Text

E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 4
	ML15350A410
Person / Time
Site:	Hatch
Issue date:	12/15/2015
From:	Pierce C R; Southern Co, Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML15351A023	List: ML15350A409; ML15350A410; ML15350A411; NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 4; NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 3 of 4; NL-14-1075, Technical Specifications. Part 4 of 4;
References
	NL-14-1075
	Download: ML15350A410 (74)
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Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.8 3.6 CONTAINMENT SYSTEMS 3.6.1.8 Suppression Chamber-to-Drywell Vacuum Breakers LCO 3.6.1.8 Ten suppression chamber-to-drywell vacuum breakers shall be OPERABLE for opening.AND Twelve suppression chamber-to-drywell vacuum breakers shall be closed, except when performing their intended function.APPLICABILITY:

MODES 1, 2, and 3.ACTIONS_________________

___CONDITION REQUIRED ACTION COMPLETION TIME A. One required suppression A.1 Restore one vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months chamber-to-drywell vacuum breaker to OPERABLE breaker inoperable for status.opening.C.dywl C.umbeae-- 1 bekr On uppression chamber- Close the open vacuum 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months not closed.Required Action and Be MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D2 I~ f onitonCIBe in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months IlNSERT- TS 3.6.1.8I lCondition B HATCH UNIT 2 361 3.6-19 TS 3.6.1.8. -Condition B Insert B. 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RHR Suppression Pool Cooling 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 APPLICABILITY:

Two RHR suppression pool cooling subsystems shall be OPERABLE.MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression pool cooling subsystem inoperable.

lTwo RHR suppression pool S cooling subsystems inoperable.

[tRequired Action and associated Completion Time

Condition C I.JNSERT -TS 3.6.2.3I ,Condition B A. 1 Restore RHR suppression pool cooling subsystem to OPERABLE status.7 daysone RHR suppression pool cooling subsystem to OPERABLE status.MODE 3.IIf B nMODE 4.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 12 hours 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling In accordance with subsystem manual, power operated, and automatic the Surveillance valve in the flow path that is not locked, sealed, or Frequency Control otherwise secured in position is in the correct Program position or can be aligned to the correct position.(continued)

HATCH UNIT 2 362 3.6-25 TS 3.6.2.3 -Condition B Insert B. 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RHR Suppression Pool Spray 3.6.2.4 3.6 CONTAINMENT SYSTEMS 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray LCO 3.6.2.4 APPLICABILITY:

Two RHR suppression pool spray subsystems shall be OPERABLE.MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression pool A.1 Restore RHR 7 days spray subsystem suppression pool spray inoperable, subsystem to OPERABLE status.B. Two RHR suppression pool B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months spray subsystems suppression pool spray inoperable, subsystem to OPERABLE status.C. Required Action and C.1 ..Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion

/Time not met.-NOTE----LCO 3.0.4.a is not 0 .2 Dei- MODE. 4. applicable when entering M D 3........................._

_ _ _ _ _ _ _SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify each RHR suppression pool spray In accordance with subsystem manual, power operated, and the Surveillance automatic valve in the flow path that is not locked, Frequency Control sealed, or otherwise secured in position is in the Program correct position or can be aligned to the correct position.(continued)

HATCH UNIT 2 3.6-27 HATH^NI 23.-2....1 1 1 1 1... .210 Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 APPLICABILITY:-NOTE-------....

LCO 3.0.4.a is not applicable when entering MODE 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).ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment A.1 Restore secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable in MODE 1, 2, containment to or 3. OPERABLE status.B. Required Action and B.1 kBe in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not ____met.C. Secondary containment C.1------NOTE-

--inoperable during LCO 3.0.3 is not movement of irradiated fuel applicable.

assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel OPDRVs. assemblies in the secondary containment.

AND__________________________________________________(continued)

HATCH UNIT 2 363 3.6-33 Secondary Containment 3.6.4.1 No change. Included for information only.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)

C.2 Suspend CORE Immediately ALTERATIONS.

AND C.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 with hatches are closed and sealed. the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify one secondary containment access door in In accordance with each access opening is closed, the Surveillance Frequency Control Program SR 3.6.4.1.3-----------NOTE-

The number of standby gas treatment (SGT)subsystem(s) required for this Surveillance is dependent on the secondary containment configuration, and shall be one less than the number required to meet LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," for the given configuration.

Verify required SGT subsystem(s) will draw In accordance with down the secondary containment to > 0.20 inch the Surveillance of vacuum water gauge in < 120 seconds. Frequency Control Program (continued)

HATCH UNIT 2 3.6-34 HATC UNI 2 36-34Amendment No. 210 SGT System 3.6.4.3 No change. Included for information only.3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 APPLICABILITY:

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 the Unit 1 hardened vent rupture disk, entry into associated Conditions and Required Actions may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , provided both Unit 2 SGT subsystems are OPERABLE.CONDITION REQUIRED ACTION COMPLETION TIME A. One required Unit 1 SGT A.1 Restore required Unit 1 30 days from subsystem inoperable SGT subsystem to discovery of failure to while: OPERABLE status. mfeet the LCO 1. Four SGT subsystems required OPERABLE, and 2. Unit 1 reactor building-to-refueling floor plug not installed.(continued)

HATCH UNIT 2 3.6-39 HATC UNI 2 36-39Amendment No. 135

-NOTE-LCO 3.0.4.a is not applicable when entering MODE 3.SGT System 3.6.4.3 MUL I [L;UU]I~t]U~gU)

__ _ _ _ _ __ _ _ _ _CONDITION REQUIRED ACTION COMPLETION TIME B. One required Unit 2 SGT B.1 Restore required SOT 7 days subsystem inoperable, subsystem to OPERABLE status. AND OR 30 days from One required Unit 1 SGT discovery of failure to subsystem inoperable for meet the LCO reasons other than Condition A.C. Required Action and C.1 " Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B A-E not met in MODE 1, 2, or 3. I D. Required Action and---------NOTE-

---associated Completion LCO 3.0.3 is not applicable.

Time of Condition A or B not met during movement of irradiated fuel D.1 Place remaining Immediately assemblies in the OPERABLE SOT secondary containment, subsystem(s) in during CORE operation.

ALTERATIONS, or during OPDRVs. OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to Immediately suspend OPDRVs.(continued)

HATCH UNIT 2 364 3.6-40

-NOTE-.......

LCO 3.0O4.a is not applicable when entering MODE 3.SGT System 3.6.4.3 ACTIONS (continued)

CONDITION RQUIRED ACTION COMPLETION TIME E. Two or more required SGT E.1 "'!-- .I ..datt subsystems inoperable in MODE 1,2, or3. einMD 3. ____,--_12hours F. Two or more required SGT F.1------NOTE-.........

subsystems inoperable LCO 3.0.3 is not during movement of applicable.

irradiated fuel assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel OPDRVs. assemblies in secondary containment.

AND F.2 Suspend CORE Immediately ALTERATIONS.

AND F.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 Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP (continued)

HATCH UNIT 23641 3.6-41 RHRSW System 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System LCO 3.7.1 Two RHRSW subsystems shall be OPERABLE.APPLICABILITY:

MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHRSW pump A.1 Restore RHRSW pump 30 days inoperable, to OPERABLE status.B. One RHRSW pump in each B.1 Restore one RHRSW 7 days subsystem inoperable, pump to OPERABLE status.C. One RHRSW subsystem-------------NOTE-------

inoperable for reasons Enter applicable Conditions and other than Condition A. Required Actions of LCO 3.4.7,"Residual Heat Removal (RHR)Shutdown Cooling System -Hot Shutdown," for RHR shutdown cooling miade inoperable by RHRSW System.C.1 Restore RHRSW 7 days subsystem to OPERABLE status.-, INSERT -TS 3.7.1 Condition D (continued)

HATCH UNIT 2 3.7-1 HATH UIT 3.-1A,,-e 1 d,,-e 1 t ,No. 1.901 TS 3.7.1 -Condition D Insert D. 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RHRSW System 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Both RHRSW subsystems inoperable for reasons other than Condition B.Enter applicable Conditions and Required Actions of LCO 3.4.7 for RHR shutdown cooling made inoperable by RHRSW System.8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s] Required Action and LI I associated Completion Time ln ot met.Iof Condition E Be in MODE 3.AND Be in MODE 4.HATCH UNIT 2 3.7-2 PSW System and UHS 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Plant Service Water (PSW) System and Ultimate Heat Sink (UHS)LCO 3.7.2 Two P3W subsystems and UHS shall be OPERABLE.APPLICABILITY:

MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One PSW pump inoperable.

A.1 Restore PSW pump to 30 days OPERABLE status.B. One PSW turbine building B.1 Restore PSW turbine 30 days isolation valve inoperable, building isolation valve to OPERABLE status.C. One PSW pump in each C.1 Restore one PSW 7 days subsystem inoperable, pump to OPERABLE status.D. One PSW tur'bine building D.1 Restore one PSW 72 hpurs isolation valve in each turbine building subsystem inoperable, isolation valve to OPERABLE status.INSERT -TS 3.7.2 Condition E (continued)

HATCH UNIT 2373 3.7-3 TS 3.7.2 -Condition E Insert E. 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months PSW System and UHS 3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION [COMPLETION TIME One PSW subsystem inoperable for reasons other than Conditions A and B.-~~NOTES--

1.Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources -Operating," for diesel generator made inoperable by PSW System.2. Enter applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System -Hot Shutdown," for RHR shutdown cooling made inoperable by PSW System.Restore the PSW subsystem to OPERABLE status.72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s+Required Action and associated Completion Time of Condition

~por et.Be in MODE 3.AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours Be in MODE 4.ORR -Both PSW subsystems inoperable for reasons other than Conditions C and D.OR UHS inoperable.

L:5.r 3.7-4 HATCH UNIT 2 3.7-4 Amcndmcnt No. 135 MCREC System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Main Control Room Environmental Control (MCREC) System No change. Included for information only.LCO 3.7.4 Two MCREC subsystems shall be OPERABLE.-----------------

NOTE----------------

The main control room envelope (ORE) boundary may be opened intermittently under administrative 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).ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MCREC subsystem A.1 Restore MCREC 7 days inoperable for reasons subsystem to other 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. AND B.2 Verify mitigating actions 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ensure ORE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.AND B.3 Restore ORE boundary 90 days to OPERABLE status.(continued)

HATCH UNIT 2 3.7-8 HATC UNI 2 37-8Amendment No. 212

-NOTE-LCO 3.0.4.a is not applicable when entering MODE 3.MCREC System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B I/not met in MODE 1,2, or 3.I D. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDR Vs.-----------------

NOTE-------

LCO 3.0.3 is not applicable.

D.1 Place OPERABLE MCREC subsystem in pressurization mode.OR_D.2.1 Suspend movement of irradiated fuel assemblies in the secondary containment.

AND D.2.2 Suspend CORE ALTERATIONS.

AND Immediately Immediately Immediately Immediately

-.......NOTE-------....

LCO 3.0.4.a is not lapplicable when entering IMODE 3.'1 D.2.3 Initiate action to"\ suspend OPDRVs.E. Two MCREC subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B.E.1 E 1 1 t~~1 LCO 3.3.3 T""12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

HATCH UNIT 237-3.7-9 MCREC System 3.7.4 No change. Included for information only.ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two MCREC subsystems-------NOTE-----

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel assemblies in the secondary containment, F. 1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS, or during assemblies in the OPDR Vs. secondary containment.

OR AND One or more MCREC F.2 Suspend CORE Immediately subsystems inoperable due ALTERATIONS.

to an inoperable CRE boundary during movement AND of irradiated fuel assemblies in the F.3 Initiate action to Immediately secondary containment, suspend OPDRVs.during CORE ALTERATIONS, or during OPDR Vs.SURVEILLANCEREQUIREMENTS

_______SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREC subsystem

> 15 minutes. In accordance with the Surveillance Frequency Control Program SR 3.7.4.2 Perform required MCREC filter testing in In accordance with accordance with the Ventilation Filter Testing the VFTP Program (VFTP).SR 3.7.4.3 Verify each MCREC subsystem actuates on an In accordance with actual or simulated initiation signal. the Surveillance Frequency Control Program (continued)

HATCH UNIT 2 3.7-10 HATC UNI 2 37-10Amendment No. 212 Control Room AC System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Control Room Air Conditioning (AC) System No change. Included for information only.LCO 3.7.5 APPLICABILITY:

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).ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room AC A.1 Restore control room 30 days subsystem inoperable.

AC subsystem to OPERABLE status.B. Two control room AC B.1 Verify control room area Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months subsystems inoperable, temperature

< 90°F.AND B.2 Restore one control 7 days room AC subsystem to OPERABLE status.C. Three control room AC C.1 Verify control room area Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months subsystems inoperable, temperature

< 90°F.AND C.2 Restore one control 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months room AC subsystem to OPERABLE status.(continued)

HATCH UNIT 2 3.7-12 HATC UNI 2 37-12Amendment No. 214 AC-~NOTE----

LCO 3.0.4.a is not applicable when entering MODE 3.Control Room AC System 3.7.5 CONDITION XREQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion

___________

Time of Condition A, B, or I C not met in MODE 1, 2, or 3. h9 eP in .MODEl A.16hor E. Required Action and---------NOTE-

---associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met------------

during movement of irradiated fuel assemblies in E.1 Place OPERABLE Immediately the secondary containment, control room AC during CORE subsystems in ALTERATIONS, or during operation.

OPDRVs.OR E.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND E.2.2 Suspend CORE Immediately ALTERATIONS.

AND E.2.3 Initiate action to Immediately suspend OPDR Vs.(continued)

HATCH UNIT 2 3.7-13 HATC UNI 2 37-13Amedmont ,No. 2 11 Main Condenser Offgas 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Main Condenser Offgas LCO 3.7.6 APPLICABILITY:

The gross gamma activity rate of the noble gases measured at the main condenser 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 air ejector (SJAE) in operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Gross gamma activity rate A.1 Restore gross gamma 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the noble gases not activity rate of the noble within limit, gases to within limit.B. Required Action and B.1 Isolate all main steam 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion lines.Time not met.-NOTE------OR LCO 3.0.4.a is not 8.2 Isolate SJAE. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months applicable when entering\MODE 3. OR..l Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B,,.3.., l l % l,.l,,,, -I.v l -I HATCH UNIT 2 371 3.7-16 AC Sources -Operating 3.8.1 INo change. Included for 3.8 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 network and 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 and the Unit 1 onsite Class 1 E AC Electrical Power Distribution subsystem(s) needed to support the Unit 1 equipment required to be 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 Air Conditioning (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 pressure coolant injection (LPCI) valve load center; and g. One qualified circuit between the offsite transmission network and the applicable onsite Class 1 E AC electrical power distribution subsystems needed to support each Unit 2 LPCI valve load center required by LCO 3.5.1, "ECCS -Operating." APPLICABILITY:

MODES 1, 2, and 3.3.8-1 HATC UNI 2 38-1Amendment No. 152 AC Sources -Operating 3.8.1 ACTIONS No change. Included for information only.-NOTE.LCO 3.0.4.b is not applicable to DGs.CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

OPERABLE required offsite circuits.

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Declare required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery feature(s) with no offsite of no offsite power to power available one 4160 V ESF bus inoperable when the concurrent with redundant required inoperability of feature(s) are redundant required inoperable, feature(s)

AND A.3 Restore required offsite 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s*circuit to OPERABLE status. AND 17 days from discovery of failure to meet LCO 3.8.1.a, b, or c B. One Unit 2 or the swing DG B.I1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

OPERABLE required offsite circuit(s).

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND________________________

______________________(continued)

HATCH UNIT 2 3.8-2 HATC UNI 2 38-2Amendment No. 190 AC Sources -Operating 3.8.1 No change. Included for information only.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) 8.2 Declare required feature(s), supported by the inoperable DC, inoperable when the redundant required feature(s) are inoperable.

AND B.3.1 Determine OPERABLE DG(s) are not inoperable due to common cause failure.OR 8.3.2 Perform SR 3.8.1.2.a for OPERABLE DC(s)AND 8.4 Restore DG to OPERABLE status.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition B concurrent with inoperability of redundant required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 hours 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for a Unit 2 DC with the swing DC not inhibited or maintenance restrictions not met AND 14 days for a Unit 2 DG with the swing DC inhibited from automatically aligning to Unit 1 and maintenance restrictions met AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for the swing diesel with maintenance restrictions not met (continued)

HATC UNI 2 38-3Amendment No. 203 HATCH UNIT 2 3.8-3 AC Sources -Operating 3.8.1 No change. Included for information only.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)

B.4 (continued)

AND 14 days for the swing diesel with maintenance restrictions met AND 17 days from discovery of failure to meet LCO 3.8.1 .a, b, or c C. One required Unit 1 DG inoperable.

C.1 Perform SR 3.8.1.1 for OPERABLE required offsite circuit(s).

AND C.2 Declare required feature(s), supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable.

AND C.3.1 Determine OPERABLE DG(s) are not inoperable due to common cause failure.OR C.3.2 Perform SR 3.8.1.2.a for OPERABLE DG(s).1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition C concurrent with inoperability of redundant required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 hours (continued) 3.8-4 HATC UNI 2 38-4Amendment No. 203 AC Sources -Operating 3.8.1 No change. Included for information only.IJ CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)

AND C.4 Restore required DG to OPERABLE status.7 days with the swing DG not inhibited or maintenance restrictions not met AND 14 days with the swing DG inhibited from automatically aligning to Unit 2 and maintenance restrictions met 4 4 D. Two or more required offsite circuits inoperable.

D.1 Declare required feature(s) with no offsite power available inoperable when the redundant required feature(s) are inoperable.

AND D.2 Restore all but one required offsite circuit to OPERABLE status.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from discovery of Condition D concurrent with inoperability of redundant required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4 4 E. One required offsite circuit inoperable.

AND One required DG inoperable.

-~~NOTE--

--Enter applicable Conditions and Required Actions of LCO 3.8.7,"Distribution Systems -Operating," when Condition E is entered with no AC power source to one 4160 V ESF bus.E.1 Restore required offsite circuit to OPERABLE status.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

Amendment No. 203 HATCH UNIT 238-3.8-5 AC Sources -Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. (continued)

OR E.2 Restore required DG 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to OPERABLE status.F. Two or more (Unit 2 and F.1 Restore all but one 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months swing) DGs inoperable.

Unit 2 and swing DGs to OPERABLE status.G. No DGs capable of G.1 Restore one DG 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months supplying power to any capable of supplying Unit 2 LPCI valve load power to Unit 2 LPCI center. valve load center to OPERABLE status.H. Required Action and H.1 /t1e in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion f Time 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 p more required DGs jINOTE inoperable.

JLCO 3.0.4.a is not tapplicable when entering OR JMODE 3.Two or more required offsite circuits and one required DG inoperable.

HATCH UNIT 2 3.8-6 HATCHUNIT2 3.-6 Amndrn ,'oN. 20311 DC Sources -Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources -Operating No change. Included for information only.LCO 3.8.4 The following DC electrical power subsystems shall be OPERABLE: a. The Unit 2 Division 1 and Division 2 station service DC electrical power subsystems;

b. The Unit 2 and the swing DGs DC electrical power subsystems; and c. The Unit 1 OG DC electrical power subsystems needed to support the equipment required to be OPERABLE by LCO 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 TIME A. Swing DG DC electrical A.1 Restore DG DC 7 days power subsystem electrical power inoperable due to subsystem to performance of SR 3.8.4.7 OPERABLE status.or SR 3.8.4.8.OR One or more required Unit I DG DC electrical power subsystems inoperable.(continued)

HATCH UNIT 2 3.8-26 HATC UNI 2 38-26Amendment No. 169 DC Sources -Operating 3.8.4 ACTIONS (continued)_________________________

CONDITION REQUIRED ACTION COMPLETION TIME B. One Unit 2 DG DC B.1 Restore DG DC 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months electrical power subsystem electrical power inoperable, subsystem to OPERABLE status.OR_ R______SINOTE----

Swing DG DC electrical ILCO 3.0.4.a is not power subsystem

[- applicable when entering inoperable for reasons _MODE 3 other than Condition A. -3..........

C. One Unit 2 station service C.1\ Restore station service 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DC electrical power \ DC electrical power subsystem inoperable, subsystem to OPERABLE status.D. Required Action and D.1 "Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time of Condition A, B, N or C not met.E. Two or more DC electrical E.1 Enter LCO 3.0.3. Immediately power subsystems inoperable that result in a loss of function.HATCH UNIT 2 382 3.8-27 Distribution Systems -Operating 3.8.7 No change. Included for information only.3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems -Operating LCO 3.8.7 APPLICABILITY:

The following AC and DC electrical power distribution subsystems shall be 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; and b. Unit 1 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 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." MODES 1, 2, and 3.ACTIONS ________CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 7 days Unit 1 AC or DC electrical Unit 1 AC and DC power distribution subsystem(s) to subsystems inoperable.

OPERABLE status.(continued)

HATCH UNIT 2 3.8-37 HATH NI 2 .837Amendment No. 210 I Distribution Systems -Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more (Unit 2 or B.1 Restore DG DC 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months swing bus) DG DC electrical power electrical power distribution distribution subsystem AND subsystems inoperable, to OPERABLE status.16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO 3.8.7.a C. One or more (Unit 2 or C.1 Restore AC electrical 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months swing bus) AC electrical power distribution power distribution subsystem to AND subsystems inoperable.

OPERABLE status.16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO 3.8.7.a D. One Unit 2 station service D.1 Restore Unit 2 station 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DC electrical power service DC electrical distribution subsystem power distribution AND inoperable, subsystem to OPERABLE status. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO 3.8.7.a E. Required Action and associated Completion Time of Condition A, B, C, or D not met.F. Two or more electrical power distribution subsystems inoperable that result in a loss of function.HATCH UNIT 2 383 3.8-38 RPS Electric Power Monitoring B 3.3.8.2 BASES ACTIONS Al1 (continued) operations personnel to take corrective actions or to place the plant in the 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 service would result in a scram or isolation), Condition C or D, as applicable, must be entered and its Required Actions taken.B._.11 If 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 system protective function is lost. In this condition, 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is allowed to restore one assembly to OPERABLE status for each inservice power supply. If one inoperable assembly for each inservice power supply cannot be restored to OPERABLE status, the associated power supply(s) must be removed from service within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (Required Action B.1). An alternate power supply with OPERABLE assemblies may then be used to power one RPS bus. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is sufficient for the plant operations personnel to take corrective actions and is acceptable because it minimizes risk while allowing time for restoration or removal from service of the electric power monitoring assemblies.

Alternately, if it is not desired to remove the power supply(s) from service (e.g., as in the case where removing the power supply(s) from service would result in a scram or isolation), Condition C or D, as applicable, must be entered and its Required Actions taken.p ~ ~ ~ ~ ~tepant smtonusscmpi paigt be proant in withDEin 12 hoyReuirs dAto n asoiae ThemaloeCmpeti ono Codtonditi ae on C e (contin2 o 3ap~rt .u ed)--HATCHtUNIT-1 3.3.- 196^- .."'^-^";. ....

INSERT -Bases 3.3.8.2 Condition C Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 4) and because the time spent in MODE 3 to perform 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 when entering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startup with 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 of entering MODE 3, and establishment of risk management actions, if appropriate.

LCO 3.0.4 is not 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 a shutdown of the unit.

RPS Electric Power Monitoring B 3.3.8.2 BASES ACTIONS C. 11=-. (continued) required plant conditions from full power conditions in an orderly manner and without challenging plant systems.Dl.1 D.2.1. and D.2.2 If any Required Action and associated Completion Time of Condition A or B are not met in MODE 4 or 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies or with both RHR shutdown cooling valves open, the operator must immediately initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.

Required Action 0.1 results in the least reactive condition for the reactor core and ensures that the safety function of the RPS (e.g., scram of control rods) is not required.In addition, action must be immediately initiated to either restore one electric power monitoring assembly to OPERABLE status for the inservice power source supplying the required instrumentation powered from the RPS bus (Required Action 0.2.1) or to isolate the RHR Shutdown Cooling System (Required Action 0.2.2). Required Action 0.2.1 is provided because the RHR Shutdown Cooling System may be needed to provide core cooling. All actions must continue until the applicable Required Actions are completed.

SURVEILLANCE REQUIRE MENTS The Surveillances are modified by a Note to indicate that when an RPS electric power monitoring assembly is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the other RPS electric power monitoring assembly for the associated power supply maintains trip capability.

Upon completion of the Surveillance, or expiration of the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.(continued)

HATCH UNIT 1B3319 B 3.3-197 RPS Electric Power Monitoring B 3.3.8.2 BASES (continued)

REFERENCES

1. FSAR, Section 8.7.2. NRC Generic Letter 9 1-09, "Modification of Surveillance Interval for the Electrical Protective Assemblies in Power Supplies 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 1B33-9 B 3.3-199 INSERT -Bases 3.3.8.2 Reference 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

ECCS -Operating B 3*5.1 BASES ACTIONS A.1 (continued) based on a reliability study (Ref. 11) that evaluated the impact on ECCS availability, assuming various components and subsystems were taken out of service. The results were used to calculate the average availability of EGOS equipment needed to mitigate the consequences of a LOCA as a function of allowed outage times (i.e., Completion Times).B.1 plant risk If the inoperable low pressure ECCS subsystem cannot be restored to OPERABLE status within the associ efd Completion Time, the plant must be brought to a MODE in which'e LCde ota#,, To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .. _-,wun,,, ,u* he allowed Completion easonable, based on ope experience, to reach the required plah conditions from full power c qditions in an orderly manner and wit ut challenging plant systems.]--Time is INSERT -BASES 3.5.1 I C.1 and 0.2 Condition B If the HPCI System is inoperable and the RCIC System is verified to be OPERABLE, the HPCI System must be restored to OPERABLE status within 14 days. In this condition, adequate core cooling is ensured by the OPERABILITY of the redundant and diverse low pressur~e ECCS injection/spray subsystems in conjunction with ADS.Also, the RCIC System will automatically provide makeup water at most reactor operating pressures.

Verification of RCIC OPERABILITY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is therefore required when HPCI is inoperable.

This may be performed as an administrative check by examining logs or other information to determine if RCIC is out of service for maintenance or other reasons. It does not mean to perform the Surveillances needed to demonstrate the OPERABILITY of the RCIC System. If the OPERABILITY of the RCIC System cannot be verified, however, Condition E must be immediately entered. If a single active component fails concurrent with a design basis LOCA, there is a potential, depending on the specific failure, that the minimum required ECCS equipment will not be available.

A 14 day Completion Time is based on a reliability study cited in Reference 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 B Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 15), because the time spent in MODE 3 to perform 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 when entering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startup with 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 of entering MODE 3, and establishment of risk management actions, if appropriate.

LCO 3.0.4 is not 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 a shutdown of the unit.

ECCS -Operating B 3.5.1 BASES ACTIONS D.1 and D.2 If any one low pressure ECCS injection/spray subsystem is inoperable in addition to an inoperable HPCI System, the inoperable low pressure ECCS injection/spray subsystem or the HPCI System must be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . In this condition, adequate core cooling is ensured by the OPERABILITY of the ADS and the remaining low pressure ECCS subsystems.

However, the overall ECCS reliability is significantly reduced because a single failure in one of the remaining OPERABLE subsystems concurrent with a design basis LOCA may result in the ECCS not being able to perform its intended safety function.

Since both a high pressure system (HPCI) and a low pressure subsystem are inoperable, a more restrictive Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is required to restore either the HPCI System or the low pressure ECCS injection/spray subsystem to OPERABLE status. This Completion Time is based on a reliability study cited in Reference 11 and has been found to be acceptable through operating experience.

F.1an~d F.2 With one ADS valve inoperable, no action is required, because an analysis demonstrated that the remaining six ADS valves are capable of providing the ADS function, per Reference 13.INSERT -BASES 35.1 Condition E i.I;I .... n .... :__,J A--J.: .... .J A:_,I._-I .... "If--: .... Klj~y~tny rr~uguiwu

~CLIOfl ano a~uociaioo

~om e~en-~me ~I ........ .......... ,or flwoor more ADS valves are inoperable, the plant must be brought to a condition in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reactor steam dome pressure reduced to < 150 psig within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . Entry into MODE 3 is not required if the reduction in reactor steam dome pressure to < 150 psig results in exiting the Applicability for the Condition, and the < 150 psig is achieved within the given 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without 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 E E.__If any Required Action and associated Completion Time of Condition C or D is not met, the plant must be brought to a MODE in which overall plant risk is minimized.

To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 15) and because the time spent in MODE 3 to perform 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 when entering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startup with 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 of entering MODE 3, and establishment of risk management actions, if appropriate.

LCO 3.0.4 is not 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 a shutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

ECCS -Operating B 3.5.1 BASES (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 2 SAFER/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 ECCS Components," 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 Nuclear Power Plant Units 1 and 2 Updated Safety/Relief Valve Performance Requirements," April 1996.14. ASME, OM Code -1995, "Code for Operation and Maintenance of Nuclear Power Plants," Appendix I.ilNSERT- BASES 3.5.1 I< Reference' d HATCH UNIT 1 B351 B 3.5-13 INSERT -Bases 3.5.1 Reference 15. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

RCIC System B 3.5.3 BASES ACTIONS A.1 and A.2 (continued)

If the RCIC System is inoperable during MODE 1, or MODE 2 or 3 with reactor steam dome pressure > 150 psig, and the HPCI System is verified to be OPERABLE, the RCIC System must be restored to OPERABLE status within 14 days. In this condition, loss of the RCIC System will not affect the overall plant capability to provide makeup inventory at high reactor pressure since the HPCI System is the only high pressure system assumed to function during a loss of coolant accident (LOCA). OPERABILITY of HPCI is therefore verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months when the RCIC System is inoperable.

This may be performed as an administrative check, by examining logs or other information, to determine if HPCI is out of service for maintenance or other reasons.It does not mean it is necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the HPCI System. If the OPERABILITY 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 coolant because of its relatively small capacity, which allows easier control of the RPV water level. Therefore, a limited time is allowed to restore the 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 various components and subsystems were taken out of service. The results were used to calculate the average availability of ECCS equipment needed to mitigate the consequences of a LOCA as a function of allowed outage times (AOTs). Because of similar functions of HPCI and RCIC, the AOTs (i.e., Completion Times) determined for HPCI are also applied to RCIC.If the RCIC System cannot be restored to OPERABLE status within overall 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 must bem brought toatleast~

MOD 153 s within 36 hurs.~n he allowsedmbased on operating experience, to reach the r uired plant conditions from full power condi l~ons in an (continued)

HATCH UNIT 1 B352 B 3.5-23 INSERT -Bases 3.6.3 Condition B Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 6) and because the time spent in MODE 3 to perform 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 when entering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startup with 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 of entering MODE 3, and establishment of risk management actions, if appropriate.

LCO 3.0.4 is not 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 a shutdown of the unit.

RCIC System B 3.5.3 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.5.3.5 (continued) low water level (Level 2) signal received subsequent to an RPV high water level (Level 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.2 overlaps this Surveillance to provide complete testing of the assumed safety function.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.This SR is modified by a Note that excludes vessel injection during the Surveillance.

Since all active components are testable and full flow 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 ECCS Components," December 1, 1975.4. GE Report AES-41-0688, "Safety Evaluation for Relaxation of RCIC Performance Requirements for Plant'Hatch Units 1 and 2," July 1988.5. NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.IINSERT -BASES 3.5.3 1Reference HATCH UNIT 1 B352 B 3.5-26 INSERT -Bases 3.5.3 Reference 6. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

Reactor Building-to-Suppression Chamber Vacuum Breakers B 3.6.1.7 BASES ACTIONS 0. 1 (continued)

With one line with one or more vacuum breakers inoperable for opening, the leak tight primary containment boundary is intact. The ability to mitigate an event that causes a containment depressurization is threatened, however, if both vacuum breakers in at least one vacuum breaker penetration are not OPERABLE.

Therefore, the inoperable vacuum breaker must be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . This is consistent with the Completion Time for Condition 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 for opening, the primary containment boundary is intact. However, in the event of a containment depressurization, the function of the vacuum breakers is lost. Therefore, all vacuum breakers in one line must be restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . This Completion Time is consistent with the ACTIONS of LCO 3.6.1.1, which require that primary containment be restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .If the vacuum breakers in one or more lines cannot bethplnmutbbruhtoaMDinwchheLOdsnt closed or restored to OPERABLE status within py oaheeti tts h ln utb ruh oa es MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The the required Completion allowed Completion Times are reasonable, based on operating Time, experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.SURVEILLANCE SR 3.6.1.7.1 REQUIREMENTS Each vacuum breaker is verified to be closed to ensure that a potential breach in the primary containment boundary is not present.This Surveillance is performed by observing local or control room indications of vacuum breaker position or by verifying a differential pressure of 0.5 psid is maintained between the reactor building and suppression chamber. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.(continued)

HATCH UNIT 1 B363 B 3.6-38 INSERT -Bases 3.6.1.7 Condition D 0.1_If one line has one or more reactor building-to-suppression chamber vacuum breakers inoperable for opening and they are not restored within the Completion Time in Condition C, the remaining breakers in the remaining lines can provide the opening function.

The plant must be brought to a condition in which overall plant risk is minimized.

To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 4) and because the time spent in MODE 3 to perform 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 when entering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startup with 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 of entering MODE 3, and establishment of risk management actions, if appropriate.

LCO 3.0.4 is not 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 a shutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

Reactor Building-to-Suppression Chamber Vacuum Breakers B 3.6.1.7 BASES (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 3.6.1.7 IReference HATCH UNIT 1 B364 B 3.6-40 INSERT -Bases 3.6.1.7 Reference 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

Suppression Chamber-to-Drywell Vacuum Breakers 8 3.6.1.8 BASES ACTIONS A. 1 (continued) considered acceptable due to the low probability of an event in which the remaining vacuum breaker capability would not be adequate.INSERT -BASES 3.6.1.8[--7 Condition B An open vacuum breaker allows communication between the drywell and suppression chamber airspace, and, as a result, there is the potential for suppression chamber overpressurization due to this bypass leakage if a LOCA were to occur. Therefore, the open vacuum breaker must be closed. The required 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 not appl .To achieve this status, the plant must be brought to at least MOD 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allow d Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant o,,÷,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 is performed by observing the vacuum breaker position indication or by verifying that a differential pressure of 0.5 psid between the drywell and suppression chamber is maintained for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months without makeup.However, if vacuum breaker position indication is not reliable, either due 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 of verifying that the vacuum breaker is closed are detailed in Technical Requirements Manual (TRM) (Ref. 4), T3.6.1, "Suppression (continued)

HATCH UNIT 1 B364 B 3.6-44 INSERT -Bases 3.6.1.8 Condition B If a required suppression chamber-to-drywell vacuum breaker is inoperable for opening and is not restored to OPERABLE status within the required Completion Time, the plant must be brought to a condition in which overall plant risk is minimized.

To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 5) and because the time spent in MODE 3 to perform 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 when entering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startup with 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 of entering MODE 3, and establishment of risk management actions, if appropriate.

LCO 3.0.4 is not 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 a shutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

Suppression Chamber-to-Drywell Vacuum Breakers B 3.6.1.8 BASES (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 3.6.1.8 IReference HATCH UNIT 1 .-6REIIN3 B 3.6-46 INSERT -Bases 3.6.1.8 Reference 5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

RHR Suppression Pool Cooling (continued)

With two RHR suppression pooi cooling subsystems inoperable, one subsystem must be restored to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . In this condition, there is a substantial loss of the primary containment pressure and temperature mitigation function.

The 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Completion Time is based on this loss of function and is considered acceptable due to the low probability of a DBA and because alternative methods to remove heat from primary containment are available.

I-- Required Action and associated Completion Time'-cannot be met, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions 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, and automatic valves in the RHR suppression pool cooling mode flow path provides assurance that the proper flow path exists for system operation.

This does not apply to valves that are locked, sealed, or otherwise secured in position since these valves were verified to be in the correct position prior to locking, sealing, or securing.

A valve is also allowed to be in the nonaccident position provided it can be aligned to the accident position within the time assumed in the accident analysis.

This is acceptable since the RHR suppression pool cooling mode is manually initiated.

This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position.

This SR 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 B B__t If one RHR suppression pool cooling subsystem is inoperable and is not restored to OPERABLE status within the required Completion Time, the plant must be brought to a condition in which overall plant risk is minimized.

To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 4) and because the time spent in MODE 3 to perform 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 when entering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startup with 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 of entering MODE 3, and establishment of risk management actions, if appropriate.

LCO 3.0.4 is not 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 a shutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

RHR Suppression Pool Cooling B 3.6.2.3 BASES SURVEILLANCE 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 cooling mode with flow through the associated heat exchanger ensures that pump performance has not degraded during the cycle. Flow is a normal test of centrifugal pump performance required by ASME Code,Section XI (Ref. 2). This test confirms one point on the pump design curve, and the results are indicative of overall performance.

Such inservice tests confirm component OPERABILITY and detect incipient failures by indicating abnormal performance.

The Frequency of this SR 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 B365 B 3.6-58 I INSERT -Bases 3.6.2.3 Reference 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

RHR Suppression Pool Spray B 3.6.2.4 BASES ACTIONS A. 1 (continued)

However, the overall reliability is reduced because a single failure in the OPERABLE subsystem could result in reduced primary containment bypass mitigation capability.

The 7 day Completion Time was chosen in light of the redundant RHR suppression pool spray capabilities afforded by the OPERABLE subsystem and the low probability of a DBA occurring during this period.B.__1 With both RHR suppression pool spray subsystems inoperable, at least one subsystem must be restored to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . In this Condition, there is a substantial loss of the primary containment bypass leakage mitigation function.

The 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Completion Time is based on this loss of function and is considered acceptable due to the low probability of a DBA and because alternative methods to remove heat from primary containment are available.

c_.1 .rminimized___

._: _If any Required Action and associated Completion Time cannot be met, the plant must be brought to a MODE in whicl the-LC- -1 tI~jTo achieve this status, the plant must be brought to at least MODE 3 within 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sI .he allowed Completio reasonable, based on operating

_expe~ "-tea£, to Tmisreach the/required plant conditions from full power conditions in an-'I~ie i Iorderly manner and without challenging plant systems. INSERT -BASES- 3.6.2.4 Condition C SURVEILLANCE SR 3.6.2.4.1 REQUIREMENTS Verifying the correct alignment for manual, power operated, and automatic valves in the RHR suppression pool spray mode flow path provides assurance that the proper flow paths will exist for system operation.

This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these valves were verified to be in the correct position prior to locking, sealing, or securing.A valve is also allowed to be in the nonaccident position provided it can be aligned to the accident position within the time assumed in the accident analysis.

This is acceptable since the RHR suppression pool (continued)

HATCH UNIT 1 B366 B 3.6-61 INSERT -Bases 3.6.2.4 Condition C Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 3) and because the time spent in MODE 3 to perform 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 when entering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startup with 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 of entering MODE 3, and establishment of risk management actions, if appropriate.

LCO 3.0.4 is not 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 a shutdown of the unit.

RHR Suppression Pool Spray B 3.6.2.4 BASES SURVEILLANCE REQUIREMENTS SR 3.6.2.4.1 (continued) cooling mode is manually initiated.

This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of being mispositioned are in the correct position.

This SR 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 spray nozzles are not obstructed and that flow will be provided when required.

The Surveillance Fequency is controlled under the Surveillance 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 3.24 HATCH UNIT 1 .66 B 3.6-62 INSERT -Bases 3.6.2.4 Reference 3. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

Secondary Containment B 3.6.4.1 B]ASES (continued)

ACTIONS A. 1 If secondary containment is inoperable, it must be restored to OPERAB]LE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time provides a period of time to correct the problem that is commensurate with the importance of maintaining secondary containment during MODES 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 status minimized.

within te requi ed Completion Time, the plant must be brought to a MODE in which"FeL; ,sat apl. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I MOD 4w:,~h,- 3P, allowed Completion Iic Iiei reasonable, based on ope a*tig experience, to reach the required plant conditions from full power rnditions in an orderly manner and without challenging plant systems.]INSERT -BASES 3.6.4.1 C.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 cause fissibn product release to the secondary containment.

In such- cases, the secondary containment is the only barrier to release of fission products to the environment.

CORE ALTERATIONS and movement of irradiated fuel assemblies must be immediately suspended if the secondary containment is inoperable.

Suspension of these activities shall not preclude completing an action that involves moving a component to a safe position.

Also, action must be immediately initiated to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.

Required Action C.1 has been modified by a Note stating that LCO 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. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations.

Therefore, in either (continued)

HATCH UNIT 1 B 3.6-78'.......I INSERT -Bases 3.6.4.1 Condition B Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 5), because the time spent in MODE 3 to perform 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 when entering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startup with 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 of entering MODE 3, and establishment of risk management actions, if appropriate.

LCO 3.0.4 is not 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 a shutdown of the unit.

Secondary Containment B 3.6.4.1 BASES SURVEILLANCE 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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at a flow rate < 4000 cfm for each SGT subsystem.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months test period allows secondary containment to be in thermal equilibrium at steady state conditions.

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 SGT subsystem.

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 the required combinations are dependent on the configuration of the secondary containment and are detailed in the Technical Requirements Manual (Ref. 3). The Note to SR 3.6.4.1.3 and SR 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, 'Standby Gas Treatment (SGT) System," for the given configuration.

The Surveillance 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 1 B 3.6-80 HATCH 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 to Selected Required End States for BWR Plants, December 2002.

SGT System B 3.6.4.3 BASES ACTIONS A.1 and B.1 (continued) additional single failure (which is not necessary to assume while in ACTIONS) the secondary containment volume may be drawn to a vacuum 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 within the required Coin pion Time in MODE 1, 2, or 3, the plant must be brought to a MODE To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .J---Time is lan toMOD 4w~t!.q36hou~a./The allowed Completion I reasonable, based on operating e oerience, to reach the required plant conditions from full power cor itions in an orderly manner and without challenging plant systems. __INSERT _ BASES 3.6.4.3 D.1. D.2.1, D.2.2, and D.2.3 During movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, when Required Action A. 1 or B. 1 cannot be completed within the required Completion Time, the rerriaining required OPERABLE SGT subsystems should immediately be placed in operation.

This action ensures that the remaining subsystems are OPERABLE, that no failures that could prevent automatic actuation have occurred, and that any other failure would be readily detected.An alternative to Required Action D.1 is to immediately suspend activities that represent a potential for releasing radioactive material to the secondary containment, thus placing the plant in a condition that minimizes risk. If applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies must immediately be suspended.

Suspension of these activities must not preclude completion of movement of a component to a safe position.

Also, if applicable, actions must immediately be initiated to suspend OPDRVs in order to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.(continued)

HATCH UNIT 1 B369 B 3.6-91 INSERT -Bases 3.6.4.3 Condition C Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 6), because the time spent in MODE 3 to perform 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 when entering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startup with 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 of entering MODE 3, and establishment of risk management actions, if appropriate.

LCO 3.0.4 is not 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 a shutdown of the unit.

SGT System B 3.6.4.3 BASES ACTIONS D.1, D.2.t, D.2.2. and D.2.3 (continued)

The Required Actions of Condition D have been modified by a Note stating that LCO 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. 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 fuel assemblies would not be a sufficient reason to require a reactor shutdown.E.__1 If two or more required SGT subsystems are inoperable in MODE 1, 2 or 3, the Unit 1 and Unit 2 SGT Systems may not be capable of supporting the required radioactivity release control function..

INSERT -BASES 3.6.4.3 F.1, .2, ad F.3Condition E When two or more required SOT subsystems are inoperable, if applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies in secondary containment must immediately be suspended.

Suspension of these activities shall not preclude completion of movement of a component to a safe position.

Also, if applicable, actions must immediately be initiated to suspend OPDRVs in order' to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.

Required Action F.1 has been modified by a Note stating that LCO 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. 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 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 E Therefore, the plant must be brought to a MODE in which overall plant risk is minimized.

To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .Remaining in the Applicability of the LCO is acceptable because the plant risk in MODE 3 is similar to or lower than the risk in MODE 4 (Ref. 6) and because the time spent in MODE 3 to perform 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 when entering MODE 3. This Note prohibits the use of LCO 3.0.4.a to enter MODE 3 during startup with 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 of entering MODE 3, and establishment of risk management actions, if appropriate.

LCO 3.0.4 is not 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 a shutdown of the unit.The allowed Completion Time is reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SGT System B 3.6.4.3 BASES (continued)

REFERENCES 1 2 3 4 5* 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 3.6-94 HACHUIT1B

.-9 I I INSERT -Bases 3.6.4.3 Reference 6. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

RHRSW System B 3.7.1 IINSERT -BASES 3.7.1 BASES Condition D ACTIONS (continued)

With both RHRSW subsystems inoperable for reasons other than Condition B (e.g., both subsystems with inoperable flow paths, or one subsystem with an inoperable pump and one subsystem with an inoperable flow path), the RHRSW System is not capable of performing its intended function.

At least one subsystem must be restored to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Completion Time for restoring one RHRSW subsystem to OPERABLE status, is based on the Completion Times provided for the RHR suppression pool cooling and spray functions.

The Required Action is modified by a Note indicating that the applicable Conditions of LCO 3.4.7 be entered and Required Actions taken if an inoperable RHRSW subsystem results in an inoperable RHR shutdown cooling subsystem.

This is an exception to LCO 3.0.6 and ensures the proper actions are taken for these components.

--of Condition E If the RHRSW subsystems cannot be not rest( .d to OPERABLE status within the associated Completion Times ,the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.SURVEILLANCE SR 3.7.1.1 REQUIRE MENTS Verifying the correct alignment for each manual, power operated, and automatic valve in each RHRSW subsystem flow path provides assurance 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 correct position prior to locking, sealing, or securing.

A valve is also allowed to be in the nonaccident position, and yet considered in the correct position, provided it can be realigned to its accident position.

This is acceptable 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 Breakers 3.6.1.8 3.6 CONTAINMENT SYSTEMS 3.6.1.8 Suppression Chamber-to-Drywell Vacuum Breakers LCO 3.6.1.8 Ten suppression chamber-to-drywell vacuum breakers shall be OPERABLE for opening.AND Twelve suppression chamber-to-drywell vacuum breakers shall be closed, except when performing their intended function.APPLICABILITY:

MODES 1, 2, and 3.ACTIONS_________________

___CONDITION REQUIRED ACTION COMPLETION TIME A. One required suppression A.1 Restore one vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months chamber-to-drywell vacuum breaker to OPERABLE breaker inoperable for status.opening.C.dywl C.umbeae-- 1 bekr On uppression chamber- Close the open vacuum 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months not closed.Required Action and Be MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D2 I~ f onitonCIBe in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months IlNSERT- TS 3.6.1.8I lCondition B HATCH UNIT 2 361 3.6-19 TS 3.6.1.8. -Condition B Insert B. 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RHR Suppression Pool Cooling 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 APPLICABILITY:

Two RHR suppression pool cooling subsystems shall be OPERABLE.MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression pool cooling subsystem inoperable.

lTwo RHR suppression pool S cooling subsystems inoperable.

[tRequired Action and associated Completion Time

Condition C I.JNSERT -TS 3.6.2.3I ,Condition B A. 1 Restore RHR suppression pool cooling subsystem to OPERABLE status.7 daysone RHR suppression pool cooling subsystem to OPERABLE status.MODE 3.IIf B nMODE 4.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 12 hours 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling In accordance with subsystem manual, power operated, and automatic the Surveillance valve in the flow path that is not locked, sealed, or Frequency Control otherwise secured in position is in the correct Program position or can be aligned to the correct position.(continued)