NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 3 of 4

E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 3 of 4

ML15350A411
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
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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
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NL-14-1075
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{{#Wiki_filter:INSERT -Bases 3.7.1 Condition D 0.If one RHRSW subsystem is inoperable or one RHRSW pump in one or two subsystems is inoperable and not restored within the provided 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 hours.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 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. RHRSW System B83.7.1 BASES SURVEILLANCE SR 3.7.1.1 (continued) REQUIREMENTS 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.REFERENCES

1. FSAR, Section 10.6.2. FSAR, Subsection 14.4.3.3. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.4. GEH 0000-0126-6532-Ri, "Ultimate Heat sink Temperature Increase to 97 0 F Impact on OBA-LOCA Analysis and DW Equipment Qualification Analysis," June 2011.INSERT -BASES 3.7.1I Reference HATCH UNIT 1 B 3.7-6 HATCH UNIT 1 B 3.7-6 L~~1 INSERT -Bases 3.7.1 Reference 5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

PSW System and UHS B 3.7.2 BASES ACTIONS 0.(continued) With one PSW pump inoperable in each subsystem, one inoperable pump must be restored to OPERABLE status within 7 days. With the unit in this condition, the remaining OPERABLE PSW pumps are adequate to perform the PSW heat removal function; however, the overall reliability is reduced. The 7 day Completion Time is based on the remaining PSW heat removal capability to accommodate an additional single failure and the low probability of an event occurring during this time period.0.1_&With one PSW turbine building isolation valve inoperable in each subsystem, one inoperable valve must be restored to OPERABLE status within 72 hours. With the unit in this condition, the remaining OPERABLE PSW valves are adequate to perform the PSW nonessential load isolation function; however, the overall reliability is reduced. The 72 hour Completion Time is based on the remaining PSW heat removal capability to accommodate an additional single failure and the low probability of an event occurring during this time period.INSERT -BASES 3.7.2 Condition EI With one PSW subsystem inoperable for reasons other than Condition A and Condition B (e.g., inoperable flow p~ath, both pumps inoperable in a loop, or both turbine building isolation valves inoperable in a loop), the PSW subsystem must be restored to OPERABLE status within 72 hours. With the unit in this condition, the remaining OPERABLE PSW subsystem is adequate to perform the (continued) HATCH UNIT 1 .71 B 3.7-10 INSERT -Bases 3.7.2 Condition E E.__I If one PSW pump in one or both subsystems is inoperable, or one PSW turbine building isolation valve in one or both subsystems is inoperable, and is not restored to OPERABLE status within the required Completion Times, 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 hours.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 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. PSW System and UHS B 3.7.2 BASES ACTIONS (continued) heat removal function. However, the overall reliability is reduced because a single failure in the OPERABLE PSW subsystem could result in loss of PSW function.The 72 hour Completion Time is based on the redundant PSW System capabilities afforded by the OPERABLE subsystem, the low probability of an accident occurring during this time period, and is consistent with the allowed Completion Time for restoring an inoperable 0G.Required Action d6diied by two Notes indicating that the applicable Conditions of LCO 3.8.1, "AC Sources -Operating," LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System -Hot Shutdown," be entered and Required Actions taken if the inoperable PSW subsystem results in an inoperable DG or RHR shutdown cooling subsystem, respectively. This is in accordance with LCO 3.0.6 and ensures the proper actions are taken for these components. Conitionibte meCt,° orP Iboth npsW mwsubfsystems are inoperable for reasons other than Conditions C and D, or the UHS is determined inoperable, 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 hours and in MODE 4 within 36 hours. 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 3.7.2.1 REQUI REMENTS This SR verifies the UHS is OPERABLE by ensuring the water level in the pump well of the intake structure to be sufficient for the proper operation of the PSW pumps (net positive suction head and pump vortexing are considered in determining this limit). In addition, if a temporary weir is in place, the river level must also correspond to a level in the pump well of the intake structure of > 60.7 ft MSL with no weir in place. If the water level is > 61.7 ft MSL, there is sufficient (continued) HATCH UNIT 1 .71 B 3.7-11 PSW System and UHS B 3.7.2 BASES SURVEILLANCE SR 3.7.2.3 (continued) REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES

1. FSAR, Section 10.7.2. FSAR, Section 5.2.3. FSAR, Chapter 14.4. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.IINSERT -BASES 3.7.2<IReference HATCH UNIT 1 B371 B 3.7-13 INSERT -Bases 3.7.2 Reference 5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

MCREC System B 3.7.4 BASES ACTIONS B.1, B.2, and B.3 (continued) probability that CRE occupants will have to implement protective measures that may adversely affect their ability to control the reactor and maintain it in a safe shutdown condition in the event of a DBA. In addition, the 90 day Completion Time is a reasonable time to diagnose, plan and possibly repair, and test most problems with the CRE boundary.c.1 In MODE 1, 2, or 3, if the inoperable MCREC subsystem or the CRE loveral ln boundary cannot be restored to OPERABLE status within the required Copeto Time, the unit must be placed in a MODE that minimizes Iisc~cJ~risk. To achieve this status, the unit must be placed in at least MODE 3 within 12 oursrJq +/-i OE The allowed Completion based on operating experience, to reach the requir~ unit conditions from full power\conditions in an orderly manner nd without challenging unit syst ins.L--Time is I INSERT -BASES 3.7.4 D.1, D.2.1. D.2.2. and D.2.3 ICondition C The Required Actions of Condition D are modified by a Note indicating that LCO 3.0.3 does not apply. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, inability to suspend movement of irradiated fuel assemblies is not sufficient reason to require a reactor shutdown.During movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, if the inoperable MCREC subsystem cannot be restored to OPERABLE status within the required Completion Time, the OPERABLE MCREC subsystem may be placed in the pressurization mode. This action ensures that the remaining subsystem is OPERABLE, that no failures that would prevent automatic actuation have occurred, and that any active failure will be readily detected.An alternative to Required Action D.1 is to immediately suspend activities that present a potential for releasing radioactivity that might require isolation of the CRE. This places the unit in a condition that minimizes the accident risk.If applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies in the secondary containment must be suspended (continued) HATCH UNIT 1 .72 B 3.7-22 INSERT -Bases 3.7.4 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. 11), 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. MCREC System B 3.7.4 BASES ACTI ONS 0.1, D.2.1. D.2.2, and D.2.3 (continued) immediately. Suspension of these activities shall not preclude completion of movement of a component to a safe position. Also, if applicable, action must be initiated immediately to suspend OPDRVs to minimize the probability of a vessel draindown and the subsequent potential for fission product release. Actions must continue until the OPDRVs are suspended. IINSERT -BASES 3.7.4 E.1 ICondition EI If both MCeC bsystems are inoperable in MODE 1, 2, or 3 for reasons oth erthan an inoperable ORE boundary (i.e., Condition B), the System may not be capable of performing the intended F.1. F.2, and F.3 The Required Actions of Condition F are modified by a Note indicating that LCO 3.0.3 does not apply. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, inability to suspend movement of irradiated fuel assemblies is not sufficient reason to require a reactor shutdown.During movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, with two MCREC subsystems inoperable or with one or more MOREC subsystems inoperable due to an inoperable ORE boundary, action must be taken immediately to suspend activities that present a potential for releasing radioactivity that might require isolation of the ORE. This places the unit in a condition that minimizes the accident risk.If applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies in the secondary containment must be suspended immediately. Suspension of these activities shall not preclude completion of movement of a component to a safe position. If applicable, action must be initiated immediately to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until the OPDRVs are suspended.(continued) HATCH UNIT 1 B372 B 3.7-23 INSERT -Bases 3.7.4 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 hours.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. 11) 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. MCREC System B 3.7.4 BASES SURVEILLANCE SR 3.7.4.4 (continued) REQUIREMENTS consequences is no more than 5 rem TEDE and the ORE occupants are protected from hazardous chemicals and smoke. This SR verifies that the unfiltered air inleakage into the ORE is no greater than the flow rate assumed in the licensing basis analyses of DBA consequences When unfiltered air inleakage is greater than the assumed flow rate, Condition B must be entered. Required Action B.3 allows time to restore the ORE boundary to OPERABLE status provided mitigating actions can ensure that the ORE remains within the licensing basis habitability limits for the occupants following an accident. Compensatory measures are discussed in Regulatory Guide 1.196, Section 0.2.7.3, (Ref. 9) which endorses, with exceptions, NEI 99-03, Section 8.4 and Appendix F (Ref. 10). These compensatory measures may also be used as mitigating actions as required by Required Action B.2. Temporary analytical methods may also be used as compensatory measures to restore OPERABILITY (Ref. 11). Options for restoring the ORE boundary to OPERABLE status include changing the licensing basis DBA consequence analysis, repairing the ORE boundary, or a combination of these actions. Depending upon the nature of the problem and the corrective action, a full scope inleakage test may not be necessary to establish that the ORE boundary has been restored to OPERABLE status.REFERENCES

1. Unit 2 FSAR, Section 6.4.2. Unit 2 FSAR, Section 9.4.1.3. FSAR, Section 5.2.4. FSAR, Chapter 14.5. Unit 2 FSAR, Section 6.4.1.2.2.

6. Unit 2 FSAR, Table 15.1-28.7. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.8. Technical Requirements Manual, Table T2.1-1.9. Regulatory Guide 1.196.10. NEI 99-03, "Control Room Habitability Assessment," June 2001.~INSERT -BASES 3.7.4 Reference (continued)

HATCH UNIT 1B3724 B 3.7-24b INSERT -Bases 3.7.4 Reference 11. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002. Control Room AC System B 3.7.5 BASES ACTIONS C.1 and C.2 (continued) With three control room AC subsystems inoperable, the Control Room AC System may not be capable of performing its intended function.Therefore, the control room area temperature is required to be monitored to ensure that temperature is being maintained such that equipment in the control room is not adversely affected. With the control room temperature being maintained within the temperature limit, 72 hours is allowed to restore a Control Room AC subsystem to OPERABLE status. This Completion time is reasonable considering that the control room temperature is being maintained within limits and the low probability of an event occurring requiring control room isolation. Alternate methods of maintaining control room temperature, such as non-safety grade air conditioning systems or fans, can also be used to maintain control room temperature. D. 1 --overall plantI In MODE 1, 2, or 3, with any Requi ed Action and associated Completion Time of Condition A, C not met, the unit must be placed in a MODE that minimizes risk. To achieve this status, the unit must be placed in at least MODE 3 within 12 hours ;,D i ~,, allowed Completion~ reasonabe based on operatig experience, to reach the required nit conditions from full power co ditions in an orderly manner and wi hout challenging unit sy ,tems.\,.*, -BASES 3.7.5 Tiime is" i Condition D E.1, E.2.1, E.2.2. and E.2.3 The Required Actions of Condition E are modified by a Note indicating that LCO 3.0.3 does not apply. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, inability to suspend movement of irradiated fuel assemblies is not sufficient reason to require a reactor shutdown.During movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, if Required Action and associated Completion Time for Condition A is not met, the OPERABLE control room AC subsystems may be placed immediately in operation. This action ensures that the remaining subsystems are OPERABLE, that no failures that would prevent actuation will occur, and that any active failure will be readily detected.('continued) HATCH UNIT 1 B372 B 3.7-28 INSERT -Bases 3.7.5 Condition D 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. Control Room AC System B 3.7.5 BASES SURVEILLANCE SR 3.7.5.1 REQUIREMENTS This SR verifies that the heat removal capability of the system is sufficient to remove the control room heat load assumed in the safety analysis. The SR consists of a combination of testing and calculation. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES

1. Unit 2 FSAR, Sections 6.4 and 9.4.1.2. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.3. Technical Requirements Manual, Table T2.1-1.INSERT -BASES 3.7.5 S Reference HATCH UNIT 1 B373 B 3.7-30 INSERT -Bases 3.7.5 Reference 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

Main Condenser Offgas B 3.7.6 BASES (continued) APPLICABILITY The LCO is applicable when steam is being exhausted to the main condenser and the resulting noncondensables are being processed via the Main Condenser Offgas System. This occurs during MODE 1, and during MODES 2 and 3 with any main steam line not isolated and the SJAE in operation. In MODES 4 and 5, steam is not being exhausted to the main condenser and the requirements are not applicable. ACTIONS A.1 If the offgas radioactivity rate limit is exceeded, 72 hours is allowed to restore the gross gamma activity rate to within the limit. The 72 hour Completion Time is reasonable, based on engineering judgment, the time required to complete the Required Action, the large margins associated with permissible dose and exposure limits, and the low probability of a Main Condenser Offgas System rupture.If the gross gamma activity rate is not restored to within the limits in the associated Completion Time, all main steam lines or the SJAE must be isolated. This isolates the Main Condenser Offgas System from the source of the radioactive steam. The main steam lines are considered isolated if at least one main steam isolation valve in each main steam line is closed, and at least one main steam line drain valve in the drain line is closed. The 12 hour Completion Time is reasonable, based on operating experience, to perform the action~s from full power conditions in an orderly manner and without overall plant risk is Ichallenging unit systems.minimzed.An alternative to Required ctions B.1 and B.2 is to place the unit in a MODE in whicl To achieve this status, the unit must be placed in at least MODE 3 within 12 hours .adi ;OE4;',th" q3 bsr.The allowed Completion reasonable, based on op ~ating ex erience,'t reach the required unit conditions/from full power]Time is conditions in an orderly manner and without ch Illenging unit systems. INSERT -BASES 3.7.6 L (continued) HATCH UNIT 1 .73 B 3.7-32 INSERT -Bases 3.7.6 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. 4), 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.3 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. Main Condenser Offgas B 3.7.6 BASES (continued) SURVEILLANCE REQUIREMENTS SR 3.7.6.1 This SR, on a 31 day Frequency, requires an isotopic analysis of an offgas sample to ensure that the required limits are satisfied. The noble gases to be sampled are Xe-133, Xe-135, Xe-i138, Kr-85m, Kr-87, and Kr-88. If the measured rate of radioactivity increases significantly (by > 50% after correcting for expected increases due to changes in THERMAL POWER), an isotopic analysis is also performed within 4 hours after the increase is noted, to ensure that the increase is not indicative of a sustained increase in the radioactivity rate. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.This SR is modified by a Note indicating that the SR is not required to be performed until 31 days after any main steam line is not isolated and the SJAE is in operation. Only in this condition can radioactive fission gases be in the Main Condenser Offgas System at significant rates.REFERENCES

1. FSAR, Section 9.4 and Appendix E.2. 10 CFR 50.67.3. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements," July 23, 1993."INSERT -BASES 3.7.6 Reference HATCH UNIT 1 B373 B 3.7-33 INSERT -Bases 3.7.6 Reference 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

AC Sources -Operating B 3.8.1 BASES ACTIONS F.1 (continued) Guide 1.93. In addition, the loss of a required Unit 2 DG concurrent with the loss of a Unit 1 or swing DG, is analogous to the loss of a single DG in the Regulatory Guide 1.93 assumptions; thus, entry into this Condition is not required in this case.)G.___With both Unit 2 DGs and the swing DG inoperable (or otherwise incapable of supplying power to the LPCI valve load centers), and an assumed loss of offsite electrical power, insufficient standby AC sources are available to power the LPCI valve load centers. Since the offsite electrical power system is the only source of AC power for the LPCI valve load centers at this level of degradation, the risk associated with operation for a very short time could be less than that associated with an immediate controlled shutdown. (The immediate shutdown could cause grid instability, which could result in a total loss of AC power.) Since any inadvertent unit generator trip could also result in a total loss of offsite AC power, the time allowed for continued operation is severely restricted. The intent here is to avoid the risk associated with an immediate controlled shutdown and minimize the risk associated with an immediate controlled shutdown and minimize the risk associated with this level of degradation. According to Regulatory Guide 1.93 (Ref. 6), with two or more DGs inoperable, operation may continue for a period that should not exceed 2 hours. (Regulatory'Guide 1.93 assumed the unit had two DGs. Thus, a loss of both DGs results in a total loss of onsite power.)Therefore, a loss of both Unit 2 DGs and the swing DG results in degradation no worse than that assumed in Regulatory Guide 1 .93, and the 2 hour Completion Time is acceptable. H.1 __overall plant risk is If the inoperable AC electrical power orso cnnt erestored to OPERABLE status within the associ dCmltonTmte unit must be brought to a MODE in which~t" LC c. .To ITime is achieve. .this status,_, the, ,-,--unit must, ...be brought to at least MODE 3 within 12 ,..... ........... q.The allowed Completion lreasonable, based on op rating experience, to reach the required plant conditions from full pow r conditions in an orderly manner and without challenging plant systems.(continued) HATCH UNIT 1 B381 B 3.8-17 INSERT -Bases 3.8.1 Condition H 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 H.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. AC Sources -Operating B 3.8.1 No change. Included for BASES information only.SURVEILLANCE SR 3.8.1.18 (continued) REQUIREMENTS the DGs must be started from standby conditions, that is, with the engine coolant and oil continuously circulated and temperature maintained consistent with manufacturer recommendations. It is permissible to place all three DGs in test simultaneously, for the performance of this Surveillance. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.I SR 3.8.1.19 With the exception of this Surveillance, all other Surveillances of this Specification (SR 3.8.1.1 through SR 3.8.1.18) are applied only to the Unit 1 DG and offsite circuits, and swing DG. This Surveillance is provided to direct that the appropriate Surveillances for the required Unit 2 DG and offsite circuit are governed by the Unit 2 Technical Specifications. Performance of the applicable Unit 2 Surveillances will satisfy both any Unit 2 requirements, as well as satisfying this Unit 1 SR. Several exceptions are noted to the Unit 2 SRs: SR 3.8.1.6 is excepted since only one Unit 2 circuit is required by the Unit 1 Specification (therefore, there is not necessarily a second circuit to transfer to); SRs 3.8.1.10, 15, and 17 are excepted since they relate to the DG response to a Unit 2 ECCS initiation signal, which is not a necessary function for support of the Unit 1 requirement for an OPERABLE Unit 2 DG.The Frequency required by the applicable Unit 2 SR also governs performance of that SR for both Units.REFERENCES

1. 10 CFR 50, Appendix A, GDC 17.2. FSAR, Sections 8.3 and 8.4.3. FSAR, Chapter 5.4. FSAR, Chapter 6.5. FSAR, Chapter 14.6. Regulatory Guide 1.93, December 1974.(continued)

HATCH UNIT 1 B383 EIIN6 B 3.8-36 REVISION 69 AC Sources -Operating B83.8.1 BASES REFERENCES (continued)

7. Generic Letter 84-15.8. 10 CFR 50, Appendix A, GDC 18.9. Regulatory Guide 1.9, March 1971.10. Regulatory Guide 1.108, August 1977.11. Regulatory Guide 1.137, October 1979.12. IEEE Standard 387-1984.13. IEEE Standard 308-1980.14. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.INSERT -BASES 3.8.1 S Reference HATCH UNIT 1 B383 B 3.8-37 INSERT -Bases 3.8.1 Reference 15. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

DC Sources -Operating B 3.8.4 BASES ACTIONS B._I (continued) case accident, continued power operation should not exceed 12 hours. The 12 hour Completion Time provides a period of time to correct the problem commensurate with the importance of maintaining the OG DC electrical power subsystem OPERABLE. (The DG DC electrical power subsystem affects both the DG and the offsite circuit, as well as the breaker closure power for various 4160 VAC loads, but does not affect 125/250 VDC station service loads.)C._1 Condition C represents one Unit 1 station service division with a loss of ability to completely respond to an event, and a potential loss of ability to remain energized during normal operation. It is therefore imperative that the operator's attention focus on stabilizing the unit, minimizing the potential for complete loss of DC power to the affected division. The 2 hour limit is consistent with the allowed time for an inoperable DC Distribution System division.If one of the required DC electrical power subsystems is inoperable (e.g., inoperable battery, inoperable battery charger(s), or inoperable battery charger and associated inoperable battery), the remaining DC electrical power subsystems have the capacity to support a safe shutdown and to mitigate an accident condition. Since a subsequent postulated worst case single failure could result in the loss of minimum necessary DC electrical subsystems to mitigate a postulated worst case accident, continued power op~ration should not exceed 2 hours. The 2 hour Completion Time is based on Regulatory Guide 1.93 (Ref. 7) and reflects a reasonable time to assess unit status as a function of the inoperable DC electrical power subsystem and, if the DC electrical power subsystem is not restored to OPERABLE status, to prepare to effect an orderly and safe unit shutdown.F.overall plant risk is D. 1 rt-9 minimized. If the DC electrical power subsy tem cannot be restored to OPERABLE status within the r~ uired Completion Time, the unit must be brought to a MODE in which I'"cLOds t py.j To achieve this status, the unit must be brought to at least MODE 3 within Condirdpation ditosfo(fl inanorderly HATCH UNIT 1 B 3.8-56 PEl, ZI,_,.,,ON 3 INSERT -Bases 3.8.4 Condition D 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. 11) 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 D.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. DC Sources -Operating B 3.8.4 BASES ACTIONS D.1 and 0.2 (continuod) ~u ~ tl~ uiittu r~1oDEi 4 ~, ~11 ~t~Ijt ~;th th~ t;iie ie~uied ~flegulatc~y Cu~de 1.~3 (rzcf. 7).E.1 Condition E corresponds to a level of degradation in the DC electrical power subsystems that causes a required safety function to be lost.When more than one DC source is lost, and this results in the loss of a required function, the plant is in a condition outside the accident analysis. Therefore, no additional time is justified for continued operation. LCO 3.0.3 must be entered immediately to commence a controlled shutdown.SURVEILLANCE The SRs are modified by a Note to indicate that SR 3.8.4.1 through REQUIREMENTS SR 3.8.4.8 apply only to the Unit 1 DC sources, and that SR 3.8.4.9 applies only to the Unit 2 DC sources.SR 3.8.4.1 Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. Voltage requirements are based on the nominal design voltage of the battery and are consistent with the initial voltages assumed in the battery sizing calculations. The voltage requirement for battery terminal voltage is based on the open circuit voltage of a lead-calcium cell of nominal 1.215 specific gravity.Without regard to other battery parameters, this voltage is indicative of a battery that is capable of performing its required safety function.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.SR 3.8.4.2 Visual inspection to detect corrosion of the battery cells and connections, or measurement of the resistance of each inter-cell, (continued) HATCH UNIT 1 B385 B 3.8-57 DC Sources -Operating B 3.8.4 BASES (continued) REFERENCES

1. 10 CFR 50, Appendix A, GOC 17.2. Regulatory Guide 1.6.3. IEEE Standard 308-1971.4. FSAR, Section 8.5.5. FSAR, Chapters 5 and 6.6. FSAR, Chapter 14.7. Regulatory Guide 1.93, December 1974.8. IEEE Standard 450-1987.9. Technical Requirements Manual, Section 9.0.10. Regulatory Guide 1.32, February 1977.INSERT -BASES 3.8.4 ______ReferenceI 11 I Ni [ iu ued 12. IEEE Standard 485-1983.13. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.14. Not used.HATCH UNIT 1 B386 B 3.8-62 INSERT -Bases 3.8.4 Reference 11. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

Distribution Systems -Operating B 3.8.7 BASES ACTIONS D.__1 (continued) This Completion Time allows for an exception to the normal "time zero" for beginning the allowed outage time "clock." This allowance results in establishing the "time zero" at the time LCO 3.8.7.a was initially not met, instead of at the time Condition D was entered. The 16 hour Completion Time is an acceptable limitation on this potential of failing to meet the LCO indefinitely.Ioverall plant risk is If the inoperable distribution subsys m cannot be restored to OPERABLE status within the associfrd Completion Time, the unit must be brought to a MODE in whic / , achieve this status, the plant must be brought to at least MODE 3 within 12 hou t, .. '-he allowedl Completion reasonable, based on ope ~,ng experience, to reach the required plt conditions from full power co qditions in an orderly manner and witl out challenging plant systems.Tie s INSERT -BASES 3.8.7 1 F. 1 Condition E Condition F corresponds to a level of degradation in the electrical power distribution system that causes a required safety function to be lost. When more than one AC or DC electrical power distribution subsystem is lost, and this results in the loss of a required function, the plant is in a condition outside the accident analysiS. Therefore, no additional time is justified for continued operation. LCO 3.0.3 must be entered immediately to commence a controlled shutdown.SURVEILLANCE SR 3.8.7.1 REQUIREMENTS This Surveillance verifies that the AC and DC electrical power distribution systems are functioning properly, with the correct circuit breaker alignment. The correct breaker alignment ensures the appropriate separation and independence of the electrical buses are maintained, and the appropriate voltage is available to each required bus. The verification of proper voltage availability on the buses ensures that the required voltage is readily available for motive as well as control functions for critical system loads connected to these buses. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.(continued) HATCH UNIT 1 .-0REIINO B 3.8-80 INSERT -Bases 3.8.7 Condition E 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 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. Distribution Systems -Operating B 3.8.7 BASES REFERENCES

1. FSAR, Chapters 5 and 6.2. FSAR, Chapter 14.3. Regulatory Guide 1.93, December 1974.4. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.INSERT -BASES 3.8.7 Reference HATCH UNIT 1 B 3.8-81 HATCH UNIT 1 B 3.8-81 II~ jI INSERT -Bases 3.8.7 Reference 5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

RPS Electric Power Monitoring B 3.3.8.2 BASES ACTIONS A.__1 (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.1 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 hour 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 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 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.plant shutdown is accomplished byplacing te plant in MOE3within n Ob 4 ;9,,,,,.3 allowed Completion lLm c c rlreasonabe bae noeaiexperience, to reach the" I NSERT -BASES 3.38.2 ! Time ICondition C l(continued) HAT H NI 2B 3.3-196 III I HATCH UNIT 2 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 0.1 (continued) required plant conditions from full power conditions in an orderly manner and without challenging plant systems.0.1, 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 D.2.1) or to isolate the RHR Shutdown Cooling System (Required Action D.2.2). Required Action D.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 REQUIREMENTS 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 hours 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 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 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 2B33-7 B 3.3-197 RPS Electric Power Monitoring B 3.3.8.2 BASES (continued) REFERENCES

1. FSAR, Section 8.3.1.1.4.B.

2. NRC Generic Letter 91-09, "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.INSERT -BASES 3.3.8.2 S Reference HATCH UNIT 2B3319 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. 12) 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 ECOS 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 ted Completion Time, the plant must be brought to a MODE in C osntapy To achieve this status, the plant must be brought to at least MODE 3 within 12 hours allowed Completion rJeasonable, based on ope itng experience, to reach the required conditions from full power c oditions in an orderly manner and wit ut challenging plant systems.)T-iime ... is I INSERT -BASES 3.5.1 1 C.1 and C.2 ICondition 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 pressure ECCS injection/sprayosubsystems in conjunction with ADS.Also, the RCIC System will automatically provide makeup water at most reactor operating pressures. Verification of RCIC OPERABILITY within 1 hour 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 12 and has been found to be acceptable through operating experience.(continued) HATCH UNIT 2B356 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. 18), 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 LCOG 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. LCOG 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. EGOS -Operating B 3.5.1 BASES (continued) ACTIONS D.1 and D.2 If any one low pressure EGOS injection/spray subsystem is inoperable in addition to an inoperable HPCI System, the inoperable low pressure EGOS injection/spray subsystem or the HPCI System must be restored to OPERABLE status within 72 hours. In this condition, adequate core cooling is ensured by the OPERABILITY of the ADS and the remaining low pressure EGOS subsystems. However, the overall EGOS 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 EGOS 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 hours is required to restore either the HPCI System or the low pressure EGOS injection/spray subsystem to OPERABLE status. This Completion Time is based on a reliability study cited in Reference 12 and has been found to be acceptable through operating experience.F. adg2J INSERT -BASES 3.5.1 Condition E 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 16.I aeny ,equ:,red Act:,n and assoc",ated Comp'et=,n Ti,,me Mf JC ...... ... .......... jtwo or 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 hours and reactor steam dome pressure reduced to < 150 psig within 36 hours. 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 hours. 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 multi Il EGOS subsystems are inoperable, as stated in Condition he plant is in a condition outside of the accident analyses. Therefore, LCO 3.0.3 must be entered immediately.(continued) HATCH UNIT 2B35-B3.5-7 INSERT -Bases 3.5.1 Condition E 5.__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 hours.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. 18) 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. EGOS -Operating B 3.5.1 No change. Included for linformation only.BASES SURVEILLANCE REQUIREMENTS SR 3.5.1.12 (continued) seat of the S/RV is verified by steam testing at the vendor facility before installation. SRs 3.5.1.11 and 3.3.5.1.5 overlap this SR to provide testing of the S/RV relief mode function. Additional functional testing is performed by tests required by the ASME OM Code (Ref.17).The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.SR 3.5.1.13 This SR ensures that the EGOS RESPONSE TIMES are less than or equal to the maximum values assumed in the accident analysis.Response time testing acceptance criteria are included in Reference

14. A Note to the Surveillance states that the instrumentation portion of the response time may be assumed from established limits. The exclusion of the instrumentation from the response time surveillance is supported by Reference 15, which concludes that instrumentation will continue to respond in the microsecond to millisecond range prior to complete failure.The Surveillance Frequency is controlled under the Frequency Control Program.Surveillance REFERENCES

1. FSAR, Paragraph 6.3.2.2.3.

2. FSAR, Paragraph 6.3.2.2.4.

3. FSAR, Paragraph 6.3.2.2.1.

4. FSAR, Paragraph 6.3.2.2.2.

5. FSAR, Subsection 15.1.39.(continued)

HATCH UNIT 2 B351 EIIN8 B 3.5-13 REVISION 81 ECCS -Operating B 3.5.1 BASES REFERENCES

6. FSAR, Subsection 15.1.40.(continued)

7. FSAR, Subsection 15.1.33.8. 10 CFR 50, Appendix K.9. FSAR, Subsection 6.3.3.10. NEDC-31376P, "E.I. Hatch Nuclear Plant Units 1 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Analysis," December 1986.11. 100CFR 50.46.12. Memorandum from R. L. Baer (NRC) to V. Stello, Jr. (NRC),"Recommended Interim Revisions to LCOs for ECCS Components," December 1, 1975.13. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.14. Technical Requirements Manual, Table T5.0-1.15. NEDO-32291, "System Analyses for Elimination of Selected Response Time Testing Requirements," January 1994.16. NEDC-32041P, "Safety Review for Edwin I. Hatch Nuclear Power Plant Units 1 and 2 Updated Safety/Relief Valve Performance Requirements," April 1"996.17. ASME, OM Code -2004 Edition, "Code for Operation and Maintenance of Nuclear Power Plants," Appendix I.INSERT -BASES 3.5.1 Reference HATCH UNIT 2 B351 B 3.5-14 INSERT -Bases 3.5.1 Reference 18. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.I RCIC System B 3.5.3 BASES ACTIONS A.1 and A.2 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 hour 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 HPCI) 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[minimized.J sim .aneously inoperable, the plant must be brought to a condition in whicw .ITo achieve this status, the plant must be bou£ht o atleat MDE 3witin 2 horsln The allow sed Completio reasonable, based on operating xperience, to reach the r quired plant conditions from full power condi ons in an (continued) HATCH UNIT 2 B 3.5-23I INSERT -Bases 3.5.3 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 SR 3.5.3.5 (continued) REQUIREMENTS 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 5.5.6.3. 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-4!-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.INSERT -BASES 3.5.3< iReference HATCH UNIT 2 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 hours. This is consistent with the Completion Time for Condition A and the fact that the leak tight primary containment INSERT -BASES 3.6.1.7 }_ boundary is being maintained. Condition 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 hour. This Completion Time is consistent with the ACTIONS of LCO 3.6.1.1, which requires that primary containment be restored to OPERABLE status within 1 hour.If the vacuum breakers in one or more lines cannot be lra, a~tb closed or restored to IH he plant must be brought to a MODE in which the LCO does not OPERABLE status within __ply/. To achieve this status, the plant must brought to at least the equied Cmpleion MODE 3 within 12 hours and to MODE 4 within 36 hours. The Therqired, oplto allowed Completion Times are reasonable, based on operating Timeexperience, 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 REQUI REM ENTS 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 2 B364 B 3.6-40 INSERT -Bases 3.6.1.7 Condition D D. 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 hours.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 D.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 SURVEILLANCE SR 3.6.1.7.1 (continued) REQUIREMENTS Two Notes are added to this SR. The first Note allows reactor building-to-suppression chamber vacuum breakers opened in conjunction with the performance of a Surveillance to not be considered as failing this SR. These periods of opening vacuum breakers are controlled by plant procedures and do not represent inoperable vacuum breakers. The second Note is included to clarify that vacuum breakers, which are open due to an actual differential pressure, are not considered as failing this SR.SR 3.6.1.7.2 Each vacuum breaker must be cycled to ensure that it opens properly to perform its design function and returns to its fully closed position.This ensures that the safety analysis assumptions are valid. The 92 day Frequency of this SR is in accordance with the requirements of the Inservice Testing Program.SR 3.6.1.7.3 Demonstration of vacuum breaker opening setpoint is necessary to ensure that the safety analysis assumption regarding vacuum breaker full open differential pressure of < 0.5 psid is valid. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES

1. FSAR, Section 6.2.1.2. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.INSERT- BASES 3.6.1.7I< Reference HATCH UNIT 2 B364 B 3.6-41 INSERT -Bases 3.6.1.7 Reference 3. 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 B 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.ISR -BSES 36.18 F_Condition B ~T 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 hour Completion Time is allowed to close the vacuum breaker due to the low probability of an event that would pressurize primary containment. D~.1 and D'2I gi# e 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 MODI 3 within 12 hours and to MODE 4 within 36 hours. The allowe~ Completion Times are reasonable, based on operating experi nce, to reach the required plant conditions from full power conditi ns in an orderly manner and without challenging plant system I.Jf the open suppression chamber-to-drywell vacuumbraebe 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 hour without makeup.However, if vacuum breaker position indication is not reliable due to, for example, a dual or open indication with torus-to-drywell differential pressure remaining < 0.5 psid, alternate methods of verifying that the vacuum breaker is closed are detailed in Technical Requirements Manual (TRM) (Ref. 4), T3.6.1, "Suppression Chamber-to-Drywell (continued) HATCH UNIT 2 B 3.6-451 INSERT -Bases 3.6.1.8 Condition B BA 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 hours.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. Suppression Chamber-to-Drywell Vacuum Breakers B 3.6.1.8 BASES (continued) REFERENCES

1. FSAR, Section 6.2.1.2. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.3. Technical Requirements Manual.INSERT -BASES 3.6.1.8 Reference HATCH UNIT 2 B364 B 3.6-47 INSERT -Bases 3.6.1.8 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 Cooling (continued) With two RHR suppression pool cooling subsystems inoperable, one subsystem must be restored to OPERABLE status within 8 hours. In this 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 methods to remove heat from primary containment are available. Reuie 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 hours and to MODE 4 within 36 hours. 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 SR does not apl:ily 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.(continued) HATCH UNIT 2 B365 B 3.6-58 INSERT -Bases 3.6.2.3 Condition B g__1 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 hours.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, Section 6.2.2.2. ASME, Boiler and Pressure Vessel Code, Section XI.3. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

_ BASES3.23/ Reference 3.23 B 3.6-59 HATCH UNITV2,B 3,6-59 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.__ (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 hours. In this Condition, there is a substantial loss of the primary containment bypass leakage 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 methods to remove heat from primary containment are available. C. 1 i [minimized.I \If any Required Action and associated Completion T/ime cannot be met, the plant must be brought to a MODE in which.hLCdcsnt To achieve this status, the plant must be brought to at least MODE 3 within 12 hourslo... .,,. ,u .Tde allowed SCompletioni-, esa-1reasonable, based on operating expe eto Tmisreach the r buired plant conditions from full power conditions in an "[Tie i Iorderly manner and without challenging plant systems. cninINsERT-cBASES 3.6.2.4 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 2 B 3.6-62I 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 Frequency 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 Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES

1. FSAR, Section 6.2.2. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.-BASES 3.6.2.4 Reference HATCH UNIT 2 B366 EIIN7 B 3.6-63 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 BASES (continued) ACTIONS A.1_If secondary containment is inoperable, it must be restored to OPERABLE status within 4 hours. The 4 hour 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 OPERABILITY) occurring during periods where secondary containment is inoperable is minimal.overall plant risk is If secondary containment cannot be restored to OPERABLE status[minimized, within the requ ed Completion Time, the plant must be brought to a MODE in whichl .I To achieve this status, the plant must be brought to at least MODE 3 within 12 ,vu he allowed Completion WIi reasonable, based on ope experience, to reach the required plant conditions from full power con #t.,ns 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 fission 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 case, (continued) HATCH UNIT 2 B 3.6-79 IEIIN7 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 SR 3.6.4.1.3 and SR 3.6.4.1.4 (continued) REQUIREMENTS maintain > 0.20 inch of vacuum water gauge for 1 hour at a flow rate< 4000 cfm for each SGT subsystem. The 1 hour 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, Section 15.1.39.2. FSAR, Section 15.1.41.3. Technical Requirements Manual, Section 8.0.4. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.-BASES 3.6.4.1 Reference HATCH UNIT 2 B368 EIIN7 B 3.6-81 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) failure in one of the remaining required OPERABLE subsystems could result in the radioactivity release control function not being adequately performed. The 7 and 30 day Completion Times are based on consideration of such factors as the availability of the OPERABLE redundant SGT subsystems and the low probability of a DBA occurring during this period. Additionally, the 30 day Completion Time of Required Action A.1 is based on three remaining OPERABLE SOT subsystems, of which two are Unit 2 subsystems, and the secondary containment volume in the Unit 1 reactor building being open to the common refueling floor where the two Unit 2 SGT subsystems can readily provide rapid drawdown of vacuum. Testing and analysis has shown that in this configuration, even with an 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.C.1 an -- ___overall plant risk is I-- ' I minimized.I If the SOT subsyst m cannot be restored to OPERABLE status within the required Compl ,tion Time in MODE 1, 2, or 3, the plant must be brought to a MODEn w~~~ ~cLOde o plITo achieve this status, the plant must be brought to at least MODE 3 within 12 i Icd cMOE4 ;itMq allowed Completion [[{e"-rr reasonable, based on operating ~perience, to reach the required plant conditions from full power co ditions in an orderly manner and without challenging plant systems. IJNSERT -BASES 3.6.4.3 In the event that a Unit 1 SOT subsystem is the one not restored to OPERABLE status as required by Required Action A.1 or B.1, operation of Unit 2 can continue provided that Unit 1 is shut down, the Unit 1 reactor building zone is isolated from the remainder of secondary containment and the SOT System, and the Unit 1 Technical Specifications do not require Operability of Zone I. In this modified secondary containment configuration, only three SOT subsystems are required to be OPERABLE to meet LCO 3.6.4.3, and no limitation is applied to the inoperable Unit 1 SOT subsystem. This in effect is an alternative to restoring the inoperable Unit 1 SOT subsystem, i.e., shut down Unit 1 and isolate its reactor building zone from secondary containment and SOT System.(continued) HATCH UNIT 2 B369 B3.6-92 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. 8), 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. SGT System B 3.6.4.3 BASES ACTIONS D.1, D.2.1, D.2.2, and 0.2.3 (continued) 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 remaining 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. The Required Actions of Condition 0 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 t6 suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown.E.__11 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 3.6.4.3I \[Condition E (continued) HATCH UNIT 2 B 3.6-93 HATCH UNIT 2B[3.6-93 f ,','l~O 741 I 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 hours.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. 8) 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 SURVEILLANCE SR 3.6.4.3.3 REQUIREMENTS (continued) This SR verifies that each required Unit 1 and Unit 2 SOT subsystem starts on receipt of an actual or simulated initiation signal. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.2.5 overlaps this SR to provide complete testing of the safety function. This Surveillance can be performed with the reactor at power. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES

1. 10 CFR 50, Appendix A, GDC 41.2. Unit 1 FSAR, Section 5.3.2.3.3. Unit 2 FSAR, Section 6.2.4.4. Unit 2 FSAR, Section 15.2.5. Unit 2 FSAR, Section 15.3.6. Technical Requirements Manual, Section 8.0.7. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.IiNSERT -BASES 3.6.4.3< Reference HATCH UNIT 2 B369 B 3.6-95 INSERT -Bases 3.6.4.3 Reference 8. 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 BASES ACTIONS 0.__1 (continued) INSERT -BASES 3.7.1 Condition D 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 the 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. 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 hours. The 8 hour 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. ofCondition eJ If the RHRSW subsystems cannot be not rest r d status within the associated Completion Times, he 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 hours and in MODE 4 within 36 hours. 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 REQUIREMENTS Verifying the correct alignment for each manual, power operated, and automatic valve in each RHRSW subsystem flow path provides (continued) HATCH UNIT 2 B 3.7-5 HATCHUNIT2 B .7-5REVISION 49 INSERT -Bases 3.7.1 Condition D 0.If one RHRSW subsystem is inoperable or one RHRSW pump in one or two subsystems is inoperable and not restored within the provided 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 hours.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 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. RHRSW System B83.7.1 BASES SURVEILLANCE SR 3.7.1.1 (continued) REQUIREMENTS 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.REFERENCES

1. FSAR, Section 10.6.2. FSAR, Subsection 14.4.3.3. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.4. GEH 0000-0126-6532-Ri, "Ultimate Heat sink Temperature Increase to 97 0 F Impact on OBA-LOCA Analysis and DW Equipment Qualification Analysis," June 2011.INSERT -BASES 3.7.1I Reference HATCH UNIT 1 B 3.7-6 HATCH UNIT 1 B 3.7-6 L~~1 INSERT -Bases 3.7.1 Reference 5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

PSW System and UHS B 3.7.2 BASES ACTIONS 0.(continued) With one PSW pump inoperable in each subsystem, one inoperable pump must be restored to OPERABLE status within 7 days. With the unit in this condition, the remaining OPERABLE PSW pumps are adequate to perform the PSW heat removal function; however, the overall reliability is reduced. The 7 day Completion Time is based on the remaining PSW heat removal capability to accommodate an additional single failure and the low probability of an event occurring during this time period.0.1_&With one PSW turbine building isolation valve inoperable in each subsystem, one inoperable valve must be restored to OPERABLE status within 72 hours. With the unit in this condition, the remaining OPERABLE PSW valves are adequate to perform the PSW nonessential load isolation function; however, the overall reliability is reduced. The 72 hour Completion Time is based on the remaining PSW heat removal capability to accommodate an additional single failure and the low probability of an event occurring during this time period.INSERT -BASES 3.7.2 Condition EI With one PSW subsystem inoperable for reasons other than Condition A and Condition B (e.g., inoperable flow p~ath, both pumps inoperable in a loop, or both turbine building isolation valves inoperable in a loop), the PSW subsystem must be restored to OPERABLE status within 72 hours. With the unit in this condition, the remaining OPERABLE PSW subsystem is adequate to perform the (continued) HATCH UNIT 1 .71 B 3.7-10 INSERT -Bases 3.7.2 Condition E E.__I If one PSW pump in one or both subsystems is inoperable, or one PSW turbine building isolation valve in one or both subsystems is inoperable, and is not restored to OPERABLE status within the required Completion Times, 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 hours.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 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. PSW System and UHS B 3.7.2 BASES ACTIONS (continued) heat removal function. However, the overall reliability is reduced because a single failure in the OPERABLE PSW subsystem could result in loss of PSW function.The 72 hour Completion Time is based on the redundant PSW System capabilities afforded by the OPERABLE subsystem, the low probability of an accident occurring during this time period, and is consistent with the allowed Completion Time for restoring an inoperable 0G.Required Action d6diied by two Notes indicating that the applicable Conditions of LCO 3.8.1, "AC Sources -Operating," LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System -Hot Shutdown," be entered and Required Actions taken if the inoperable PSW subsystem results in an inoperable DG or RHR shutdown cooling subsystem, respectively. This is in accordance with LCO 3.0.6 and ensures the proper actions are taken for these components. Conitionibte meCt,° orP Iboth npsW mwsubfsystems are inoperable for reasons other than Conditions C and D, or the UHS is determined inoperable, 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 hours and in MODE 4 within 36 hours. 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 3.7.2.1 REQUI REMENTS This SR verifies the UHS is OPERABLE by ensuring the water level in the pump well of the intake structure to be sufficient for the proper operation of the PSW pumps (net positive suction head and pump vortexing are considered in determining this limit). In addition, if a temporary weir is in place, the river level must also correspond to a level in the pump well of the intake structure of > 60.7 ft MSL with no weir in place. If the water level is > 61.7 ft MSL, there is sufficient (continued) HATCH UNIT 1 .71 B 3.7-11 PSW System and UHS B 3.7.2 BASES SURVEILLANCE SR 3.7.2.3 (continued) REQUIREMENTS The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES

1. FSAR, Section 10.7.2. FSAR, Section 5.2.3. FSAR, Chapter 14.4. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.IINSERT -BASES 3.7.2<IReference HATCH UNIT 1 B371 B 3.7-13 INSERT -Bases 3.7.2 Reference 5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

MCREC System B 3.7.4 BASES ACTIONS B.1, B.2, and B.3 (continued) probability that CRE occupants will have to implement protective measures that may adversely affect their ability to control the reactor and maintain it in a safe shutdown condition in the event of a DBA. In addition, the 90 day Completion Time is a reasonable time to diagnose, plan and possibly repair, and test most problems with the CRE boundary.c.1 In MODE 1, 2, or 3, if the inoperable MCREC subsystem or the CRE loveral ln boundary cannot be restored to OPERABLE status within the required Copeto Time, the unit must be placed in a MODE that minimizes Iisc~cJ~risk. To achieve this status, the unit must be placed in at least MODE 3 within 12 oursrJq +/-i OE The allowed Completion based on operating experience, to reach the requir~ unit conditions from full power\conditions in an orderly manner nd without challenging unit syst ins.L--Time is I INSERT -BASES 3.7.4 D.1, D.2.1. D.2.2. and D.2.3 ICondition C The Required Actions of Condition D are modified by a Note indicating that LCO 3.0.3 does not apply. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, inability to suspend movement of irradiated fuel assemblies is not sufficient reason to require a reactor shutdown.During movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, if the inoperable MCREC subsystem cannot be restored to OPERABLE status within the required Completion Time, the OPERABLE MCREC subsystem may be placed in the pressurization mode. This action ensures that the remaining subsystem is OPERABLE, that no failures that would prevent automatic actuation have occurred, and that any active failure will be readily detected.An alternative to Required Action D.1 is to immediately suspend activities that present a potential for releasing radioactivity that might require isolation of the CRE. This places the unit in a condition that minimizes the accident risk.If applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies in the secondary containment must be suspended (continued) HATCH UNIT 1 .72 B 3.7-22 INSERT -Bases 3.7.4 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. 11), 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. MCREC System B 3.7.4 BASES ACTI ONS 0.1, D.2.1. D.2.2, and D.2.3 (continued) immediately. Suspension of these activities shall not preclude completion of movement of a component to a safe position. Also, if applicable, action must be initiated immediately to suspend OPDRVs to minimize the probability of a vessel draindown and the subsequent potential for fission product release. Actions must continue until the OPDRVs are suspended. IINSERT -BASES 3.7.4 E.1 ICondition EI If both MCeC bsystems are inoperable in MODE 1, 2, or 3 for reasons oth erthan an inoperable ORE boundary (i.e., Condition B), the System may not be capable of performing the intended F.1. F.2, and F.3 The Required Actions of Condition F are modified by a Note indicating that LCO 3.0.3 does not apply. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, inability to suspend movement of irradiated fuel assemblies is not sufficient reason to require a reactor shutdown.During movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, with two MCREC subsystems inoperable or with one or more MOREC subsystems inoperable due to an inoperable ORE boundary, action must be taken immediately to suspend activities that present a potential for releasing radioactivity that might require isolation of the ORE. This places the unit in a condition that minimizes the accident risk.If applicable, CORE ALTERATIONS and movement of irradiated fuel assemblies in the secondary containment must be suspended immediately. Suspension of these activities shall not preclude completion of movement of a component to a safe position. If applicable, action must be initiated immediately to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until the OPDRVs are suspended.(continued) HATCH UNIT 1 B372 B 3.7-23 INSERT -Bases 3.7.4 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 hours.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. 11) 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. MCREC System B 3.7.4 BASES SURVEILLANCE SR 3.7.4.4 (continued) REQUIREMENTS consequences is no more than 5 rem TEDE and the ORE occupants are protected from hazardous chemicals and smoke. This SR verifies that the unfiltered air inleakage into the ORE is no greater than the flow rate assumed in the licensing basis analyses of DBA consequences When unfiltered air inleakage is greater than the assumed flow rate, Condition B must be entered. Required Action B.3 allows time to restore the ORE boundary to OPERABLE status provided mitigating actions can ensure that the ORE remains within the licensing basis habitability limits for the occupants following an accident. Compensatory measures are discussed in Regulatory Guide 1.196, Section 0.2.7.3, (Ref. 9) which endorses, with exceptions, NEI 99-03, Section 8.4 and Appendix F (Ref. 10). These compensatory measures may also be used as mitigating actions as required by Required Action B.2. Temporary analytical methods may also be used as compensatory measures to restore OPERABILITY (Ref. 11). Options for restoring the ORE boundary to OPERABLE status include changing the licensing basis DBA consequence analysis, repairing the ORE boundary, or a combination of these actions. Depending upon the nature of the problem and the corrective action, a full scope inleakage test may not be necessary to establish that the ORE boundary has been restored to OPERABLE status.REFERENCES

1. Unit 2 FSAR, Section 6.4.2. Unit 2 FSAR, Section 9.4.1.3. FSAR, Section 5.2.4. FSAR, Chapter 14.5. Unit 2 FSAR, Section 6.4.1.2.2.

6. Unit 2 FSAR, Table 15.1-28.7. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.8. Technical Requirements Manual, Table T2.1-1.9. Regulatory Guide 1.196.10. NEI 99-03, "Control Room Habitability Assessment," June 2001.~INSERT -BASES 3.7.4 Reference (continued)

HATCH UNIT 1B3724 B 3.7-24b INSERT -Bases 3.7.4 Reference 11. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002. Control Room AC System B 3.7.5 BASES ACTIONS C.1 and C.2 (continued) With three control room AC subsystems inoperable, the Control Room AC System may not be capable of performing its intended function.Therefore, the control room area temperature is required to be monitored to ensure that temperature is being maintained such that equipment in the control room is not adversely affected. With the control room temperature being maintained within the temperature limit, 72 hours is allowed to restore a Control Room AC subsystem to OPERABLE status. This Completion time is reasonable considering that the control room temperature is being maintained within limits and the low probability of an event occurring requiring control room isolation. Alternate methods of maintaining control room temperature, such as non-safety grade air conditioning systems or fans, can also be used to maintain control room temperature. D. 1 --overall plantI In MODE 1, 2, or 3, with any Requi ed Action and associated Completion Time of Condition A, C not met, the unit must be placed in a MODE that minimizes risk. To achieve this status, the unit must be placed in at least MODE 3 within 12 hours ;,D i ~,, allowed Completion~ reasonabe based on operatig experience, to reach the required nit conditions from full power co ditions in an orderly manner and wi hout challenging unit sy ,tems.\,.*, -BASES 3.7.5 Tiime is" i Condition D E.1, E.2.1, E.2.2. and E.2.3 The Required Actions of Condition E are modified by a Note indicating that LCO 3.0.3 does not apply. If moving irradiated fuel assemblies while in MODE 1, 2, or 3, the fuel movement is independent of reactor operations. Therefore, inability to suspend movement of irradiated fuel assemblies is not sufficient reason to require a reactor shutdown.During movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs, if Required Action and associated Completion Time for Condition A is not met, the OPERABLE control room AC subsystems may be placed immediately in operation. This action ensures that the remaining subsystems are OPERABLE, that no failures that would prevent actuation will occur, and that any active failure will be readily detected.('continued) HATCH UNIT 1 B372 B 3.7-28 INSERT -Bases 3.7.5 Condition D 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. Control Room AC System B 3.7.5 BASES SURVEILLANCE SR 3.7.5.1 REQUIREMENTS This SR verifies that the heat removal capability of the system is sufficient to remove the control room heat load assumed in the safety analysis. The SR consists of a combination of testing and calculation. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES

1. Unit 2 FSAR, Sections 6.4 and 9.4.1.2. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.3. Technical Requirements Manual, Table T2.1-1.INSERT -BASES 3.7.5 S Reference HATCH UNIT 1 B373 B 3.7-30 INSERT -Bases 3.7.5 Reference 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

Main Condenser Offgas B 3.7.6 BASES (continued) APPLICABILITY The LCO is applicable when steam is being exhausted to the main condenser and the resulting noncondensables are being processed via the Main Condenser Offgas System. This occurs during MODE 1, and during MODES 2 and 3 with any main steam line not isolated and the SJAE in operation. In MODES 4 and 5, steam is not being exhausted to the main condenser and the requirements are not applicable. ACTIONS A.1 If the offgas radioactivity rate limit is exceeded, 72 hours is allowed to restore the gross gamma activity rate to within the limit. The 72 hour Completion Time is reasonable, based on engineering judgment, the time required to complete the Required Action, the large margins associated with permissible dose and exposure limits, and the low probability of a Main Condenser Offgas System rupture.If the gross gamma activity rate is not restored to within the limits in the associated Completion Time, all main steam lines or the SJAE must be isolated. This isolates the Main Condenser Offgas System from the source of the radioactive steam. The main steam lines are considered isolated if at least one main steam isolation valve in each main steam line is closed, and at least one main steam line drain valve in the drain line is closed. The 12 hour Completion Time is reasonable, based on operating experience, to perform the action~s from full power conditions in an orderly manner and without overall plant risk is Ichallenging unit systems.minimzed.An alternative to Required ctions B.1 and B.2 is to place the unit in a MODE in whicl To achieve this status, the unit must be placed in at least MODE 3 within 12 hours .adi ;OE4;',th" q3 bsr.The allowed Completion reasonable, based on op ~ating ex erience,'t reach the required unit conditions/from full power]Time is conditions in an orderly manner and without ch Illenging unit systems. INSERT -BASES 3.7.6 L (continued) HATCH UNIT 1 .73 B 3.7-32 INSERT -Bases 3.7.6 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. 4), 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.3 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. Main Condenser Offgas B 3.7.6 BASES (continued) SURVEILLANCE REQUIREMENTS SR 3.7.6.1 This SR, on a 31 day Frequency, requires an isotopic analysis of an offgas sample to ensure that the required limits are satisfied. The noble gases to be sampled are Xe-133, Xe-135, Xe-i138, Kr-85m, Kr-87, and Kr-88. If the measured rate of radioactivity increases significantly (by > 50% after correcting for expected increases due to changes in THERMAL POWER), an isotopic analysis is also performed within 4 hours after the increase is noted, to ensure that the increase is not indicative of a sustained increase in the radioactivity rate. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.This SR is modified by a Note indicating that the SR is not required to be performed until 31 days after any main steam line is not isolated and the SJAE is in operation. Only in this condition can radioactive fission gases be in the Main Condenser Offgas System at significant rates.REFERENCES

1. FSAR, Section 9.4 and Appendix E.2. 10 CFR 50.67.3. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements," July 23, 1993."INSERT -BASES 3.7.6 Reference HATCH UNIT 1 B373 B 3.7-33 INSERT -Bases 3.7.6 Reference 4. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

AC Sources -Operating B 3.8.1 BASES ACTIONS F.1 (continued) Guide 1.93. In addition, the loss of a required Unit 2 DG concurrent with the loss of a Unit 1 or swing DG, is analogous to the loss of a single DG in the Regulatory Guide 1.93 assumptions; thus, entry into this Condition is not required in this case.)G.___With both Unit 2 DGs and the swing DG inoperable (or otherwise incapable of supplying power to the LPCI valve load centers), and an assumed loss of offsite electrical power, insufficient standby AC sources are available to power the LPCI valve load centers. Since the offsite electrical power system is the only source of AC power for the LPCI valve load centers at this level of degradation, the risk associated with operation for a very short time could be less than that associated with an immediate controlled shutdown. (The immediate shutdown could cause grid instability, which could result in a total loss of AC power.) Since any inadvertent unit generator trip could also result in a total loss of offsite AC power, the time allowed for continued operation is severely restricted. The intent here is to avoid the risk associated with an immediate controlled shutdown and minimize the risk associated with an immediate controlled shutdown and minimize the risk associated with this level of degradation. According to Regulatory Guide 1.93 (Ref. 6), with two or more DGs inoperable, operation may continue for a period that should not exceed 2 hours. (Regulatory'Guide 1.93 assumed the unit had two DGs. Thus, a loss of both DGs results in a total loss of onsite power.)Therefore, a loss of both Unit 2 DGs and the swing DG results in degradation no worse than that assumed in Regulatory Guide 1 .93, and the 2 hour Completion Time is acceptable. H.1 __overall plant risk is If the inoperable AC electrical power orso cnnt erestored to OPERABLE status within the associ dCmltonTmte unit must be brought to a MODE in which~t" LC c. .To ITime is achieve. .this status,_, the, ,-,--unit must, ...be brought to at least MODE 3 within 12 ,..... ........... q.The allowed Completion lreasonable, based on op rating experience, to reach the required plant conditions from full pow r conditions in an orderly manner and without challenging plant systems.(continued) HATCH UNIT 1 B381 B 3.8-17 INSERT -Bases 3.8.1 Condition H 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 H.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. AC Sources -Operating B 3.8.1 No change. Included for BASES information only.SURVEILLANCE SR 3.8.1.18 (continued) REQUIREMENTS the DGs must be started from standby conditions, that is, with the engine coolant and oil continuously circulated and temperature maintained consistent with manufacturer recommendations. It is permissible to place all three DGs in test simultaneously, for the performance of this Surveillance. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.I SR 3.8.1.19 With the exception of this Surveillance, all other Surveillances of this Specification (SR 3.8.1.1 through SR 3.8.1.18) are applied only to the Unit 1 DG and offsite circuits, and swing DG. This Surveillance is provided to direct that the appropriate Surveillances for the required Unit 2 DG and offsite circuit are governed by the Unit 2 Technical Specifications. Performance of the applicable Unit 2 Surveillances will satisfy both any Unit 2 requirements, as well as satisfying this Unit 1 SR. Several exceptions are noted to the Unit 2 SRs: SR 3.8.1.6 is excepted since only one Unit 2 circuit is required by the Unit 1 Specification (therefore, there is not necessarily a second circuit to transfer to); SRs 3.8.1.10, 15, and 17 are excepted since they relate to the DG response to a Unit 2 ECCS initiation signal, which is not a necessary function for support of the Unit 1 requirement for an OPERABLE Unit 2 DG.The Frequency required by the applicable Unit 2 SR also governs performance of that SR for both Units.REFERENCES

1. 10 CFR 50, Appendix A, GDC 17.2. FSAR, Sections 8.3 and 8.4.3. FSAR, Chapter 5.4. FSAR, Chapter 6.5. FSAR, Chapter 14.6. Regulatory Guide 1.93, December 1974.(continued)

HATCH UNIT 1 B383 EIIN6 B 3.8-36 REVISION 69 AC Sources -Operating B83.8.1 BASES REFERENCES (continued)

7. Generic Letter 84-15.8. 10 CFR 50, Appendix A, GDC 18.9. Regulatory Guide 1.9, March 1971.10. Regulatory Guide 1.108, August 1977.11. Regulatory Guide 1.137, October 1979.12. IEEE Standard 387-1984.13. IEEE Standard 308-1980.14. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.INSERT -BASES 3.8.1 S Reference HATCH UNIT 1 B383 B 3.8-37 INSERT -Bases 3.8.1 Reference 15. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

DC Sources -Operating B 3.8.4 BASES ACTIONS B._I (continued) case accident, continued power operation should not exceed 12 hours. The 12 hour Completion Time provides a period of time to correct the problem commensurate with the importance of maintaining the OG DC electrical power subsystem OPERABLE. (The DG DC electrical power subsystem affects both the DG and the offsite circuit, as well as the breaker closure power for various 4160 VAC loads, but does not affect 125/250 VDC station service loads.)C._1 Condition C represents one Unit 1 station service division with a loss of ability to completely respond to an event, and a potential loss of ability to remain energized during normal operation. It is therefore imperative that the operator's attention focus on stabilizing the unit, minimizing the potential for complete loss of DC power to the affected division. The 2 hour limit is consistent with the allowed time for an inoperable DC Distribution System division.If one of the required DC electrical power subsystems is inoperable (e.g., inoperable battery, inoperable battery charger(s), or inoperable battery charger and associated inoperable battery), the remaining DC electrical power subsystems have the capacity to support a safe shutdown and to mitigate an accident condition. Since a subsequent postulated worst case single failure could result in the loss of minimum necessary DC electrical subsystems to mitigate a postulated worst case accident, continued power op~ration should not exceed 2 hours. The 2 hour Completion Time is based on Regulatory Guide 1.93 (Ref. 7) and reflects a reasonable time to assess unit status as a function of the inoperable DC electrical power subsystem and, if the DC electrical power subsystem is not restored to OPERABLE status, to prepare to effect an orderly and safe unit shutdown.F.overall plant risk is D. 1 rt-9 minimized. If the DC electrical power subsy tem cannot be restored to OPERABLE status within the r~ uired Completion Time, the unit must be brought to a MODE in which I'"cLOds t py.j To achieve this status, the unit must be brought to at least MODE 3 within Condirdpation ditosfo(fl inanorderly HATCH UNIT 1 B 3.8-56 PEl, ZI,_,.,,ON 3 INSERT -Bases 3.8.4 Condition D 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. 11) 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 D.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. DC Sources -Operating B 3.8.4 BASES ACTIONS D.1 and 0.2 (continuod) ~u ~ tl~ uiittu r~1oDEi 4 ~, ~11 ~t~Ijt ~;th th~ t;iie ie~uied ~flegulatc~y Cu~de 1.~3 (rzcf. 7).E.1 Condition E corresponds to a level of degradation in the DC electrical power subsystems that causes a required safety function to be lost.When more than one DC source is lost, and this results in the loss of a required function, the plant is in a condition outside the accident analysis. Therefore, no additional time is justified for continued operation. LCO 3.0.3 must be entered immediately to commence a controlled shutdown.SURVEILLANCE The SRs are modified by a Note to indicate that SR 3.8.4.1 through REQUIREMENTS SR 3.8.4.8 apply only to the Unit 1 DC sources, and that SR 3.8.4.9 applies only to the Unit 2 DC sources.SR 3.8.4.1 Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. Voltage requirements are based on the nominal design voltage of the battery and are consistent with the initial voltages assumed in the battery sizing calculations. The voltage requirement for battery terminal voltage is based on the open circuit voltage of a lead-calcium cell of nominal 1.215 specific gravity.Without regard to other battery parameters, this voltage is indicative of a battery that is capable of performing its required safety function.The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.SR 3.8.4.2 Visual inspection to detect corrosion of the battery cells and connections, or measurement of the resistance of each inter-cell, (continued) HATCH UNIT 1 B385 B 3.8-57 DC Sources -Operating B 3.8.4 BASES (continued) REFERENCES

1. 10 CFR 50, Appendix A, GOC 17.2. Regulatory Guide 1.6.3. IEEE Standard 308-1971.4. FSAR, Section 8.5.5. FSAR, Chapters 5 and 6.6. FSAR, Chapter 14.7. Regulatory Guide 1.93, December 1974.8. IEEE Standard 450-1987.9. Technical Requirements Manual, Section 9.0.10. Regulatory Guide 1.32, February 1977.INSERT -BASES 3.8.4 ______ReferenceI 11 I Ni [ iu ued 12. IEEE Standard 485-1983.13. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.14. Not used.HATCH UNIT 1 B386 B 3.8-62 INSERT -Bases 3.8.4 Reference 11. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

Distribution Systems -Operating B 3.8.7 BASES ACTIONS D.__1 (continued) This Completion Time allows for an exception to the normal "time zero" for beginning the allowed outage time "clock." This allowance results in establishing the "time zero" at the time LCO 3.8.7.a was initially not met, instead of at the time Condition D was entered. The 16 hour Completion Time is an acceptable limitation on this potential of failing to meet the LCO indefinitely.Ioverall plant risk is If the inoperable distribution subsys m cannot be restored to OPERABLE status within the associfrd Completion Time, the unit must be brought to a MODE in whic / , achieve this status, the plant must be brought to at least MODE 3 within 12 hou t, .. '-he allowedl Completion reasonable, based on ope ~,ng experience, to reach the required plt conditions from full power co qditions in an orderly manner and witl out challenging plant systems.Tie s INSERT -BASES 3.8.7 1 F. 1 Condition E Condition F corresponds to a level of degradation in the electrical power distribution system that causes a required safety function to be lost. When more than one AC or DC electrical power distribution subsystem is lost, and this results in the loss of a required function, the plant is in a condition outside the accident analysiS. Therefore, no additional time is justified for continued operation. LCO 3.0.3 must be entered immediately to commence a controlled shutdown.SURVEILLANCE SR 3.8.7.1 REQUIREMENTS This Surveillance verifies that the AC and DC electrical power distribution systems are functioning properly, with the correct circuit breaker alignment. The correct breaker alignment ensures the appropriate separation and independence of the electrical buses are maintained, and the appropriate voltage is available to each required bus. The verification of proper voltage availability on the buses ensures that the required voltage is readily available for motive as well as control functions for critical system loads connected to these buses. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.(continued) HATCH UNIT 1 .-0REIINO B 3.8-80 INSERT -Bases 3.8.7 Condition E 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 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. Distribution Systems -Operating B 3.8.7 BASES REFERENCES

1. FSAR, Chapters 5 and 6.2. FSAR, Chapter 14.3. Regulatory Guide 1.93, December 1974.4. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.INSERT -BASES 3.8.7 Reference HATCH UNIT 1 B 3.8-81 HATCH UNIT 1 B 3.8-81 II~ jI INSERT -Bases 3.8.7 Reference 5. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.

RPS Electric Power Monitoring B 3.3.8.2 BASES ACTIONS A.__1 (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.1 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 hour 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 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 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.plant shutdown is accomplished byplacing te plant in MOE3within n Ob 4 ;9,,,,,.3 allowed Completion lLm c c rlreasonabe bae noeaiexperience, to reach the" I NSERT -BASES 3.38.2 ! Time ICondition C l(continued) HAT H NI 2B 3.3-196 III I HATCH UNIT 2 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 0.1 (continued) required plant conditions from full power conditions in an orderly manner and without challenging plant systems.0.1, 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 D.2.1) or to isolate the RHR Shutdown Cooling System (Required Action D.2.2). Required Action D.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 REQUIREMENTS 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 hours 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 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 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 2B33-7 B 3.3-197 RPS Electric Power Monitoring B 3.3.8.2 BASES (continued) REFERENCES

1. FSAR, Section 8.3.1.1.4.B.

2. NRC Generic Letter 91-09, "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.INSERT -BASES 3.3.8.2 S Reference HATCH UNIT 2B3319 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. 12) 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 ECOS 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 ted Completion Time, the plant must be brought to a MODE in C osntapy To achieve this status, the plant must be brought to at least MODE 3 within 12 hours allowed Completion rJeasonable, based on ope itng experience, to reach the required conditions from full power c oditions in an orderly manner and wit ut challenging plant systems.)T-iime ... is I INSERT -BASES 3.5.1 1 C.1 and C.2 ICondition 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 pressure ECCS injection/sprayosubsystems in conjunction with ADS.Also, the RCIC System will automatically provide makeup water at most reactor operating pressures. Verification of RCIC OPERABILITY within 1 hour 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 12 and has been found to be acceptable through operating experience.(continued) HATCH UNIT 2B356 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. 18), 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 LCOG 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. LCOG 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. EGOS -Operating B 3.5.1 BASES (continued) ACTIONS D.1 and D.2 If any one low pressure EGOS injection/spray subsystem is inoperable in addition to an inoperable HPCI System, the inoperable low pressure EGOS injection/spray subsystem or the HPCI System must be restored to OPERABLE status within 72 hours. In this condition, adequate core cooling is ensured by the OPERABILITY of the ADS and the remaining low pressure EGOS subsystems. However, the overall EGOS 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 EGOS 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 hours is required to restore either the HPCI System or the low pressure EGOS injection/spray subsystem to OPERABLE status. This Completion Time is based on a reliability study cited in Reference 12 and has been found to be acceptable through operating experience.F. adg2J INSERT -BASES 3.5.1 Condition E 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 16.I aeny ,equ:,red Act:,n and assoc",ated Comp'et=,n Ti,,me Mf JC ...... ... .......... jtwo or 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 hours and reactor steam dome pressure reduced to < 150 psig within 36 hours. 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 hours. 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 multi Il EGOS subsystems are inoperable, as stated in Condition he plant is in a condition outside of the accident analyses. Therefore, LCO 3.0.3 must be entered immediately.(continued) HATCH UNIT 2B35-B3.5-7 INSERT -Bases 3.5.1 Condition E 5.__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 hours.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. 18) 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. EGOS -Operating B 3.5.1 No change. Included for linformation only.BASES SURVEILLANCE REQUIREMENTS SR 3.5.1.12 (continued) seat of the S/RV is verified by steam testing at the vendor facility before installation. SRs 3.5.1.11 and 3.3.5.1.5 overlap this SR to provide testing of the S/RV relief mode function. Additional functional testing is performed by tests required by the ASME OM Code (Ref.17).The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.SR 3.5.1.13 This SR ensures that the EGOS RESPONSE TIMES are less than or equal to the maximum values assumed in the accident analysis.Response time testing acceptance criteria are included in Reference

14. A Note to the Surveillance states that the instrumentation portion of the response time may be assumed from established limits. The exclusion of the instrumentation from the response time surveillance is supported by Reference 15, which concludes that instrumentation will continue to respond in the microsecond to millisecond range prior to complete failure.The Surveillance Frequency is controlled under the Frequency Control Program.Surveillance REFERENCES

1. FSAR, Paragraph 6.3.2.2.3.

2. FSAR, Paragraph 6.3.2.2.4.

3. FSAR, Paragraph 6.3.2.2.1.

4. FSAR, Paragraph 6.3.2.2.2.

5. FSAR, Subsection 15.1.39.(continued)

HATCH UNIT 2 B351 EIIN8 B 3.5-13 REVISION 81 ECCS -Operating B 3.5.1 BASES REFERENCES

6. FSAR, Subsection 15.1.40.(continued)

7. FSAR, Subsection 15.1.33.8. 10 CFR 50, Appendix K.9. FSAR, Subsection 6.3.3.10. NEDC-31376P, "E.I. Hatch Nuclear Plant Units 1 and 2 SAFER/GESTR-LOCA Loss-of-Coolant Analysis," December 1986.11. 100CFR 50.46.12. Memorandum from R. L. Baer (NRC) to V. Stello, Jr. (NRC),"Recommended Interim Revisions to LCOs for ECCS Components," December 1, 1975.13. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.14. Technical Requirements Manual, Table T5.0-1.15. NEDO-32291, "System Analyses for Elimination of Selected Response Time Testing Requirements," January 1994.16. NEDC-32041P, "Safety Review for Edwin I. Hatch Nuclear Power Plant Units 1 and 2 Updated Safety/Relief Valve Performance Requirements," April 1"996.17. ASME, OM Code -2004 Edition, "Code for Operation and Maintenance of Nuclear Power Plants," Appendix I.INSERT -BASES 3.5.1 Reference HATCH UNIT 2 B351 B 3.5-14 INSERT -Bases 3.5.1 Reference 18. NEDC-32988-A, Revision 2, Technical Justification to Support Risk-Informed Modification to Selected Required End States for BWR Plants, December 2002.I RCIC System B 3.5.3 BASES ACTIONS A.1 and A.2 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 hour 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 HPCI) 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[minimized.J sim .aneously inoperable, the plant must be brought to a condition in whicw .ITo achieve this status, the plant must be bou£ht o atleat MDE 3witin 2 horsln The allow sed Completio reasonable, based on operating xperience, to reach the r quired plant conditions from full power condi ons in an (continued) HATCH UNIT 2 B 3.5-23I INSERT -Bases 3.5.3 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 SR 3.5.3.5 (continued) REQUIREMENTS 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 5.5.6.3. 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-4!-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.INSERT -BASES 3.5.3< iReference HATCH UNIT 2 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 hours. This is consistent with the Completion Time for Condition A and the fact that the leak tight primary containment INSERT -BASES 3.6.1.7 }_ boundary is being maintained. Condition 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 hour. This Completion Time is consistent with the ACTIONS of LCO 3.6.1.1, which requires that primary containment be restored to OPERABLE status within 1 hour.If the vacuum breakers in one or more lines cannot be lra, a~tb closed or restored to IH he plant must be brought to a MODE in which the LCO does not OPERABLE status within __ply/. To achieve this status, the plant must brought to at least the equied Cmpleion MODE 3 within 12 hours and to MODE 4 within 36 hours. The Therqired, oplto allowed Completion Times are reasonable, based on operating Timeexperience, 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 REQUI REM ENTS 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 2 B364 B 3.6-40 INSERT -Bases 3.6.1.7 Condition D D. 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 hours.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 D.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 SURVEILLANCE SR 3.6.1.7.1 (continued) REQUIREMENTS Two Notes are added to this SR. The first Note allows reactor building-to-suppression chamber vacuum breakers opened in conjunction with the performance of a Surveillance to not be considered as failing this SR. These periods of opening vacuum breakers are controlled by plant procedures and do not represent inoperable vacuum breakers. The second Note is included to clarify that vacuum breakers, which are open due to an actual differential pressure, are not considered as failing this SR.SR 3.6.1.7.2 Each vacuum breaker must be cycled to ensure that it opens properly to perform its design function and returns to its fully closed position.This ensures that the safety analysis assumptions are valid. The 92 day Frequency of this SR is in accordance with the requirements of the Inservice Testing Program.SR 3.6.1.7.3 Demonstration of vacuum breaker opening setpoint is necessary to ensure that the safety analysis assumption regarding vacuum breaker full open differential pressure of < 0.5 psid is valid. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES

1. FSAR, Section 6.2.1.2. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.INSERT- BASES 3.6.1.7I< Reference HATCH UNIT 2 B364 B 3.6-41 INSERT -Bases 3.6.1.7 Reference 3. 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 B 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.ISR -BSES 36.18 F_Condition B ~T 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 hour Completion Time is allowed to close the vacuum breaker due to the low probability of an event that would pressurize primary containment. D~.1 and D'2I gi# e 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 MODI 3 within 12 hours and to MODE 4 within 36 hours. The allowe~ Completion Times are reasonable, based on operating experi nce, to reach the required plant conditions from full power conditi ns in an orderly manner and without challenging plant system I.Jf the open suppression chamber-to-drywell vacuumbraebe 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 hour without makeup.However, if vacuum breaker position indication is not reliable due to, for example, a dual or open indication with torus-to-drywell differential pressure remaining < 0.5 psid, alternate methods of verifying that the vacuum breaker is closed are detailed in Technical Requirements Manual (TRM) (Ref. 4), T3.6.1, "Suppression Chamber-to-Drywell (continued) HATCH UNIT 2 B 3.6-451 INSERT -Bases 3.6.1.8 Condition B BA 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 hours.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. Suppression Chamber-to-Drywell Vacuum Breakers B 3.6.1.8 BASES (continued) REFERENCES

1. FSAR, Section 6.2.1.2. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.3. Technical Requirements Manual.INSERT -BASES 3.6.1.8 Reference HATCH UNIT 2 B364 B 3.6-47 INSERT -Bases 3.6.1.8 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 Cooling (continued) With two RHR suppression pool cooling subsystems inoperable, one subsystem must be restored to OPERABLE status within 8 hours. In this 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 methods to remove heat from primary containment are available. Reuie 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 hours and to MODE 4 within 36 hours. 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 SR does not apl:ily 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.(continued) HATCH UNIT 2 B365 B 3.6-58 INSERT -Bases 3.6.2.3 Condition B g__1 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 hours.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, Section 6.2.2.2. ASME, Boiler and Pressure Vessel Code, Section XI.3. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

_ BASES3.23/ Reference 3.23 B 3.6-59 HATCH UNITV2,B 3,6-59 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.__ (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 hours. In this Condition, there is a substantial loss of the primary containment bypass leakage 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 methods to remove heat from primary containment are available. C. 1 i [minimized.I \If any Required Action and associated Completion T/ime cannot be met, the plant must be brought to a MODE in which.hLCdcsnt To achieve this status, the plant must be brought to at least MODE 3 within 12 hourslo... .,,. ,u .Tde allowed SCompletioni-, esa-1reasonable, based on operating expe eto Tmisreach the r buired plant conditions from full power conditions in an "[Tie i Iorderly manner and without challenging plant systems. cninINsERT-cBASES 3.6.2.4 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 2 B 3.6-62I 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 Frequency 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 Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES

1. FSAR, Section 6.2.2. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.-BASES 3.6.2.4 Reference HATCH UNIT 2 B366 EIIN7 B 3.6-63 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 BASES (continued) ACTIONS A.1_If secondary containment is inoperable, it must be restored to OPERABLE status within 4 hours. The 4 hour 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 OPERABILITY) occurring during periods where secondary containment is inoperable is minimal.overall plant risk is If secondary containment cannot be restored to OPERABLE status[minimized, within the requ ed Completion Time, the plant must be brought to a MODE in whichl .I To achieve this status, the plant must be brought to at least MODE 3 within 12 ,vu he allowed Completion WIi reasonable, based on ope experience, to reach the required plant conditions from full power con #t.,ns 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 fission 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 case, (continued) HATCH UNIT 2 B 3.6-79 IEIIN7 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 SR 3.6.4.1.3 and SR 3.6.4.1.4 (continued) REQUIREMENTS maintain > 0.20 inch of vacuum water gauge for 1 hour at a flow rate< 4000 cfm for each SGT subsystem. The 1 hour 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, Section 15.1.39.2. FSAR, Section 15.1.41.3. Technical Requirements Manual, Section 8.0.4. NRC No. 93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.-BASES 3.6.4.1 Reference HATCH UNIT 2 B368 EIIN7 B 3.6-81 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) failure in one of the remaining required OPERABLE subsystems could result in the radioactivity release control function not being adequately performed. The 7 and 30 day Completion Times are based on consideration of such factors as the availability of the OPERABLE redundant SGT subsystems and the low probability of a DBA occurring during this period. Additionally, the 30 day Completion Time of Required Action A.1 is based on three remaining OPERABLE SOT subsystems, of which two are Unit 2 subsystems, and the secondary containment volume in the Unit 1 reactor building being open to the common refueling floor where the two Unit 2 SGT subsystems can readily provide rapid drawdown of vacuum. Testing and analysis has shown that in this configuration, even with an 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.C.1 an -- ___overall plant risk is I-- ' I minimized.I If the SOT subsyst m cannot be restored to OPERABLE status within the required Compl ,tion Time in MODE 1, 2, or 3, the plant must be brought to a MODEn w~~~ ~cLOde o plITo achieve this status, the plant must be brought to at least MODE 3 within 12 i Icd cMOE4 ;itMq allowed Completion [[{e"-rr reasonable, based on operating ~perience, to reach the required plant conditions from full power co ditions in an orderly manner and without challenging plant systems. IJNSERT -BASES 3.6.4.3 In the event that a Unit 1 SOT subsystem is the one not restored to OPERABLE status as required by Required Action A.1 or B.1, operation of Unit 2 can continue provided that Unit 1 is shut down, the Unit 1 reactor building zone is isolated from the remainder of secondary containment and the SOT System, and the Unit 1 Technical Specifications do not require Operability of Zone I. In this modified secondary containment configuration, only three SOT subsystems are required to be OPERABLE to meet LCO 3.6.4.3, and no limitation is applied to the inoperable Unit 1 SOT subsystem. This in effect is an alternative to restoring the inoperable Unit 1 SOT subsystem, i.e., shut down Unit 1 and isolate its reactor building zone from secondary containment and SOT System.(continued) HATCH UNIT 2 B369 B3.6-92 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. 8), 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. SGT System B 3.6.4.3 BASES ACTIONS D.1, D.2.1, D.2.2, and 0.2.3 (continued) 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 remaining 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. The Required Actions of Condition 0 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 t6 suspend movement of irradiated fuel assemblies would not be a sufficient reason to require a reactor shutdown.E.__11 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 3.6.4.3I \[Condition E (continued) HATCH UNIT 2 B 3.6-93 HATCH UNIT 2B[3.6-93 f ,','l~O 741 I 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 hours.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. 8) 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 SURVEILLANCE SR 3.6.4.3.3 REQUIREMENTS (continued) This SR verifies that each required Unit 1 and Unit 2 SOT subsystem starts on receipt of an actual or simulated initiation signal. The LOGIC SYSTEM FUNCTIONAL TEST in SR 3.3.6.2.5 overlaps this SR to provide complete testing of the safety function. This Surveillance can be performed with the reactor at power. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.REFERENCES

1. 10 CFR 50, Appendix A, GDC 41.2. Unit 1 FSAR, Section 5.3.2.3.3. Unit 2 FSAR, Section 6.2.4.4. Unit 2 FSAR, Section 15.2.5. Unit 2 FSAR, Section 15.3.6. Technical Requirements Manual, Section 8.0.7. NRC No. 93-1 02, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.IiNSERT -BASES 3.6.4.3< Reference HATCH UNIT 2 B369 B 3.6-95 INSERT -Bases 3.6.4.3 Reference 8. 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 BASES ACTIONS 0.__1 (continued) INSERT -BASES 3.7.1 Condition D 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 the 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. 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 hours. The 8 hour 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. ofCondition eJ If the RHRSW subsystems cannot be not rest r d status within the associated Completion Times, he 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 hours and in MODE 4 within 36 hours. 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 REQUIREMENTS Verifying the correct alignment for each manual, power operated, and automatic valve in each RHRSW subsystem flow path provides (continued) HATCH UNIT 2 B 3.7-5 HATCHUNIT2 B .7-5REVISION 49}}