor vessel water level instrumentation setpoint which initiates RCIC is ? -47 inches. This level is approximately 9 feet above the top of the active fuel and is referred to as Level 2. This setpoint insures that RCIC is started in tirne to preclude conditic.ns which lead to inade-quate core cooling.
- 2. RCIC Turbine Overspeed The RCIC turbine is automatically shutdown by tripping the RCIC turbine stop valve closed when the 125% speed at rated flow setpoint on the mech-anical governor is reached. Turbine overspeed is indicative of a condi-tion whir.h threatens the physical integrity of the system. An electrical tachometer trip setpoint of 110% also will trip the RCIC turbine stop valve
, closed.
t
- 3. MIC Turbine Exhaust Pressure Hich When RCIC turbine exhaust pressure reaches the setpoint (< 45 psig), the l RCIC turbine is automatically shut down by tripping the CIC turbine stop salve closed. RCIC turbine exhaust high pressure is indicative of a con-(, dition which threatens the physical integrity of the exhaust line.
- 4. R,Q10 Pumo Suction Pressure low One differential pressure transmitter is used to detect low RCIC system pump suction pressure and is set to trip the RCIC turbine at 512.6 inches of mer-cury vacuum.
HATCH - UNil 1 3.2-S$ Amendment No. If, M 3, H A, 121
BASES FOR tlHITING CONDIT!ONS FOR OPIMTION
)
3.2.C.$. Etyctor vessel Weter level Hioh (Level 91 A high reactor water level trip is indicative that the.RCIC system has , performed satisf actorily in providing makeup water to the reactor vessel. The reactor vessel high water level setting which trips the RCIC turbine is near the top of the steam beparators and sufficiently low to prevent gross ) 1 moisture carryover to t:e RCIC turbine. Two differential pressure trans-mitters trip to initiate a RCIC turbine shutdown. Once tripped the system is capable of automatic reset af ter the water IPyel drops below Level 8. This automatic reset eliminates the need for manual reset of the system before the operator can take manual control to avoid fluctuating water levels. )
- 6. RCIC Pumo Discharge Flow l To prevent damage by overheating at reduced RCIC system pump flow, a pump discharge minimum flow bypass is provided. The bypass is controlled by an automatic. D. C. motor-operated valve. A high flow signal from a flow l meter downstream of the pump on the main RCIC line will cause the bypass l valve to close. Two signals are required to open the valve: A RCIC pump discharge pressure transmitter high differential pressure signal must be j received to act as a pernissive to opSn the bypass valve in the presence of a low flow signal f rom the dif f erential pressure transmitter. 1 Notet Because the steam supply line to the RCIC turbine is part of g )
j the nuclear system process barrier, the following conditic,ns i (1 - 13) automatically isolate this line. causing shutdown of the RCIC system turbine, i
'Dekked.
AC4f4eeeeene--Ar-ea4eoler--Ambient Temper 4tureJtiqL---
- 7. l 449 h-4mb i e n t-t emp e ra t u r+-4 n - t he-S C I C-eq u i pme n t-r o om-ne a r-t he - eme rg e ncy-aree-tooler-tould-4ndicate 44reak-4n-the-RCIC-system-turbine 4 team-44eer--
The -a ut oma t4 c-<40$ u re-o f-t he4C IC-s t eam-4 4 ne-valves-preven t s--t he-e nt e s-s i ve-lo s s-o f-reuc t o rw oola nt-a nd-t he-rel ea se-o f -tignif i ca nt-4 mount Fof-rad 40act4ve-mater 4al-f rom-the nuclear-system-pr+ cess-barr4 err-The449h-tempe ra t u re-s e t t4 eg-o f- 5-469 '4-wa s-s ele t-t ed-t o4e-44 r-e n oug h-a b o ve-e nt4- ) e 4 pa t ed -normal 4 C4 Ca y s t em -op e ra t 4 ona l-l e ve16-t o4 vo id a pu r4eu s-45044 t 4 ce-b ut -40w-enoug h -to-p r ov i d e-t 4 me l y-d e tec t i on-o f-4-4 C I C-t u rb i nea t ea m-44 ne-
)
-brea kr--
T eleted.
- 8. 904t-Stum-59pos v-Arener+-tos Low-pressure-in-the-ACIC-steam-supply 40u14-ind4cate-44reak in-the RCIC-s team--line r--Theref ororthe4C IC-steam-supply-4tolat ton-valves-are-auto-mat 4c-al4y-<40sedr 4he -steam-44ne-40w-pressure-function-ieprodded40- )
t h a t-4 n -t he -event-a-g r os s-ruptu re-o f-t he-E CI C-s t e a m 44 n e-oc t u r r e d-up-- s t rea m-fr om - t h e-h i g h-f40w -s e n s 4 ng -loc a t i onethus-negating-the44gh flow-- l indic ating-f unctionr -45olation-would4e-ef f ec ted-on-low +ressure. The-iso- l l a t 4 on-s e t po i n t - o f-t40- p s % 9 -4+-c ho s e e-e t-+-p re s s u re-below-t h a t-e t-wh4 c4+ the4EI C-tv eb i ne-c e n -+ f fec t i vely-o pera ter-- I I HATCH - UNIT 1 3.2-$6 Amendment No. 63. 103, 121 i l .
_ . . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ . . . _ ~ - _ - _ _ ___ _ _ -_ _ - _ l BASES F0k LIMITihG CONDITION! FOR OPERATION ( 3.2.C.9.
' . W4-ed 1041eem-line-4481 I105 hi4h-- l S C144 urb in64 %g h- S t e am -fl ow-c ould4 nd it s t a-a- brea k-4 n-theJ C I C4 u rbine-Steam 44ner-The-automstic-closure-of-tht ACIC-5 team 41464soial4on-valvet-pre ents-the-eatessive40s&-of-reac tor-t eolant- sd-the-etlease-ef-signif-i--- f s aM-amour.t s-of-ra d 404 G t iv e 4.a t e r4416-f rom-the -Aucle a r-s y s t em-pr oc e s s- '
be eri e e r-SPN. -4 e t e t t 46n-o f4 C I C- t u rbi nt-h ig h-s t e am44 ew-t he4 C I C-t u rbi ne- ' vitam-449e -i s -i s o l a t ed r--T he-h ig h-s t e a m 410w-t r i p-s e t t ing-o f-306b (40w- ] was-selected 4tgh-enough-to-avoid-spur 40us $tointlon, 4,4c,-above4he-h4gh-st ram-f 40w-rate-encountered-4uring-turtiine-starts The-setting wat-s el e c t e d .40w-e noug h-t o-.prov 4 d e 44 me l y- d e t e c t i on-o f-e n4C I C-tu rbi ne- s t e am - 14ne 4reaL,- ( W ehed. 10, 901 C-T u rbi n e4 . h o u s t -Dia ph re em - p res sv ee4 t e h-
#49 h-pre $$ure4n-the-ACIC4urbine-eahausbcould4ndicate.-that-the-turbine---
rotor-4 6 -not4W rA4 ng ,-thu s -a 14owing-reac tor- pre s s u r*40-a c t -on-t he-t u r bi ne-e x haus t-44ne r-4 he-ACI C-st eam-44 ne-4 sota t (on-va l ves-a re-a utomat 4 c 4149-G40se640-provent-overpressurtaat!4naf4hh4urbine-exhaust-14 nee The4ur-b$ne-enhaust-diaphragm pressure t r4p-setting-of-5-20-psig 4s-selected high l enough-to-avotJ4solat4on-of-theJCIC 4f-the turbine 4s-operating,--yet 4cw-enough40-4ff ect isolat. ion 4efore4he4urbine-exhaust 14ne 4s-unculy-pres -- sur4 aed. beiched
- 11. suppres s ion-ChamtseNA rea -Amb ient -Tem?tra t u re-Hich- , l
- 1Es-in-the-SCIC-equipmert-roomr -and-for-the-same-reason r -temperature-of.- a l
9 $469 t F-wi 414 ni t ia t e -a -t ime r-t o -i so l a te-the -AC IC4u rb ine-s te am4 tr.sv-
'belcatr). l
- 12. Eppv $ s 4 an-Chambe r-A rea-04 f i e rent 4 a l-Air- Temperat e FHigh-A high-4ifJerential-air- temporature4etween-the4ntet-and-outlet-duct 6-whith-vent 444t+4he--supprer,540n-chamber-area-wt41 thttate-a-timer--to- l t6014te-the4 Cit- wrbine-stunJine -
13 RLIC Loaic Power Failure Monitor The RCIC Logic Power Failure Monitor monitors the availability of power to the logic system, in the event of loss of availability of power to the logic system, an alarm is annunciated in the control room, i
- 14. Condensate Storace Tank level Low The low CST level signal transfers RCIC suction from the CST to the suppression pool. The setpoint was chosen to ensure an uninterrupted supply of water during suction transfer.
c 15. Suporession pool Water Level Hiah ( A high water level in 1% suppression chamber automatically switches RCIC surtion from the CST to the suppression pool. (
"" 3.2-$7 Amendment No. JOI. 103, 121 HATCH
- UNil 1 g
4 , 3
4 BA$[3 f 0R LIMITING CONDITIONS FOR OPERATION
- 2. Drwe11 Pressure Wieh.
)
Primary containment high pressure could indicate a break in the l nuclear systes process barrier inside the drywell. The high drywell pressure setpoiht is selected to be high enough to l avoid spurious starts but low enough to allow timely system initiation. I
- 3. Reactor Vessel Steam Dome Pressure tw
)
ru.um-for ente _,mse- mete- te%-oe-cueue 4the-Genes-f o@ i f ic a t ion-3,2, A . G r-With an analytical limit of > 300 psig and a nominal trip setpoint of 370 psig, the recirculation discharge valve will close successfully during 8 a LOCA condition. ' Once the LPCI system is initiated, a reactor low pressure setpoint of 460 l ! psig produces a signal which is used as a permissive to open the LPCI in-jection valves. The valves do not open, however, until reactor pressure falls below the discharge head of LPCI. l
)
)
HATCH - UNIT 1 3.2-60 Amendment No. 54,18I,121 I
- r -
.--_c. - , , , . - , - - -
(' BASES FOR LIMITING CONDITIONS FOR OPERATION 4.2 PROTECTIVE INSTRUNfNTATION g ig y g* 1he instrumentation listed in Tables 4.2-1 thru 4.2-13 ill be functio'nally . tested and calibrated at regularly scheduled intervals. P: '::= da4p-e+-- {. "ni1My ;::1 -:: th 5:et:r "r:te:ti:n Ey;4r :f 0.00000 h ;:n:e644y :::MS r all applications of one-out-of-two-taken-twice logic. Therefore, on-off se ors are tested once every three months, and bi-stable trips associated with nalog sensors and amplifiers are tested once per week. The ATTS inst ments are te ted once per month per WE00-21617-A. 1 hose ins uments which, when tripped, result in a rod block have thei contacts (. arranged i one-out-of-n logic, and all are capable of 'being bypas)(d. For such a tripping a gement with bypass capability provided, there is eryoptimum test intervalthats%ouldbemaintainedinordertomaximPethereliabilityofagiven channel (Referent 1). This takes account of the fact that testing degrades re-liabiftty and the timum interval between tests is approxima ly given by: Where: i = the optimum inta val between tests,
'f t = the time the trip c tacts are disabled /f rom performing their function while the te is in progr r = the expected failure rat of the rAlays.
( .
/
To test the trip relays requires that t fthannel be bypassed, the test made, and the system returned to its initial statp. It is assumed this task requires an es-timated 30 minutes to complete in a therou and workmanlike manner and that the relays have a failure rate of 10-* f,silures r hour. Using this data and the aboveoperation,theoptimumtest)fitervalis: i= 2, 1 11 = 108 ho s A0** s= 42 days A test interval of once- r-month will be used initially. The sensors and electronic apparatus have not been included re as these are ana-log devices with restlouts in the control room and the sensors d electronic ap-paratus can be chgked by comparison with other like instruments The checks which are made orf a daily or once per shif t basis are adequate to sture cper- l ability of the/ sensors and electronic apparatus, and the test inter 1 given above providti for. optimum testing of the relay circuits. The above/c Iculated test interval optimizes each individual channel pco dering [ it to be' independent of all others. As an example, assume that there are o L channpis with an individual technician assigned to each. Each technician te is his, channel at the optimum f requency, but the two technicians are not allowed To coprnunicate so that one can advise tM other that his channel is under test. Uh f:fr=?y. thesetconditions, u, ::: re that it istpossible h t:: hahfor both
!!n: channels to
;re,re';uired ta be under
- ^--"'a k at testt simultane t ad thet-h k
HATCH - UNIT 1 . 3.2-6g Amendment No. 58,103
, _ _ .- ,.-1, . _ _ , . ,
--w
Insert E (to P. 3.2 69) lhe minimum functional test frecuencies and allowable outage times for selected instrumentation relatec to isolation actuation, ECCS and RCIC actuation, and control rod block have been revised. The NRC-approved reliability based methodology in References 1 through 4
~)rovides a basis for these changes and is consistent with similar changes to 1PS instrumentation. The frequency of functional testing and calibration for other instrumentation is based on historical methodology (Reference 5). i A. References
- 1. NEDC-30851P-A, "BWR Owners' Group Technical Specification improvement Analysis for BWR Reactor Protection System," Harch 1988.
- 2. NEDC-31677P-A, " Technical Specification Improvement Analysis for BWR isolation Actuation Instrumentation," July 1990.
- 3. NEDC-30936P A, "BWR Owners' Group Technical Specification improvement Methodology (with Demonstration for BWR ECCS Actuation Instrumentation)
Part 2," June 1987.
- 4. NEDC-30851P-A, Supplement 1. " Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation," October 1988.
- 5. UCRL-50451, " Improving Availability and Readiness of Field Equipment Through Periodic Inspection," Benjamin Epstein, Albert Shiff, July 16, 1968, page 10. Equation (24) Lawerence Radiation Laboratory, l
elC* k
/ )
\ BASES FOR LIMITING CONDITIONS FOR OPERATION /
\ /
4.2 ROTECTIVE INSTRUMENTATION (Continued) / channels' are never tested at the same time. x Forbidding simultaneous testing improves the availability of the system over that ) which Nould be achieved by testing each channel independently. These one out of n trip ' systems will be tested one at a time in order to take advantage /of this in-herent improvement in availability. Optimizing \ stem consider-ing the overayeachrules channel independently of system operation.may not trulytrue However, optimize the ) timization is systenyop
- a complex proble;m. The optimums are broad, not sharp, and optiairing the individ-ual channels is benerally adequate for the system.
The formula given a ve minimizes the unavailability of a fingle channel which must , be bypassed during t sting. The minimization of the unavailability is illustrated by Curve No. 1 of Figuh 4.2-1 which atsumes that a cha hel has a failure rate of 0.1 x 10**/ hour and that 0.5 hours is required to $t it. The unavailability is a minimum at a test int rval 1, of 3.16 x 10* hou . If two similar channels are b ed in ae-out-of- Go configuration, test interval for minimum unavailability cha(gges 4 'unctio of the rules for testing. The simplest case is to test each ohg ing w ndent the other. In this case, there is assumed to be a finite probab(11ty that bot may be bypassed at one time. This case is shown by Curve No. 2. Noththat the,unavbilability is lower as expected for a redundtnt system and the minimum occurs gt the same test interval. Thus, if the ; two channels are tested independently th6 equation on the preceding page yields the test interval for minimum unavaila ity. A more usual case is that the testin 5 n t done independently, if bot'h channels are bypassed and tested at the same' time, t result is shown in Curve No. 3. Note that the minimum occurs at about 40,000 hours much longer than for Cases 1 and 2. Also,theminimumisnotnearly/slowasCase(whichindicatesthatthismethod of testing does not take f ull pdvantage of the rbdundant channel. Bypassing both channels for simultaneous testing should be avoidsti.
/ \
The most likely case wou14/be to atipulate that one ciannel t by bypassed, tested, and restored, and then immedistely following, the second c nnel be bypassed, tested, and restored. Thisis/hownbyCurveNo.4. Note that here is no true minimum.
. The curve does have ajtlefinite knee and very little reduction in system unavailabil-ity is achieved by sting at a shorter interval than compUt<ed by the equation for 3
a single channel. The best test p cedure of all those examined is to perfectly s qgger the tests. That is, if the test intervtl is four months, test one or the other channel every two months /1his is shown in Curve No. 5. The difference between\(ases 4 and 5 is negligible. There may be other arguments, however, that more strongly support the perfectly staggered tests, including reductions in human error. \
~
)
The to usions to be drawn are these:
- i. one-out-of-n system may be treated the same as a single channel in tehms of choosing a test interval; and N
'f i. More than one channel should not be bypassed for testind at any one time.
l N
~
HATCH - UNIT 1 3.2-70 l
- p t'I,(3$t1 t
N BA$ts F0P LIMITING CONDITIONS FOR OPERATION ' x l 4.2 PRO'TECTIVE IN$1RUMENTATlpg (Continued) s .
~
[- . . The radiation-Inonitors in the refueling floor exhaust ventilation duct which initi-att butiding is'o)ation and standby gas treatment operation are, arranged in two one-out-of-two logic systems. The bases given for the rod blocks' apply here also and
~
were used to arrive at the, functional testing frequentyg-d he offgas post treatment monitors are connected in a'two-out-of-two logic arranypant. Based on esperience with instruments of similar design, a testing in.terval of once every three months has been found adequate. ~~x y The automatic pressure relief instrumenta on can be considered to be a one-out-
. of-two logic system and the discussion above applies also.
A. References /
/ N,
,N,
~
- 1. UCRL-50451..!mproving Availability and Readiness of F'ield Equipment Through Periodic Inspection, Benjamin Epstein, Albert Shiff, .luly 16.1968, page 10 Equation (24), Lawerence Radiation Laboratory. 'N
.,/
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8 6 0 1 10 2 10 3 10 10 10 \ ') T EST INTE RVAL - 0) HOUR $
.-RGURE-4.21r-GYSTEM UN AVAll ABILITY I
h e
"""11pITING [DNDITIDN5 FDF Or[R ATIDN 5URV[IllANEI REDUIRIMUG5 3.6.H. i insete cf Filled bittbarne a.$.H. Maintenante of Filled DisthEAt
>, g whenever the C5 system LPCl, The following surveillante re-HPCI,orRCitarereQulred- l guirements shall be perform d-to be operable, the discharge to assure that the diltharge piping f rom the pump discharge piping of the C5 system, LPCI, l of these systems to the last NPCI, and RCIC are blJtt valvt shall be Illied. filled when requiredt s
The tuttien Of the HPC) pumps shall be aligned to the conden. 1. (very month, the distharge J Sate storage tant. piping of the LPCI and C$ systems shall be vented f rom the high poiht and water flow observed.
- 2. Following any period where e the LPCl or C$ systems l have not been required L. . -
to be operable, or have been inoperable, the disthargt l-piping of the system or sys-tems being returned to ser-vite shell be vented from the high point prior to re-turn of the system to service.
- 1. Whentver the HPCI or RCIC system is lined up to take suctich'from the condensate storage tank, the discharge piping of the HPCI and RCIC shall be vented from the high poiht of the system'
+ and water flow observed on a monthly basis.
- 4. The level switches whith" monitor the discharge lines shall te R.th=", Onted ri n it n e talibrated every 3 months.
- 1. Minimum River level 1. Minimum River Level
- 1. If the water level. as The water level as, measured measured in the owmp well . .in the pump well and the is less than 61.2 ft MSL, level in.the river
- thall the discharge f rom each plant be verified with the follow-service water (P5W) pump will ing frecuencient be throttled such that each pump does not exceed 7000 gpm. Level itsil Frecuency
.f
- 2. If the water level,'as measured l 1. > 61.7 ft Biweekly, in the punip well, decreases to less than 60.7 ft MSL or if 2, 1 61.7 ft tvery 12 hrs, the level in the river
- Grops to a level equivalent to less
*0nly pump well monitoring is required if a temporary weir is not in place. -l f s.
3.5-11 Amendment No. II, 15(, 170' HATCH - UN11 1
' - * ' +'+++,4-<vw.wm_ -
,_% , , , . , y.
I
r g tlHlfTu coroil 0*s f on Orteatina havili,tAMt 6t0uingtNfs 3.6.H.1. [tjjlf /$af ety valvet 4.6.H.1. $elief/5afety Val.v.t1
- a. When one or more relief / safety a. tnd of Oberatino Cvt11 valve (s) is known to be f ailed"* an j orderly shutdown shall be initiated Approntmately one-half of all
(-- and the reactor depressurtred to relief /laf ety valves sh411 be less than 113 plig within 24 hours, benchchttked or replaced with Prior to rentor startup f rom a a benchthecked valve each re-cold condition all relief /saf ety fueling outage. All 11 valves vahes shall be operable.** wt11 have been checked or re-
. placed upon the completion of every second operating cycle.
- b. With one or more relief / safety b. Each Oreratina Cycle valve (s) stuck open, place the reactor mode switch in the shutdown position. Once during each operating cycle, at a reactor pressure
> 100 psig each relief valve shall be manually opened until
( thermocouples downstream of the valve indicate steam 15 flow-ing from the valve.
- c. With one or more safety / relief valve c. Lnitrity of Pelief Valve tailpipe pressure switches of a LtLi t.
wP safety / relief valve declared inoperable and the associated The integrity of the relief valve safety / relief valve (s) otherwise bellows shall be continuously indicated to be open, place the monitored and the pressure reattor mode switch in the Shut- switch calibrated once per down polition, operating cycle and the accu-mulators and air piping shall be inspected for leakage once per operating cycle.
- d. With one safety / relief valve tailpipe d. Pelief valve Maintenantg
( pressure switch o' a safety / relief valve declared inoperable and the asso- At least one relief valve shall ciated safety / relief valve (s) otherwise be disassembled and inspected indicated to be closed, plant operation each operating cycle, may sontinue. Remove the function i i that pressure switch from the low low e. Operability of Tailpice set logic circuitry until the next COLD Pressure Switches 5HUIDOWN. Upon C0t0 5HUTDOWN restore the pressure switch (es) to 0F[RABLE 1he tailpipe pressure switch status before STAk1UP. of each reitef/ safety valve gg shall be demonstrated operable
- e. With both safety / relief valve tailpipe by performance of at pressure switches of a safety / relief valve declared inoperable and the 4550- 1. Functional Test cisted safety / relief valve (s) otherwise indicated to be closed, restore at least a. At least once per 44C92.
( one inoperable switch to OPERABLE status days, except that all ( within 14 days or be in at least HOT portions o' 1strumen-
$HUTDOWN within the next 12 hours tation insice the pri-and in COLD SHUTDOWN within the mary containment may be following 24 hours, escluded f rom the functional test, and e *Does not apply to two stage Target Rock 5RVs
.biC "ThT%eH4e+/Saf ety valves are not rectired to be operable for pertornance of intervice
( hydrostatic or pressure testing with rsactor pressure greater than 113 psig and all control rods inserted. Overpressure protection will be provided as required by A5ME Code.
' '*The f ailure or malf unction of any safety / relief valve shall be reported by telephone within 24 hours; confirmed by telegraph, mailgram, or f acsimile transmission to the Director of the Regional Of fice or his designee no later than the first working day following the event and a written f ollowup report within 30 days. The written f ollowup report should be completed in accordance with 10 CFR 50.T3 or other applicable requirements.
WWOrc. Mitment ,chrmel rec.q be (nepemble b up g y hem % geq reyaed surWlanced pnec w cMednq c&er cmpucete AcHom. HATCH - UNIT 1 3.6-g Amensent No. 16,71,103,137,149
4 4 LIM 111NG CONDITIONS FOR OPERA 110N SURVElltkNCE REQUIREMENT $ 4.6.H.1. Relief /$afety Valvel (Continued) l
)-
- e. Goerability of Tail Pine l Pressure Switches
- 1. Functional Test l
- b. At each scheduled out- l age greater than 72 hours during which en-try is anade into the primary containment, if not performed with- l e previous (
i 2.- Calibration and verifying l the setpoint to be 85, +15
-5 psig at least once per 18 months.
3.6.H.2. Relief / Safety Valves low Low 4.6.H.2. Relief /$afetv Valves low Low set Function Set Function During power operation startup, The low low set relief valve func-and hot standby, the relief tion and the low low set function-valve function and the low low pressure actuation instrumenta-set function of the-following tion shall be demonstrated OPERABLEM reactor coolant system safety / by performance of at I relief valves shall be OPERABLE with the following low low set 4. CHANNEL FUNCTIONAL TEST, function lift settings: including calibration of the trip unit and the dedicated Low Low Set Allowable Value (psig)* high steam dome pressure Valve Function' 933 G,lgit chant. dis **, at least once per MQ.ucu-+er-Low .i 1005 1 857 0 Medium- 1 1020 1 812 b. CHANNEL CALIBRATION, Logic Medium High i 1035 1 887 System Function Test, and High- 1 1045 1 897 simulated automatic cperation of the entire system at least
- a. With the relief valve function and/or once per 18 months.
the low low set function of one of the above required reactor coolant ' system safety / relief valves inoper-able, restore the relief valve func-tion and the low low set functior. to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours and COLD SHUTDOWN within the fo110 wing'24 hours._
)
- The lif t setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
**The setpoint for dedicated high steam dome pressure channels is 51054 psig.
i ) Nd Cre indnwient olp.nnel be inopercah b up % 6 how% pet-knn requireca durveill r\Ce5 prir 40 enter-incg gJ4Er-cqpVcable A$cn% 6
, HATCH ~ UNIT.1 3.6-9a Amendment No. 71, #f, if, 103
~
m _ _ _ __ _ _ ,_-~ - - _ _ _ _ . . -
LIMITING CONDITIONS FOR OPERATION 5URVEILLANCL e[0UIRfMENTS 4.g.A.6. Lmereenev ?$0 Voit Ce. to 600 Volt AC Inverters (Continue,9 )
- b. Once every scheduled refueling outage, the emergency 250 volt '
DC/600 volt /C inverters shall be ; subjected te a load test to demonstra% operational readiness.
} :
3.g.A.1. Lonic $vstems 4.g.A.1. Loaie $vs t?t, The following logic systems shall The logic systems shall be tested in be operablet the manner and frequency as follows:
- a. The com on accident signal 4. Each division of the comon logic system is operable. accident signal logic system shall be tested every scheduled refueling ,.
outage to demonstrate that it will function on actuation of the core spray system to provide an automatic start signal to all 3 1
- diesel generators.
t
- b. The undervoltage relays and b .1. Once every scheduled refueling supporting system are operable. outage, the conditions under which the undervoltage logic system is required shall be simulated with an undervoltage on each start bus to demonstrate that the diesel gtmerators will start. The testint ' ')
of the undervoltage logic shall demonstrste the operability of the ' 4160 volt-load shedding and auto bus transfer circuits. The simulations shall test both the degraded voltage and the loss of off-site power relays. vcir H-d.
- 2. On94 per 6ys wn1
- jMitiat,e~ju'onth.fher energitati f the '
emergehty Gen storywhenby(es vs' e Diti lost by(ttage 1 emergencybufesand tart-ransfpfmer 1, will
- f une.tionally[ tested /p6 ~ .
- 1
- c. The common accident signal logic c.1. Once per eerating cycle each' l tiesel gew rator shall be dem-system, and undervoltage relays-and supporting system are operable, ofstrated operable by simulating Nth _ a loss of of f-site power and a !
degraddd voltage condition in conjunction with an accident test 'h l- 'F signal and verifyingr -, i 1 I
~
3.g-4 Amendment No. U , 48, 88 - HATCH - UNIT 1.
.l ._
' O
INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.14.1 The radioactive liquid effluent monitoring instrumentation channels shown in table 3.14.1-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of specification 3.15.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). C APPLICABItlTY As shown in table 3.14.1-1. ACTION
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents. monitored by the affected channel, declare the channel inoperable, or change to a conservative value.
- b. WiththenumberofchannelsOPERABLNiessthanthe minimum channels required by table 3.14.1-1, take the ACTION shown in table 3.14.1-1.
- c. The provisions of Specification 6.9.1.13(b) are not applicable,
- d. When the ACTION statement or other requirements of _this LCO cannot be met, steps need not be taken to change the Operational Mode of the Unit. Entry into an Operatiem i Mode or other specified condition may be made if, as 6 minimum, the requirements of the ACTION statement are satisfied.
( s - SURVEILLANCE REQUIREMENTS 4.14.1 Each radioactive liquid effluent monitoring (= instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK SOURCE CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in table 4.14.1-1. Acre (nrAtumeny channel i Wi .nble br q> -ic G hem -to reeptred &w vet rces t- % e.a eger ctgp ticohte HATCH-UNIT 1 3.14-1 Amendment No. 110
i *
}
o TABLE 3.14.2-1 (SHEET 3 0F 4) { RADI0 ACTIVE GAcEDUS EFFLUENT MONITORING INSTRUMENTATION l o Table Notations '
. + Monitor must be capable of rrspending to a Lower Limit of '
Detection of 1 x 10-' pCi/mi.
*0uring releases via this pathway.
"During main condenser offgas treatment system operation.
'"During operation of the main condenser air ejector.
ACTION 104 - With the number of channels OPERABLE less than, required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided the flowrate is estimated at least once per 4 hours. If the number of channels OPERABLE remaint less tha_n ~ required by the Minimum Channels OPERABLE requirement for Add 9,g4 p"\over 30 days,inan included the explanation next semi-annualof effluent the circumstances release report. shall be required by the Minimum Channels OPERABLE requirement, kmo9 ) ACTION 105 - With the number of channels
. deet C' effluent releases via this pathway may continue, provided grab samples are taken daily and analyzed daily for gross activity within 24 hours. With the number of main stack monitoring system channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, without delay >
suspend drywell purge. If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for .
- g. over 30 days, an explanation of the circumstances : ball be p, included in the next semi-annual effluent relcase report.
(
~
ACTION 106 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may continue provided: (a) Gas samples are co11 acted once per 4 hours-and analyzed within the ensuing 4 hours, or (_
, (b) Using a temporary hydrogen analyzer installed in the
. offgas system line downstream of the recombiner, hydrogen concentration readings are taken and logged every 4 hours.
HATCH-UNIT 1 3.14-9 Amendment No. 110 > e m- --
- w r . n-, ,- ,- , - , - - , - - , , - ,---,y - - - - - - - , - -
TABLE 3.14.2-1 (SHEET 4 0F 4)
)
RAD _10 ACTIVE GASEOUS EFFLUENT MONITORING __ INSTRUMENTATION Table Notations (Continued) l If the number of channels OPERABLE remains less than
)
required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be Add included in the next semi-annual effluent release report. -
. eng i:#_
ACTION 107 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided samples are continuously collected with auxiliary sampling equipment for periods on the order of 7 days and analyzed within 48 hours after the end of the sampling period. If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be M included in the next semi-annual effluent release report, k*WJ+ F " _ ACTION 10B - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, release to the environment may continue for up to 72 hours ) provided: -
- a. The offgas system is not bypassed, and
- b. The offgas post-treatment monitor (011-K615) or the main stack monitor (011-K600) is OPERABLE. .
Otherwise, be in at least HOT STANDBY within 12 hours. If the number of channels OPERABLE remains less than ' , required by the Minimum Channels OPERABLE requirenent for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. g
*Lwert F'--
reser+ F : One inehmenF channel mcty be inoperrtble ) 9er up % lo hours +c perVerro recpined darveillctnces pricr R, en+ering c4her-l CLppdGOMfi MCdiCn5
}
HATCH-UNIT 1 3.14-10 Amendment No. 110
\ \~~l ~ i
-0L - r0 REACTIVITY ~~ CONTROL SYSTEMS fAC CONTROL R00 SCRAM ACCUMULATORS -) 4s LIMITING CONDITION FOR OPERATION A) bib 's
$1 = 2 .)
- . p o 3.1.3.5 All control rod scram accumulators shall be OPERABLE. -
LCp y3G APPLICABILITY: C0f4DITIONS 1., 2 and 5".
~D y e ACTION: >- a. In CONDITION 1 or 2 with one control rod scram accumulator )'
d "' ,b inoperable, the provisions of Specification 3.0.4 are not E applicable and operation may continue, provided that within 8 73
, hours:
E 1. The inoperable accumulator is restored to OPERABLE status, q (, or .f ,
-: 2. The control rod associated with the inoperable accumulator
- is declared inoperable and the requirements of o
((o Specification 3.1.3.1 are satisfied. jOI Otherwise, be in at least HOT SHUTOOWN within the next 12 hours. s o 'e
,g
%. ~)
b, In CONDITION 5* with a withdrawn control rod' scram accumulator hS g inoperable, fully insert the affected control rod and 0 4 w- electrically disarm the directional control valves or close the ' withdraw isolation valve within one hour. The provisions of
-f Specification 3.0.3 are not applicable.
l , SURVEILLANCE REQUIREMENTS 4.1.3.5 The control rod scram accumulators shall be determined OPERABLE:
- a. At least once per 7 days by verifying that the pressure and ]
leak detectors are not in the alarmed condition, and
- b. At least once per 18 months by performance of a:
- 1. CHANNEL FUNCTIONAL TEST of the leak detectors, and
- 2. CHANNEL CALIBRATION of the pressure detectors to alarm at 2: 940 psig.
l , p
*At least the accumulator associated with each withdrawn control rod.
Not applicable to control rods removed per Specification 3.9.11.1 or }- 3.9.11.2. HATCH - UNIT 2 3/4 1-8 Amendment No. 55 (
) 1 REACTIVITY CONTROL SYSTEMS ROD BLOCK HONITOR f QMITING CONDITION FOR OPERATION 3.1.4.3 Both Rod Block Monitor (RBM) channels shall be OPERABLE. APPLICABILITY: CONDITION 1, when THERMAL POWER is greater than or l equal to 30T of RATED THERMAL POWER and when the MCPR is less than ! the value provided in the CORE OPERATING LIMITS REPORT. ( ACTION: 4
- a. With one RBM channel inoperable, POWER OPERATION may continue provided that the inoperable RBM channel is restored to OPERABLE status within 24 hours; otherwise, trip at least one rod block ,
monitor channel within the next hour, j
- b. With both RBM channels inoperable, trip at least one rod block monitor channel within one hour, c,, C.)ne. ins 4rtArnmf Chctnnel rncq be incpertxhic 4tr- kp 4c /r hot.tNa 40 per9tarrn cqeticza h Atcehaired Dtd s. durveillctnces .PHC& do en+er-in3 c4her-(.
$URVEILLANCE REQUIREMENTS 4.1.4.3 a. With both RBM channels OPERABLE, surveillance requirements are given in Specification 4.3.5.
- b. With one RBM channel INOPERABLE, the other channel shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST prior to withdrawal of control rods.
( L HATCH UNIT 2 3/4 1-17 Amendment No. 19', 106
---C,. Cro in Amrved civunnel rq in incpernble Er- up ic (r hours lo pcrfer'n req c+ %a-A-Wredone. OPEPAF>LEs
- hrvstitanced chctnre) prior -f o erdednq In die awe N p >Wezm le, nwn,iftrincone 3/4.3 2NSTRUMENTATION &&[m mehr'.
3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION f LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels ( shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2. Set points and interlocks are given in Table 2.2.1-1. APPLICABILITY: As shown in Table 3.3.1-1. (. ACTION:
- a. With the requirements for the minimum nimber of OPERABLE channels not ,
satisfied for one trip system, place at least one inoperable channel in the tripped condition within 12 hours,
- b. With the requirements for the minimum number of OPERABLE channels not satisfied for both trip systems, place at least one inoperable channel in at leant one trip system
- in the tripped condition within I hour l and take the ACTION required by Table 3.3.1-1.
cl,g. The provisions of Specification 3.0.3 are not applicable in OPERA- - { TIONAL CONDITION 5. SURVEILLANCE REQUIREMENTS l 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL 4 FUNCTI' NITEST and CHANNEL CALIBRATION operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1-1, 4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system. ( 4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function of Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one logic train ; l .such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every I (~- N times 18 months we N is the total number of redundant channels in a specific reactor trip function, tekere. ( *!f both channels inoperable channelare inoperable in that trip system intoone tripinsystem, place select the tripped at least one [. condition except when this could cause the Trip Function to occur. HATCH - UNIT 2 3/4 3-1 Amendment Nu, 6, 100
,TA_BLE 3,3,1-1 (Continued)
REACTOR PROTECTION SY$7EM INSTRUMENTATION ACTION 9 - In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTDOWN within 6 hours. In OPERATIONAL CON 0!T10N 3 or 4, lock the reactor mode switch in the $hutdown position within 1 hour. l In OPERATIONAL CON 0! TION 5. Suspend 411 operations involving CORE ALTERATIONS or positive reactivity ch6nges and fully insert all insertable control rods within 1 hour. l TABLE NOTATION $ w eded. C- s. -A-chennel-say-be-placed-in-an-inoperable- ttatus-fee-vp-to-64ours-fee- l the-trip-system-in-the-tripped
-reeutred-surveillance
-cond i t i on-p rov ided-s hl e a s t-without-placingkiE-channel-in one-OP E RA the-same-trip-system-
-4 6-monitoring-that-pa ramete er ,
- b. The " shorting links" shall be removed from the RP$ circuitry during CORE ALTERATIONS and shutdown margin demonstrations performed in accordance with Specification 3.10.3.
- c. The IRM scrams are automatically bypassed when the reactor vessel mode switch is in the Run position and all APRM channels are OPERABLE and on scale,
- d. An APRM channel is inoterable if there are less than 2 LPRM inputs per level or less than 11 LPRM inputs to an APRM channel. l r
(' e. These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed.
- f. This function is automatically bypassed when the reactor moae switch is in other than the Run position,
- g. This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
- h. With any control rod withdrawn. Not applicable to control rods removed per $pecification 3.9.11.1 or 3.9.11.2.
- 1. These functions'are bypassed when turbine first stage pressure is s2$0*
psig, equivalent to THERW L POWER less than 30% of RATED THERMAL POWER.
- j. Within 24 hours prior to the planned start of the hydrogen injection test
(- ' vith the reactor power at greater than 20% rated power, the normal full-power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection.- The background radiation level shall be determined and C* associated trip setpoints shall be set within 24 hours of re-establishing
. normal radiation levels after completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.
t
- Initial setpoint. Final setpoint to be determined during startup testing.
i k l HATCH - UNIT 2 3/4 3-$ Amendment No. 8,29,D ,0 .58 l 100
. . -. s,
I INSTRUMENTATION j $ ,T 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION
}y(L LIM _ITjNGCONDITIONFOROPERATION 4;4 m . .
9 j7 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the I
$o values shown in the Trip Setpoint column of Table 3.3.2-2 and with ,o5
{_ ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.
.5 0 g APPL _ICABILITY: As shown in Table 3.3.2-1.
3 ACTION: b
.h
- a. With an isolation actuation instrumentation channel trip setpoint a, less conservative than the value shown in the Allowable Values 9- column of Table 3.3.2-2, declare the channel inoperable and place O the inoperable channel in the tripped condition
- until the
]#c 'Delch*
hb . orkl*D#g channel adjusted is restored consistenttowith OPERABLE status with the Trip Setpoint its trip setpoint value. e S z,,. y
,4, g g b. With herequi/ements or the inimum pumber oV0PERABI,l channeis
/
- i. ,
not atisfie4 for one trip sy tem pl#ce at I sst one/inoperatile
%,[
e g'
,ch4 ne.Lin thC_tr.ipp .d_raondi ion
- EatIhAnngj i tour. / _ ,/
- c. With the requirements for the minimum number of OPERABLE channels
-A rfft-satisfied for both trip systems, place at least one inoper-able channel in at least one trip system" in the tripped condition within one hour and take the ACTION required by Table 634 3.3.2-1.
d The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5. SURVEILLANCE REQUIREMENTS _ 4.3.2.1 Each isolation actuation instrumentation channel shall be e demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL ( , FUNCTIONAL TEST AND CHANNEL CALIBRATION operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4,3.2-1.
- i With a design providing only one channel per trip system, an inoperable
(' channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.
**1f both channels are inoperable in one trip system, select at least
( one inoperable channel in that trip system to place in the tripped condition, except when that would cause the Trip Function to occur. HATCH - UNIT 2 3/4 3-9 Amendment No. 8 l
.Y
i Inw rt A (to p. 3/4 3 9) With the number of OPERABLE channels less than required by the minimum OPERABLE channels per trip system requirement for one trip system, either:
- 1. Place the inoperable channel (s) in the tripped condition
- within 12 hours OR
- 2. Take the ACTION required by Table 3.3.2-1. -
The provisions of Specification 3.0.4 are not applicable. i l l i l l l l l
, , - - _ , . . + _ _ , _ . . ~ , . . _ ...-_.,..__s _ , _ . . . . __ _ --...
g; 3 TaDLE 3.L21 (CetinM ,
}T EOLATION ACTUAT10N IN$TRuutNTAt10N
- ACTION 4)
ACTION 20 - Be in at least HOT SHUTDWN within 6 hours and in COLD SHUTDCVN
$ within the next 30 hours.
'b pr '
.4: ACT10N 21 - Be in at least STARTUP with the main steam liet isolatica valves cicted within 2 hours or be in at least HOT SHUTDOW within 6 hours and in COLD D'UTDOWN within the nest 30 hours.
ACTION ;t - Be in at least STARTUP within 2 hov M WN f
- in at least STARTUP with the Oro.- 1 1 solation valves closed thin 2 hours or in at least HOT SH TDCT H within 6 hours.
, A?lM s
- Establish SECONDARY CONTAl* MENT INTECRITY with the standby
, - gas treatment system operating within one hodr. ACTION 25 - Isolate the reactor water cleanup system. ACTION 26
- Close the affected system isolation valves and declare the affected system inoperable,
(- ACTION P - Verify power availability to the but at least once per 12 hours - -- M or close the affected syttem isolation valves and declare the affected system inoperable. . ACTION 28 - Close the t5utdovn cooling supply and reactor vessel head spray isoletten valves unless reacter steam dome pressure s 145 psig. ACTION 29 - Either close the affected isolation valves within 24 hours or be in HOT SHUTDOWN within the next 6 hours and in COLD SHUTDOVN withir th neat 30 hours. NOTES Actuates the standby gas treatment system. 4- "' - " When handling irradiated fuel in the secondary containment. ( e-
- When performing inservice hydrostatic or leak testing wi.h the reactor coolant temre-ature above 212' F.
See Specificattor 3.6.3, Table 3.4 31 fo* valves in etc5 valve group. ts b. . A charydel may be p[ aced it /inoperablejitatusfordptu2h[ursfor
," required sur,eilldnte W.hout placing the trip syst'em in th/ tripped condition provid4d at leasthne other DPERABLE ct)Jnnel in the same } 1p
,51/ tem 15monij6rinothat,$arameter.[ / / / _
- c. With a design providing only one channel per trip an inoperable a channel neett not be placed in the tripped conditto. 'aere this woulJ cause the Trip Fuhetion to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours or the ACTION required by Table 3.3.2-1 for that Trip Functio 9 shall be taken,
- d. Trips the enchanical vacuum pumps.
(_ e. A channel 15 V ERABLE if 2 of 4 instruments in that channel are OPERABLE.
- f. May oe typassed with all turoine stop valves closed. -
- g. Closes only RWCU outlet isolation valve 2031-F004 ,
- h. Alarm of.ly.
[ 1. Adjustable up to 50 minutes. k j. ISeistes containment purge and vent valves,
- k. Within 24 hours prior to the plannad start of the hydroger injection test with the reactor power et great.r than 2C*4 rated powt , the normal full-power radiation backgro.nd level and associatrd trip setpciets may be changed based on a calculated value of the radiation level expected during
, the test. The background radiation level and associated tric set,oints may I ~ be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The backgrounc
** radiation level shall be 6ete-mired a%J associated trip setpoirts shall be set within 24 hours of N-establishing normal radiation levels after completion of hydrogen injection and prior to establishing reactor power levels btlow 20% rated power.
KATCH - Unit 2 3/4 3-15 Amen nent rio. 9.39.7J.78.P8.91
2 --- -,
,,,% y q. . , ,
g_ .
~
' g, : _ v7g:. ~ --.
H , .
', ~
- m, u e
,m. . .._~
(
,.s n
...e m .- .
x . e ,
, ., ; y .w
-. L T ABL ; is . 3. 2_1f
.' ;r c 3=. ~ ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUfREPeENT_S;
~ * ~.
- p. - S? '
CHANNEL ,
' OPERATIONAL .
f 1e FUNCIIOMAL-- CHANNEL- COND4 TIONS f M WICH ~
" CHANNEL
^
~ CHECK'_ TEST CAlfBRATION }URVE1LIANCE RiQUIRED
;[ t #1P FUNCTIOMi j '. s. . PRIMARY'COdTAINMTNT lSOLATION t ;_
ro .-
.a. Reactor. Vessel Water Level .
i R- ' 1, ' . 2, 3' S_ Jt" '. li - 1. Low (Level3)- 5 #" R 1,2,3 Low l.ov (Level'2) 1, 2, 3
- 2..
ft"
= R j .3. Low Low Low (Level 1) . .S. _
R- 1,2,3'
- b. -Orw ell Pressure - High- :S- Jt-' Cf .
4
- c. Main Steam'Line' . .
W- R 1, 2,. 3
- 1. Radiation - High' PS. D NA 0- 1.
- 2. Pressure - Low Al s 1. 2, 3' i W C $-' R
- 3. Flow liigh -
- d. Main Steen Line Tunnet R 1, 2, 3 Temperature - High S M- Q WMA Q~
1, 2#, 3#
- e. ~ Condenser Vacuum - Low 'NA N f'. Turbirm 9ullding Aree Temp. - R - 1, 2, T.
- High NA' K- Q 2, 3 Os M 9 DrywelI Radiation - High Fd - Wh R' '1, a
- 2. SECONDARY CONTAINMENT 'ISOLATIOM
- s. ; Reactor But iding Exhaust 1,'2, 3, 5 and
- Radiation - High. $ ' PgCO R R 1,2,3
- b. Drywell Pressure - High S .*Q N Reactor Vessel . Water Level Ri 1,'2, 3 c.
WQ Low Low (Level 2) S 4' I,
, d. RefueiIng Floor Exhaust P 6' W AJA Q 1,-2,'3, 3 end'*'
- 3 -Radiation .High i
. . . , , i 8- ' '
.*When handling irradiated fuel in the. secondary containment.
tas - #May be bypassed with a ll turbine stop valves closed.
- talinstrument slignment using a standard. current source.
w W. . CD
. ~ - ,, _ s ._
TABLE 14.3.2-1 (Continued) T ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCC REGUIREMENTS
.g CHANNEL OPERATIONAL CONDITIONS IN WHICH h CilANNEL FUNCTIONAL TEST CHANNEL CALIBRATION SURVEILLANCE REQU1R7D , CHECX TRIP FUNCTION C
3
-f
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION
&d M- Q R 1, 2, 3 y a. 'A Flow - High R 1, 2, 3 f S M-Q
- b. ~Ar a Temperature - High 1, 2, 3 l ,
- c. Area Ventilation 6 S WQ R Temperature - High 1,2,3 R NA \
NA SLCS Initiation i
- d. R 1, 2, 3 ,l S M- Q
- e. Reactor Vessel Water Level -
Low Low (Level ~2) Is . HICH PRESSURE COOLANT INJECTION SYSTEM ISOLATION 1, 2, 3 l
-#t- O' R HPCI Steam Line Flow-High S a, 1, 2, 3
- b. HPCI Steam Supply Pressure- S M- Q R 1, 2, 3 Low Mg R S
w c, HPCI Turbine Exnaust
% Diaphragm Pressure - High 1, 2, 3 l # d. HPCI Pipe Penetration Room S WQ R ,
- w Temperature - High 1,2,3 l Suppression Pool Area Ambient k e. S M-(4 R to Temp. - High ' 1, 2, 3 l
- f. Suppression Pool Area AT - S H-Q '
R High , 1, 2, 3
- g. Suppression Pool Area Temp. NA SA R Timer P.elays 1, 2, 3
- h. Emergency Ares Cooler Temp. - S M-Q R 1, 2, 3 High R Drywell Pressure - High G M-Q R NA 1, 2, 3
- 8. NA J. Logic Power Monitor ko O.
o f et 2
? ,
D' V D Y n _
. n -
wt- - - -, o o n o a_o a_ ;.
.( -s TABLE is. 3.2-1#(Continued)
I ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS OPERATIONAL-N Z CHANNEL CHANNEL FUNCTIONAL CHAN:4EL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CAllBRATIC*J SURVEILLANCE REQUIRED C 5. REACTOR CORE ISOLATION g o COOLING SYSILM iSOLATlON R 1, 2, . 3 H a. RCIC Steam Lane flou-High S
- G R 1, 2, 3 m b. RCIC Stea!n Supply Pressure- S V, Low or
- c. RCIC Turbine Exhaust S MQ R 1, 2, 3, l Diaphragm Pressure-High -
R 1, 2, 3 l
- d. Emergency Area Cooler Tempera ture - High S 4P Q *. *-
- e. Suppression Pool Area S
& Q R 1, 2, 3 .l.
Ambient Tempe ra tu re-H i gh k i ': Suppression Pool . Area AT - S & R 1, 2, 3 f. High s' 4, g. Suppresslori PooI ' Area Temp. Timer Relays NA SA R 7, 2, 2 D ryve l l Pressure - High & R 1, 2, 3 .I i h.
- 1. Log ic Powe r Moni to r NA S
R Q NA 1, 2, 3
- 6. SHUTDOWN COOLINC SYSTEM ISOLATION g,,, p. Reactor vessel Water Level - S M- C R 3, la , S g Low (Level 3) w b. Reactor Steam Dome Pressure - High S *Q R 1, 2, 3 l_
kw E 4 h
=
CL
=>
2
.O (J
W
- IL _ .._. _-
e , f INSTRUMENTATION
)
$h' 3/4 3..3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION n 't
'; c IL h yL L1HITING CONDITION FOR OPERATION m '
* ~
C 3 b 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation p d shown in Table 3.3.3-1 55all be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table
lr p;it 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEM RESPONSE TIME as shown in E, [_d Q Table 3.3.3-3.
L ~ W t)
, ')
t d 7 APPLICABIllTY: As shown in Table 3.3.3-1.
. 22 y a ACYL (.N:
$s5y ~
With an ECCS actuation instrumentation channel trip setpoint less EL[f) i. conservative than the value shown in the Allowable Values column '1 7 > E - LL of Table 3.3.3-2, rieclare the channel inoperable and place the
'*fG inoperable channel in the tripped condition until the channel is restored to OPERABLE status with its trip setpoint adjusted yL consistent with the Trip Setpoint value.
i .{g
- b. With the requirements for the minimum number of OPERABLE channeh pj ff
?
not satisfied for one trip system, place the inoperable channel in the tripped condition or declare the associated ECCS inoperable
)
I within p e4 w .
~
m0g <-12 hour"5
$l c. With the requirements for the minimum number of OPERABLE channels , w dU rot satisfied for both trip systems, declare the associated ECCS l inoperable within one hour.
Ooa , 3 0 The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION 5. SURVEILLANCE REQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3-1. e , 4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of ) all channels shall be' performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system. w f* ) s HATCH .tlNIT 2 3/4 3-24 (( ; b a._. _ . .-
..s..- ,. ..y n p. . -f .y. r., 'p
)
TABLE 4b3.3-1' x d. n. EMERCEhW CORE COOLING ' SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS I . CHANNEL OPERATIONAL
, CllANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH '
TRIP FUNCTION C1tECK TEST CAllBRATION SURVEILLANCE REQUIRED c d
-I
- 1. CORE SPRAY SYSTEM m a. Reactor. Vessel Water Level -
Low Low Low (Level 1) S XQ R 1, 2, 3, 4, 5.
- b. Drywell ' Pressure - High S Jt' Q R 1, 2, 3
- c. Reactor Steam Dome Pressure - Low S ' WQ R NA 1, 2,.3, 4, 5 1,2,3,4,5
- d. Logic Power Monitor NA R
- 2. LOW PRESSURE COOLANT INJECTION MODE OF R11R SYSTEM
- a. Drywell Pressure - High.
Reactor Vessel Water Level - S Jt' k R 1, 2, 3 b. Low Low Low (Level 1) S WQ R 1, 2, 3, 4*, 5*
- c. Ronctor Vesse1 Shroud -LeveI d.
(ieve1 0) Reacter Steam Dome S WQ R 1,2,3,4*,5* l Pressure - Low S Jt' R 1, 2, 3, 4*, 5*
- e. Reactor Steam Dome Pressure - Low S M' R 1, 2,'3, 4*, 3*
- r. RHR Pump Start-Time Deley Relay NA NA R 1, 2, 3, 4*, 3*'
R b
- g. Logic Power Monitor NA R NA 1, 2, 3, 4*, 5' Y
-ta
* *Not applicable when two core spray subsystems are OPERABLE per Specification 3.5.3.1.
B rD 3 CL i N to D et
-'1 2
O tot O N l f
, , _ +
~)
TABLE 4.3.3-1 (Continuedl c EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEllLANCE REQUIREMENTS g C:lANNEL OPERATlONAL
-c CHANNEL CONDITIONS IN WHICH CHANNEL ' FUNCTIONAL SURVElLLANCL REQUIREDE ' CHECK _ TEST CALIBRATION TRIP FUNCTION c
3 -t 3, 'llLQl PRESSURE COOLANT INJECTION SYSTEM g a. Reactor vessel Water Level - S P Q R 1,2,3 Low Low (Lovei 2) R 1,2,3
- b. Drywell Pre ssu re-H igh S M'~ Q .
- c. Condensate Storage Tank Level - _M- AfA Q 1,2,3 NA Low Suppression Chamber Water R 1, 2, 3 d.
Level - High S M' R Q NA 1, 2, 3 Logic Power Monitor HA 1,2,3
- e. R
- f. Reactor Vessel Water Level-High S WQ (Level 8)
- 4. AUTOMATIC DEPRESSURIZATION SYSTEM 1, 2, 3
- a. Drywe l l Pres su re-High S &Q R
- b. Reactor vessel Water Level - S &G R 1, 2, 3 Low Low Low (Levei 1) R 1,2,3 NA NA w c. ADS Timer NA NA R 1, 2, 3 l
% d. ADS Low Water Level Actuation Timer R 1, 2, 3
- e. Reactor Vessel Water Level - Low S M- Q ,
l w (Level 3) Core Spray Pump Discharge 1, 2, 3 l 8 f R
$ Tressure - liigh S M- G l
- g. RHR (LPCI MODE) Pump Discharge R 1, E, 3 Prep are - High S &- Q NA 1,2,3 NA R
- h. Contr6: Power Monitor
- 5. LOW LOW SET S/ W SYSTEM
- a. Reactor ? tv i Dome Pressure - S H R 1,2,3 High g HPCI and ADS are not required to be OPERABLE with reactor steam dome presore 5150 psig.
CL {
= t .
o 2
?
w W w M n . .. .n
~
((~ ! f, ,
'4O INSTRUMENTATION * 'E - 3/4.3.4 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION i
/\ a CL. . .
.J JL. - ' cJ LIMITING CONDITION FOR OPERATION T~84 l P 2 o 3.3.4 The reactor core isolation cooling (RCIC) system actuatiun instru- 3 y p mentation'shown in Table 3.3.4-1 shall be OPERABLE with their trip set-
, _ rJ points set consistent with the values shown in the Trip Setpcint column l.- d4 of Table 3.3.4-2. I _t APPLICABILITY: CONDITIONS I, 2 and 3 with reactor steam dome pressure
> 150 psig.
I p . .V [ E ACTION: Q) f sd [ghy a. With a RCIC system actuation instrumentation channel trin set-point less conservative than the value shown in the Allowable Values column of Table 3,3.4-2, declare the channel inoperable f' y and place.the inoperable channel in the tripped condition until ciLO
- O the channel is restored to OPERABLE status with its trip set '
p gnt adjusted consistent with the Trip Setpoint value, 1 i g hpc b. With the-requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place the in-
$n y' cC g operable channel in the tripped condition or declare the RCIC
- 3 q) system inoperable within e e-hour.
O! ilt hoe. SM c. With the requirements for the minimum number of OPERABLE channels not satisfied for both trip systems, declare the <T RCIC system inoperable within one hour. L__ _ _ L SlJRVEILLANCE REQUIREMENTS
=.
4.3.4.1 Each RCIC system actuation instrumentation chanael shall be demonstrated OPERABLE by the performance of the CHANNEL CiiECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION at the frequencies shown in Table 4.3.4-1. 4.3.4.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system. L (' - ) - HATCH - UNIT 2 3/4 3-33 W -.
. TABLE 3. 3. ts- 1 % INSTRUMENTATION REACTOR CORE 1501ATION COOLING SYSTEM ACTUATION M
o MINIMUM NUMBER OF - Z OPERABLE CHANNoLS
' PER TPip SYSTEM FUNCTIONAL UNITS C 2
- a. Reactor VesselB,Water Level - Low Low (Level 2)
-4 (2821-N692 A, C, D) to Condensst; Storage Tank 2(a) *=.
h,N,Wate'
- LeveI - Lov (2E51-N060. 2E51-N061) 2(al C. Suppression Pool Water Leve l-H i gli (2E51-N062A, D)
LAE N Jb G3 e CaJ JD i i .' ! 1 is'
@ (a) Provides signal to RCIC Pump Suction valves only
=
ft Z~
.O N
.VG s c
, o +
- --- - ~
n.-~~- -
- - ~ = -..-
I \4
1 e , tI V V S T N E M E R I U N Q O - E R LI ET NA V E NR R Q Q C AB N Hl A Cl L A L -C I E V R U S M % O i L A 4 A T LA' EN Q I A 3
/
N NOT " - E M U NIS ATE J 4 W W- - liC R C g T . 1 S ~.
- N s
V I
- f. i 3 N -
O 4 I T E A L U B T A C ' T A L EK M NC E NE S A A T . AH M N S HC Y C S G N I L O '- O l C e v N e k r O L n I a e T r T t A L O S
.T I
e t-a) e g W a V S N W2 a r l I U o li o o E L ee t P R A sv S O N so nh C O eL ew o ;. I V( to il R T aL sH O T C A E R C N U F rw oo tL c sn-et de pe aw nv pv eo oe ue s e-rt b RL CL SL F a b c V_ _ n r 3N2 , C2 . w% w@ a2=tc 2? wV* U J .
~
, .- ._ _ - - - . - - - . - . - . m..-.,. - - , - . ~ -
p - 4 - p INSTRUMENTATION-s r- [{H H p 3/4.3.5 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION m i LIMITING CONDITION FOR OPERATION 4 r ,- . 18 p' ' ' ..
' 3"3.3.5 ThecontrolrodwithdrawalblockinstrumentationshownknTable-f '3.3.5-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.5-2.
~
k[w F A
- 1. ApPLIP BILITY: As shown in Table 3.3.5-1.
[ ACTION: y - - - a .~ - Nith a control rod withdrawal block instrumer.tation channel - trip setpoint less conservative than the value shown in the r
'Allowal b Values column of Table 3.3.5-2, declare-the channel ,
e inoperable until the channel is restored to OPERABLE status vith .it s trip setpoint adjusted consistent with the Trip [ Setpois,t value.
-b. With '.he requirements for the minimum number of OPERABLE
[~ channels.not satisfied for any trip function, place that . .
+ rip fur -tf u in the tripped condition within one hour.
n (w^A : -- (;. m dt. The p-ovisions of Specification 3.0.3 are not applicable 7 in OPERATIONAL CONDITION 5. SURVEILLANCE ~ REQUIRPiENTS _, (p - 4i3.5' Each 'of the above required control rod withdrawal block instrumen-tation~ channels shall be demonstrated OPERABLE by the performance of-the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CliANNEL CALIBRATION operations during the OPERATIONAL CONDITIONS =and at the frequencies ( shown in Table 4.3.5-1.
- h. _.O,;Orseg in Sch tmwd thCumkK6j be hopemble Sd- up io t w e a c ee m m www smees gw
[- +c; enkH oce omec ctppiicnL,le Aerto/JS. b- 6 f .
- p- .
HATCH - UNIT 3/4 3-37
.- . - i .,
- , - - ,e,-- -- , ,e r y
TABLE 3.3.5-1 g -. CONTROL ROD WITHDRAWAL BLOCK :INSTRUMEr4 TAT lON
'c> MINIMUM huMBER Of APPL! CABLE -
2 OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION PER TRIP FUNCTION CONDITIONS s' E 1. _VRM-(2 CSS-k605 A, B, C, D, E, F)
- a. Flow Parerenced Simulate.1 Therma l; 'si 1 l' ru ,4.
Powe. - Upscale-Qg- :*- l G*; b, - I nope ra t ive - '4 1, i. $ 4
~b. '
'c. Downscale 4 4
1
.2, 5
- d. Neutron Flux - High, ~e2%-
.2. ROD BLOCK MONITOR (2C51-K605 RBM A and B) 1
- a. Upscale 1 1 1'*8
.b. I nope ra tive
- c, Downscale 1 1'**
p 3. SOURCE RANGE MONITORS (2C51-K60V A, B, O. D) 3 2
- a. _ Detector not full in'**
? 5 Upscale t *3 3 2
- b. 2 5
- c. I nope ra t i ve '
- 2 3 2 g 2 5 Downscale 3 2
'd.
A 2 - 5 y e W 14 INTERMEDIATE RANCE v.ONIT6etS g' (2C51-K601 A, B, C, D, E, F, C. H) i '8 6 2, 5
- a. 'et9c' or not full in 2, 5
- b. Upscale 6 Inope ra t ive 6 2, 5 c.
- d. Downscate'** 6' 2
- 5. SCRAM DISCilARGE VOLUMF, (I'G.1-N013C) a Water Level-High '; I* 2 I
r E. CL n, r* Z'
?' . % . 3 s
m- -a . -c_ - _.. - - . - _ _
- t
. TABLE 3.3.5-1-(Continued) - .
U }O:- CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION
; -. . . i INOTE: -
ri , W ; a. -- ;When the. limiting condition defined in section 3.1.4.3 exists. k l
;bL This function is bypassed if detector is' reading > 100 cps or the IRM i channels are on range =3.or higher.
[C -- c . . This function is bypassed when the associated IRM channels are on frange 8 or_ higher.
~
Ld. ' A total of.6:IRM-instruments must be OPERABLE.
- e. .<
Tnis-function 1s-bypassed when the IRM channels are on range 1. -l
' f .= . 'With any controit rod withdrawn. Not applicable to control rods 1
- removed per Specification-3.9.11.1 or 3.9.11.2. l LJiW5ywd d - c4>vvLvo ( rods 'i s %t p en;hL Aw,7O -
l repsuU s uv e i b t.c bsth 3 q t 1 1
}
4 1 5 . ,. L 4
^
-] l e
I ii t
%- t HATCH -: UNIT;2' 3/4 3 Amendment No. 39, 106 ' l-
- 1 l
iJ
~ p~; .J =;,;, .. ;,, ...; ... ;. ;3:, ;;= ,. ;. ...,; ; ; . . z. ; :; ~ ~ .-- ~ .- ; , , ,, . , ,, __
__it_________________________________
.. . .o - <
lQ, WO
< ;) 1Y, .
^
t i r yQ- _
.Q ;,
. p w >
; i, ;f l' ib' -4 TABLE 4.315.-11 c3 .
2s K' . CONTROL' ROD WITHDRAWAL BLOCK . INSTRUMENTATION SURVEILLANCE REQUIREMENTS-- s ' CHANNEL-' ' > .. 'OPERAfl0NAL: C . CHANNEL FUNCTIOMAL CHAMMEL - COMOI TI081S ' IN WHICM :
- TEST
..CAllBRATIONIal'
' SURVEILLANCE REQUIRED
.. - TRIP FUMCTION~ CHECK :
, -4 i,j '1 4 APRM: g.
a.. Flow Referenced Simulated Thermal Power-Upscale NA :' 'S/U **,Q 9 R 1.
. 2- Inope ra tive _C1 S/U
S/U'**,Q. r' ;NA. 1,2,5
- c. Cmmsca ie ' . . .MA R 1
- - d. Neuiron Flux.'- high,.127, NA. S/U'*8,Qt R. 2, 5
-l
'2. Rod Block Monitor:
3 <a
'^
- a. . Upscale -NA- . S/t 78 Q -' R 1888-
- b. Inope ra tive NA S/U'*8,, Qu NA. 1888 S/U'
- 8. , Qi
- c. Downscale NA R t'*8 3.- ~ Source Range Monitors: '*-
, s. Detector not full in NA S/U,W NA 2, 5
. b. Upscale '. _ 'NA: S/U,W R 2, 5
- c. Inope ra t ive NA S/U8*8 MA 2, 5
- - . 68 d. Downscale'. MA S/U'*8,W ,W R 2, 5 4 N .,
A I.t Intermediate Range Monitors: w lo E W
- a. ' Detector not full in- .NA - S/U,W
S/U,W'** NA 2, 5 ' 2, 5 s b, Upscale NA R l c. Inopera t ive NA 4 S/U,W NA'- 2, 5: I d. Downscale NA S/U8**,W R 2, 5
- . m j 5. Scram Discharge Volume
! a. Water Level-High .NA Q R 1, 2, 5'*' l f 4 i s ; CL i B i- (D ' 3
, w a
O w W
^ (
W , C i
?
O t. I f
- 3
'i
[ e l n INSTRUMENTATION f['J 3/4.3.6 MONITORING INSTRUMENTATION l RADIATION MONITORING INSTRUMENTATION
'h = LIMITING CONDITION FOR OPERATION 3.3.6.1 The radiation monitoring instrumentation channels shown in
~
Table 3.3.6.1-1 shall be OPERABLE with their alarm / trip setpoints within the-specified limits. APPLICABILITY: As shown in Table 3.3.6.1-1. , ACTION:
- a. With a radiation monitoring instrumentation :;hannel alarm / trip setpoint exceeding the value shown in Table 3.3.6.1-1, adjust the setpoint to wit 51n the limit within 4 hours or declare the channel inopt.rable,
- b. With one or more of the above required radiation tronitoring instrumentation channels inoperable, take the ACTION required-J<
by Tgble 3.3.6.1-1.
~
- d. g. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
-C.One inedtttrent* C9 Cone;l rmy be inoperrthle 4br upio do flour-5,
-to phrfCf'vT reCpired Surveillace pt-icy -{D enWnct. C+her~
9.'RVEILLANCE REQUIfREMENTS hPPUcobie AGT1 CMS. l l 4.3.6.1- Each of th: above required radiation monitoring instrumentation channcis shall be demonstrated OPERABLE by the performance of the CHANNEL CHECX, CHANNEL FUNiTIONAL TEST and CHANNEL CALIBRATION operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.6.1-1. {. l . !C HATCH - UNIT 2 3/4 3-43 l
3 .
, INSTRilMENTATION L~ SEISMIC MONITORING INSTRUMENTATION I
LIMITIN3 CONDITION FOR OPERATION _ e
. O 3.3.6.2 The seismic monitoring instrumentation shown in Table 3.3.6.2-1 i shall be OPERABLE.
O' - APPLICABILITY: At all times, t.. . ACTION:
- e. With one or more of the above required seismic monitoring '
, instruments inoperable for more than 30 days, prepare and l ' submit a Special Report to the Commission within the next l' 10 days outlining the esuse of the malfunction and the plans for restoring the instrument (s) to OPERABLE status. !
s c 5 The provisions of Specifications 3.0.3 and 3,0.4 are not i applicable.
-b.
!>epermerm ic o gtrumen+ OinnnelSurveiHanceh rgygwrrd any Le incpertthde Pntr{ccioLtp+> 40 lohourn en er-inc Mer-I i
SURVEILLANCE REQUIREMENTS. CiP Pikmble. AcTy .i s 4.3.6.2.1 Each of the above reqJired seismic monitoring instruments ' shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNE8. FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the fre-quencies shown in Table 4.3.6.2-1. 4.0.6.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status within 24 hours and a CHANNEL. CALIBRATION performed within 30 days following the seismic event. Data shall be retrieved from actuated (- L instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the l Commission pursuant to Specification,6.9.2 v.ithin 10 days describing the magnitude, irequency spectrum and resultant effect upon facility features impertant to safety. HATCH - UNIT 2 . 3/4 3-47 Amendment No. JJ, 86 4 . s
e, ;;g : . .m- . , p.p _ y - ai * '
~
INSTRUMENTATION 3 -. . ~ . ffS REMOTE SHUTDOWN MONITORING INSTRUMENTATION 14 t . n -.
.)
~
4 - _
- aDj
{ LIMITING-CONDITION FOR OPERATION -
- TM 3;; -
~
e ?/M3.6.-3' Thel remote shutdown monitoring instrumentation channels' shown l in Table-3.3.6.3-1 shall be OPERABLE with readouts displayed external to
- g. --the control room.
h* .m t APPLICABILIH: CONDITIONS I, 2 and 3. g , ACTION:
]
g a.- With one or more of:the above required remote shutdown monitoring
-instrumentation channels inoperable, either restore the inoperable
[b; ; channel (s) to OPERABLE status within 30 days or be in at least HOT- -1 l SHUTDOWN within the-next-12 hours and in COLD SHUTDOWN within the @v following 24 hours,
=
'G.)'; -The provisions of Specification 3.0.4 are not applicable.-
/
-h. Cne-inshumer+ cnannel may be inopetttbAe b upit 6 hcurs _ .
; l
; 4t p e d er1% _ _ 11(ccC{ 6Lirvei((cmce25 pr1'cF Mo enfetinc
- ~'
w c4her aPPlicct le Aert6M5. ] _ SURVEILLANCE REQUIREMENTS 4.3.6.3 Each of the above required remote shutdown. monitoring instrumen-tation channels shall be_ demonstrated OPERABLE by performance of the i
- CHANNEL CHECK and CHANNEL CALIBRATION operations at the_ frequencies '
shown-i_n Table _4.3.6.3-1.
*- +-4 f,
i= y. j
~ - -
co a-i[ HAT'CH - UNIT-2 3/4 3-50 )k - 4 . ~ . - .
l
' INSTRUMENTATION- l
. .- l P ST-ACCIDENT-MONITORING-INSTRUMENTATION 1
LIMITING CONDITION FOR OPERATION p ,
'3-3.6.4- The_ post-accident-monitoring instrumentation channels shown in Table 3.3.6.4-1 shall be OPERABl.E.
APPLICABILITY: CONDITIONS 1, 2, and 3*. { ACTION,:
- a. :With one or more of the above required post-accident monitoring channels.
inoperable,-either restore the inoperable channel (s) to OPERABLE status ' within 30 days or'be in at least HOT SHUTDOWN within the next 12 hours. Gy. The provisions of Specification 3.0.4 are not applicable,
- b. One (notrume:nh channel mcq be (noperctble fer- up 4o 6 hottrs
+c perkern rce tir cdher oppuccMeannepue .ed durveittacces price io enaerirscx-
~J. SURVEILLANCE REQUIREMENTS 7 ,.
Q 4'.3.6;4 Each of the above required post accident monitoring instrumentation
- channels shall be demonstrated OPERABLE by performance- of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and. CHANNEL CALIBRATION operations at the frequencies l
- shown in Table:4.3.6.4-1. -
[ ifl 1
-w "Condid on 3jis aopticable only to Items 12, 13, and 14 of Table 3.3.6.4-1.
HATCH'- UNIT 2 3/4 3-53 Amendment No.-45'
- , g. . . . . , , . . . . . . - .
7 4 .. ' g:. i E- ,
!l
!j l!,
Iq j!) ; 8 g' ' i . Q r s - e t u n -
) )
im 0 C - 3 ( c c( n
) ) i MLlS E_ ) b b h -
UEB ) ) b ( ( t MNA a a' ( i NR 2 2 2 2 2 2 2 2 2' ( ( 2 2 1 1 w INAE y HP . IMCO
)
i l t
'v -
)
M ) i N - 1 b O M K 3 a
- I * - 6 p ^
T K d R a A n - c T d a 1 N n 1 g E a H D n
- M - 2 i U
')
H A ) ( l p
< R -
T 7 A 4 B r m 1 S 2 0 o a s
- l i ) 6 1 0 , t 4 f 5 R 0 M A i 1 - 3 - 1 n s 6 C 6 7 9 1 0 o u M R 4 - 2 6 M o 3 I - T 1 B R ) u R 1 2 ) 2 2 - 1 t n
_ ' 3 O 2 9 B ( 8 3 n i T 8 [ 0 2 4 6 e t E I 2 ) 6 6 ) ( r T R u n L M 8 2 R Q o 2 - i o B D
, 6 - r t 1 r r
c A M 0 ', R 8 , o a , 1 /, T 1 A - 4 C t c ) B D E h T 6 ' 7 T
)
- a. i B c d
( t t e ,. , 3 '% . N P 2 4 2 , , i E - 2 T 7 B i n , A r n w D ) 1 6 2 , 2 ' , d i A 1 o e e" I
- 8 2 R ( 8 ) C ) n t d C 8 - 0 9 R A 8 I y 1 2 i i l C , 2 8 e 6 0 - -
r 0 6 n c b A A ( 4 r R 6 7 2 , y a 6 K o c a
- T u - R- 4 T26 A r. R - M A r T 3 l 2 t 8 a.d m o 8 n - 1 - e p
S 2 e ( a 4 8 2 K r
- 1. 1 t t o
O 6 v T 4 - 0 i c 4 D n s P e 6 r e 2 e o p 2( R e l T 1 1
- L e 2 6 1 R P. S 2 ( u P e.
ev e em ' 1 . 2 0 - ( i bA 2 r , . 6 2 3 n n n r m C B e L T r 8 R ( 3 P i i r i o o e o r uE n l
.lL O
2 t - u 0 - ( r r s 6 7 n 2 t t u t . e a e e s 3 4 o ( i i s a t l ha s e t t e - T s s s i n P r u a a r 5 2 i r W W P 4 T ( t a e P P
- o. o e d r a d e
t sn g s - I z P R i n ri s o r r r 2 e d( e ly v v e e c V e c e er e r e e e r a zu r h b b b u R a l l g g A yd ' P S m m m e t n a a n n - t g n l an . a a a r a a A V V a a no l l . h h h u r m s r r. R R s i o d Ai e e C C C s e m p a O e e h h P t s s s l s s n 'n n e m C - i a l ig g i Ou na e e o o o r eP T A H l
- e. e H H c B l i k u t
V v i i i a s s s C R R Hc
- r. r 'e, s s l l O l / / l l t r a o ot e e l l l y y l l S o l T
t c c r r p p p w w r e e.Lt- ew e t t ef wy yw ni ac e e t lS eC wC
- N a a p p p y y s y f r a e .
E M e e u u u r r R R S S S D D o r PaD aS S D D M R
- r. yE r
U Dn % R ) ) a T b e S . . . . . . . . . a. . . . . hf N 1 2 3 4 5 6 7 8 9 0 1 2 3 4 To I 1 1 1 1 1 " F g
~ I l
, . * ,k l*
$*8 c::a y N a a t&4 @ gm3t :e * . . -
i N
. lf , ' ,* ' , .' .
h
.y INSTRUMENTATION g -
je > r SOURCE RANGE MONITORS g. P.g LIMITING CONDITION FOR-OPERATION _ __
- w. .
p 3.3.6.5 Three source range monitors shall be OPERABLE. s .a [ AP'PLICABILITY: CONDITIONS 2*, 3 and 4. Ll ACTION: h o
- a. In CONDITION 2* with one of the above required source range monitors )
7 inoperable, restore 3 source range monitors to OPERABLE status i~ within 4 hours or be in at least HOT SHUTDOWN within the next 6 hours.
$ b. In CONDITION 3 or 4, with two or more of the above required source ti range monitors inoperable, verify all control rods to be fully inserted =_
in the core and lock the reactor mode switch in the Shutdown position within one hour. O, Onr. indt unen! channel n tuj t.c ic .q crtdAo Sc r up b [4 htar,b i a vnn nxudred thrvcdllcmoen, SURVEILLANCE REQUIREMENTS prvr E eMerircd M& appuccdge A03 tC&5 rt - - b 4.3.6.5 Each of the above required source range monitors shall be demon- ') strated OPERABLE by:
- a. Performance of a:
,7
- 1. CHANNEL CHECK at least once per: .
(a) 12 hours in CONDITION 2*, and (b) 24 hours in CONDITION 3 or 4. - 1 CHANNEL CALIBRATION ** at least once per 18 months, 2.
- b. Performance of a CHANNEL FUNCTIONAL TEST:
- g. 1. Within 24 hours prior to moving the reactor trade switch from )
the Shutdown position if not performed within the previous 7 days, and g 2. At least once per 31 days.
- c. Verifying, prior to withdrawal of control rods, that the SRM count )
rate is at least 3 cps with the detector fully inserted. l
*With 166 on range 2 or below. -
p { **May exclude neutron detectors. j h HAllH-UNIT 2 - 3/4 3-56 r
;. INSTRUMENTATIO_N MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM (MCRECS) ACTUATION INSTlIOMENTATION i
LIMITING CONDITION FOR OPERATION ' 9 i l h 3.3.6.7 The MCRECS nctuation instrumentation channels shown in Table 3.3.6.7-1 shall be uPERABLE, with their trip setpoints set consistent with the j values shown in the Trip Setpoint column of Table 3.3.6.7-2.
)
APPLICABILITY: As shown in Table 3.3.6.7-1.
! ACTION:6.As shown in Table 3.3.6.7-1. ' b. Ore indrurnent cho.nnet on/ be intpxtrJ9e for ((
40 per4ccro tuf ttir ccl $ttrveiHctmds prior 4c+er-i a >p nc de 6 hcae cAher- c(PP UGL'WC AOTIDMS. t SURVEILLANCE REQUIREMENTS
.8 4.3.6.7 Each MCRECS acta tion channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations'during the OPERA 1IONAL CONDITION and at the frequen'cles )'
1hown in Table 4.3.5.7-1. l
.]
h HATCH - UNIT 2 3/4 3-58 Amendment No. 71
E I e. TABLE 3.3.6.7-1 ($HEET 2 0F 2] MCRECS ACTUATION DS'4UMENTAT10N ACTION , ACTION 52 - Take the ACTION required by Specificat1on 3.3,3. ACTION 53 - Take the ACTION required by Specification 3.3.2. ACTION 54 -
. a. With one of the required radiation monitors inoperable, restore the monitor to OPERABLE status within 7 days or, within the next 6 hours, ,
initiate and maintain operation of the MCRECS in the pressurization mode of operation. <
- b. With no radiation monitors OPERABLE, within 1 hour initiate and maintain operation of the MCRECS in the pres urization mode of operation, c The provisions of Specification 3.0.4 are not applicable, n s EO,JEj!
'j When handlin T>eJe4ed.g irradiated fuel in secondary containment._
- a. A chan I may bg placed i an inoper'abla sta Ls for upAcY ho s for requi d survefilance wi out plac hg the t p system in the Ipped condi, ton,. prghided at } ast one her OPES BLE chanp/'l in same t
e t ip tyltJm is morfit,orino thht par me} r, / /
- b. With'a design providing only one channel per trip system, an inoperable ch.cnnel need not be placed in the tripped condition where this would cause -the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within hours or the ACTION required by Table 3.3.6.7-1 for_that Trip Funct'on shall be taken.
12., -
- c. Actuates the MCRECS tr the control room pressuri.ation mode, l
- d. (Deleted)
- e. Within 24 hours prior to the planned start of the hydrogen in,4ection test with the reactor power at greater than 20-percent rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on uther calculations or measurements of actual radiation levels resulting from hydrogen j injection. The background _ radiation level shall be determined and _
associated trip setpoints shall be set ,vithin 24 hours of re-establishing , i normal radiation levels af ter completion of hydrogen injection and prior ~j j to establishing reactor power levels below 20 percent rated pcwer. HATCH - UNIT 2 3/4 3-58b Amendment No. 7J, dB, 96 I c- -
2 IABLE le.3.6.7-1 N n MCRECS ACTUAllON INSTRUMEt4 TAT ION SURVE lll ANCE REQO f flLMtNTS
- CHANNEL OPER#fIONAL e Cl1ANNEL fUNCT10NAL CHANNEL COND41 IONS IN MIICH TRIP TUfiCT!ON CliECK FEST CAttBRATION SURVEftlANCE REQUIRED c.
z Q l. Reactor Vesses ;.ater Level - S . pQ R 1,2,3 Low Low Low (Level 1) N
- 2. Dryve l l' Pres su re - H igh S yQ R. 1, 2, 3 . ,g .
- 3. ~ Main Steam Line Radiation - ;gh p' D ' W8*8 R 1,2,3 ts . Main Steam Line flow - High. S >t' Q R .1, 2, 3
- 5. Rerueling Floor Area Radiation - gd W Cy M Q 1, 2, 3. 5
- liigh
- 6. Control Rcom Air' Inlet NA F AI 9 R 1, 2, 3, 3,
- _
Radiation - liigh w N b w s , <n CL
- When handling irradiated fuel en the secondary contanssme.t.
- a. Instrument alignment using a standard current source. - 4-3a B
O a n., D $ 4 1 . 3 to "l3
\
2 O N o m a N A & Q I
e p . [. p 1 c INSTRbMENTATION-p RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION f LIMITING CONDITION FOR OPERATION i . jh~ _13.3.6.9 The radioactive liquid effluent monitoring instrumentation channels shown in table 3.3.6.9-1 shall be
- OPERABLE with their alarm / trip setpoints set to ensure that the
" limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (0DCM). APPLICABILITY As shown in table 3.3.6.9-1. ACTION
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpcint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, declare the channel-inoperable, or change to a conservative value.
.s. ~
. b. With the number of channels OPERABLE less tnan the minimum channels required by table 3.3.6.9-1, take the ACTION shown in table 3.3.6.9-1.
.g. The provisions of Specifications 3.0.3, 3'.0.4, and 6.9.1.13(b) are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.6.9 ~ Each radioactive liquid effluent monitoring , instrumentation channel shall be demonstrated OPERABLE by performance or the CHANNEL CHECK, SOURCE CHECK, CHANNEL
.,_ CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the
( frequencies snown in table 4.3.6.9-1,. o.One g er insumed Ecr m re deel redyLLd beEtimpertate er up +c I.o hours llCuTe5 priCF 40 err',,e.rin
- c4her appiioc6te AoytoM6.
t .. HATCH . UNIT 2 3/4 3-60a Amendment No. 48 r +g w -e p * *
- we- m.--w' .a.es..a go- m . we-e. - . p - gpr4
[ INSTRUMENTATION ,, RADI0 ACTIVE GASEOUS EFFLUENT INSTRilMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.10 The radioactive gaseous effluent monitoring instrumentation channels shown in table 3.3.6.10-1 shall be
}
OPERABLE with their alarm / trip setpoints set to ensure that the h limits of Specification 3.11.2.1(a) are not exceeded. The _-alarm / trip setpoints of these channels shall be determined in j 'accordance with the ODCM. 4 APPLICABILITY I As shown in table 3.3.6.10-1. r ACTION
- a. e u h a radioactive gaseous effluent monitoring natrumentation channel alarm / trip setpoint less conservative than a value that will ensure that the o limits of 3.11.2.1(a) are met, without dele / restore the setpoint to a value that will ensure that the limits of Specification 3.11.2.1(a) are met or declare the channel inoperable.
)
b, With the number of channels OPEDABLE less than the . A minimom channels required by table 3.3.6.10-1, take the ACTION shown in table 3.3.6.10-1. C g. The provisions of Specifications 3.0.3, 3.0.4, and 6.9.2.13(b) are not applicable. CURVEILLANCE REQUIREMENTS 4.3.6.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the irm uencies shown in table 4.3.6.10-1. 4, One inshumetY Cd'4Lon8I 0)Cu/ be inCpercd.>le Onr- up ~fe ~ [p h0Lors 40 per@crrv\ recfuiMrd 'iltrv'Gi((RnOES pricr-
.+c enknncj c4her app \idctbie AGTmus. y 4
r HATCH - UNIT 2 3/4 3-60f Amendment No. 48
?
,. INSTRUMENTAQ0N
,(
3/4.3.8 DEGRADED STATION VOLTAGE PROTECTION INSTRUMENTATION
~ ? LIMITING CONDITION FOR 0?ERATION _
3.3.8 The degraded station voltage relay channels shown in Teble 3.3 B-1
* , 'shall be OPERABLE,
' APPLICABILITY: CONDITIONS 1, 2, and 3.
ACTION: a,With the number of OPERABLE channels one less than the required OPERABLE channels, operatien may procated 'Jntil performarn,e of the next scheduled instrument functional test provided a trip signal is placed in the LOSP
- lock-out relay logic for the applicable inoperable channel.
+
SURVEILLANCE REQUIREMENTS 4.3.8 Each c,f the above required degraded station voltage relay channels
- hall be demonstrated OPERABLE by performance of the CHANNEL CALIBRATION and
- - CHANNEL FUNCTIONAL, TEST operation at the frequencies shown in Table 4.3.8-1.
T_. l
. k .bOne insh ment' Cluned may be incperrdde. Scr up it Ic hcurs 4o perQ Frq n= td reci 6urveillctnCe5 pricr -in erdeHnc caer ctppucche K5' CMS.
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- P HATCH-UNIT 2 3/4 3-63 Amendment No. 27
____-_.m_.-_____.___._______m__ . _ , _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , , , _ , _ _ _ _ _ _ _ , _ _
INSTRUMENTAT10N
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3/4.3.9 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION
&THSRECIRCULATIONPUMPTRIPSYSTEMINSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.9.1 The anticipated tienslent without scram recirculation pump trip (ATHS-RPT) system instrumentation channels shown in Table 3.3.9.1-1 shall be OPERABLE with their trip setpoints set consistent with values shown in the Trip Setpoint column of Table 3.3.9.1-2.
l APPLICABILITY: OPERATIONAL FONDIT10N 1. '
)
ACTION:
- a. With kn ATHS recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.9.1-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel trip setpoint adjusted consistent with the Trip Setpoint value.
- b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System reautrement for one or both trip systems, place the inoperabit Channel in the tripped condition hop.
within '- /lZ k n With the number of OPERABLE channels two less than required by the c. Minimum OPERABLE Channels per Trip System requirement for one. trip )
, system and,
- 1. If the inoperable channels consist of one reactor vessel water level channel and one reactor vessel pressure channel, place both inoperable channels in the tripped condition within 1--4,ow.
Althwr%
- 2. If the inoperable channels include two reactor vessel water level channels or two reactor vessel pressure channels, declare the trip system inoperat>1e.
- d. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 14 days or be in at least STARTUP within the next 6 hours,
- e. With 00th trip systems inoperable, restore at least one trip system to OPERABLE status within I nour or be in at least STARTUP within the next 6 hours.
SURVE!LLANCE REQUIREMENTS
}
4.3.9.1.1 Each ATHS recirculation pump trip system instrumentation channel shall be demonstrated OPL.J.BLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.9.1-1. 4.3.9.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months. ) HATCH - UNIT 2 3/4 3-66 Amendment No O , 110
- ay gg OM hours indhmec+
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i . INSTRUMENTATION
' ') -
g END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION t LIMITING CONDIf 0N FOR OPERATION ,_, 3.3.9.2 The end-of-cycle recirculation pump trip (EOC-RPT) system ' instrumentation channels shown in Table 3.3.9.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint i column of Table 3.3.9.2-2 and with the dND-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.9.2-3. i APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER. ACTION:
- a. With an end-of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.9.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel setpoint adjusted consistent with the Trip Setpoint value.
- b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both 4 trip systems, place the inoperable channel (s) in the tripped )
, condition within one-houo.
12 lv.u rd .
- c. With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system and:
- 1. If the inoperable channels consist of one turbine control valve channel and one turbine stop valve channel, place both inoperable channels in the trippeo condition within ona hour.
d.17 k ur-5.
- 2. If the inoperable channels include two turbine control valve channels or two turbine stop valve channels, declare the trip system inoperable.
- d. With one trip system inoperable, restore the inoperable trip system to OPERABLE status within 72 hours or reduce THERMAL POWER to less than 30% of RATED THERMAL POWER within the next 6 hours,
- e. With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or reduce THERMAL POWER to less y than 30% of RATED THERMAL POWER within the next 6 hours, k Crc indrumed c'harmel rey be iGCperable itr up it (f httu s +c per crto FGgidr d du.rvciliculeeS pr-ict- '
Yo enMMoo e'rker- a.ppuccile. AOTlcus. h HATCH - UNIT 2 3/4 3-70 Amendment No. 69
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l i HATCH ; UNIT 2 3/4 3-72 Amendment No. 69 Y- t 4 i t) l ~i t _-____-A-_-__-___________-
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T ABLE ti. 3.9.2.J-1 1 M Q!D-OF-CYCLE REC 1RCULAf f 0M FUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS o X CitANNEL CHAMMEL 8 FUNCTIONAL TEST PALIBRATtOM C: z TRlr FUNCTlot! R
- 1. Turbine Stop Valve - Closure Q >(*
to R _ 2i Turbine Control Valve - Fast Closure Cf ff* w b Y N (n l l l
- D 3
O. O ro 3
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*the Recirculation Pump Breakers need not be tripped on part of the Channel functionsf Test.
All channel alarm functions and only that portion or' the trip ronctions which can be tested without causing a trip of the Breakers Functionst Test. (and Recirculation Pumps) need be tested durirrg the Channel L __
.,+.y . ., , .
J REACTOR COOLANT SYSTEN,
- .;k gOL .3/4.4.2 ' SAFETY / RELIEF YALVES
# C-g LINITING CONDITION FOR OPEeATION
-J' i 3.4.2.1 .The safety valve function of the following reactor coolant system
- 0 , g. Tsafety/ relief valves shall be OPERABLE with the mechanical lift settings
-within i 11 of the indicated pressures *.
E._g . g 4 Safety-relief valves 9 1090 psig.
;-~ g 4 Safety-relief valves 91100 psig".
-6 3 Safety-relief valves 9 1110 psig**.
U C ]b APPLICABILITY: CONDITIONS 1, 2 and 3.
-O b ' ACTION:
?
- a. For low-low set valves, take the action required by Specification 3.4.2.2. For ADS valves, take the action required by Specification 3.5.2. *
*Q % b.. With one or more safety / relief valves stuck open, place the reactor yWct:0 -
mode switch,in the Shutdown position.
- c. With one or more TRY tailpipe pressure switches of an S/RV declared
.gL -
inoperable and the associated S/RV(s) otherwise indicated to be open,
- g. place the reactor mode switch in the shutdown position.
-5 .
- d. With one $/RV tailpipe pressure swltch of an S/RV declared inoperable -
g d , and the associated S/RV(s) otherwise indicated to be closed, plant operation may continue. Remove the function of that pressure switch
-b ] from the low low set logic circuitry until the next COLD SHUTDOWN.
{. Upon COLD SHUTDOWN, restore the pressure switch (s) to OPERABLE status before STARTUP.
<bo '
' e. With both S/RV tallpipe pressure switches of an S/RV declared inop- -
h erable and the associated S/RV(s) otherwise indicated to be closed,
- y. restore at lea;t one inoperable switch to OPERABLE status-within c
14 days or be in at least HOT SHUT 00WN within the next 12-hours and -
- -s in COLD SHUTDOWN within the following 24 hours,r 7 - f. The failure or malfunction of any safety / relief 9alve shall be Y -
_ reported by telephone within 24 hours; confirmed by telegraph, a , mailgram, or facsimile transmission to the Birector of the Regional Office, or his designee no later than the first working day
.F following the event; and a written followup report within 30 days.
The written followup report should be completed in'accordance with 10 CFR-50.73 or other applicable requirements. SURVEILLANCE REOUIRENENTS= 4.4.2.1 The tail-pipe pressure switches of each safety / relief valve shall be-demonstrated OPERABLE by performance of:
- a. CHANNEL FUNCTIONAL TEST: -
- 1. At least once per 4 except that all portions of the channel inside the primary containment may be excluded from the CHANNEL FUNCTIONAL. TEST, and.
- 2. At each scheduled outage of greater than'72 hours during which}}