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{{Adams
#REDIRECT [[NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 4]]
| number = ML15350A410
| issue date = 12/15/2015
| title = E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 4
| author name = Pierce C R
| author affiliation = Southern Co, Southern Nuclear Operating Co, Inc
| addressee name =
| addressee affiliation = NRC/NRR
| docket = 05000321, 05000366
| license number =
| contact person =
| case reference number = NL-14-1075
| package number = ML15351A023
| document type = Technical Specifications
| page count = 74
}}
 
=Text=
{{#Wiki_filter:Suppression Chamber-to-Drywell Vacuum Breakers3.6.1.83.6 CONTAINMENT SYSTEMS3.6.1.8 Suppression Chamber-to-Drywell Vacuum BreakersLCO 3.6.1.8Ten suppression chamber-to-drywell vacuum breakers shall beOPERABLE for opening.ANDTwelve suppression chamber-to-drywell vacuum breakers shall beclosed, except when performing their intended function.
APPLICABILITY:
MODES 1, 2, and 3.ACTIONS_________________
___CONDITION REQUIRED ACTION COMPLETION TIMEA. One required suppression A.1 Restore one vacuum 72 hourschamber-to-drywell vacuum breaker to OPERABLEbreaker inoperable for status.opening.C.dywl C.umbeae-- 1 bekrOn uppression chamber-Close the open vacuum 2 hoursnot closed.Required Action and Be MODE 3. 12 hoursassociated Completion Time not met. AND D2I~ f onitonCIBe in MODE 4. 36 hoursIlNSERT-TS 3.6.1.8IlCondition BHATCH UNIT 2 3613.6-19 TS 3.6.1.8.
-Condition B InsertB. Required Action and B.1 ----NOTE----------.....
associated Completion LCO 3.0.4a is not applicable Time of Condition A not when entering MODE 3.met.Be in MODE 3. 12 hours RHR Suppression Pool Cooling3.6.2.33.6 CONTAINMENT SYSTEMS3.6.2.3 Residual Heat Removal (RHR) Suppression Pool CoolingLCO 3.6.2.3APPLICABILITY:
Two RHR suppression pool cooling subsystems shall be OPERABLE.
MODES 1, 2, and 3.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One RHR suppression poolcooling subsystem inoperable.
lTwo RHR suppression poolS cooling subsystems inoperable.
[tRequired Action andassociated Completion Time
* Condition CI.JNSERT
-TS 3.6.2.3I,Condition BA. 1Restore RHRsuppression poolcooling subsystem toOPERABLE status.7 daysone RHRsuppression poolcooling subsystem toOPERABLE status.MODE 3.IIf B nMODE 4.8 hours12 hours36 hoursSURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling In accordance withsubsystem manual, power operated, and automatic the Surveillance valve in the flow path that is not locked, sealed, or Frequency Controlotherwise secured in position is in the correct Programposition or can be aligned to the correct position.
(continued)
HATCH UNIT 2 3623.6-25 TS 3.6.2.3 -Condition B InsertB. Required Action and B. 1 ---NOTE .............
associated Completion LCO 3.0.4.a is not applicable Time of Condition A not when entering MODE 3.met.Be in MODE 3. 12 hours RHR Suppression Pool Spray3.6.2.43.6 CONTAINMENT SYSTEMS3.6.2.4 Residual Heat Removal (RHR) Suppression Pool SprayLCO 3.6.2.4APPLICABILITY:
Two RHR suppression pool spray subsystems shall be OPERABLE.
MODES 1, 2, and 3.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One RHR suppression pool A.1 Restore RHR 7 daysspray subsystem suppression pool sprayinoperable, subsystem toOPERABLE status.B. Two RHR suppression pool B.1 Restore one RHR 8 hoursspray subsystems suppression pool sprayinoperable, subsystem toOPERABLE status.C. Required Action and C.1 ..Be in MODE 3. 12 hoursassociated Completion
/Time not met.-NOTE----
LCO 3.0.4.a is not 0 .2 Dei- MODE. 4. applicable when enteringM D 3........................._
_ _ _ _ _ _ _SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify each RHR suppression pool spray In accordance withsubsystem manual, power operated, and the Surveillance automatic valve in the flow path that is not locked, Frequency Controlsealed, or otherwise secured in position is in the Programcorrect position or can be aligned to the correctposition.
(continued)
HATCH UNIT 23.6-27HATH^NI 23.-2....
11111... .210 Secondary Containment 3.6.4.13.6 CONTAINMENT SYSTEMS3.6.4.1 Secondary Containment LCO 3.6.4.1APPLICABILITY:
-NOTE-------....
LCO 3.0.4.a is notapplicable when enteringMODE 3.The secondary containment shall be OPERABLE.
MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel--(OPDRV).ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. Secondary containment A.1 Restore secondary 4 hoursinoperable in MODE 1, 2, containment toor 3. OPERABLE status.B. Required Action and B.1 kBe in MODE 3. 12 hoursassociated Completion Time of Condition A not ____met.C. Secondary containment C.1------NOTE-
--inoperable during LCO 3.0.3 is notmovement of irradiated fuel applicable.
assemblies in thesecondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuelOPDRVs. assemblies in thesecondary containment.
AND__________________________________________________(continued)
HATCH UNIT 2 3633.6-33 Secondary Containment 3.6.4.1No change. Included forinformation only.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEC. (continued)
C.2 Suspend CORE Immediately ALTERATIONS.
ANDC.3 Initiate action to Immediately suspend OPDR Vs.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment equipment In accordance withhatches are closed and sealed. the Surveillance Frequency ControlProgramSR 3.6.4.1.2 Verify one secondary containment access door in In accordance witheach access opening is closed, the Surveillance Frequency ControlProgramSR 3.6.4.1.3-----------NOTE-
------The number of standby gas treatment (SGT)subsystem(s) required for this Surveillance isdependent on the secondary containment configuration, and shall be one less than thenumber required to meet LCO 3.6.4.3, "StandbyGas Treatment (SGT) System,"
for the givenconfiguration.
Verify required SGT subsystem(s) will draw In accordance withdown the secondary containment to > 0.20 inch the Surveillance of vacuum water gauge in < 120 seconds.
Frequency ControlProgram(continued)
HATCH UNIT 23.6-34HATC UNI 2 36-34Amendment No. 210 SGT System3.6.4.3No change. Included forinformation only.3.6 CONTAINMENT SYSTEMS3.6.4.3 Standby Gas Treatment (SGT) SystemLCO 3.6.4.3APPLICABILITY:
The Unit 1 and Unit 2 SOT subsystems required to support LCO 3.6.4.1,"Secondary Containment,"
shall be OPERABLE.
MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel(OPDRV).ACTIONS, IrvI-----------
Nil)!When two Unit 1 SOT subsystems are placed in an inoperable status solely for inspection of theUnit 1 hardened vent rupture disk, entry into associated Conditions and Required Actions maybe delayed for up to 24 hours, provided both Unit 2 SGT subsystems are OPERABLE.
CONDITION REQUIRED ACTION COMPLETION TIMEA. One required Unit 1 SGT A.1 Restore required Unit 1 30 days fromsubsystem inoperable SGT subsystem to discovery of failure towhile: OPERABLE status. mfeet the LCO1. Four SGT subsystems required
: OPERABLE, and2. Unit 1 reactorbuilding-to-refueling floor plug not installed.
(continued)
HATCH UNIT 23.6-39HATC UNI 2 36-39Amendment No. 135
-NOTE-LCO 3.0.4.a is notapplicable when enteringMODE 3.SGT System3.6.4.3MUL I [L;UU]I~t]U~gU)
__ _ _ _ _ __ _ _ _ _CONDITION REQUIRED ACTION COMPLETION TIMEB. One required Unit 2 SGT B.1 Restore required SOT 7 dayssubsystem inoperable, subsystem toOPERABLE status. ANDOR30 days fromOne required Unit 1 SGT discovery of failure tosubsystem inoperable for meet the LCOreasons other thanCondition A.C. Required Action and C.1 " Be in MODE 3. 12 hoursassociated Completion Time of Condition A or B A-Enot met in MODE 1, 2, or 3. ID. Required Action and---------NOTE-
---associated Completion LCO 3.0.3 is not applicable.
Time of Condition A or Bnot met during movementof irradiated fuel D.1 Place remaining Immediately assemblies in the OPERABLE SOTsecondary containment, subsystem(s) induring CORE operation.
ALTERATIONS, or duringOPDRVs. ORD.2.1 Suspend movement of Immediately irradiated fuelassemblies insecondary containment.
ANDD.2.2 Suspend CORE Immediately ALTERATIONS.
ANDD.2.3 Initiate action to Immediately suspend OPDRVs.(continued)
HATCH UNIT 2 3643.6-40
-NOTE-.......
LCO 3.0O4.a is notapplicable when enteringMODE 3.SGT System3.6.4.3ACTIONS (continued)
CONDITION RQUIRED ACTION COMPLETION TIMEE. Two or more required SGT E.1 "'!-- .I ..dattsubsystems inoperable inMODE 1,2, or3. einMD 3. ____,--_12hours F. Two or more required SGT F.1------NOTE-.........
subsystems inoperable LCO 3.0.3 is notduring movement of applicable.
irradiated fuel assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuelOPDRVs. assemblies insecondary containment.
ANDF.2 Suspend CORE Immediately ALTERATIONS.
ANDF.3 Initiate action to Immediately suspend OPDR Vs.SURVEILLANCE REQUIREMENTS
_______SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each required SGT subsystem for In accordance with> 15 continuous minutes.
the Surveillance Frequency ControlProgramSR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance withwith the Ventilation Filter Testing Program (VFTP). the VFTP(continued)
HATCH UNIT 236413.6-41 RHRSW System3.7.13.7 PLANT SYSTEMS3.7.1 Residual Heat Removal Service Water (RHRSW) SystemLCO 3.7.1Two RHRSW subsystems shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One RHRSW pump A.1 Restore RHRSW pump 30 daysinoperable, to OPERABLE status.B. One RHRSW pump in each B.1 Restore one RHRSW 7 dayssubsystem inoperable, pump to OPERABLEstatus.C. One RHRSW subsystem-------------NOTE-------
inoperable for reasons Enter applicable Conditions andother than Condition A. Required Actions of LCO 3.4.7,"Residual Heat Removal (RHR)Shutdown Cooling System -HotShutdown,"
for RHR shutdowncooling miade inoperable byRHRSW System.C.1 Restore RHRSW 7 dayssubsystem toOPERABLE status.-, INSERT -TS 3.7.1Condition D(continued)
HATCH UNIT 23.7-1HATH UIT 3.-1A,,-e 1d,,-e1t ,No. 1.901 TS 3.7.1 -Condition D InsertD. Required Action and D.1 ----NOTE- ---associated Completion LCO 3.0.4.a is not applicable Time of Condition A, B, or when entering MODE 3.C not met.Be in MODE 3. 12 hours RHRSW System3.7.1ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIMEBoth RHRSW subsystems inoperable for reasonsother than Condition B.Enter applicable Conditions andRequired Actions of LCO 3.4.7for RHR shutdown cooling madeinoperable by RHRSW System.8 hours] Required Action and LI Iassociated Completion Time ln ot met.Iof Condition EBe in MODE 3.ANDBe in MODE 4.HATCH UNIT 23.7-2 PSW System and UHS3.7.23.7 PLANT SYSTEMS3.7.2 Plant Service Water (PSW) System and Ultimate Heat Sink (UHS)LCO 3.7.2Two P3W subsystems and UHS shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One PSW pump inoperable.
A.1 Restore PSW pump to 30 daysOPERABLE status.B. One PSW turbine building B.1 Restore PSW turbine 30 daysisolation valve inoperable, building isolation valveto OPERABLE status.C. One PSW pump in each C.1 Restore one PSW 7 dayssubsystem inoperable, pump to OPERABLEstatus.D. One PSW tur'bine building D.1 Restore one PSW 72 hpursisolation valve in each turbine buildingsubsystem inoperable, isolation valve toOPERABLE status.INSERT -TS 3.7.2Condition E(continued)
HATCH UNIT 23733.7-3 TS 3.7.2 -Condition E InsertE. Required Action and E.1-----NOTE-............
associated Completion LCO 3.0.4.a is not applicable Time of Condition A, B, C, when entering MODE 3.or Dnot met.Be in MODE 3. 12 hours PSW System and UHS3.7.2ACTIONS (continued)
CONDITION REQUIRED ACTION [COMPLETION TIMEOne PSW subsystem inoperable for reasonsother than Conditions Aand B.-~~NOTES--
1.Enter applicable Conditions and Required Actions ofLCO 3.8.1, "AC Sources -Operating,"
for dieselgenerator made inoperable by PSW System.2. Enter applicable Conditions and Required Actions ofLCO 3.4.7, "Residual HeatRemoval (RHR) ShutdownCooling System -HotShutdown,"
for RHRshutdown cooling madeinoperable by PSWSystem.Restore the PSWsubsystem toOPERABLE status.72 hours+Required Action andassociated Completion Time of Condition
~por et.Be in MODE 3.AND12 hours36 hoursBe in MODE 4.ORR -Both PSW subsystems inoperable for reasonsother than Conditions Cand D.ORUHS inoperable.
L:5.r3.7-4HATCH UNIT 2 3.7-4 Amcndmcnt No. 135 MCREC System3.7.43.7 PLANT SYSTEMS3.7.4 Main Control Room Environmental Control (MCREC) SystemNo change. Included forinformation only.LCO 3.7.4Two MCREC subsystems shall be OPERABLE.
-----------------
NOTE----------------
The main control room envelope (ORE) boundary may be opened intermittently underadministrative control.APPLICABILITY:
MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel(OPDRVs).
ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One MCREC subsystem A.1 Restore MCREC 7 daysinoperable for reasons subsystem toother than Condition
: 8. OPERABLE status.B. One or more MCREC B.1 Initiate action to Immediately subsystems inoperable due implement mitigating to inoperable ORE actions.boundary in MODE 1, 2,or 3. ANDB.2 Verify mitigating actions 24 hoursensure ORE occupantexposures toradiological,
: chemical, and smoke hazards willnot exceed limits.ANDB.3 Restore ORE boundary 90 daysto OPERABLE status.(continued)
HATCH UNIT 23.7-8HATC UNI 2 37-8Amendment No. 212
-NOTE-LCO 3.0.4.a is notapplicable when enteringMODE 3.MCREC System3.7.4ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIMEC. Required Action and C.1 Be in MODE 3. 12 hoursassociated Completion Time of Condition A or B I/not met in MODE 1,2, or 3.ID. Required Action andassociated Completion Time of Condition A notmet during movement ofirradiated fuel assemblies in the secondary containment, during COREALTERATIONS, or duringOPDR Vs.-----------------
NOTE-------
LCO 3.0.3 is not applicable.
D.1 Place OPERABLEMCREC subsystem inpressurization mode.OR_D.2.1 Suspend movement ofirradiated fuelassemblies in thesecondary containment.
ANDD.2.2 Suspend COREALTERATIONS.
ANDImmediately Immediately Immediately Immediately
-.......NOTE-------....
LCO 3.0.4.a is notlapplicable when enteringIMODE 3.'1D.2.3 Initiate action to"\ suspend OPDRVs.E. Two MCREC subsystems inoperable in MODE 1, 2,or 3 for reasons other thanCondition B.E.1 E11t~~1LCO 3.3.3T""12 hours(continued)
HATCH UNIT 237-3.7-9 MCREC System3.7.4No change. Included forinformation only.ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIMEF. Two MCREC subsystems-------NOTE-----
inoperable during LCO 3.0.3 is not applicable.
movement of irradiated fuelassemblies in thesecondary containment, F. 1 Suspend movement of Immediately during CORE irradiated fuelALTERATIONS, or during assemblies in theOPDR Vs. secondary containment.
OR ANDOne or more MCREC F.2 Suspend CORE Immediately subsystems inoperable due ALTERATIONS.
to an inoperable CREboundary during movement ANDof irradiated fuelassemblies in the F.3 Initiate action to Immediately secondary containment, suspend OPDRVs.during COREALTERATIONS, or duringOPDR Vs.SURVEILLANCEREQUIREMENTS
_______SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREC subsystem
> 15 minutes.
In accordance withthe Surveillance Frequency ControlProgramSR 3.7.4.2 Perform required MCREC filter testing in In accordance withaccordance with the Ventilation Filter Testing the VFTPProgram (VFTP).SR 3.7.4.3 Verify each MCREC subsystem actuates on an In accordance withactual or simulated initiation signal. the Surveillance Frequency ControlProgram(continued)
HATCH UNIT 23.7-10HATC UNI 2 37-10Amendment No. 212 Control Room AC System3.7.53.7 PLANT SYSTEMS3.7.5 Control Room Air Conditioning (AC) SystemNo change. Included forinformation only.LCO 3.7.5APPLICABILITY:
Three control room AC subsystems shall be OPERABLE.
MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel(OPDRVs).
ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One control room AC A.1 Restore control room 30 dayssubsystem inoperable.
AC subsystem toOPERABLE status.B. Two control room AC B.1 Verify control room area Once per 4 hourssubsystems inoperable, temperature
< 90&deg;F.ANDB.2 Restore one control 7 daysroom AC subsystem toOPERABLE status.C. Three control room AC C.1 Verify control room area Once per 4 hourssubsystems inoperable, temperature
< 90&deg;F.ANDC.2 Restore one control 72 hoursroom AC subsystem toOPERABLE status.(continued)
HATCH UNIT 23.7-12HATC UNI 2 37-12Amendment No. 214 AC-~NOTE----
LCO 3.0.4.a is notapplicable when enteringMODE 3.Control Room AC System3.7.5CONDITION XREQUIRED ACTIONCOMPLETION TIMED. Required Action and D.1 Be in MODE 3. 12 hoursassociated Completion
___________
Time of Condition A, B, or IC not met in MODE 1, 2, or3. h9 eP in .MODEl A.16horE. Required Action and---------NOTE-
---associated Completion LCO 3.0.3 is not applicable.
Time of Condition A not met------------
during movement ofirradiated fuel assemblies in E.1 Place OPERABLE Immediately the secondary containment, control room ACduring CORE subsystems inALTERATIONS, or during operation.
OPDRVs.ORE.2.1 Suspend movement of Immediately irradiated fuelassemblies in thesecondary containment.
ANDE.2.2 Suspend CORE Immediately ALTERATIONS.
ANDE.2.3 Initiate action to Immediately suspend OPDR Vs.(continued)
HATCH UNIT 23.7-13HATC UNI 2 37-13Amedmont
,No. 2 11 Main Condenser Offgas3.7.63.7 PLANT SYSTEMS3.7.6 Main Condenser OffgasLCO 3.7.6APPLICABILITY:
The gross gamma activity rate of the noble gases measured at the maincondenser evacuation system pretreatment monitor station shall be< 240 mCi/second.
MODE 1,MODES 2 and 3 with any main steam line not isolated and steam jet airejector (SJAE) in operation.
ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. Gross gamma activity rate A.1 Restore gross gamma 72 hoursof the noble gases not activity rate of the noblewithin limit, gases to within limit.B. Required Action and B.1 Isolate all main steam 12 hoursassociated Completion lines.Time not met.-NOTE------OR LCO 3.0.4.a is not 8.2 Isolate SJAE. 12 hoursapplicable when entering\
MODE 3. OR..l Be in MODE 3. 12 hoursB,,.3.., l l % l,.l,,,,
-I.v l -IHATCH UNIT 2 3713.7-16 AC Sources -Operating 3.8.1INo change. Included for3.8 ELECTRICAL POWER SYSTEMS linformation only.3.8.1 AC Sources -Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:
: a. Two qualified circuits between the offsite transmission networkand the Unit 2 onsite Class 1 E AC Electrical Power Distribution System;b. Two Unit 2 diesel generators (DGs);c. The swing OG;d. One Unit 1 DG;e. One qualified circuit between the offsite transmission network andthe Unit 1 onsite Class 1 E AC Electrical Power Distribution subsystem(s) needed to support the Unit 1 equipment required tobe OPERABLE by LCO 3.6.4.3, "Standby Gas Treatment (SGT)System";
LCO 3.7.4, "Main Control Room Environmental Control(MCREC) System";
and LCO 3.7.5, "Control Room AirConditioning (AC) System";f. Two DGs (any combination of Unit 1 DGs and the swing DG),each capable of supplying power to one Unit 2 low pressurecoolant injection (LPCI) valve load center; andg. One qualified circuit between the offsite transmission network andthe applicable onsite Class 1 E AC electrical power distribution subsystems needed to support each Unit 2 LPCI valve load centerrequired by LCO 3.5.1, "ECCS -Operating."
APPLICABILITY:
MODES 1, 2, and 3.3.8-1HATC UNI 2 38-1Amendment No. 152 AC Sources -Operating 3.8.1ACTIONSNo change. Included forinformation only.-NOTE.LCO 3.0.4.b is not applicable to DGs.CONDITION REQUIRED ACTION COMPLETION TIMEA. One required offsite circuit A.1 Perform SR 3.8.1.1 for 1 hourinoperable.
OPERABLE requiredoffsite circuits.
ANDOnce per 8 hoursthereafter ANDA.2 Declare required 24 hours from discovery feature(s) with no offsite of no offsite power topower available one 4160 V ESF businoperable when the concurrent withredundant required inoperability offeature(s) are redundant requiredinoperable, feature(s)
ANDA.3 Restore required offsite 72 hours*circuit to OPERABLEstatus. AND17 days fromdiscovery of failure tomeet LCO 3.8.1.a, b,or cB. One Unit 2 or the swing DG B.I1 Perform SR 3.8.1.1 for 1 hourinoperable.
OPERABLE requiredoffsite circuit(s).
ANDOnce per 8 hoursthereafter AND________________________
______________________(continued)
HATCH UNIT 23.8-2HATC UNI 2 38-2Amendment No. 190 AC Sources -Operating 3.8.1No change. Included forinformation only.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEB. (continued) 8.2 Declare requiredfeature(s),
supported bythe inoperable DC,inoperable when theredundant requiredfeature(s) areinoperable.
ANDB.3.1 Determine OPERABLEDG(s) are notinoperable due tocommon cause failure.OR8.3.2 Perform SR 3.8.1.2.a forOPERABLE DC(s)AND8.4 Restore DG toOPERABLE status.4 hours from discovery of Condition Bconcurrent withinoperability ofredundant requiredfeature(s) 24 hours24 hours72 hours for aUnit 2 DC withthe swing DC notinhibited ormaintenance restrictions not metAND14 days for aUnit 2 DG withthe swing DCinhibited fromautomatically aligning toUnit 1 andmaintenance restrictions metAND72 hours for the swingdiesel withmaintenance restrictions not met(continued)
HATC UNI 2 38-3Amendment No. 203HATCH UNIT 23.8-3 AC Sources -Operating 3.8.1No change. Included forinformation only.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEB. (continued)
B.4 (continued)
AND14 days for the swingdiesel withmaintenance restrictions metAND17 days fromdiscovery of failure tomeet LCO 3.8.1 .a, b,or cC. One required Unit 1 DGinoperable.
C.1 Perform SR 3.8.1.1 forOPERABLE requiredoffsite circuit(s).
ANDC.2 Declare requiredfeature(s),
supported bythe inoperable DG,inoperable when theredundant requiredfeature(s) areinoperable.
ANDC.3.1 Determine OPERABLEDG(s) are notinoperable due tocommon cause failure.ORC.3.2 Perform SR 3.8.1.2.a forOPERABLE DG(s).1 hourANDOnce per 8 hoursthereafter 4 hours fromdiscovery of Condition Cconcurrent withinoperability ofredundant requiredfeature(s) 24 hours24 hours(continued) 3.8-4HATC UNI 2 38-4Amendment No. 203 AC Sources -Operating 3.8.1No change. Included forinformation only.IJCONDITION REQUIRED ACTIONCOMPLETION TIMEC. (continued)
ANDC.4Restore required DG toOPERABLE status.7 days with theswing DG notinhibited ormaintenance restrictions not metAND14 days with theswing DG inhibited from automatically aligning to Unit 2 andmaintenance restrictions met4 4D. Two or more requiredoffsite circuits inoperable.
D.1 Declare requiredfeature(s) with no offsitepower available inoperable when theredundant requiredfeature(s) areinoperable.
ANDD.2 Restore all but onerequired offsite circuit toOPERABLE status.12 hours from discovery of Condition Dconcurrent withinoperability ofredundant requiredfeature(s) 24 hours4 4E. One required offsite circuitinoperable.
ANDOne required DGinoperable.
-~~NOTE--
--Enter applicable Conditions andRequired Actions of LCO 3.8.7,"Distribution Systems -Operating,"
when Condition E isentered with no AC power sourceto one 4160 V ESF bus.E.1 Restore required offsitecircuit to OPERABLEstatus.12 hours(continued)
Amendment No. 203HATCH UNIT 238-3.8-5 AC Sources -Operating 3.8.1ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIMEE. (continued)
ORE.2 Restore required DG 12 hoursto OPERABLE status.F. Two or more (Unit 2 and F.1 Restore all but one 2 hoursswing) DGs inoperable.
Unit 2 and swing DGsto OPERABLE status.G. No DGs capable of G.1 Restore one DG 2 hourssupplying power to any capable of supplying Unit 2 LPCI valve load power to Unit 2 LPCIcenter. valve load center toOPERABLE status.H. Required Action and H.1 /t1e in MODE 3. 12 hoursAssociated Completion fTime of Condition A, B, C,D, E, F, or G not met.One or more required 11 Enter LCO 3.0.3. Immediately offsite circuits and two or pmore required DGs jINOTEinoperable.
JLCO 3.0.4.a is nottapplicable when enteringOR JMODE 3.Two or more requiredoffsite circuits and onerequired DG inoperable.
HATCH UNIT 23.8-6HATCHUNIT2 3.-6 Amndrn ,'oN. 20311 DC Sources -Operating 3.8.43.8 ELECTRICAL POWER SYSTEMS3.8.4 DC Sources -Operating No change. Included forinformation only.LCO 3.8.4The following DC electrical power subsystems shall be OPERABLE:
: a. The Unit 2 Division 1 and Division 2 station service DCelectrical power subsystems;
: b. The Unit 2 and the swing DGs DC electrical powersubsystems; andc. The Unit 1 OG DC electrical power subsystems needed tosupport the equipment required to be OPERABLE byLCO 3.6.4.3, "Standby Gas Treatment (SGT) System";LCO 3.7.4, "Main Control Room Environmental Control (MCREC)System";
LCO 3.7.5, "Control Room Air Conditioning (AC) System";and LCO 3.8.1, "AC Sources -Operating."
APPLICABILITY:
MODES 1, 2, and 3.ACTIONS ________CONDITION REQUIRED ACTION COMPLETION TIMEA. Swing DG DC electrical A.1 Restore DG DC 7 dayspower subsystem electrical powerinoperable due to subsystem toperformance of SR 3.8.4.7 OPERABLE status.or SR 3.8.4.8.OROne or more requiredUnit I DG DC electrical power subsystems inoperable.
(continued)
HATCH UNIT 23.8-26HATC UNI 2 38-26Amendment No. 169 DC Sources -Operating 3.8.4ACTIONS (continued)_________________________
CONDITION REQUIRED ACTION COMPLETION TIMEB. One Unit 2 DG DC B.1 Restore DG DC 12 hourselectrical power subsystem electrical powerinoperable, subsystem toOPERABLE status.OR_ R______SINOTE----
Swing DG DC electrical ILCO 3.0.4.a is notpower subsystem
[- applicable when enteringinoperable for reasons _MODE 3other than Condition A. -3..........
C. One Unit 2 station service C.1\ Restore station service 2 hoursDC electrical power \ DC electrical powersubsystem inoperable, subsystem toOPERABLE status.D. Required Action and D.1 "Be in MODE 3. 12 hoursAssociated Completion Time of Condition A, B, Nor C not met.E. Two or more DC electrical E.1 Enter LCO 3.0.3. Immediately power subsystems inoperable that result in aloss of function.
HATCH UNIT 2 3823.8-27 Distribution Systems -Operating 3.8.7No change. Included forinformation only.3.8 ELECTRICAL POWER SYSTEMS3.8.7 Distribution Systems -Operating LCO 3.8.7APPLICABILITY:
The following AC and DC electrical power distribution subsystems shallbe OPERABLE:
: a. Unit 2 AC and DC electrical power distribution subsystems comprised of:1. 4160 V essential buses 2E, 2F, and 2G;2. 600 V essential buses 2C and 20;3. 120/208 V essential cabinets 2A and 2B;4. 120/208 V instrument buses 2A and 2B;5. 125/250 V DC station service buses 2A and 2B;6. DG DC electrical power distribution subsystems; andb. Unit 1 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE byLCO 3.6.4.3, "Standby Gas Treatment (SGT) System";
LCO 3.7.4,"Main Control Room Environmental Control (MCREC) System";LCO 3.7.5, "Control Room Air Conditioning (AC) System";
andLCO 3.8.1, "AC Sources -Operating."
MODES 1, 2, and 3.ACTIONS ________CONDITION REQUIRED ACTION COMPLETION TIMEA. One or more required A.1 Restore required 7 daysUnit 1 AC or DC electrical Unit 1 AC and DCpower distribution subsystem(s) tosubsystems inoperable.
OPERABLE status.(continued)
HATCH UNIT 23.8-37HATH NI 2 .837Amendment No. 210 I Distribution Systems -Operating 3.8.7ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIMEB. One or more (Unit 2 or B.1 Restore DG DC 12 hoursswing bus) DG DC electrical powerelectrical power distribution distribution subsystem ANDsubsystems inoperable, to OPERABLE status.16 hours fromdiscovery of failure tomeet LCO 3.8.7.aC. One or more (Unit 2 or C.1 Restore AC electrical 8 hoursswing bus) AC electrical power distribution power distribution subsystem to ANDsubsystems inoperable.
OPERABLE status.16 hours fromdiscovery of failure tomeet LCO 3.8.7.aD. One Unit 2 station service D.1 Restore Unit 2 station 2 hoursDC electrical power service DC electrical distribution subsystem power distribution ANDinoperable, subsystem toOPERABLE status. 16 hours fromdiscovery of failure tomeet LCO 3.8.7.aE. Required Action andassociated Completion Time of Condition A, B, C,or D not met.F. Two or more electrical power distribution subsystems inoperable thatresult in a loss of function.
HATCH UNIT 2 3833.8-38 RPS Electric Power Monitoring B 3.3.8.2BASESACTIONS Al1 (continued) operations personnel to take corrective actions or to place the plant inthe required condition in an orderly manner and without challenging plant systems.Alternately, if it is not desired to remove the power supply from service(e.g., as in the case where removing the power supply(s) from servicewould result in a scram or isolation),
Condition C or D, as applicable, must be entered and its Required Actions taken.B._.11If both power monitoring assemblies for an inservice power supply(MG set or alternate) are inoperable or both power monitoring assemblies in each inservice power supply are inoperable, the systemprotective function is lost. In this condition, 1 hour is allowed torestore one assembly to OPERABLE status for each inservice powersupply. If one inoperable assembly for each inservice power supplycannot be restored to OPERABLE status, the associated powersupply(s) must be removed from service within 1 hour (Required Action B.1). An alternate power supply with OPERABLE assemblies may then be used to power one RPS bus. The 1 hour Completion Time is sufficient for the plant operations personnel to take corrective actions and is acceptable because it minimizes risk while allowingtime for restoration or removal from service of the electric powermonitoring assemblies.
Alternately, if it is not desired to remove the power supply(s) fromservice (e.g., as in the case where removing the power supply(s) fromservice would result in a scram or isolation),
Condition C or D, asapplicable, must be entered and its Required Actions taken.p ~ ~ ~ ~ ~tepant smtonusscmpi paigt be proant in withDEin12 hoyReuirs dAto n asoiae ThemaloeCmpeti onoCodtonditi ae on C e (contin2 o 3ap~rt .u ed)--HATCHtUNIT-1 3.3.- 196^- .."'^-^";.
.... ''
INSERT -Bases 3.3.8.2 Condition CRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 4) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action C.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
RPS Electric Power Monitoring B 3.3.8.2BASESACTIONSC. 11=-. (continued) required plant conditions from full power conditions in an orderlymanner and without challenging plant systems.Dl.1 D.2.1. and D.2.2If any Required Action and associated Completion Time ofCondition A or B are not met in MODE 4 or 5 with any control rodwithdrawn from a core cell containing one or more fuel assemblies orwith both RHR shutdown cooling valves open, the operator mustimmediately initiate action to fully insert all insertable control rods incore cells containing one or more fuel assemblies.
RequiredAction 0.1 results in the least reactive condition for the reactor coreand ensures that the safety function of the RPS (e.g., scram of controlrods) is not required.
In addition, action must be immediately initiated to either restore oneelectric power monitoring assembly to OPERABLE status for theinservice power source supplying the required instrumentation powered from the RPS bus (Required Action 0.2.1) or to isolate theRHR Shutdown Cooling System (Required Action 0.2.2). RequiredAction 0.2.1 is provided because the RHR Shutdown Cooling Systemmay be needed to provide core cooling.
All actions must continueuntil the applicable Required Actions are completed.
SURVEILLANCE REQUIRE MENTSThe Surveillances are modified by a Note to indicate that when anRPS electric power monitoring assembly is placed in an inoperable status solely for performance of required Surveillances, entry intoassociated Conditions and Required Actions may be delayed for up to6 hours provided the other RPS electric power monitoring assemblyfor the associated power supply maintains trip capability.
Uponcompletion of the Surveillance, or expiration of the 6 hour allowance, the assembly must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken.SR 3.3.8.2.1 A CHANNEL FUNCTIONAL TEST is performed on each overvoltage, undervoltage, and underfrequency channel to ensure that the entirechannel will perform the intended function.
Any setpoint adjustment shall be consistent with the assumptions of the current plant specificsetpoint methodology.
(continued)
HATCH UNIT 1B3319B 3.3-197 RPS Electric Power Monitoring B 3.3.8.2BASES (continued)
REFERENCES
: 1. FSAR, Section 8.7.2. NRC Generic Letter 9 1-09, "Modification of Surveillance Interval for the Electrical Protective Assemblies in PowerSupplies for the Reactor Protection System."3. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.IINSERT -BASES 3.3.8.2< iReference HATCH UNIT 1B33-9B 3.3-199 INSERT -Bases 3.3.8.2 Reference
: 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
ECCS -Operating B 3*5.1BASESACTIONS A.1 (continued) based on a reliability study (Ref. 11) that evaluated the impact onECCS availability, assuming various components and subsystems were taken out of service.
The results were used to calculate theaverage availability of EGOS equipment needed to mitigate theconsequences of a LOCA as a function of allowed outage times (i.e.,Completion Times).B.1 plant riskIf the inoperable low pressure ECCS subsystem cannot be restored toOPERABLE status within the associ efd Completion Time, the plantmust be brought to a MODE in which'e LCde ota#,, Toachieve this status, the plant must be brought to at least MODE 3within 12 hours .. _-,wun,,,
,u* he allowedCompletion easonable, based on ope experience, toreach the required plah conditions from full power c qditions in anorderly manner and wit ut challenging plant systems.]
--Time is INSERT -BASES 3.5.1 IC.1 and 0.2 Condition BIf the HPCI System is inoperable and the RCIC System is verified tobe OPERABLE, the HPCI System must be restored to OPERABLEstatus within 14 days. In this condition, adequate core cooling isensured by the OPERABILITY of the redundant and diverse lowpressur~e ECCS injection/spray subsystems in conjunction with ADS.Also, the RCIC System will automatically provide makeup water atmost reactor operating pressures.
Verification of RCICOPERABILITY within 1 hour is therefore required when HPCI isinoperable.
This may be performed as an administrative check byexamining logs or other information to determine if RCIC is out ofservice for maintenance or other reasons.
It does not mean toperform the Surveillances needed to demonstrate the OPERABILITY of the RCIC System. If the OPERABILITY of the RCIC Systemcannot be verified,
: however, Condition E must be immediately entered.
If a single active component fails concurrent with a designbasis LOCA, there is a potential, depending on the specific failure,that the minimum required ECCS equipment will not be available.
A14 day Completion Time is based on a reliability study cited inReference 11 and has been found to be acceptable through operating experience.
(continued)
HATCH UNIT 1B3.-B 3.5-6 INSERT -Bases 3.5.1 Condition BRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 15), because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action B.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
ECCS -Operating B 3.5.1BASESACTIONSD.1 and D.2If any one low pressure ECCS injection/spray subsystem is inoperable in addition to an inoperable HPCI System, the inoperable lowpressure ECCS injection/spray subsystem or the HPCI System mustbe restored to OPERABLE status within 72 hours. In this condition, adequate core cooling is ensured by the OPERABILITY of the ADSand the remaining low pressure ECCS subsystems.
: However, theoverall ECCS reliability is significantly reduced because a singlefailure in one of the remaining OPERABLE subsystems concurrent with a design basis LOCA may result in the ECCS not being able toperform its intended safety function.
Since both a high pressuresystem (HPCI) and a low pressure subsystem are inoperable, a morerestrictive Completion Time of 72 hours is required to restore eitherthe HPCI System or the low pressure ECCS injection/spray subsystem to OPERABLE status. This Completion Time is based ona reliability study cited in Reference 11 and has been found to beacceptable through operating experience.
F.1an~d F.2With one ADS valve inoperable, no action is required, because ananalysis demonstrated that the remaining six ADS valves are capableof providing the ADS function, per Reference 13.INSERT -BASES 35.1Condition Ei.I;I .... n .... :__,J A--J.: .... .JA:_,I._-I ....
"If--: .... Klj~y~tny rr~uguiwu
~CLIOfl ano a~uociaioo
~om e~en-~me
~I ........ ..........
,or flwoor more ADS valves areinoperable, the plant must be brought to a condition in which the LCOdoes not apply. To achieve this status, the plant must be brought toat least MODE 3 within 12 hours and reactor steam dome pressurereduced to < 150 psig within 36 hours. Entry into MODE 3 is notrequired if the reduction in reactor steam dome pressure to < 150 psigresults in exiting the Applicability for the Condition, and the < 150 psigis achieved within the given 12 hours. The allowed Completion Timesare reasonable, based on operating experience, to reach the requiredplant conditions from full power conditions in an orderly manner andwithout challenging plant systems.When~ mult ECCSt subsystemsi aroe inoPerable, as Stacteddein analyses.
Therefore, LCO 3.0.3 must be entered immediately.
(continued)
HATCH UNIT 1B35-B 3.5-7 INSERT -Bases 3.5.1 Condition EE.__If any Required Action and associated Completion Time of Condition C or D is not met, theplant must be brought to a MODE in which overall plant risk is minimized.
To achieve thisstatus, the plant must be brought to at least MODE 3 within 12 hours.Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 15) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action E. 1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach therequired plant conditions from full power conditions in an orderly manner and withoutchallenging plant systems.
ECCS -Operating B 3.5.1BASES (continued)
REFERENCES
: 1. FSAR, Section 6.4.3.2. FSAR, Section 6.4.4.3. FSAR, Section 6.4.1.4. FSAR, Section 6.4.2.5. FSAR, Section 14.4.3.6. FSAR, Section 14.4.5.7. 10 CFR 50, Appendix K.8. ESAR, Section 6.5.9. NEDC-31376P, "ElI. Hatch Nuclear Plant Units 1 and 2SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis,"
December 1986.10. 10 CFR 50.46.11. Memorandum from R.L. Baer (NRC) to V. Stello, Jr. (NRC),"Recommended Interim Revisions to LCOs for ECCSComponents,"
December 1, 1975.12. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.13. NEDC-32041P, "Safety Review for Edwin I. Hatch NuclearPower Plant Units 1 and 2 Updated Safety/Relief ValvePerformance Requirements,"
April 1996.14. ASME, OM Code -1995, "Code for Operation andMaintenance of Nuclear Power Plants,"
Appendix I.ilNSERT-BASES 3.5.1 I< Reference' dHATCH UNIT 1 B351B 3.5-13 INSERT -Bases 3.5.1 Reference
: 15. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
RCIC SystemB 3.5.3BASESACTIONS A.1 and A.2(continued)
If the RCIC System is inoperable during MODE 1, or MODE 2 or 3with reactor steam dome pressure
> 150 psig, and the HPCI Systemis verified to be OPERABLE, the RCIC System must be restored toOPERABLE status within 14 days. In this condition, loss of the RCICSystem will not affect the overall plant capability to provide makeupinventory at high reactor pressure since the HPCI System is the onlyhigh pressure system assumed to function during a loss of coolantaccident (LOCA). OPERABILITY of HPCI is therefore verified within1 hour when the RCIC System is inoperable.
This may be performed as an administrative check, by examining logs or other information, todetermine if HPCI is out of service for maintenance or other reasons.It does not mean it is necessary to perform the Surveillances neededto demonstrate the OPERABILITY of the HPCI System. If theOPERABILITY of the HPCI System cannot be verified, however,Condition B must be immediately entered.
For non-LOCA events,RCIC (as opposed to H PCI) is the preferred source of makeup coolantbecause of its relatively small capacity, which allows easier control ofthe RPV water level. Therefore, a limited time is allowed to restorethe inoperable RCIC to OPERABLE status.The 14 day Completion Time is based on a reliability study (Ref. 3)that evaluated the impact on ECCS availability, assuming variouscomponents and subsystems were taken out of service.
The resultswere used to calculate the average availability of ECCS equipment needed to mitigate the consequences of a LOCA as a function ofallowed outage times (AOTs). Because of similar functions of HPCIand RCIC, the AOTs (i.e., Completion Times) determined for HPCIare also applied to RCIC.If the RCIC System cannot be restored to OPERABLE status withinoverall plant risk is Ithe associated Completion Time, or if the HPCI System is[minimized.
sim"I aneousl inoperable, the plant must be brought to a condition in" whc'l,,h LCOdoc no To achieve this status, the plant mustbem brought toatleast~
MOD 153 s within 36 hurs.~n he allowsedm based on operating experience, toreach the r uired plant conditions from full power condi l~ons in an(continued)
HATCH UNIT 1 B352B 3.5-23 INSERT -Bases 3.6.3 Condition BRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 6) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action B.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
RCIC SystemB 3.5.3BASESSURVEILLANCE REQUIREMENTS (continued)
SR 3.5.3.5 (continued) low water level (Level 2) signal received subsequent to an RPV highwater level (Level 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The LOGICSYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.2 overlaps thisSurveillance to provide complete testing of the assumed safetyfunction.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.This SR is modified by a Note that excludes vessel injection duringthe Surveillance.
Since all active components are testable and fullflow can be demonstrated by recirculation through the test line,coolant injection into the RPV is not required during the Surveillance.
REFERENCES
: 1. 10 CFR 50, Appendix A, GDC 33.2. FSAR, Section 4.7.3. Memorandum from R. L. Baer (NRC) to V. Stello, Jr. (NRC),"Recommended Interim Revisions to LCOs for ECCSComponents,"
December 1, 1975.4. GE Report AES-41-0688, "Safety Evaluation for Relaxation ofRCIC Performance Requirements for Plant'Hatch Units 1and 2," July 1988.5. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.IINSERT -BASES 3.5.31Reference HATCH UNIT 1 B352B 3.5-26 INSERT -Bases 3.5.3 Reference
: 6. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
Reactor Building-to-Suppression Chamber Vacuum BreakersB 3.6.1.7BASESACTIONS 0. 1(continued)
With one line with one or more vacuum breakers inoperable foropening, the leak tight primary containment boundary is intact. Theability to mitigate an event that causes a containment depressurization is threatened,
: however, if both vacuum breakers in at least onevacuum breaker penetration are not OPERABLE.
Therefore, theinoperable vacuum breaker must be restored to OPERABLE statuswithin 72 hours. This is consistent with the Completion Time forCondition A and the fact that the leak tight primary containment boundary is being maintained.
ConditionD D,~With two lines with one or more vacuum breakers inoperable foropening, the primary containment boundary is intact. However, in theevent of a containment depressurization, the function of the vacuumbreakers is lost. Therefore, all vacuum breakers in one line must berestored to OPERABLE status within 1 hour. This Completion Time isconsistent with the ACTIONS of LCO 3.6.1.1, which require thatprimary containment be restored to OPERABLE status within 1 hour.If the vacuum breakers inone or more lines cannot bethplnmutbbruhtoaMDinwchheLOdsnt closed or restored toOPERABLE status within py oaheeti tts h ln utb ruh oa esMODE 3 within 12 hours and to MODE 4 within 36 hours. Thethe required Completion allowed Completion Times are reasonable, based on operating Time, experience, to reach the required plant conditions from full powerconditions in an orderly manner and without challenging plantsystems.SURVEILLANCE SR 3.6.1.7.1 REQUIREMENTS Each vacuum breaker is verified to be closed to ensure that apotential breach in the primary containment boundary is not present.This Surveillance is performed by observing local or control roomindications of vacuum breaker position or by verifying a differential pressure of 0.5 psid is maintained between the reactor building andsuppression chamber.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.(continued)
HATCH UNIT 1 B363B 3.6-38 INSERT -Bases 3.6.1.7 Condition D0.1_If one line has one or more reactor building-to-suppression chamber vacuum breakersinoperable for opening and they are not restored within the Completion Time in Condition C, theremaining breakers in the remaining lines can provide the opening function.
The plant must bebrought to a condition in which overall plant risk is minimized.
To achieve this status, the plantmust be brought to at least MODE 3 within 12 hours.Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 4) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action 0.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach therequired plant conditions from full power conditions in an orderly manner and withoutchallenging plant systems.
Reactor Building-to-Suppression Chamber Vacuum BreakersB 3.6.1.7BASES (continued)
REFERENCES
: 1. FSAR, Section 5.2.2. Unit 2 FSAR, Section 6.2.1.3. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.ItNSERT -BASES 3.6.1.7IReference HATCH UNIT 1 B364B 3.6-40 INSERT -Bases 3.6.1.7 Reference
: 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
Suppression Chamber-to-Drywell Vacuum Breakers8 3.6.1.8BASESACTIONS A. 1 (continued) considered acceptable due to the low probability of an event in whichthe remaining vacuum breaker capability would not be adequate.
INSERT -BASES 3.6.1.8[--7 Condition BAn open vacuum breaker allows communication between the drywelland suppression chamber airspace, and, as a result, there is thepotential for suppression chamber overpressurization due to thisbypass leakage if a LOCA were to occur. Therefore, the openvacuum breaker must be closed. The required 2 hour Completion Time is allowed to close the vacuum breaker due to the low probability of an event that would pressurize primary containment.
he plant must be brought to a MODE in which the LCO does notappl .To achieve this status, the plant must be brought to at leastMOD 3 within 12 hours and to MODE 4 within 36 hours. Theallow d Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full powerconditions in an orderly manner and without challenging planto,,&#xf7;,4syste h pn upeso chme-odyelycu reae[~cannot be closed within the required Completion Time,SURVEILLANCE SR 3.6.1.8.1 REQUIREMENTS Each vacuum breaker is verified closed to ensure that this potential large bypass leakage path is not present.
This Surveillance isperformed by observing the vacuum breaker position indication or byverifying that a differential pressure of 0.5 psid between the drywelland suppression chamber is maintained for 1 hour without makeup.However, if vacuum breaker position indication is not reliable, eitherdue to: 1) dual or open indication while torus-to-drywell differential pressure remains normal, or 2) closed indication while torus-to-drywell differential pressure remains steady at 0 psid, alternate methods ofverifying that the vacuum breaker is closed are detailed in Technical Requirements Manual (TRM) (Ref. 4), T3.6.1, "Suppression (continued)
HATCH UNIT 1 B364B 3.6-44 INSERT -Bases 3.6.1.8 Condition BIf a required suppression chamber-to-drywell vacuum breaker is inoperable for opening and isnot restored to OPERABLE status within the required Completion Time, the plant must bebrought to a condition in which overall plant risk is minimized.
To achieve this status, the plantmust be brought to at least MODE 3 within 12 hours.Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 5) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action B.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach therequired plant conditions from full power conditions in an orderly manner and withoutchallenging plant systems.
Suppression Chamber-to-Drywell Vacuum BreakersB 3.6.1.8BASES (continued)
REFERENCES
: 1. FSAR, Section 5.2.2. Unit 2 FSAR, Section 6.2.1.3. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.4. Technical Requirements Manual, TLCO 3.6.1.IINSERT -BASES 3.6.1.8IReference HATCH UNIT 1 .-6REIIN3B 3.6-46 INSERT -Bases 3.6.1.8 Reference
: 5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
RHR Suppression Pool Cooling(continued)
With two RHR suppression pooi cooling subsystems inoperable, onesubsystem must be restored to OPERABLE status within 8 hours. Inthis condition, there is a substantial loss of the primary containment pressure and temperature mitigation function.
The 8 hour Completion Time is based on this loss of function and is considered acceptable due to the low probability of a DBA and because alternative methodsto remove heat from primary containment are available.
I-- Required Action and associated Completion Time'-cannot bemet, the plant must be brought to a MODE in which the LCO doesnot apply. To achieve this status, the plant must be brought to atleast MODE 3 within 12 hours and to MODE 4 within 36 hours. Theallowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full powerconditions in an orderly manner and without challenging plant systems.SURVEILLANCE SR 3.6.2.3.1 REQUIREMENTS Verifying the correct alignment for manual, power operated, andautomatic valves in the RHR suppression pool cooling mode flow pathprovides assurance that the proper flow path exists for systemoperation.
This does not apply to valves that are locked, sealed,or otherwise secured in position since these valves were verified to bein the correct position prior to locking,
: sealing, or securing.
A valve isalso allowed to be in the nonaccident position provided it can bealigned to the accident position within the time assumed in theaccident analysis.
This is acceptable since the RHR suppression poolcooling mode is manually initiated.
This SR does not require anytesting or valve manipulation; rather, it involves verification that thosevalves capable of being mispositioned are in the correct position.
ThisSR does not apply to valves that cannot be inadvertently misaligned, such as check valves.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.I (continued)
HATCH UNIT 1 B 3.6-57 IN1 INSERT -Bases 3.6.2.3 Condition BB__tIf one RHR suppression pool cooling subsystem is inoperable and is not restored toOPERABLE status within the required Completion Time, the plant must be brought to acondition in which overall plant risk is minimized.
To achieve this status, the plant must bebrought to at least MODE 3 within 12 hours.Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 4) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action B.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach therequired plant conditions from full power conditions in an orderly manner and withoutchallenging plant systems.
RHR Suppression Pool CoolingB 3.6.2.3BASESSURVEILLANCE REQUIREMENTS (continued)
SR 3.6.2.3.2 Verifying that each required RHR pump develops a flow rate> 7700 gpm while operating in the suppression pool coolingmode with flow through the associated heat exchanger ensures thatpump performance has not degraded during the cycle. Flow is anormal test of centrifugal pump performance required by ASME Code,Section XI (Ref. 2). This test confirms one point on the pump designcurve, and the results are indicative of overall performance.
Suchinservice tests confirm component OPERABILITY and detect incipient failures by indicating abnormal performance.
The Frequency of thisSR is in accordance with the Inservice Testing Program.REFERENCES
: 1. FSAR, Sections 5.2 and 14.4.3.2. ASME, Boiler and Pressure Vessel Code, Section XI.3. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.
-BASES 3.6.2.3[ Reference HATCH UNIT 1 B365B 3.6-58I INSERT -Bases 3.6.2.3 Reference
: 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
RHR Suppression Pool SprayB 3.6.2.4BASESACTIONS A. 1 (continued)
: However, the overall reliability is reduced because a single failure inthe OPERABLE subsystem could result in reduced primarycontainment bypass mitigation capability.
The 7 day Completion Timewas chosen in light of the redundant RHR suppression pool spraycapabilities afforded by the OPERABLE subsystem and the lowprobability of a DBA occurring during this period.B.__1With both RHR suppression pool spray subsystems inoperable, atleast one subsystem must be restored to OPERABLE status within8 hours. In this Condition, there is a substantial loss of the primarycontainment bypass leakage mitigation function.
The 8 hourCompletion Time is based on this loss of function and is considered acceptable due to the low probability of a DBA and becausealternative methods to remove heat from primary containment areavailable.
c_.1 .rminimized___
._: _If any Required Action and associated Completion Time cannot bemet, the plant must be brought to a MODE in whicl the-LC- -1tI~jTo achieve this status, the plant must be brought to at leastMODE 3 within 12 hoursI .he allowedCompletio reasonable, based on operating
_expe~ "-tea&#xa3;, toTmisreach the/required plant conditions from full power conditions in an-'I~ie i Iorderly manner and without challenging plant systems.
INSERT -BASES- 3.6.2.4Condition CSURVEILLANCE SR 3.6.2.4.1 REQUIREMENTS Verifying the correct alignment for manual, power operated, andautomatic valves in the RHR suppression pool spray mode flow pathprovides assurance that the proper flow paths will exist for systemoperation.
This SR does not apply to valves that are locked, sealed,or otherwise secured in position since these valves were verified to bein the correct position prior to locking,
: sealing, or securing.
A valve is also allowed to be in the nonaccident position provided itcan be aligned to the accident position within the time assumed in theaccident analysis.
This is acceptable since the RHR suppression pool(continued)
HATCH UNIT 1 B366B 3.6-61 INSERT -Bases 3.6.2.4 Condition CRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 3) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action 0.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
RHR Suppression Pool SprayB 3.6.2.4BASESSURVEILLANCE REQUIREMENTS SR 3.6.2.4.1 (continued) cooling mode is manually initiated.
This SR does not require anytesting or valve manipulation; rather, it involves verification that thosevalves capable of being mispositioned are in the correct position.
ThisSR does not apply to valves that cannot be inadvertently misaligned, such as check valves.The Surveillance Fequency is controlled under the Surveillance Frequency Control Program.SR 3.6.2.4.2 This Surveillance is performed every 10 years to verify that the spraynozzles are not obstructed and that flow will be provided whenrequired.
The Surveillance Fequency is controlled under theSurveillance Frequency Control Program.REFERENCES
: 1. FSAR, Sections 5.2 and 14.4.3.2. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.
-BASES3.24 Reference 3.24HATCH UNIT 1 .66B 3.6-62 INSERT -Bases 3.6.2.4 Reference
: 3. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
Secondary Containment B 3.6.4.1B]ASES (continued)
ACTIONS A. 1If secondary containment is inoperable, it must be restored toOPERAB]LE status within 4 hours. The 4 hour Completion Timeprovides a period of time to correct the problem that is commensurate with the importance of maintaining secondary containment duringMODES 1, 2, and 3. This time period also ensures that the probability of an accident (requiring secondary containment OPERAB]ILITY) occurring during periods where secondary containment is inoperable is minimal.overall plant risk is IIf secondary containment cannot be restored to OPERAB]LE statusminimized.
within te requi ed Completion Time, the plant must be brought to aMODE in which"FeL;
,sat apl. To achieve this status, theplant must be brought to at least MODE 3 within 12 hours IMOD 4w:,~h,-
3P, allowed Completion Iic Iieireasonable, based on ope a*tig experience, to reach the requiredplant conditions from full power rnditions in an orderly manner andwithout challenging plant systems.]
INSERT -BASES 3.6.4.1C.1, C.2, and C.3 Condition B]Movement of irradiated fuel assemblies in the secondary containment, CORE ALTERATIONS, and OPDRVs can be postulated to causefissibn product release to the secondary containment.
In such- cases,the secondary containment is the only barrier to release of fissionproducts to the environment.
CORE ALTERATIONS and movementof irradiated fuel assemblies must be immediately suspended if thesecondary containment is inoperable.
Suspension of these activities shall not preclude completing anaction that involves moving a component to a safe position.
Also,action must be immediately initiated to suspend OPDRVs to minimizethe probability of a vessel draindown and subsequent potential forfission product release.
Actions must continue until OPDRVs aresuspended.
Required Action C.1 has been modified by a Note stating thatLCO 3.0.3 is not applicable.
If moving irradiated fuel assemblies whilein MODE 4 or 5, LCO 3.0.3 would not specify any action. If movingirradiated fuel assemblies while in MODE 1, 2, or 3, the fuelmovement is independent of reactor operations.
Therefore, in either(continued)
HATCH UNIT 1 B 3.6-78'.......I INSERT -Bases 3.6.4.1 Condition BRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 5), because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action B.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
Secondary Containment B 3.6.4.1BASESSURVEILLANCE REQUIREMENTS SR 3.6.4.1.3 and SR 3.6.4.1.4 (continued) demonstrates that the required SGT subsystem(s) can maintain> 0.20 inch of vacuum water gauge for 1 hour at a flow rate < 4000cfm for each SGT subsystem.
The 1 hour test period allowssecondary containment to be in thermal equilibrium at steady stateconditions.
Therefore, these two tests are used to ensure secondary containment boundary integrity.
Since these SRs are secondary containment tests, they need not be performed with each SGTsubsystem.
The SGT subsystems are tested on a STAGGERED TEST BASIS, however, to ensure that in addition to the requirements of LCO 3.6.4.3, each SGT subsystem or combination of subsystems will perform this test. The number of SGT subsystems and therequired combinations are dependent on the configuration of thesecondary containment and are detailed in the Technical Requirements Manual (Ref. 3). The Note to SR 3.6.4.1.3 andSR 3.6.4.1.4 specifies that the number of required SGT subsystems be one less than the number required to meet LCO 3.6.4.3,
'StandbyGas Treatment (SGT) System,"
for the given configuration.
TheSurveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES
: 1. FSAR, Subsection 14.4.3.2. FSAR, Subsection 14.4.4.3. Technical Requirements Manual, Se'ction 8.0.4. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.IINSERT -BASES 3.6.4.1< Reference HATCH UNIT 1B 3.6-80HATCH UNIT B 3.6-80 I '.
INSERT -Bases 3.6.4.1 Reference
: 5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
SGT SystemB 3.6.4.3BASESACTIONS A.1 and B.1 (continued) additional single failure (which is not necessary to assume while inACTIONS) the secondary containment volume may be drawn to avacuum in the time required to support assumptions of analyses.
: 0. .overall plant risk is* "F'.....
, minimized.I If the SGT subsyst m cannot be restored to OPERABLE status withinthe required Coin pion Time in MODE 1, 2, or 3, the plant must bebrought to a MODE To achieve thisstatus, the plant must be brought to at least MODE 3 within 12 hours.J---Time islan toMOD 4w~t!.q36hou~a./The allowed Completion Ireasonable, based on operating e oerience, to reach the requiredplant conditions from full power cor itions in an orderly manner andwithout challenging plant systems.
__INSERT
_ BASES 3.6.4.3D.1. D.2.1, D.2.2, and D.2.3During movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, whenRequired Action A. 1 or B. 1 cannot be completed within the requiredCompletion Time, the rerriaining required OPERABLE SGTsubsystems should immediately be placed in operation.
Thisaction ensures that the remaining subsystems are OPERABLE, thatno failures that could prevent automatic actuation have occurred, andthat any other failure would be readily detected.
An alternative to Required Action D.1 is to immediately suspendactivities that represent a potential for releasing radioactive materialto the secondary containment, thus placing the plant in acondition that minimizes risk. If applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies must immediately besuspended.
Suspension of these activities must not precludecompletion of movement of a component to a safe position.
Also, ifapplicable, actions must immediately be initiated to suspend OPDRVsin order to minimize the probability of a vessel draindown andsubsequent potential for fission product release.
Actions mustcontinue until OPDRVs are suspended.
(continued)
HATCH UNIT 1 B369B 3.6-91 INSERT -Bases 3.6.4.3 Condition CRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 6), because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action 0.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
SGT SystemB 3.6.4.3BASESACTIONS D.1, D.2.t, D.2.2. and D.2.3 (continued)
The Required Actions of Condition D have been modified by a Notestating that LCO 3.0.3 is not applicable.
If moving irradiated fuelassemblies while in MODE 4 or 5, LCO 3.0.3 would not specify anyaction. If moving irradiated fuel assemblies while in MODE 1, 2, or 3,the fuel movement is independent of reactor operations.
Therefore, in either case, inability to suspend movement of irradiated fuelassemblies would not be a sufficient reason to require a reactorshutdown.
E.__1If two or more required SGT subsystems are inoperable in MODE 1, 2or 3, the Unit 1 and Unit 2 SGT Systems may not be capable ofsupporting the required radioactivity release control function..
INSERT -BASES 3.6.4.3F.1, .2, ad F.3Condition EWhen two or more required SOT subsystems are inoperable, ifapplicable, CORE ALTERATIONS and movement of irradiated fuelassemblies in secondary containment must immediately besuspended.
Suspension of these activities shall not precludecompletion of movement of a component to a safe position.
Also, ifapplicable, actions must immediately be initiated to suspend OPDRVsin order' to minimize the probability of a vessel draindown andsubsequent potential for fission product release.
Actions mustcontinue until OPDRVs are suspended.
Required Action F.1 has been modified by a Note stating thatLCO 3.0.3 is not applicable.
If moving irradiated fuel assemblies while in MODE 4 or 5, LCO 3.0.3 would not specify any action. Ifmoving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuelmovement is independent of reactor operations.
Therefore, in eithercase, inability to suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown.
(continued)
HATCH UNIT 1 B 3.6-92 !7l INSERT -Bases 3.6.4.3 Condition ETherefore, the plant must be brought to a MODE in which overall plant risk is minimized.
Toachieve this status, the plant must be brought to at least MODE 3 within 12 hours.Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 6) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action E.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach therequired plant conditions from full power conditions in an orderly manner and withoutchallenging plant systems.
SGT SystemB 3.6.4.3BASES (continued)
REFERENCES 12345* 10 CFR 50, Appendix A, GDC 41... Unit 1 FSAR, Section 5.3.2.3.*. Unit 2 ESAR, Sections 6.2.4, 15.2 and 15.3.* Technical Requirements Manual, Section 8.0.NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.INSERT -BASES 3.6.4.3< Reference B 3.6-94HACHUIT1B
.-9 I I INSERT -Bases 3.6.4.3 Reference
: 6. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
RHRSW SystemB 3.7.1IINSERT -BASES 3.7.1BASES Condition DACTIONS (continued)
With both RHRSW subsystems inoperable for reasons other thanCondition B (e.g., both subsystems with inoperable flow paths, or onesubsystem with an inoperable pump and one subsystem with aninoperable flow path), the RHRSW System is not capable ofperforming its intended function.
At least one subsystem must berestored to OPERABLE status within 8 hours. The 8 hour Completion Time for restoring one RHRSW subsystem to OPERABLE status, isbased on the Completion Times provided for the RHR suppression pool cooling and spray functions.
The Required Action is modified by a Note indicating that theapplicable Conditions of LCO 3.4.7 be entered and Required Actionstaken if an inoperable RHRSW subsystem results in an inoperable RHR shutdown cooling subsystem.
This is an exception to LCO 3.0.6and ensures the proper actions are taken for these components.
--of Condition EIf the RHRSW subsystems cannot be not rest( .d to OPERABLEstatus within the associated Completion Times ,the unit must beplaced in a MODE in which the LCO does not apply. To achieve thisstatus, the unit must be placed in at least MODE 3 within 12 hoursand in MODE 4 within 36 hours. The allowed Completion Times arereasonable, based on operating experience, to reach the required unitconditions from full power conditions in an orderly manner and withoutchallenging unit systems.SURVEILLANCE SR 3.7.1.1REQUIRE MENTSVerifying the correct alignment for each manual, power operated, andautomatic valve in each RHRSW subsystem flow path providesassurance that the proper flow paths will exist for RHRSW operation.
This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these valves are verified to be in the correctposition prior to locking,
: sealing, or securing.
A valve is also allowedto be in the nonaccident
: position, and yet considered in the correctposition, provided it can be realigned to its accident position.
This isacceptable because the RHRSW System is a manually initiated system. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being(continued)
HATCH UNIT 1B37-B 3.7-5 Suppression Chamber-to-Drywell Vacuum Breakers3.6.1.83.6 CONTAINMENT SYSTEMS3.6.1.8 Suppression Chamber-to-Drywell Vacuum BreakersLCO 3.6.1.8Ten suppression chamber-to-drywell vacuum breakers shall beOPERABLE for opening.ANDTwelve suppression chamber-to-drywell vacuum breakers shall beclosed, except when performing their intended function.
APPLICABILITY:
MODES 1, 2, and 3.ACTIONS_________________
___CONDITION REQUIRED ACTION COMPLETION TIMEA. One required suppression A.1 Restore one vacuum 72 hourschamber-to-drywell vacuum breaker to OPERABLEbreaker inoperable for status.opening.C.dywl C.umbeae-- 1 bekrOn uppression chamber-Close the open vacuum 2 hoursnot closed.Required Action and Be MODE 3. 12 hoursassociated Completion Time not met. AND D2I~ f onitonCIBe in MODE 4. 36 hoursIlNSERT-TS 3.6.1.8IlCondition BHATCH UNIT 2 3613.6-19 TS 3.6.1.8.
-Condition B InsertB. Required Action and B.1 ----NOTE----------.....
associated Completion LCO 3.0.4a is not applicable Time of Condition A not when entering MODE 3.met.Be in MODE 3. 12 hours RHR Suppression Pool Cooling3.6.2.33.6 CONTAINMENT SYSTEMS3.6.2.3 Residual Heat Removal (RHR) Suppression Pool CoolingLCO 3.6.2.3APPLICABILITY:
Two RHR suppression pool cooling subsystems shall be OPERABLE.
MODES 1, 2, and 3.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One RHR suppression poolcooling subsystem inoperable.
lTwo RHR suppression poolS cooling subsystems inoperable.
[tRequired Action andassociated Completion Time
* Condition CI.JNSERT
-TS 3.6.2.3I,Condition BA. 1Restore RHRsuppression poolcooling subsystem toOPERABLE status.7 daysone RHRsuppression poolcooling subsystem toOPERABLE status.MODE 3.IIf B nMODE 4.8 hours12 hours36 hoursSURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling In accordance withsubsystem manual, power operated, and automatic the Surveillance valve in the flow path that is not locked, sealed, or Frequency Controlotherwise secured in position is in the correct Programposition or can be aligned to the correct position.
(continued)
HATCH UNIT 2 3623.6-25 TS 3.6.2.3 -Condition B InsertB. Required Action and B. 1 ---NOTE .............
associated Completion LCO 3.0.4.a is not applicable Time of Condition A not when entering MODE 3.met.Be in MODE 3. 12 hours RHR Suppression Pool Spray3.6.2.43.6 CONTAINMENT SYSTEMS3.6.2.4 Residual Heat Removal (RHR) Suppression Pool SprayLCO 3.6.2.4APPLICABILITY:
Two RHR suppression pool spray subsystems shall be OPERABLE.
MODES 1, 2, and 3.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One RHR suppression pool A.1 Restore RHR 7 daysspray subsystem suppression pool sprayinoperable, subsystem toOPERABLE status.B. Two RHR suppression pool B.1 Restore one RHR 8 hoursspray subsystems suppression pool sprayinoperable, subsystem toOPERABLE status.C. Required Action and C.1 ..Be in MODE 3. 12 hoursassociated Completion
/Time not met.-NOTE----
LCO 3.0.4.a is not 0 .2 Dei- MODE. 4. applicable when enteringM D 3........................._
_ _ _ _ _ _ _SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify each RHR suppression pool spray In accordance withsubsystem manual, power operated, and the Surveillance automatic valve in the flow path that is not locked, Frequency Controlsealed, or otherwise secured in position is in the Programcorrect position or can be aligned to the correctposition.
(continued)
HATCH UNIT 23.6-27HATH^NI 23.-2....
11111... .210 Secondary Containment 3.6.4.13.6 CONTAINMENT SYSTEMS3.6.4.1 Secondary Containment LCO 3.6.4.1APPLICABILITY:
-NOTE-------....
LCO 3.0.4.a is notapplicable when enteringMODE 3.The secondary containment shall be OPERABLE.
MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel--(OPDRV).ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. Secondary containment A.1 Restore secondary 4 hoursinoperable in MODE 1, 2, containment toor 3. OPERABLE status.B. Required Action and B.1 kBe in MODE 3. 12 hoursassociated Completion Time of Condition A not ____met.C. Secondary containment C.1------NOTE-
--inoperable during LCO 3.0.3 is notmovement of irradiated fuel applicable.
assemblies in thesecondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuelOPDRVs. assemblies in thesecondary containment.
AND__________________________________________________(continued)
HATCH UNIT 2 3633.6-33 Secondary Containment 3.6.4.1No change. Included forinformation only.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEC. (continued)
C.2 Suspend CORE Immediately ALTERATIONS.
ANDC.3 Initiate action to Immediately suspend OPDR Vs.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment equipment In accordance withhatches are closed and sealed. the Surveillance Frequency ControlProgramSR 3.6.4.1.2 Verify one secondary containment access door in In accordance witheach access opening is closed, the Surveillance Frequency ControlProgramSR 3.6.4.1.3-----------NOTE-
------The number of standby gas treatment (SGT)subsystem(s) required for this Surveillance isdependent on the secondary containment configuration, and shall be one less than thenumber required to meet LCO 3.6.4.3, "StandbyGas Treatment (SGT) System,"
for the givenconfiguration.
Verify required SGT subsystem(s) will draw In accordance withdown the secondary containment to > 0.20 inch the Surveillance of vacuum water gauge in < 120 seconds.
Frequency ControlProgram(continued)
HATCH UNIT 23.6-34HATC UNI 2 36-34Amendment No. 210 SGT System3.6.4.3No change. Included forinformation only.3.6 CONTAINMENT SYSTEMS3.6.4.3 Standby Gas Treatment (SGT) SystemLCO 3.6.4.3APPLICABILITY:
The Unit 1 and Unit 2 SOT subsystems required to support LCO 3.6.4.1,"Secondary Containment,"
shall be OPERABLE.
MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel(OPDRV).ACTIONS, IrvI-----------
Nil)!When two Unit 1 SOT subsystems are placed in an inoperable status solely for inspection of theUnit 1 hardened vent rupture disk, entry into associated Conditions and Required Actions maybe delayed for up to 24 hours, provided both Unit 2 SGT subsystems are OPERABLE.
CONDITION REQUIRED ACTION COMPLETION TIMEA. One required Unit 1 SGT A.1 Restore required Unit 1 30 days fromsubsystem inoperable SGT subsystem to discovery of failure towhile: OPERABLE status. mfeet the LCO1. Four SGT subsystems required
: OPERABLE, and2. Unit 1 reactorbuilding-to-refueling floor plug not installed.
(continued)
HATCH UNIT 23.6-39HATC UNI 2 36-39Amendment No. 135
-NOTE-LCO 3.0.4.a is notapplicable when enteringMODE 3.SGT System3.6.4.3MUL I [L;UU]I~t]U~gU)
__ _ _ _ _ __ _ _ _ _CONDITION REQUIRED ACTION COMPLETION TIMEB. One required Unit 2 SGT B.1 Restore required SOT 7 dayssubsystem inoperable, subsystem toOPERABLE status. ANDOR30 days fromOne required Unit 1 SGT discovery of failure tosubsystem inoperable for meet the LCOreasons other thanCondition A.C. Required Action and C.1 " Be in MODE 3. 12 hoursassociated Completion Time of Condition A or B A-Enot met in MODE 1, 2, or 3. ID. Required Action and---------NOTE-
---associated Completion LCO 3.0.3 is not applicable.
Time of Condition A or Bnot met during movementof irradiated fuel D.1 Place remaining Immediately assemblies in the OPERABLE SOTsecondary containment, subsystem(s) induring CORE operation.
ALTERATIONS, or duringOPDRVs. ORD.2.1 Suspend movement of Immediately irradiated fuelassemblies insecondary containment.
ANDD.2.2 Suspend CORE Immediately ALTERATIONS.
ANDD.2.3 Initiate action to Immediately suspend OPDRVs.(continued)
HATCH UNIT 2 3643.6-40
-NOTE-.......
LCO 3.0O4.a is notapplicable when enteringMODE 3.SGT System3.6.4.3ACTIONS (continued)
CONDITION RQUIRED ACTION COMPLETION TIMEE. Two or more required SGT E.1 "'!-- .I ..dattsubsystems inoperable inMODE 1,2, or3. einMD 3. ____,--_12hours F. Two or more required SGT F.1------NOTE-.........
subsystems inoperable LCO 3.0.3 is notduring movement of applicable.
irradiated fuel assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuelOPDRVs. assemblies insecondary containment.
ANDF.2 Suspend CORE Immediately ALTERATIONS.
ANDF.3 Initiate action to Immediately suspend OPDR Vs.SURVEILLANCE REQUIREMENTS
_______SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each required SGT subsystem for In accordance with> 15 continuous minutes.
the Surveillance Frequency ControlProgramSR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance withwith the Ventilation Filter Testing Program (VFTP). the VFTP(continued)
HATCH UNIT 236413.6-41 RHRSW System3.7.13.7 PLANT SYSTEMS3.7.1 Residual Heat Removal Service Water (RHRSW) SystemLCO 3.7.1Two RHRSW subsystems shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One RHRSW pump A.1 Restore RHRSW pump 30 daysinoperable, to OPERABLE status.B. One RHRSW pump in each B.1 Restore one RHRSW 7 dayssubsystem inoperable, pump to OPERABLEstatus.C. One RHRSW subsystem-------------NOTE-------
inoperable for reasons Enter applicable Conditions andother than Condition A. Required Actions of LCO 3.4.7,"Residual Heat Removal (RHR)Shutdown Cooling System -HotShutdown,"
for RHR shutdowncooling miade inoperable byRHRSW System.C.1 Restore RHRSW 7 dayssubsystem toOPERABLE status.-, INSERT -TS 3.7.1Condition D(continued)
HATCH UNIT 23.7-1HATH UIT 3.-1A,,-e 1d,,-e1t ,No. 1.901 TS 3.7.1 -Condition D InsertD. Required Action and D.1 ----NOTE- ---associated Completion LCO 3.0.4.a is not applicable Time of Condition A, B, or when entering MODE 3.C not met.Be in MODE 3. 12 hours RHRSW System3.7.1ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIMEBoth RHRSW subsystems inoperable for reasonsother than Condition B.Enter applicable Conditions andRequired Actions of LCO 3.4.7for RHR shutdown cooling madeinoperable by RHRSW System.8 hours] Required Action and LI Iassociated Completion Time ln ot met.Iof Condition EBe in MODE 3.ANDBe in MODE 4.HATCH UNIT 23.7-2 PSW System and UHS3.7.23.7 PLANT SYSTEMS3.7.2 Plant Service Water (PSW) System and Ultimate Heat Sink (UHS)LCO 3.7.2Two P3W subsystems and UHS shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One PSW pump inoperable.
A.1 Restore PSW pump to 30 daysOPERABLE status.B. One PSW turbine building B.1 Restore PSW turbine 30 daysisolation valve inoperable, building isolation valveto OPERABLE status.C. One PSW pump in each C.1 Restore one PSW 7 dayssubsystem inoperable, pump to OPERABLEstatus.D. One PSW tur'bine building D.1 Restore one PSW 72 hpursisolation valve in each turbine buildingsubsystem inoperable, isolation valve toOPERABLE status.INSERT -TS 3.7.2Condition E(continued)
HATCH UNIT 23733.7-3 TS 3.7.2 -Condition E InsertE. Required Action and E.1-----NOTE-............
associated Completion LCO 3.0.4.a is not applicable Time of Condition A, B, C, when entering MODE 3.or Dnot met.Be in MODE 3. 12 hours PSW System and UHS3.7.2ACTIONS (continued)
CONDITION REQUIRED ACTION [COMPLETION TIMEOne PSW subsystem inoperable for reasonsother than Conditions Aand B.-~~NOTES--
1.Enter applicable Conditions and Required Actions ofLCO 3.8.1, "AC Sources -Operating,"
for dieselgenerator made inoperable by PSW System.2. Enter applicable Conditions and Required Actions ofLCO 3.4.7, "Residual HeatRemoval (RHR) ShutdownCooling System -HotShutdown,"
for RHRshutdown cooling madeinoperable by PSWSystem.Restore the PSWsubsystem toOPERABLE status.72 hours+Required Action andassociated Completion Time of Condition
~por et.Be in MODE 3.AND12 hours36 hoursBe in MODE 4.ORR -Both PSW subsystems inoperable for reasonsother than Conditions Cand D.ORUHS inoperable.
L:5.r3.7-4HATCH UNIT 2 3.7-4 Amcndmcnt No. 135 MCREC System3.7.43.7 PLANT SYSTEMS3.7.4 Main Control Room Environmental Control (MCREC) SystemNo change. Included forinformation only.LCO 3.7.4Two MCREC subsystems shall be OPERABLE.
-----------------
NOTE----------------
The main control room envelope (ORE) boundary may be opened intermittently underadministrative control.APPLICABILITY:
MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel(OPDRVs).
ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One MCREC subsystem A.1 Restore MCREC 7 daysinoperable for reasons subsystem toother than Condition
: 8. OPERABLE status.B. One or more MCREC B.1 Initiate action to Immediately subsystems inoperable due implement mitigating to inoperable ORE actions.boundary in MODE 1, 2,or 3. ANDB.2 Verify mitigating actions 24 hoursensure ORE occupantexposures toradiological,
: chemical, and smoke hazards willnot exceed limits.ANDB.3 Restore ORE boundary 90 daysto OPERABLE status.(continued)
HATCH UNIT 23.7-8HATC UNI 2 37-8Amendment No. 212
-NOTE-LCO 3.0.4.a is notapplicable when enteringMODE 3.MCREC System3.7.4ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIMEC. Required Action and C.1 Be in MODE 3. 12 hoursassociated Completion Time of Condition A or B I/not met in MODE 1,2, or 3.ID. Required Action andassociated Completion Time of Condition A notmet during movement ofirradiated fuel assemblies in the secondary containment, during COREALTERATIONS, or duringOPDR Vs.-----------------
NOTE-------
LCO 3.0.3 is not applicable.
D.1 Place OPERABLEMCREC subsystem inpressurization mode.OR_D.2.1 Suspend movement ofirradiated fuelassemblies in thesecondary containment.
ANDD.2.2 Suspend COREALTERATIONS.
ANDImmediately Immediately Immediately Immediately
-.......NOTE-------....
LCO 3.0.4.a is notlapplicable when enteringIMODE 3.'1D.2.3 Initiate action to"\ suspend OPDRVs.E. Two MCREC subsystems inoperable in MODE 1, 2,or 3 for reasons other thanCondition B.E.1 E11t~~1LCO 3.3.3T""12 hours(continued)
HATCH UNIT 237-3.7-9 MCREC System3.7.4No change. Included forinformation only.ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIMEF. Two MCREC subsystems-------NOTE-----
inoperable during LCO 3.0.3 is not applicable.
movement of irradiated fuelassemblies in thesecondary containment, F. 1 Suspend movement of Immediately during CORE irradiated fuelALTERATIONS, or during assemblies in theOPDR Vs. secondary containment.
OR ANDOne or more MCREC F.2 Suspend CORE Immediately subsystems inoperable due ALTERATIONS.
to an inoperable CREboundary during movement ANDof irradiated fuelassemblies in the F.3 Initiate action to Immediately secondary containment, suspend OPDRVs.during COREALTERATIONS, or duringOPDR Vs.SURVEILLANCEREQUIREMENTS
_______SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREC subsystem
> 15 minutes.
In accordance withthe Surveillance Frequency ControlProgramSR 3.7.4.2 Perform required MCREC filter testing in In accordance withaccordance with the Ventilation Filter Testing the VFTPProgram (VFTP).SR 3.7.4.3 Verify each MCREC subsystem actuates on an In accordance withactual or simulated initiation signal. the Surveillance Frequency ControlProgram(continued)
HATCH UNIT 23.7-10HATC UNI 2 37-10Amendment No. 212 Control Room AC System3.7.53.7 PLANT SYSTEMS3.7.5 Control Room Air Conditioning (AC) SystemNo change. Included forinformation only.LCO 3.7.5APPLICABILITY:
Three control room AC subsystems shall be OPERABLE.
MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel(OPDRVs).
ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One control room AC A.1 Restore control room 30 dayssubsystem inoperable.
AC subsystem toOPERABLE status.B. Two control room AC B.1 Verify control room area Once per 4 hourssubsystems inoperable, temperature
< 90&deg;F.ANDB.2 Restore one control 7 daysroom AC subsystem toOPERABLE status.C. Three control room AC C.1 Verify control room area Once per 4 hourssubsystems inoperable, temperature
< 90&deg;F.ANDC.2 Restore one control 72 hoursroom AC subsystem toOPERABLE status.(continued)
HATCH UNIT 23.7-12HATC UNI 2 37-12Amendment No. 214 AC-~NOTE----
LCO 3.0.4.a is notapplicable when enteringMODE 3.Control Room AC System3.7.5CONDITION XREQUIRED ACTIONCOMPLETION TIMED. Required Action and D.1 Be in MODE 3. 12 hoursassociated Completion
___________
Time of Condition A, B, or IC not met in MODE 1, 2, or3. h9 eP in .MODEl A.16horE. Required Action and---------NOTE-
---associated Completion LCO 3.0.3 is not applicable.
Time of Condition A not met------------
during movement ofirradiated fuel assemblies in E.1 Place OPERABLE Immediately the secondary containment, control room ACduring CORE subsystems inALTERATIONS, or during operation.
OPDRVs.ORE.2.1 Suspend movement of Immediately irradiated fuelassemblies in thesecondary containment.
ANDE.2.2 Suspend CORE Immediately ALTERATIONS.
ANDE.2.3 Initiate action to Immediately suspend OPDR Vs.(continued)
HATCH UNIT 23.7-13HATC UNI 2 37-13Amedmont
,No. 2 11 Main Condenser Offgas3.7.63.7 PLANT SYSTEMS3.7.6 Main Condenser OffgasLCO 3.7.6APPLICABILITY:
The gross gamma activity rate of the noble gases measured at the maincondenser evacuation system pretreatment monitor station shall be< 240 mCi/second.
MODE 1,MODES 2 and 3 with any main steam line not isolated and steam jet airejector (SJAE) in operation.
ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. Gross gamma activity rate A.1 Restore gross gamma 72 hoursof the noble gases not activity rate of the noblewithin limit, gases to within limit.B. Required Action and B.1 Isolate all main steam 12 hoursassociated Completion lines.Time not met.-NOTE------OR LCO 3.0.4.a is not 8.2 Isolate SJAE. 12 hoursapplicable when entering\
MODE 3. OR..l Be in MODE 3. 12 hoursB,,.3.., l l % l,.l,,,,
-I.v l -IHATCH UNIT 2 3713.7-16 AC Sources -Operating 3.8.1INo change. Included for3.8 ELECTRICAL POWER SYSTEMS linformation only.3.8.1 AC Sources -Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:
: a. Two qualified circuits between the offsite transmission networkand the Unit 2 onsite Class 1 E AC Electrical Power Distribution System;b. Two Unit 2 diesel generators (DGs);c. The swing OG;d. One Unit 1 DG;e. One qualified circuit between the offsite transmission network andthe Unit 1 onsite Class 1 E AC Electrical Power Distribution subsystem(s) needed to support the Unit 1 equipment required tobe OPERABLE by LCO 3.6.4.3, "Standby Gas Treatment (SGT)System";
LCO 3.7.4, "Main Control Room Environmental Control(MCREC) System";
and LCO 3.7.5, "Control Room AirConditioning (AC) System";f. Two DGs (any combination of Unit 1 DGs and the swing DG),each capable of supplying power to one Unit 2 low pressurecoolant injection (LPCI) valve load center; andg. One qualified circuit between the offsite transmission network andthe applicable onsite Class 1 E AC electrical power distribution subsystems needed to support each Unit 2 LPCI valve load centerrequired by LCO 3.5.1, "ECCS -Operating."
APPLICABILITY:
MODES 1, 2, and 3.3.8-1HATC UNI 2 38-1Amendment No. 152 AC Sources -Operating 3.8.1ACTIONSNo change. Included forinformation only.-NOTE.LCO 3.0.4.b is not applicable to DGs.CONDITION REQUIRED ACTION COMPLETION TIMEA. One required offsite circuit A.1 Perform SR 3.8.1.1 for 1 hourinoperable.
OPERABLE requiredoffsite circuits.
ANDOnce per 8 hoursthereafter ANDA.2 Declare required 24 hours from discovery feature(s) with no offsite of no offsite power topower available one 4160 V ESF businoperable when the concurrent withredundant required inoperability offeature(s) are redundant requiredinoperable, feature(s)
ANDA.3 Restore required offsite 72 hours*circuit to OPERABLEstatus. AND17 days fromdiscovery of failure tomeet LCO 3.8.1.a, b,or cB. One Unit 2 or the swing DG B.I1 Perform SR 3.8.1.1 for 1 hourinoperable.
OPERABLE requiredoffsite circuit(s).
ANDOnce per 8 hoursthereafter AND________________________
______________________(continued)
HATCH UNIT 23.8-2HATC UNI 2 38-2Amendment No. 190 AC Sources -Operating 3.8.1No change. Included forinformation only.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEB. (continued) 8.2 Declare requiredfeature(s),
supported bythe inoperable DC,inoperable when theredundant requiredfeature(s) areinoperable.
ANDB.3.1 Determine OPERABLEDG(s) are notinoperable due tocommon cause failure.OR8.3.2 Perform SR 3.8.1.2.a forOPERABLE DC(s)AND8.4 Restore DG toOPERABLE status.4 hours from discovery of Condition Bconcurrent withinoperability ofredundant requiredfeature(s) 24 hours24 hours72 hours for aUnit 2 DC withthe swing DC notinhibited ormaintenance restrictions not metAND14 days for aUnit 2 DG withthe swing DCinhibited fromautomatically aligning toUnit 1 andmaintenance restrictions metAND72 hours for the swingdiesel withmaintenance restrictions not met(continued)
HATC UNI 2 38-3Amendment No. 203HATCH UNIT 23.8-3 AC Sources -Operating 3.8.1No change. Included forinformation only.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEB. (continued)
B.4 (continued)
AND14 days for the swingdiesel withmaintenance restrictions metAND17 days fromdiscovery of failure tomeet LCO 3.8.1 .a, b,or cC. One required Unit 1 DGinoperable.
C.1 Perform SR 3.8.1.1 forOPERABLE requiredoffsite circuit(s).
ANDC.2 Declare requiredfeature(s),
supported bythe inoperable DG,inoperable when theredundant requiredfeature(s) areinoperable.
ANDC.3.1 Determine OPERABLEDG(s) are notinoperable due tocommon cause failure.ORC.3.2 Perform SR 3.8.1.2.a forOPERABLE DG(s).1 hourANDOnce per 8 hoursthereafter 4 hours fromdiscovery of Condition Cconcurrent withinoperability ofredundant requiredfeature(s) 24 hours24 hours(continued) 3.8-4HATC UNI 2 38-4Amendment No. 203 AC Sources -Operating 3.8.1No change. Included forinformation only.IJCONDITION REQUIRED ACTIONCOMPLETION TIMEC. (continued)
ANDC.4Restore required DG toOPERABLE status.7 days with theswing DG notinhibited ormaintenance restrictions not metAND14 days with theswing DG inhibited from automatically aligning to Unit 2 andmaintenance restrictions met4 4D. Two or more requiredoffsite circuits inoperable.
D.1 Declare requiredfeature(s) with no offsitepower available inoperable when theredundant requiredfeature(s) areinoperable.
ANDD.2 Restore all but onerequired offsite circuit toOPERABLE status.12 hours from discovery of Condition Dconcurrent withinoperability ofredundant requiredfeature(s) 24 hours4 4E. One required offsite circuitinoperable.
ANDOne required DGinoperable.
-~~NOTE--
--Enter applicable Conditions andRequired Actions of LCO 3.8.7,"Distribution Systems -Operating,"
when Condition E isentered with no AC power sourceto one 4160 V ESF bus.E.1 Restore required offsitecircuit to OPERABLEstatus.12 hours(continued)
Amendment No. 203HATCH UNIT 238-3.8-5 AC Sources -Operating 3.8.1ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIMEE. (continued)
ORE.2 Restore required DG 12 hoursto OPERABLE status.F. Two or more (Unit 2 and F.1 Restore all but one 2 hoursswing) DGs inoperable.
Unit 2 and swing DGsto OPERABLE status.G. No DGs capable of G.1 Restore one DG 2 hourssupplying power to any capable of supplying Unit 2 LPCI valve load power to Unit 2 LPCIcenter. valve load center toOPERABLE status.H. Required Action and H.1 /t1e in MODE 3. 12 hoursAssociated Completion fTime of Condition A, B, C,D, E, F, or G not met.One or more required 11 Enter LCO 3.0.3. Immediately offsite circuits and two or pmore required DGs jINOTEinoperable.
JLCO 3.0.4.a is nottapplicable when enteringOR JMODE 3.Two or more requiredoffsite circuits and onerequired DG inoperable.
HATCH UNIT 23.8-6HATCHUNIT2 3.-6 Amndrn ,'oN. 20311 DC Sources -Operating 3.8.43.8 ELECTRICAL POWER SYSTEMS3.8.4 DC Sources -Operating No change. Included forinformation only.LCO 3.8.4The following DC electrical power subsystems shall be OPERABLE:
: a. The Unit 2 Division 1 and Division 2 station service DCelectrical power subsystems;
: b. The Unit 2 and the swing DGs DC electrical powersubsystems; andc. The Unit 1 OG DC electrical power subsystems needed tosupport the equipment required to be OPERABLE byLCO 3.6.4.3, "Standby Gas Treatment (SGT) System";LCO 3.7.4, "Main Control Room Environmental Control (MCREC)System";
LCO 3.7.5, "Control Room Air Conditioning (AC) System";and LCO 3.8.1, "AC Sources -Operating."
APPLICABILITY:
MODES 1, 2, and 3.ACTIONS ________CONDITION REQUIRED ACTION COMPLETION TIMEA. Swing DG DC electrical A.1 Restore DG DC 7 dayspower subsystem electrical powerinoperable due to subsystem toperformance of SR 3.8.4.7 OPERABLE status.or SR 3.8.4.8.OROne or more requiredUnit I DG DC electrical power subsystems inoperable.
(continued)
HATCH UNIT 23.8-26HATC UNI 2 38-26Amendment No. 169 DC Sources -Operating 3.8.4ACTIONS (continued)_________________________
CONDITION REQUIRED ACTION COMPLETION TIMEB. One Unit 2 DG DC B.1 Restore DG DC 12 hourselectrical power subsystem electrical powerinoperable, subsystem toOPERABLE status.OR_ R______SINOTE----
Swing DG DC electrical ILCO 3.0.4.a is notpower subsystem
[- applicable when enteringinoperable for reasons _MODE 3other than Condition A. -3..........
C. One Unit 2 station service C.1\ Restore station service 2 hoursDC electrical power \ DC electrical powersubsystem inoperable, subsystem toOPERABLE status.D. Required Action and D.1 "Be in MODE 3. 12 hoursAssociated Completion Time of Condition A, B, Nor C not met.E. Two or more DC electrical E.1 Enter LCO 3.0.3. Immediately power subsystems inoperable that result in aloss of function.
HATCH UNIT 2 3823.8-27 Distribution Systems -Operating 3.8.7No change. Included forinformation only.3.8 ELECTRICAL POWER SYSTEMS3.8.7 Distribution Systems -Operating LCO 3.8.7APPLICABILITY:
The following AC and DC electrical power distribution subsystems shallbe OPERABLE:
: a. Unit 2 AC and DC electrical power distribution subsystems comprised of:1. 4160 V essential buses 2E, 2F, and 2G;2. 600 V essential buses 2C and 20;3. 120/208 V essential cabinets 2A and 2B;4. 120/208 V instrument buses 2A and 2B;5. 125/250 V DC station service buses 2A and 2B;6. DG DC electrical power distribution subsystems; andb. Unit 1 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE byLCO 3.6.4.3, "Standby Gas Treatment (SGT) System";
LCO 3.7.4,"Main Control Room Environmental Control (MCREC) System";LCO 3.7.5, "Control Room Air Conditioning (AC) System";
andLCO 3.8.1, "AC Sources -Operating."
MODES 1, 2, and 3.ACTIONS ________CONDITION REQUIRED ACTION COMPLETION TIMEA. One or more required A.1 Restore required 7 daysUnit 1 AC or DC electrical Unit 1 AC and DCpower distribution subsystem(s) tosubsystems inoperable.
OPERABLE status.(continued)
HATCH UNIT 23.8-37HATH NI 2 .837Amendment No. 210 I Distribution Systems -Operating 3.8.7ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIMEB. One or more (Unit 2 or B.1 Restore DG DC 12 hoursswing bus) DG DC electrical powerelectrical power distribution distribution subsystem ANDsubsystems inoperable, to OPERABLE status.16 hours fromdiscovery of failure tomeet LCO 3.8.7.aC. One or more (Unit 2 or C.1 Restore AC electrical 8 hoursswing bus) AC electrical power distribution power distribution subsystem to ANDsubsystems inoperable.
OPERABLE status.16 hours fromdiscovery of failure tomeet LCO 3.8.7.aD. One Unit 2 station service D.1 Restore Unit 2 station 2 hoursDC electrical power service DC electrical distribution subsystem power distribution ANDinoperable, subsystem toOPERABLE status. 16 hours fromdiscovery of failure tomeet LCO 3.8.7.aE. Required Action andassociated Completion Time of Condition A, B, C,or D not met.F. Two or more electrical power distribution subsystems inoperable thatresult in a loss of function.
HATCH UNIT 2 3833.8-38 RPS Electric Power Monitoring B 3.3.8.2BASESACTIONS Al1 (continued) operations personnel to take corrective actions or to place the plant inthe required condition in an orderly manner and without challenging plant systems.Alternately, if it is not desired to remove the power supply from service(e.g., as in the case where removing the power supply(s) from servicewould result in a scram or isolation),
Condition C or D, as applicable, must be entered and its Required Actions taken.B._.11If both power monitoring assemblies for an inservice power supply(MG set or alternate) are inoperable or both power monitoring assemblies in each inservice power supply are inoperable, the systemprotective function is lost. In this condition, 1 hour is allowed torestore one assembly to OPERABLE status for each inservice powersupply. If one inoperable assembly for each inservice power supplycannot be restored to OPERABLE status, the associated powersupply(s) must be removed from service within 1 hour (Required Action B.1). An alternate power supply with OPERABLE assemblies may then be used to power one RPS bus. The 1 hour Completion Time is sufficient for the plant operations personnel to take corrective actions and is acceptable because it minimizes risk while allowingtime for restoration or removal from service of the electric powermonitoring assemblies.
Alternately, if it is not desired to remove the power supply(s) fromservice (e.g., as in the case where removing the power supply(s) fromservice would result in a scram or isolation),
Condition C or D, asapplicable, must be entered and its Required Actions taken.p ~ ~ ~ ~ ~tepant smtonusscmpi paigt be proant in withDEin12 hoyReuirs dAto n asoiae ThemaloeCmpeti onoCodtonditi ae on C e (contin2 o 3ap~rt .u ed)--HATCHtUNIT-1 3.3.- 196^- .."'^-^";.
.... ''
INSERT -Bases 3.3.8.2 Condition CRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 4) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action C.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
RPS Electric Power Monitoring B 3.3.8.2BASESACTIONSC. 11=-. (continued) required plant conditions from full power conditions in an orderlymanner and without challenging plant systems.Dl.1 D.2.1. and D.2.2If any Required Action and associated Completion Time ofCondition A or B are not met in MODE 4 or 5 with any control rodwithdrawn from a core cell containing one or more fuel assemblies orwith both RHR shutdown cooling valves open, the operator mustimmediately initiate action to fully insert all insertable control rods incore cells containing one or more fuel assemblies.
RequiredAction 0.1 results in the least reactive condition for the reactor coreand ensures that the safety function of the RPS (e.g., scram of controlrods) is not required.
In addition, action must be immediately initiated to either restore oneelectric power monitoring assembly to OPERABLE status for theinservice power source supplying the required instrumentation powered from the RPS bus (Required Action 0.2.1) or to isolate theRHR Shutdown Cooling System (Required Action 0.2.2). RequiredAction 0.2.1 is provided because the RHR Shutdown Cooling Systemmay be needed to provide core cooling.
All actions must continueuntil the applicable Required Actions are completed.
SURVEILLANCE REQUIRE MENTSThe Surveillances are modified by a Note to indicate that when anRPS electric power monitoring assembly is placed in an inoperable status solely for performance of required Surveillances, entry intoassociated Conditions and Required Actions may be delayed for up to6 hours provided the other RPS electric power monitoring assemblyfor the associated power supply maintains trip capability.
Uponcompletion of the Surveillance, or expiration of the 6 hour allowance, the assembly must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken.SR 3.3.8.2.1 A CHANNEL FUNCTIONAL TEST is performed on each overvoltage, undervoltage, and underfrequency channel to ensure that the entirechannel will perform the intended function.
Any setpoint adjustment shall be consistent with the assumptions of the current plant specificsetpoint methodology.
(continued)
HATCH UNIT 1B3319B 3.3-197 RPS Electric Power Monitoring B 3.3.8.2BASES (continued)
REFERENCES
: 1. FSAR, Section 8.7.2. NRC Generic Letter 9 1-09, "Modification of Surveillance Interval for the Electrical Protective Assemblies in PowerSupplies for the Reactor Protection System."3. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.IINSERT -BASES 3.3.8.2< iReference HATCH UNIT 1B33-9B 3.3-199 INSERT -Bases 3.3.8.2 Reference
: 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
ECCS -Operating B 3*5.1BASESACTIONS A.1 (continued) based on a reliability study (Ref. 11) that evaluated the impact onECCS availability, assuming various components and subsystems were taken out of service.
The results were used to calculate theaverage availability of EGOS equipment needed to mitigate theconsequences of a LOCA as a function of allowed outage times (i.e.,Completion Times).B.1 plant riskIf the inoperable low pressure ECCS subsystem cannot be restored toOPERABLE status within the associ efd Completion Time, the plantmust be brought to a MODE in which'e LCde ota#,, Toachieve this status, the plant must be brought to at least MODE 3within 12 hours .. _-,wun,,,
,u* he allowedCompletion easonable, based on ope experience, toreach the required plah conditions from full power c qditions in anorderly manner and wit ut challenging plant systems.]
--Time is INSERT -BASES 3.5.1 IC.1 and 0.2 Condition BIf the HPCI System is inoperable and the RCIC System is verified tobe OPERABLE, the HPCI System must be restored to OPERABLEstatus within 14 days. In this condition, adequate core cooling isensured by the OPERABILITY of the redundant and diverse lowpressur~e ECCS injection/spray subsystems in conjunction with ADS.Also, the RCIC System will automatically provide makeup water atmost reactor operating pressures.
Verification of RCICOPERABILITY within 1 hour is therefore required when HPCI isinoperable.
This may be performed as an administrative check byexamining logs or other information to determine if RCIC is out ofservice for maintenance or other reasons.
It does not mean toperform the Surveillances needed to demonstrate the OPERABILITY of the RCIC System. If the OPERABILITY of the RCIC Systemcannot be verified,
: however, Condition E must be immediately entered.
If a single active component fails concurrent with a designbasis LOCA, there is a potential, depending on the specific failure,that the minimum required ECCS equipment will not be available.
A14 day Completion Time is based on a reliability study cited inReference 11 and has been found to be acceptable through operating experience.
(continued)
HATCH UNIT 1B3.-B 3.5-6 INSERT -Bases 3.5.1 Condition BRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 15), because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action B.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
ECCS -Operating B 3.5.1BASESACTIONSD.1 and D.2If any one low pressure ECCS injection/spray subsystem is inoperable in addition to an inoperable HPCI System, the inoperable lowpressure ECCS injection/spray subsystem or the HPCI System mustbe restored to OPERABLE status within 72 hours. In this condition, adequate core cooling is ensured by the OPERABILITY of the ADSand the remaining low pressure ECCS subsystems.
: However, theoverall ECCS reliability is significantly reduced because a singlefailure in one of the remaining OPERABLE subsystems concurrent with a design basis LOCA may result in the ECCS not being able toperform its intended safety function.
Since both a high pressuresystem (HPCI) and a low pressure subsystem are inoperable, a morerestrictive Completion Time of 72 hours is required to restore eitherthe HPCI System or the low pressure ECCS injection/spray subsystem to OPERABLE status. This Completion Time is based ona reliability study cited in Reference 11 and has been found to beacceptable through operating experience.
F.1an~d F.2With one ADS valve inoperable, no action is required, because ananalysis demonstrated that the remaining six ADS valves are capableof providing the ADS function, per Reference 13.INSERT -BASES 35.1Condition Ei.I;I .... n .... :__,J A--J.: .... .JA:_,I._-I ....
"If--: .... Klj~y~tny rr~uguiwu
~CLIOfl ano a~uociaioo
~om e~en-~me
~I ........ ..........
,or flwoor more ADS valves areinoperable, the plant must be brought to a condition in which the LCOdoes not apply. To achieve this status, the plant must be brought toat least MODE 3 within 12 hours and reactor steam dome pressurereduced to < 150 psig within 36 hours. Entry into MODE 3 is notrequired if the reduction in reactor steam dome pressure to < 150 psigresults in exiting the Applicability for the Condition, and the < 150 psigis achieved within the given 12 hours. The allowed Completion Timesare reasonable, based on operating experience, to reach the requiredplant conditions from full power conditions in an orderly manner andwithout challenging plant systems.When~ mult ECCSt subsystemsi aroe inoPerable, as Stacteddein analyses.
Therefore, LCO 3.0.3 must be entered immediately.
(continued)
HATCH UNIT 1B35-B 3.5-7 INSERT -Bases 3.5.1 Condition EE.__If any Required Action and associated Completion Time of Condition C or D is not met, theplant must be brought to a MODE in which overall plant risk is minimized.
To achieve thisstatus, the plant must be brought to at least MODE 3 within 12 hours.Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 15) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action E. 1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach therequired plant conditions from full power conditions in an orderly manner and withoutchallenging plant systems.
ECCS -Operating B 3.5.1BASES (continued)
REFERENCES
: 1. FSAR, Section 6.4.3.2. FSAR, Section 6.4.4.3. FSAR, Section 6.4.1.4. FSAR, Section 6.4.2.5. FSAR, Section 14.4.3.6. FSAR, Section 14.4.5.7. 10 CFR 50, Appendix K.8. ESAR, Section 6.5.9. NEDC-31376P, "ElI. Hatch Nuclear Plant Units 1 and 2SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis,"
December 1986.10. 10 CFR 50.46.11. Memorandum from R.L. Baer (NRC) to V. Stello, Jr. (NRC),"Recommended Interim Revisions to LCOs for ECCSComponents,"
December 1, 1975.12. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.13. NEDC-32041P, "Safety Review for Edwin I. Hatch NuclearPower Plant Units 1 and 2 Updated Safety/Relief ValvePerformance Requirements,"
April 1996.14. ASME, OM Code -1995, "Code for Operation andMaintenance of Nuclear Power Plants,"
Appendix I.ilNSERT-BASES 3.5.1 I< Reference' dHATCH UNIT 1 B351B 3.5-13 INSERT -Bases 3.5.1 Reference
: 15. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
RCIC SystemB 3.5.3BASESACTIONS A.1 and A.2(continued)
If the RCIC System is inoperable during MODE 1, or MODE 2 or 3with reactor steam dome pressure
> 150 psig, and the HPCI Systemis verified to be OPERABLE, the RCIC System must be restored toOPERABLE status within 14 days. In this condition, loss of the RCICSystem will not affect the overall plant capability to provide makeupinventory at high reactor pressure since the HPCI System is the onlyhigh pressure system assumed to function during a loss of coolantaccident (LOCA). OPERABILITY of HPCI is therefore verified within1 hour when the RCIC System is inoperable.
This may be performed as an administrative check, by examining logs or other information, todetermine if HPCI is out of service for maintenance or other reasons.It does not mean it is necessary to perform the Surveillances neededto demonstrate the OPERABILITY of the HPCI System. If theOPERABILITY of the HPCI System cannot be verified, however,Condition B must be immediately entered.
For non-LOCA events,RCIC (as opposed to H PCI) is the preferred source of makeup coolantbecause of its relatively small capacity, which allows easier control ofthe RPV water level. Therefore, a limited time is allowed to restorethe inoperable RCIC to OPERABLE status.The 14 day Completion Time is based on a reliability study (Ref. 3)that evaluated the impact on ECCS availability, assuming variouscomponents and subsystems were taken out of service.
The resultswere used to calculate the average availability of ECCS equipment needed to mitigate the consequences of a LOCA as a function ofallowed outage times (AOTs). Because of similar functions of HPCIand RCIC, the AOTs (i.e., Completion Times) determined for HPCIare also applied to RCIC.If the RCIC System cannot be restored to OPERABLE status withinoverall plant risk is Ithe associated Completion Time, or if the HPCI System is[minimized.
sim"I aneousl inoperable, the plant must be brought to a condition in" whc'l,,h LCOdoc no To achieve this status, the plant mustbem brought toatleast~
MOD 153 s within 36 hurs.~n he allowsedm based on operating experience, toreach the r uired plant conditions from full power condi l~ons in an(continued)
HATCH UNIT 1 B352B 3.5-23 INSERT -Bases 3.6.3 Condition BRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 6) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action B.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
RCIC SystemB 3.5.3BASESSURVEILLANCE REQUIREMENTS (continued)
SR 3.5.3.5 (continued) low water level (Level 2) signal received subsequent to an RPV highwater level (Level 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The LOGICSYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.2 overlaps thisSurveillance to provide complete testing of the assumed safetyfunction.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.This SR is modified by a Note that excludes vessel injection duringthe Surveillance.
Since all active components are testable and fullflow can be demonstrated by recirculation through the test line,coolant injection into the RPV is not required during the Surveillance.
REFERENCES
: 1. 10 CFR 50, Appendix A, GDC 33.2. FSAR, Section 4.7.3. Memorandum from R. L. Baer (NRC) to V. Stello, Jr. (NRC),"Recommended Interim Revisions to LCOs for ECCSComponents,"
December 1, 1975.4. GE Report AES-41-0688, "Safety Evaluation for Relaxation ofRCIC Performance Requirements for Plant'Hatch Units 1and 2," July 1988.5. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.IINSERT -BASES 3.5.31Reference HATCH UNIT 1 B352B 3.5-26 INSERT -Bases 3.5.3 Reference
: 6. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
Reactor Building-to-Suppression Chamber Vacuum BreakersB 3.6.1.7BASESACTIONS 0. 1(continued)
With one line with one or more vacuum breakers inoperable foropening, the leak tight primary containment boundary is intact. Theability to mitigate an event that causes a containment depressurization is threatened,
: however, if both vacuum breakers in at least onevacuum breaker penetration are not OPERABLE.
Therefore, theinoperable vacuum breaker must be restored to OPERABLE statuswithin 72 hours. This is consistent with the Completion Time forCondition A and the fact that the leak tight primary containment boundary is being maintained.
ConditionD D,~With two lines with one or more vacuum breakers inoperable foropening, the primary containment boundary is intact. However, in theevent of a containment depressurization, the function of the vacuumbreakers is lost. Therefore, all vacuum breakers in one line must berestored to OPERABLE status within 1 hour. This Completion Time isconsistent with the ACTIONS of LCO 3.6.1.1, which require thatprimary containment be restored to OPERABLE status within 1 hour.If the vacuum breakers inone or more lines cannot bethplnmutbbruhtoaMDinwchheLOdsnt closed or restored toOPERABLE status within py oaheeti tts h ln utb ruh oa esMODE 3 within 12 hours and to MODE 4 within 36 hours. Thethe required Completion allowed Completion Times are reasonable, based on operating Time, experience, to reach the required plant conditions from full powerconditions in an orderly manner and without challenging plantsystems.SURVEILLANCE SR 3.6.1.7.1 REQUIREMENTS Each vacuum breaker is verified to be closed to ensure that apotential breach in the primary containment boundary is not present.This Surveillance is performed by observing local or control roomindications of vacuum breaker position or by verifying a differential pressure of 0.5 psid is maintained between the reactor building andsuppression chamber.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.(continued)
HATCH UNIT 1 B363B 3.6-38 INSERT -Bases 3.6.1.7 Condition D0.1_If one line has one or more reactor building-to-suppression chamber vacuum breakersinoperable for opening and they are not restored within the Completion Time in Condition C, theremaining breakers in the remaining lines can provide the opening function.
The plant must bebrought to a condition in which overall plant risk is minimized.
To achieve this status, the plantmust be brought to at least MODE 3 within 12 hours.Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 4) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action 0.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach therequired plant conditions from full power conditions in an orderly manner and withoutchallenging plant systems.
Reactor Building-to-Suppression Chamber Vacuum BreakersB 3.6.1.7BASES (continued)
REFERENCES
: 1. FSAR, Section 5.2.2. Unit 2 FSAR, Section 6.2.1.3. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.ItNSERT -BASES 3.6.1.7IReference HATCH UNIT 1 B364B 3.6-40 INSERT -Bases 3.6.1.7 Reference
: 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
Suppression Chamber-to-Drywell Vacuum Breakers8 3.6.1.8BASESACTIONS A. 1 (continued) considered acceptable due to the low probability of an event in whichthe remaining vacuum breaker capability would not be adequate.
INSERT -BASES 3.6.1.8[--7 Condition BAn open vacuum breaker allows communication between the drywelland suppression chamber airspace, and, as a result, there is thepotential for suppression chamber overpressurization due to thisbypass leakage if a LOCA were to occur. Therefore, the openvacuum breaker must be closed. The required 2 hour Completion Time is allowed to close the vacuum breaker due to the low probability of an event that would pressurize primary containment.
he plant must be brought to a MODE in which the LCO does notappl .To achieve this status, the plant must be brought to at leastMOD 3 within 12 hours and to MODE 4 within 36 hours. Theallow d Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full powerconditions in an orderly manner and without challenging planto,,&#xf7;,4syste h pn upeso chme-odyelycu reae[~cannot be closed within the required Completion Time,SURVEILLANCE SR 3.6.1.8.1 REQUIREMENTS Each vacuum breaker is verified closed to ensure that this potential large bypass leakage path is not present.
This Surveillance isperformed by observing the vacuum breaker position indication or byverifying that a differential pressure of 0.5 psid between the drywelland suppression chamber is maintained for 1 hour without makeup.However, if vacuum breaker position indication is not reliable, eitherdue to: 1) dual or open indication while torus-to-drywell differential pressure remains normal, or 2) closed indication while torus-to-drywell differential pressure remains steady at 0 psid, alternate methods ofverifying that the vacuum breaker is closed are detailed in Technical Requirements Manual (TRM) (Ref. 4), T3.6.1, "Suppression (continued)
HATCH UNIT 1 B364B 3.6-44 INSERT -Bases 3.6.1.8 Condition BIf a required suppression chamber-to-drywell vacuum breaker is inoperable for opening and isnot restored to OPERABLE status within the required Completion Time, the plant must bebrought to a condition in which overall plant risk is minimized.
To achieve this status, the plantmust be brought to at least MODE 3 within 12 hours.Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 5) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action B.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach therequired plant conditions from full power conditions in an orderly manner and withoutchallenging plant systems.
Suppression Chamber-to-Drywell Vacuum BreakersB 3.6.1.8BASES (continued)
REFERENCES
: 1. FSAR, Section 5.2.2. Unit 2 FSAR, Section 6.2.1.3. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.4. Technical Requirements Manual, TLCO 3.6.1.IINSERT -BASES 3.6.1.8IReference HATCH UNIT 1 .-6REIIN3B 3.6-46 INSERT -Bases 3.6.1.8 Reference
: 5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
RHR Suppression Pool Cooling(continued)
With two RHR suppression pooi cooling subsystems inoperable, onesubsystem must be restored to OPERABLE status within 8 hours. Inthis condition, there is a substantial loss of the primary containment pressure and temperature mitigation function.
The 8 hour Completion Time is based on this loss of function and is considered acceptable due to the low probability of a DBA and because alternative methodsto remove heat from primary containment are available.
I-- Required Action and associated Completion Time'-cannot bemet, the plant must be brought to a MODE in which the LCO doesnot apply. To achieve this status, the plant must be brought to atleast MODE 3 within 12 hours and to MODE 4 within 36 hours. Theallowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full powerconditions in an orderly manner and without challenging plant systems.SURVEILLANCE SR 3.6.2.3.1 REQUIREMENTS Verifying the correct alignment for manual, power operated, andautomatic valves in the RHR suppression pool cooling mode flow pathprovides assurance that the proper flow path exists for systemoperation.
This does not apply to valves that are locked, sealed,or otherwise secured in position since these valves were verified to bein the correct position prior to locking,
: sealing, or securing.
A valve isalso allowed to be in the nonaccident position provided it can bealigned to the accident position within the time assumed in theaccident analysis.
This is acceptable since the RHR suppression poolcooling mode is manually initiated.
This SR does not require anytesting or valve manipulation; rather, it involves verification that thosevalves capable of being mispositioned are in the correct position.
ThisSR does not apply to valves that cannot be inadvertently misaligned, such as check valves.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.I (continued)
HATCH UNIT 1 B 3.6-57 IN1 INSERT -Bases 3.6.2.3 Condition BB__tIf one RHR suppression pool cooling subsystem is inoperable and is not restored toOPERABLE status within the required Completion Time, the plant must be brought to acondition in which overall plant risk is minimized.
To achieve this status, the plant must bebrought to at least MODE 3 within 12 hours.Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 4) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action B.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach therequired plant conditions from full power conditions in an orderly manner and withoutchallenging plant systems.
RHR Suppression Pool CoolingB 3.6.2.3BASESSURVEILLANCE REQUIREMENTS (continued)
SR 3.6.2.3.2 Verifying that each required RHR pump develops a flow rate> 7700 gpm while operating in the suppression pool coolingmode with flow through the associated heat exchanger ensures thatpump performance has not degraded during the cycle. Flow is anormal test of centrifugal pump performance required by ASME Code,Section XI (Ref. 2). This test confirms one point on the pump designcurve, and the results are indicative of overall performance.
Suchinservice tests confirm component OPERABILITY and detect incipient failures by indicating abnormal performance.
The Frequency of thisSR is in accordance with the Inservice Testing Program.REFERENCES
: 1. FSAR, Sections 5.2 and 14.4.3.2. ASME, Boiler and Pressure Vessel Code, Section XI.3. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.
-BASES 3.6.2.3[ Reference HATCH UNIT 1 B365B 3.6-58I INSERT -Bases 3.6.2.3 Reference
: 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
RHR Suppression Pool SprayB 3.6.2.4BASESACTIONS A. 1 (continued)
: However, the overall reliability is reduced because a single failure inthe OPERABLE subsystem could result in reduced primarycontainment bypass mitigation capability.
The 7 day Completion Timewas chosen in light of the redundant RHR suppression pool spraycapabilities afforded by the OPERABLE subsystem and the lowprobability of a DBA occurring during this period.B.__1With both RHR suppression pool spray subsystems inoperable, atleast one subsystem must be restored to OPERABLE status within8 hours. In this Condition, there is a substantial loss of the primarycontainment bypass leakage mitigation function.
The 8 hourCompletion Time is based on this loss of function and is considered acceptable due to the low probability of a DBA and becausealternative methods to remove heat from primary containment areavailable.
c_.1 .rminimized___
._: _If any Required Action and associated Completion Time cannot bemet, the plant must be brought to a MODE in whicl the-LC- -1tI~jTo achieve this status, the plant must be brought to at leastMODE 3 within 12 hoursI .he allowedCompletio reasonable, based on operating
_expe~ "-tea&#xa3;, toTmisreach the/required plant conditions from full power conditions in an-'I~ie i Iorderly manner and without challenging plant systems.
INSERT -BASES- 3.6.2.4Condition CSURVEILLANCE SR 3.6.2.4.1 REQUIREMENTS Verifying the correct alignment for manual, power operated, andautomatic valves in the RHR suppression pool spray mode flow pathprovides assurance that the proper flow paths will exist for systemoperation.
This SR does not apply to valves that are locked, sealed,or otherwise secured in position since these valves were verified to bein the correct position prior to locking,
: sealing, or securing.
A valve is also allowed to be in the nonaccident position provided itcan be aligned to the accident position within the time assumed in theaccident analysis.
This is acceptable since the RHR suppression pool(continued)
HATCH UNIT 1 B366B 3.6-61 INSERT -Bases 3.6.2.4 Condition CRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 3) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action 0.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
RHR Suppression Pool SprayB 3.6.2.4BASESSURVEILLANCE REQUIREMENTS SR 3.6.2.4.1 (continued) cooling mode is manually initiated.
This SR does not require anytesting or valve manipulation; rather, it involves verification that thosevalves capable of being mispositioned are in the correct position.
ThisSR does not apply to valves that cannot be inadvertently misaligned, such as check valves.The Surveillance Fequency is controlled under the Surveillance Frequency Control Program.SR 3.6.2.4.2 This Surveillance is performed every 10 years to verify that the spraynozzles are not obstructed and that flow will be provided whenrequired.
The Surveillance Fequency is controlled under theSurveillance Frequency Control Program.REFERENCES
: 1. FSAR, Sections 5.2 and 14.4.3.2. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.
-BASES3.24 Reference 3.24HATCH UNIT 1 .66B 3.6-62 INSERT -Bases 3.6.2.4 Reference
: 3. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
Secondary Containment B 3.6.4.1B]ASES (continued)
ACTIONS A. 1If secondary containment is inoperable, it must be restored toOPERAB]LE status within 4 hours. The 4 hour Completion Timeprovides a period of time to correct the problem that is commensurate with the importance of maintaining secondary containment duringMODES 1, 2, and 3. This time period also ensures that the probability of an accident (requiring secondary containment OPERAB]ILITY) occurring during periods where secondary containment is inoperable is minimal.overall plant risk is IIf secondary containment cannot be restored to OPERAB]LE statusminimized.
within te requi ed Completion Time, the plant must be brought to aMODE in which"FeL;
,sat apl. To achieve this status, theplant must be brought to at least MODE 3 within 12 hours IMOD 4w:,~h,-
3P, allowed Completion Iic Iieireasonable, based on ope a*tig experience, to reach the requiredplant conditions from full power rnditions in an orderly manner andwithout challenging plant systems.]
INSERT -BASES 3.6.4.1C.1, C.2, and C.3 Condition B]Movement of irradiated fuel assemblies in the secondary containment, CORE ALTERATIONS, and OPDRVs can be postulated to causefissibn product release to the secondary containment.
In such- cases,the secondary containment is the only barrier to release of fissionproducts to the environment.
CORE ALTERATIONS and movementof irradiated fuel assemblies must be immediately suspended if thesecondary containment is inoperable.
Suspension of these activities shall not preclude completing anaction that involves moving a component to a safe position.
Also,action must be immediately initiated to suspend OPDRVs to minimizethe probability of a vessel draindown and subsequent potential forfission product release.
Actions must continue until OPDRVs aresuspended.
Required Action C.1 has been modified by a Note stating thatLCO 3.0.3 is not applicable.
If moving irradiated fuel assemblies whilein MODE 4 or 5, LCO 3.0.3 would not specify any action. If movingirradiated fuel assemblies while in MODE 1, 2, or 3, the fuelmovement is independent of reactor operations.
Therefore, in either(continued)
HATCH UNIT 1 B 3.6-78'.......I INSERT -Bases 3.6.4.1 Condition BRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 5), because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action B.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
Secondary Containment B 3.6.4.1BASESSURVEILLANCE REQUIREMENTS SR 3.6.4.1.3 and SR 3.6.4.1.4 (continued) demonstrates that the required SGT subsystem(s) can maintain> 0.20 inch of vacuum water gauge for 1 hour at a flow rate < 4000cfm for each SGT subsystem.
The 1 hour test period allowssecondary containment to be in thermal equilibrium at steady stateconditions.
Therefore, these two tests are used to ensure secondary containment boundary integrity.
Since these SRs are secondary containment tests, they need not be performed with each SGTsubsystem.
The SGT subsystems are tested on a STAGGERED TEST BASIS, however, to ensure that in addition to the requirements of LCO 3.6.4.3, each SGT subsystem or combination of subsystems will perform this test. The number of SGT subsystems and therequired combinations are dependent on the configuration of thesecondary containment and are detailed in the Technical Requirements Manual (Ref. 3). The Note to SR 3.6.4.1.3 andSR 3.6.4.1.4 specifies that the number of required SGT subsystems be one less than the number required to meet LCO 3.6.4.3,
'StandbyGas Treatment (SGT) System,"
for the given configuration.
TheSurveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES
: 1. FSAR, Subsection 14.4.3.2. FSAR, Subsection 14.4.4.3. Technical Requirements Manual, Se'ction 8.0.4. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.IINSERT -BASES 3.6.4.1< Reference HATCH UNIT 1B 3.6-80HATCH UNIT B 3.6-80 I '.
INSERT -Bases 3.6.4.1 Reference
: 5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
SGT SystemB 3.6.4.3BASESACTIONS A.1 and B.1 (continued) additional single failure (which is not necessary to assume while inACTIONS) the secondary containment volume may be drawn to avacuum in the time required to support assumptions of analyses.
: 0. .overall plant risk is* "F'.....
, minimized.I If the SGT subsyst m cannot be restored to OPERABLE status withinthe required Coin pion Time in MODE 1, 2, or 3, the plant must bebrought to a MODE To achieve thisstatus, the plant must be brought to at least MODE 3 within 12 hours.J---Time islan toMOD 4w~t!.q36hou~a./The allowed Completion Ireasonable, based on operating e oerience, to reach the requiredplant conditions from full power cor itions in an orderly manner andwithout challenging plant systems.
__INSERT
_ BASES 3.6.4.3D.1. D.2.1, D.2.2, and D.2.3During movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, whenRequired Action A. 1 or B. 1 cannot be completed within the requiredCompletion Time, the rerriaining required OPERABLE SGTsubsystems should immediately be placed in operation.
Thisaction ensures that the remaining subsystems are OPERABLE, thatno failures that could prevent automatic actuation have occurred, andthat any other failure would be readily detected.
An alternative to Required Action D.1 is to immediately suspendactivities that represent a potential for releasing radioactive materialto the secondary containment, thus placing the plant in acondition that minimizes risk. If applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies must immediately besuspended.
Suspension of these activities must not precludecompletion of movement of a component to a safe position.
Also, ifapplicable, actions must immediately be initiated to suspend OPDRVsin order to minimize the probability of a vessel draindown andsubsequent potential for fission product release.
Actions mustcontinue until OPDRVs are suspended.
(continued)
HATCH UNIT 1 B369B 3.6-91 INSERT -Bases 3.6.4.3 Condition CRemaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 6), because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action 0.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.
SGT SystemB 3.6.4.3BASESACTIONS D.1, D.2.t, D.2.2. and D.2.3 (continued)
The Required Actions of Condition D have been modified by a Notestating that LCO 3.0.3 is not applicable.
If moving irradiated fuelassemblies while in MODE 4 or 5, LCO 3.0.3 would not specify anyaction. If moving irradiated fuel assemblies while in MODE 1, 2, or 3,the fuel movement is independent of reactor operations.
Therefore, in either case, inability to suspend movement of irradiated fuelassemblies would not be a sufficient reason to require a reactorshutdown.
E.__1If two or more required SGT subsystems are inoperable in MODE 1, 2or 3, the Unit 1 and Unit 2 SGT Systems may not be capable ofsupporting the required radioactivity release control function..
INSERT -BASES 3.6.4.3F.1, .2, ad F.3Condition EWhen two or more required SOT subsystems are inoperable, ifapplicable, CORE ALTERATIONS and movement of irradiated fuelassemblies in secondary containment must immediately besuspended.
Suspension of these activities shall not precludecompletion of movement of a component to a safe position.
Also, ifapplicable, actions must immediately be initiated to suspend OPDRVsin order' to minimize the probability of a vessel draindown andsubsequent potential for fission product release.
Actions mustcontinue until OPDRVs are suspended.
Required Action F.1 has been modified by a Note stating thatLCO 3.0.3 is not applicable.
If moving irradiated fuel assemblies while in MODE 4 or 5, LCO 3.0.3 would not specify any action. Ifmoving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuelmovement is independent of reactor operations.
Therefore, in eithercase, inability to suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown.
(continued)
HATCH UNIT 1 B 3.6-92 !7l INSERT -Bases 3.6.4.3 Condition ETherefore, the plant must be brought to a MODE in which overall plant risk is minimized.
Toachieve this status, the plant must be brought to at least MODE 3 within 12 hours.Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 issimilar to or lower than the risk in MODE 4 (Ref. 6) and because the time spent in MODE 3 toperform the necessary repairs to restore the system to OPERABLE status will be short.However, voluntary entry into MODE 4 may be made as it is also an acceptable low-risk state.Required Action E.1 is modified by a Note that states that LCO 3.0.4.a is not applicable whenentering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startupwith the LCO not met. However, there is no restriction on the use of LCO 3.0.4.b, if applicable, because LCO 3.0.4.b requires performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability ofentering MODE 3, and establishment of risk management
: actions, if appropriate.
LCO 3.0.4 isnot applicable to, and the Note does not preclude, changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of ashutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach therequired plant conditions from full power conditions in an orderly manner and withoutchallenging plant systems.
SGT SystemB 3.6.4.3BASES (continued)
REFERENCES 12345* 10 CFR 50, Appendix A, GDC 41... Unit 1 FSAR, Section 5.3.2.3.*. Unit 2 ESAR, Sections 6.2.4, 15.2 and 15.3.* Technical Requirements Manual, Section 8.0.NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements,"
July 23, 1993.INSERT -BASES 3.6.4.3< Reference B 3.6-94HACHUIT1B
.-9 I I INSERT -Bases 3.6.4.3 Reference
: 6. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants, December 2002.
RHRSW SystemB 3.7.1IINSERT -BASES 3.7.1BASES Condition DACTIONS (continued)
With both RHRSW subsystems inoperable for reasons other thanCondition B (e.g., both subsystems with inoperable flow paths, or onesubsystem with an inoperable pump and one subsystem with aninoperable flow path), the RHRSW System is not capable ofperforming its intended function.
At least one subsystem must berestored to OPERABLE status within 8 hours. The 8 hour Completion Time for restoring one RHRSW subsystem to OPERABLE status, isbased on the Completion Times provided for the RHR suppression pool cooling and spray functions.
The Required Action is modified by a Note indicating that theapplicable Conditions of LCO 3.4.7 be entered and Required Actionstaken if an inoperable RHRSW subsystem results in an inoperable RHR shutdown cooling subsystem.
This is an exception to LCO 3.0.6and ensures the proper actions are taken for these components.
--of Condition EIf the RHRSW subsystems cannot be not rest( .d to OPERABLEstatus within the associated Completion Times ,the unit must beplaced in a MODE in which the LCO does not apply. To achieve thisstatus, the unit must be placed in at least MODE 3 within 12 hoursand in MODE 4 within 36 hours. The allowed Completion Times arereasonable, based on operating experience, to reach the required unitconditions from full power conditions in an orderly manner and withoutchallenging unit systems.SURVEILLANCE SR 3.7.1.1REQUIRE MENTSVerifying the correct alignment for each manual, power operated, andautomatic valve in each RHRSW subsystem flow path providesassurance that the proper flow paths will exist for RHRSW operation.
This SR does not apply to valves that are locked, sealed, or otherwise secured in position, since these valves are verified to be in the correctposition prior to locking,
: sealing, or securing.
A valve is also allowedto be in the nonaccident
: position, and yet considered in the correctposition, provided it can be realigned to its accident position.
This isacceptable because the RHRSW System is a manually initiated system. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being(continued)
HATCH UNIT 1B37-B 3.7-5}}

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