Text

E.I. Hatch, Units 1 and 2 - License Amendment Request for Adoption of TSTF-423-A, Rev. 1, Technical Specification End States, NEDC-32988-A, Using the Consolidated Line Item Improvement Process. Part 1 of 4
	ML15350A409
Person / Time
Site:	Hatch
Issue date:	12/15/2015
From:	Pierce C R; Southern Co, Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML15351A023	List: ML15350A409; ML15350A410; ML15350A411; NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 2 of 4; NL-14-1075, E.I. Hatch, Units 1 and 2 - Technical Specifications. Part 3 of 4; NL-14-1075, Technical Specifications. Part 4 of 4;
References
	NL-14-1075
	Download: ML15350A409 (67)
	v • d • e

Charles R. PierceRegulatory Affairs DirectorSouthern NuclearOperating

Company, Inc.40 Inverness Center ParkwayPost Office Box 1295Birmingham, AL 35242Tel 205.992.7872 Fax 205.992.7601 SOUTHERN "NUCLEARA SOUTHERN COMPANYDEC 1 5 2015Docket Nos.: 50-32 150-366NL-14-1 075U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, D. C. 20555-001 Edwin I. Hatch Nuclear PlantLicense Amendment Request for Adoption of TSTF-423-A, Rev. 1Technical Specification End States, NEDC-32988-A Usin~q the Consolidated Line Item Improvement Process

Reference:

TSTF-423-A, Revision 1, "Technical Specifications End States,NEDC-32988-A,"

dated December 22, 2009.Ladies and Gentlemen:

In accordance with the provisions Title 10 of the Code of Federal Regulations (CFR), Section 50.90, Southern Nuclear Operating Company (SNC) is submitting a request for an amendment to the Hatch Nuclear Plant (HNP), Units 1 and 2,Technical Specifications (TS) to incorporate the NRC-approved, Technical Specification Task Force (TSTF) traveler, TSTF-423-A, Revision 1 (reference).

The proposed change would modify the TS to risk-inform requirements regarding selected Required Action end states by incorporating the Boiling Water Reactor(BWR) Owners' Group (BWROG) approved Topical Report NEDC-32988-A, Revision 2, "Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants."

Additionally, the proposedamendment would modify the TS Required Actions with a Note prohibiting theuse of limiting condition for operation (LCO) 3.0.4.a when entering the preferred end state (Mode 3) on startup.* Attachment 1 provides a description and assessment of the proposedchange, the requested confirmation of applicability, and plant-specific verifications.

Attachment 2 summarizes the regulatory commitments made in thislicense amendment request.* Attachment 3 provides markup pages of existing TS and Bases to showthe proposed changes.* Attachment 4 provides revised (clean) TS pages.ACL(

U. S. Nuclear Regulatory Commission NL-1 4-1075Page 2SNC requests approval of the proposed license amendment by November 20,2016, with the amendment being implemented within 90 days of issuance of theamendment.

In accordance with 10 CFR 50.91 (a)(1), "Notice for public comment,"

the analysisabout the issue of no significant hazards consideration (NSHC) using thestandards in 10 CFR 50.92 is being provided to the Commission in accordance with the distribution requirements in 10 CFR 50.4.In accordance with 10 CFR 50.91 (b)(1), "State Consultation,'

a copy of the thisletter and its reasoned analysis about NSHC is being provided to the designated State of Georgia officials.

Mr. C. R. Pierce states he is Regulatory Affairs Director of Southern NuclearOperating

Company, is authorized to execute this oath on behalf of SouthernNuclear Operating Company and, to the best of his knowledge and belief, thefacts set forth in this letter are true.This letter contains Commitments, which are listed in Attachment

2. If you haveany questions, please contact Ken McElroy at (205) 992-7369.

Respectfully sbitdC. R. PierceRegulatory Affairs DirectorCRP/RMJSworn to and subscribed before me this .j__ day of I ?t., 2015./Notary PublicMy commission expires:

/6 -i- 1.ot"Attachments:

1. Assessment of Proposed Change, Confirmation ofApplicability, and Plant-Specific Verifications

2. Summary of Regulatory Commitments

3. Markup Pages of Existing TS and Bases Showing ProposedChanges4. Revised (Clean) TS Pages U. S. Nuclear Regulatory Commission NL-14-1075 Page 3cc: Southern Nuclear Operatingi CompanyMr. S. E. Kuczynski,

Chairman, President

& CEOMr. D. G. Bost, Executive Vice President

& Chief Nuclear OfficerMr. D. R. Vineyard, Vice President

-HatchMr. M. D. Meier, Vice President

-Regulatory AffairsMr. D. R. Madison, Vice President

-Fleet Operations Mr. B. J. Adams, Vice President

-Engineering Mr. G. L. Johnson, Regulatory Affairs Manager -HatchRType: CHA02.004 U. S. Nuclear Regulatory Commission Mr. L. D. Wert, Regional Administrator (acting)Mr. R. E. Martin, NRR Senior Project Manager-HatchMr. D. H. Hardage, Senior Resident Inspector

-HatchState of GeorgiaMr. J. H. Turner, Environmental Director Protection Division Edwin I. Hatch Nuclear PlantLicense Amendment Request for Adoption of TSTF-423-A, Rev. 1,Technical Specifications End States, NEDC-32988-A, Attachment 1Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications Attachment 1Ito NL-14-1075

-.-Assessment of Proposed Change, Confirmation of Applicability,

.and Plant-Specific Verifications

..

.. ... .Basis for Proposed Changes1.0 Description Southern Nuclear Company, (SNC) requests an amendment to Operating SLicenses for the Edwin I. Hatch Nuclear Plant (HNP), .Units 1 .and 2, DPR-57 andNPF-5, respectively.

The proposed amendment would, modify the HNP Technical Specifications (TS) to incorporate risk-inform requirements regarding selectedRequired Action end states. Additionally, it would modify the TS RequiredActions with a Note prohibiting the use of limiting condition for operation (LCO)3.0.4.a when entering the preferred end state (Mode 3) on startup.

The changesare consistent with Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) traveler TSTF-423-A, Revision 1, "Technical Specifications End States, NEDC-32988-A,"

dated December 22, 2009 (ADAMSAccession Number ML093570241)

(Reference I). The Federal Register noticepublished on February 18, 2011 (76 FR 34) (Reference

2) announced theavailability of this TS improvement as part of the consolidated line itemimprovement process (CLIIP).2.0 Assessment 2.1 Applicability of Topical R5eport NEDC-32988-A.

TSTF-423.

and ModelSafety Evaluation SNC has reviewed Boiling Water Reactor (BWR) Owners' Group (BWROG)topical report (TR) NEDC-32988-A (Reference 3), TSTF-423, Revision 1(Reference I), and the NRC staff's model safety evaluation (Reference

4) as partof the CLIIP. SNC has concluded that the information provided in theTR NEDC-32988 and TSTF-423, and the NRC staff's model safety evaluation areapplicable to HNP Units 1 and 2 and justify this license amendment request(LAR) for incorporation of the changes to the HNP Unit 1 and 2 TS.The TSTF-423 justification references Regulatory Guide (RG) 1.182. OnNovember 27, 2012, the NRC published a Federal Register Notice stating thatRG 1.182 has been withdrawn and the subject matter has been incorporated intoRG 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear PowerPlants."

RG 1.160 endorses NUMARC 93-01, Revision 4A, dated April 2011.SNC assesses the risk of maintenance activities consistent with the guidance inRG 1.160. Therefore, the justification for adoption of TSTF-423 continues to beapplicable.

'2.2 Optional Changqes and Variations

..'.J"'SNC is proposing the following variations or deviations.fromn TR NEDC-32988-A, the TS changes described in the TSTF-423-A, Revisidn:

tI ,or- the NRC staff'Smodel safety evaluation published in the Federal May 11, 2012(77 FR 27814) as part of the CLIIP Notice of Availabilit{y.

".:..In some instances, the Technical Specification number and or title may bedifferent between the generic Improved Standard Technicail Specifications (ISTS)A1-1 Attachment 1Ito NL-14-1 075Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications (Reference

5) on which TSTF-423-A was based and the HNP Unit I and 2specific TS; however, the justification for the proposed mode change remainsdirectly applicable.

Additionally, in some cases there may be content differences between the ISTS and HNP TS due to plant-specific or historical reasons.

Thesevariations and deviations are discussed below:1. ISTS TS 3.4.3. Safety/Relief Valves. Conditions B and C (HNP TS 3.4.3)The content and structure of HNP TS 3.4.3 differs significantly from that forISTS 3.4.3. As such, the changes identified in TSTF-423-A, Revision I forISTS 3.4.3 are not suitable for adoption under the CLIIP process and arenot included in this amendment request.2. ISTS TS 3.5.1. Emergqency Core Coolingq System -- Operating.q Conditions G. and H (HNP TS 3.5.1. Conditions E and F)HNP TS 3.5.1 does not include Conditions that are equivalent to ISTSConditions E and F. The changes identified in TSTF-423-A, Revision 1 forISTS 3.5.1, new Condition G are therefore incorporated into HNP Unit 1 and2 TS 3.5.1 as new Condition E, and references to Conditions E and F areomitted.

Similarly, changes identified in TSTF-423-A for ISTS 3.5.1, newCondition H are incorporated into HNP Unit I and 2 TS 3.5.1, newCondition F. The End state Completion Time for modified Conditions E andF in HNP Unit 1 and 2 TS 3.5.1 are consistent with those evaluated inTR NEDC-32988, and provided in TSTF-423-A, Revision 1.3. ISTS TS 3.6.1.6, Low-Low Set Valves. Conditions B and C (HNP TS3.6.1.6).

ISTS 3.6.1.6 Conditions A and B provide requirements for one Low-Low Set(LLS) valve inoperable.

HNP TS 3.6.16 does not include requirements forone inoperable LLS valve, and it is not being proposed to be added by thisamendment request.

Requirements for two or more LLS valves inoperable are provided in ISTS Condition B, and reflected in TSTF-423-A, Revision 1as new Condition C. This new Condition C is equivalent to HNP TS 3.6.1.6Condition A. As such, the changes identified in TSTF-423-A, Revision 1 forISTS TS 3.6.1.6 are not applicable for HNP and are not adopted.4. ISTS TS 3.6.1.9, Main Steam Isolation Valve Leakagqe Control System.Condition CThe HNP Unit I and 2 design does not include a Main Steam Isolation Valve Leakage Control System. The changes identified in TSTF-423-A, Revision I for ISTS TS 3.6.1.9 are therefore not adopted.5. ISTS TS 3.6.4.3, Standby Gas Treatment System, Conditions B and D(HNP TS 3.6.4.3.

Conditions C and E)ISTS 3.6.4.3, Condition A, provides requirements when one standby gastreatment (SGT) subsystem is inoperable.

For HNP, the Unit 1 and 2 SGTSystems each consist of two fully redundant subsystems, each with its ownset of dampers, charcoal filter train, and controls.

The Unit 1 and Unit 2SOT Systems are shared between Units 1 and 2, and the SOT System onboth units automatically start and operate in response to actuation signalsA1-2 Attachment 1 to NL-14-1075 Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific verifications indicative of conditions or an accident that could require operation of thesystem.As a result of the ability to share the four HNP Unit 1 and Unit 2 SGTsubsystems between units, additional combinations of SGT equipment inoperability are possible that are not reflected in ISTS 3.6.4.3, and therequirements in ISTS 3.6.4.3, Condition A are represented in HNP Unit 1and 2 TS 3.6.4.3 as Conditions A and B. This difference results inrenumbering of the Conditions in HNP Unit 1 and 2 TS 3.6.4.3 relative tothose in TSTF-423-A.

Changes identified in TSTF-423-A, Revision 1 forISTS 3.6.4.3, Condition B are incorporated into the HNP Unit 1 and 2TS 3.6.4.3, Condition C. The changes identified in TSTF-423-A forISTS 3.6.4.3, Condition 0 are incorporated into HNP TS 3.6.4.3, Condition E. The end state Completion Time for modified Conditions C and E in HNPUnit I and 2 TS 3.6.4.3 are consistent with those evaluated inTR NEDC-32988, and provided in TSTF-423-A, Revision 1.6. ISTS TS 3.7.2, Plant Service Water and Ultimate Heat Sink, Conditions Cand G (HNP TS 3.6.1.6.

Conditions E and G)HNP TS 3.7.2, Conditions B and 0, provide requirements when one plantservice water turbine building isolation valve is inoperable in one or eachplant service water (PSW) subsystem.

These Conditions reflectplant-specific features of the HNP Unit 1 and 2 design, and ISTS 3.7.2 doesnot include similar Conditions.

Additionally, ISTS TS 3.7.2 includesConditions for inoperability of cooling tower fans (Condition C) and ultimateheat sink water temperature (Condition D) that are not included ornecessary in the HNP Unit 1 and 2 TS due to plant-specific differences inthe PSW system design.*These differences result in renumbering of the Conditions in HNP TS 3.7.2relative to those in TSTF-423-A.

Changes identified in TSTF-423-A, Revision 1 for ISTS 3.7.2, Condition C are incorporated into HNP Unit 1 and2 TS 3.7.5, Condition E, and plant-specific Conditions B and 0 are adoptedwithin this Condition.

The referenced Conditions in Condition G are alsorenumbered to reflect these differences.

The end state Completion Time formodified Conditions E and G in HNP Unit I and 2 TS 3.7.2 are consistent with those evaluated in TR NEDC-32988, and provided in TSTF-423-A, Revision 1.7. ISTS TS 3.7.5. Control Room Air Conditioninq System. Conditions B and D(HNP TS 3.7.5. Condition 0)ISTS 3.7.5 assumes that the control room air conditioning (AC) systemdesign consists of two 100% control room AC subsystems.

For HNPUnits 1 and 2, the control room AC safety function is provided by three 50%capacity subsystems.

With one control room AC subsystem inoperable, thetwo remaining control room AC subsystems provide 100% of the requiredcapacity.

With two subsystems inoperable, control room AC capability isdiminished, but remains capable of providing 50% of the required capacity.

This plant-specific design difference, and the historical licensing basis forHNP Units 1 and 2 are reflected in HNP Unit 1 and 2 TS 3.7.5.

Attachment 1Ito NL-14-1 075Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications The changes identified in TSTF-423-A, Revision I for ISTS 3.7.5, Condition B are incorporated into HNP Unit 1 and 2 TS 3.7.5 as Condition

0. The endstate Completion Time for modified Conditions D in HNP Unit 1 and 2TS 3.7.5 are consistent with those evaluated in TR NEDC-32988, andprovided in TSTF-423-A, Revision 1.ISTS 3.7.5 Condition D provides actions when both (all) control room ACsubsystems are inoperable.

The analogous Condition was removed fromHNP Unit 1 and 2 TS 3.7.5 in license amendment 270/2 14 (ADAMSAccession No. ML14279A261),

with the adoption of changes described inTSTF-477.

The changes identified in TSTF-423-A, Revision 1 forISTS 3.7.5, Condition D are therefore not incorporated into HNP Unit 1 and2 TS 3.7.5.8. ISTS TS 3.8.1. AC Sources -Operatingq, Condition G (HNP TS 3.8.1.Condition H)The format and content of Conditions for HNP TS 3.8.1 differs from thatprovided in TSTF.-423-A, Revision 1 for ISTS 3.8.1. HNP Unit I and 2TS 3.8.1 provides an additional condition (Condition C) for inoperability ofone required diesel generator (DG) on the opposite unit that does notappear in ISTS 3.8.1. HNP Unit I and 2 TS 3.8.1 also provides anadd itionaJ condition (Condition G) for the situation where there are no DGscapable of providing power to any low pressure coolant injection valve loadcenters that does not appear in ISTS 3.8.1. Additionally, ISTS 3.8.1includes a Condition (Condition F) for automatic load center inoperability that does not appear in HNP Unit I and 2 TS 3.8.1. These Conditions reflect plant-specific attributes of the HNP design and/or the historical HNPlicensing basis.These differences result in renumbering of the Conditions in HNP TS 3.8.1relative to those in TISTF-423-A.

Changes identified in TSTF-423-A, Revision 1 for ISTS 3.8.1, Condition G are incorporated into HNP Unit 1 and2 TS 3.8.1, Condition H, and plant-specific Conditions C and G are adoptedwithin this Condition.

The end state Completion Time for modifiedCondition H in HNP Unit I and 2 TS 3.8.1 is consistent with those evaluated in TR NEDC-32988, and provided in TSTF-423-A, Revision 1.9. ISTS TS 3.8.4, DC Sources -Operating.q Condition D (HNP TS 3.8.4,Condition 0)The structure and content of Conditions in HNP TS 3.8.4 differs from thatprovided in TSTF-423-A, Revision I for ISTS 3.8.4. ISTS 3.8.4,Conditions A, B, and C, provide requirements when conditions exist thatrender one or more DG or station service DC electrical subsystems inoperable, including battery or charger inoperability.

End staterequirements are provided in ISTS 3.8.4, Condition D when therequirements of Condition A, B, or C are not met for a station service DCelectrical subsystem, and in iSTS 3.8.4, Condition E when the requirements of Condition A, B, or C are not met for a DG DC electrical subsystem.

A 1-4 Attachment 1Ito NL-14-1075 Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications Similarly HNP TS 3.8.4, Conditions A, B, and C, provide requirements whenconditions exist that render a OG or station service DC electrical subsystem inoperable.

End state requirements are provided in ISTS 3.8.4, Condition 0when the requirements of Condition A, B, or C are not met for a stationservice DC electrical subsystem, and ISTS 3.8.4, Condition E providesactions when the requirements of Condition A, B, or C are not met for a DGDC electrical subsystem.

The changes identified in TSTF-423-A, Revision 1 for ISTS 3.8.1, Condition D are incorporated into HNP Unit 1 and 2 TS 3.8.1, Condition D. The endstate Completion Time for modified Condition D in HNP Unit 1 and 2TS 3.8.4 is consistent with those evaluated in TR NEDC-32988, andprovided in TSTF-423-A, Revision 1.10. ISTS TS 3.8.7, Inverters

-Operatincq, Condition GThe HNP Unit 1 and 2 TS do not include a specification for Inverters.

Thechanges identified in TSTF-423-A, Revision 1 for ISTS TS 3.8.7 aretherefore not adopted.11. ISTS TS 3.8.9, Distribution Systems -Operatingq, Condition D (HNPTS 3.8.7. Condition E)The structure and content of Conditions in HNP TS 3.8.7 differs from thatprovided in TSTF-423-A, Revision 1 for ISTS 3.8.9. ISTS 3.8.9,Conditions A, B, and C, provide requirements when one or more AC or DCelectrical power distribution subsystems is inoperable, or one or more ACvital buses is inoperable.

End state requirements are provided inISTS 3.8.9, Condition D when the requirements of Conditions A, B, or C arenot met.Similarly HNP TS 3.8.7, Conditions A, B, C, and D provide requirements when conditions exist that render a Unit 1, Unit 2, or swing bus AC or DCelectrical power distribution subsystem inoperable.

End state requirements are provided in HNP TS 3.8.7, Condition E when the requirements ofCondition A, B, C, or D are not met.The changes identified in TSTF-423-A, Revision 1 for ISTS 3.8.9, Condition D are incorporated into HNP Unit 1 and 2 TS 3.8.7, Condition E. The endstate Completion Time for modified Condition E in HNP Unit 1 and 2TS 3.8.7 is consistent with those evaluated in TR NEDC-32988, andprovided in TSTF-423-A, Revision 1.The Regulatory Evaluation provided in Section 2.0 of the model Safety Evaluation (SE) for TSTF-423-A, Revision 1 includes a reference to 10 CER 50, Appendix A,General Design Criterion (GDC) 17, "Electric Power Systems."

Although HNPUnit 2 was licensed to the requirements of 10 CFR 50, Appendix A, GDC, HNPUnit 1 was not. The HNP Unit 1 construction permit was received under the 70general criteria identified in 32 FR 10213, published July 11, 1967(ML043310029).

The equivalent 1967 general design criterion for 10 CFR 50,Appendix A, GDC 17 is discussed below.Al-5 Attachment 1Ito NL-14-1 075Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications 10 CFR 50, Appjendix A, General Design CriteriaCriterion 17, "Electric Power Systems,"

states:An onsite electric power system and an offsite electric power system shallbe provided to permit functioning of structures,

systems, and components important to safety. The safety function for each system (assuming theother system is not functioning) shall be to provide sufficient capacity andcapability to assure that (1) specified acceptable fuel design limits anddesign conditions of the reactor coolant pressure boundary are notexceeded as a result of anticipated operational occurrences and (2) thecore is cooled and containment integrity and other vital functions aremaintained in the event of postulated accidents.

The onsite electric power supplies, including the batteries, and the onsiteelectric distribution system, shall have sufficient independence, redundancy, and testability to perform their safety functions assuming asingle failure.Electric power from the transmission network to the onsite electricdistribution system shall be supplied by two physically independent circuits (not necessarily on separate rights of way) designed and locatedso as to minimize to the extent practical the likelihood of theirsimultaneous failure under operating and postulated accident andenvironmental conditions.

A switchyard common to both circuits isacceptable.

Each of these circuits shall be designed to be available insufficient time following a loss of all onsite alternating current powersupplies and the other offsite electric power circuit, to assure thatspecified acceptable fuel design limits and design conditions of the reactorcoolant pressure boundary are not exceeded.

One of these circuits shallbe designed to be available within a few seconds following a loss-of-coolant accident to assure that core cooling, containment integrity, andother vital safety functions are maintained.

Provisions shall be included to minimize the probability of losing electricpower from any of the remaining supplies as a result Of, or coincident with,the loss of power generated by the nuclear power unit, the loss of powerfrom the transmission

network, or the loss of power from the onsiteelectric power supplies.

HNP Unit I Equivalent:

1967 GDC Criteria:

1967 GDC Criterion 24, "Emergency Power for Protection Systems,"

states:In the event of loss of all offsite power, sufficient alternate sources ofpower shall be provided to permit the required functioning of theprotection systems.A1-6 Attachment 1Ito NL-1 4-1 075Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications 3.0 Regqulatory Analysis3.1 No Si~qnificant Hazards Consideration Southern Nuclear Corporation (SNC) has evaluated the proposedchanges to the TS using the criteria in 10 CFR 50.92 and has determined that the proposed changes do not involve a significant hazardsconsideration.

Description of Amendment Request:

A change is proposed to the TS forHNP, Units I and 2, consistent with TSTF-423, Revision 1, to allow, forsome systems, entry into hot shutdown rather than cold shutdown torepair equipment, if risk is assessed and managed consistent with theprogram in place for complying with the requirements of10 CFR 50.65(a)(4).

Changes proposed in TSTF-423 will be made to theTS for HNP, Units 1 and 2, for selected Required Action end states.As required by 10 CER 50.91(a),

the SNC analysis of the issue of nosignificant hazards consideration is presented below:1. Does the proposed change involve a significant increase in theprobability or consequences of an accident previously evaluated?

Response:

NoThe proposed change allows a change to certain required endstates when the TS Completion Times for remaining in poweroperation will be exceeded.

Most of the requested technical specification (TS) changes are to permit an end state of hotshutdown (Mode 3) rather than an end state of cold shutdown(Mode 4) contained in the current TS. The request was limited to:(1) those end states where entry into the shutdown mode is for ashort interval, (2) entry is initiated by inoperability of a single trainof equipment or a restriction on-a plant operational parameter, unless otherwise stated in the applicable TS, and (3) the primarypurpose is to correct the initiating condition and return to poweroperation as soon as is practical.

Risk insights from both thequalitative and quantitative risk assessments were used in specificTS assessments.

Such assessments are documented in Section 6 of topical reportNEDC-32988-A, Revision 2, "Technical Justification to SupportRisk Informed Modification to Selected Required Action EndStates for BWR Plants."

They provide an integrated discussion ofdeterministic and probabilistic issues, focusing on specific TSs,which are used to support the proposed TS end state andassociated restrictions.

The NRC staff finds that the risk insightssupport the conclusions of the specific TS assessments.

Therefore, the probability of an accident previously evaluated isA1-7 Attachment 1Ito NL-14-1 075Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications not significantly increased, if at all. The consequences of anaccident after adopting TSTF-423 are no different than theconsequences of an accident prior to adopting TSTF-423.

Therefore, the consequences of an accident previously evaluated are not significantly affected by this change. The addition of arequirement to assess and manage the risk introduced by thischange will further minimize possible concerns.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accidentpreviously evaluated.

2. Does the proposed change create the possibility of a new ordifferent kind of accident from any accident previously evaluated?

Response:

NoThe proposed change does not involve a physical alteration of theplant (no new or different type of equipment will be installed).

Ifrisk is assessed and managed, allowing a change to certainrequired end states when the TS Completion Times for remaining in power operation are exceeded (i.e., entry into hot shutdownrather than cold shutdown to repair equipment) will not introduce new failure modes or effects and will not, in the absence of otherunrelated

failures, lead to an accident whose consequences exceed the consequences of accidents previously evaluated.

Theaddition of a requirement to assess and manage the riskintroduced by this change and the commitment by the licensee toadhere to the guidance in TSTF-IG-05-02, "Implementation Guidance for TSTF-423, Revision 1, 'Technical Specifications EndStates, NEDC-32988-A,'"

will further minimize possible concerns.

Thus, based on the above, this change does not create thepossibility of a new or different kind of accident from an accidentpreviously evaluated.

3. Does the proposed change involve a significant reduction in amargin of safety?Response:

NoThe proposed change allows, for some systems, entry into hotshutdown rather than cold shutdown to repair equipment, if risk isassessed and managed.

The Boiling Water Reactor Owners'Group's risk assessment approach is comprehensive and followsNRC staff guidance as documented in Regulatory Guides (RG)1.174 and 1.177. In addition, the analyses show that the criteria ofthe three-tiered approach for allowing TS changes are met. Therisk impact of the proposed TS changes was assessed following the three-tiered approach recommended in RG 1.177. A riskA1-8 Attachment i to NL-14-1 075Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications assessment was performed to justify the proposed TS changes.The net change to the margin of safety is insignificant.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.Based upon the reasoning presented above, SNC concludes that therequested change involves no significant hazards consideration, as setforth in 10 CFR 50.92(c),

"Issuance of Amendment."

3.2 Verifications, Commitments, and Additional Information NeededSNO commits to the regulatory commitments identified in Attachment 2.In addition, SNC has proposed TS Bases consistent with TSTF-423, Revision 1, which provide guidance and details on how to implement thenew requirements.

Implementation of TSTF-423 requires that risk bemanaged and assessed, and the configuration risk management programis adequate to satisfy this requirement.

The risk assessment need not bequantified, but may be a qualitative assessment of the vulnerability ofsystems and components when one or more systems are not able toperform their associated function.

Finally, SNC has a Bases ControlProgram consistent with Section 5.5 of the Standard Technical Specifications.

4.0 Environmental Considerations The proposed change would change a requirement with respect to installation oruse of a facility component located within the restricted area, as defined in 10gCFR Part 20, and would change an inspection or surveillance requirement.

However, the proposed change does not involve significant hazardsconsideration, (ii) a significant change in the types or significant increase in theamounts of any effluents that may be released

offsite, or (iii) a significant increasein individual or cumulative occupational radiation exposure.

Accordingly, theproposed change meets the eligibility criterion for categorical exclusion set forthin 10 CFR 51.22(c)(9).

Therefore, pursuant to 10 CFR 51 .22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.5.0 References

1. TSTF-423, Revision 1, "Technical Specifications End States,NEDC-32988-A,"

dated December 22, 2009 (ADAMS Accession No.ML093570241).

2. Federal Register, Vol. 76, No. 34, p.9614, "Notice of Availability of theProposed Models for Plant-Specific Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1,'Technical Specifications End States, NEDC-32988-A,'

for BoilingWater Reactor Plants Using the Consolidated Line Item Improvement A1-9 Attachment i to NL-14-1 075Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications Process,"

dated December 22, 2009 (ADAMS Accession No.ML1 02730585).

3. NEDC-32988-A, Revision 2, "Technical Justification to Support Risk-Informed Modification to Selected Required Action End States forBWR Plants,"

December 2002 (ADAMS Package Accession No.ML0301 70090).4. NRC Model Safety Evaluation of TSTF-423, Revision 1, datedFebruary 2, 2011 (ADAMS Accession No. ML1 02730688).

5. NUREG-1433, "Standard Technical Specifications, General ElectricBWR/4 Plants."A1-10 Edwin I. Hatch Nuclear PlantLicense Amendment Request for Adoption of TSTF-423-A, Rev. 1,Technical Specifications End States, NEDC-32988-A, Attachment 2Summary of Regulatory Commitments Attachment 2 to NL-14-1 075Summary of Regulatory Commitments Summary of Regulatory Commitments The following tabie identifies the regulatory commitments in this document.

Anyother statements in this submittal represent intended or planned actions.

Theyare provided for information purposes and are not considered to be regulatory commitments.

REGULATORY COMMITMENTS DUE DATE / EVENT1. SNC will follow the guidance established in Section 11 of NUMARC To be implemented 93-01, "Industry Guidance for Monitoring the Effectiveness of with amendment Maintenance at Nuclear Power Plants,"

Nuclear Management andResource

Council, Revision 4A, April 2011.2. SNC will follow the guidance established in TSTF-IG-05-02, To be implemented Revision 2, "Implementation Guidance for TSTF-423, Revision 1, with amendment

'Technical Specifications End States, NEDC-32988-A"'",

with theexception that SNO will follow Regulatory Guide (RG) 1.160 in lieu ofRG 1.182, and SNC will follow Revision 4A of NUMARO 93-01 in lieuof Revision 3 of NUMARO 93-01.A2-1 Edwin I. Hatch Nuclear PlantLicense Amendment Request for Adoption of TSTF-423-A, Rev. 1,Technical Specifications End States, NEDC-32988-A, Attachment 3Markup Pages of Existing TS and Bases Showing Proposed Changes RPS Electric Power Monitoring 3.3.8.23.3 INSTRUMENTATION 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LCO 3.3.8.2APPLICABILITY:

Two RPS electric power monitoring assemblies shall be OPERABLE foreach inservice RPS motor generator set or alternate power supply.MODES 1, 2, and 3,MODES 4 and 5 with any control rod withdrawn from a core cellcontaining one or more fuel assemblies or with both residual heatremoval (RHR) shutdown cooling (SDC) isolation valves open.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One or both inservice A.1 Remove associated 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months spower supplies with one inservice powerelectric power monitoring supply(s) from service.assembly inoperable.

B. One or both inservice B.1 Remove associated 1 hourpower supplies with both inservice powerelectric power monitoring supply(s) from service.assemblies inoperable.

C. Required Action and C. Be in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sassociated Completion Time of Condition A or B not met in MODE 1, 2, or 3.* ~II Jl-#l __'-.......NOTE----LCO 3.0.4.a is notapplicable when enteringMODE 3.tconiinueo)

HATCH UNIT 1 3363.3-69 RPS Electric Power Monitoring 3.3.8.2INo change. Included forinformation only.ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIMED. Required Action and D.1 Initiate action to fully Immediately associated Completion insert all insertable Time of Condition A or B control rods in corenot met in MODE 4 or 5 cells containing one orwith any control rod more fuel assemblies.

withdrawn from a core cellcontaining one or more fuel ANDassemblies or with bothRHR SDC isolation valves D.2.1 Initiate action to restore Immediately open. one electric powermonitoring assembly toOPERABLE status forinservice powersupply(s) supplying requiredinstrumentation.

O__RD.2.2 Initiate action to isolate Immediately the RHR SDC.HATCH UNIT 13.3-70HATC UNI 1 33-70Amendment No. 266 I ECCS -Operating 3.5.13.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM3.5.1 ECCS -Operating LCO 3.5.1Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six of seven safety/relief valves shall be OPERABLE.

APPLICABILITY:

MODE 1,MODES 2 and 3, except high pressure coolant injection (HPCI) and ADSvalves are not required to be OPERABLE with reactor steamdome pressure

< 150 psig.--.......NOTE----LCO 3.0.4.a is notapplicable when enteringMODE 3.ACTIONS 'NLCO 3.0.4.b is not applicable to HPCI. lCONDITION REQUIRED ACTION COMPLETION TIMEA. One low pressure ECCS A.1 \ Restore low pressure 7 daysinjection/spray subsystem

\ ECCS injection/spray inoperable, subsystem toOPERABLE status.B. Required Action and B.1 BVe in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sassociated Completion Time of Condition A not met.B.2 n, MODE 4. C. HPCI System inoperable.

C.1 Verify by administrative 1 hourmeans RCIC System isOPERABLE.

ANDC.2 Restore HPCI System 14 daysto OPERABLE status.I(continued)

HATCH UNIT 13.5-1HATH NI 13-1Amc,.d,,c,.t

,N'. 246j ECCS -Operating 3.5.1ACTIONS (continued)

D. HPCI System inc~AND~One low pressurn~injection/spray si~is inoperable.

N REQUIRED ACTION [COMPLETION TIME)perable.

eECCSuibsystem FTwo or more ADS valvesinoperable.

to OPERABLE status.O__RD.2 Restore low pressureECCS injection/spray subsystem toOPERABLE status.MODE 3.AND reactor steamdome pressure to-<150 psig.tr LCO 3.0.3.72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s72 hours12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s36 hoursT.rn^ of C^ndition C or DftekfrL,,

,t.III~3m-I.Two or more low pressureECCS injection/spray subsystems inoperable.

O._RHPCI System and two ormore ADS valvesinoperable.

Immediately HATCH UNIT 1 .-3.5-2 TS 3.5.1 -Condition E InsertE. Required Action and E.1-----NOTE-

associated Completion LOC 3.0.4.a is not applicable Time of Condition C or D when entering MODE 3.not met.Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RCIC System3.5.33.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM3.5.3 RCIC SystemLCO 3.5.3APPLICABILITY:

The RCIC System shall be OPERABLE.

MODE 1,MODES 2 and 3 with reactor steam dome pressure

> 150 psig.ACTIONS.NOTE-LCO 3.0.4.b is not applicable to RCIC.CONDITION REQUIRED ACTION COMPLETION TIMEA. RCIC System inoperable.

A.1 Verify by administrative 1 hourmeans high pressurecoolant injection (HPCI)-.......NOTE ........System is OPERABLE.

LCO 3.0.4.a is not ANDapplicable when enteringMODE 3. Restore RCIC System 14 days*----------------------to OPERABLE status.B. Required Action and B.1 in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sassociated Completion

_____________

Time not met. {NHATCH UNIT 13.5-9HATCH NIT Nu,. 246 Reactor Building-to-Suppression Chamber Vacuum Breakers3.6.1.73.6 CONTAINMENT SYSTEMS3.6.1.7 Reactor Building-to-Suppression Chamber Vacuum BreakersLCO 3.6.1.7APPLICABILITY:

OPERABLE.

MODES 1, 2, and 3.ACTIONS-NOTE-Separate Condition entry is allowed for each line.CONDITION REQUIRED ACTION COMPLETION TIMEA. One or more lines with one A.1 Close the open vacuum 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sreactor building-to-breaker.suppression chambervacuum breaker not closed.B. One or more lines with two B.1 Close one open 1 hourreactor building-to-vacuum breaker.suppression chambervacuum breakers notclosed.C. One line with one or more C.1 Restore the vacuum 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sreactor building-to-breaker(s) tosuppression chamber OPERABLE status.vacuum breakersinoperable for opening.

with one or more ~ ~tore all vacuum 1 hourreactor building-to-breakers in one line tosuppression chamber OPERABLE status.vacuum breakersinoperable for opening.~INSERT -TS 3.6.1.7Condition D(continued)

HATCH UNIT 13.6-17HAT H NI I .6 17AuieidiieiL N o. 1951 TS 3.6.1.7 -Condition D InsertD. Required Action and D.1-----NOTE-

associated Completion LCO 3,0.4.a is not applicable Time of Condition C not when entering MODE 3.met.Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Reactor Building-to-Suppression Chamber Vacuum Breakers3.6.1.7ACTIONS (continued)

CONDITION Action and I-Associated Completion Time not met.{of Condition A, B, or EREQUIRED ACTIONCOMPLETION TIME4.ANDBe in MODE 3.Be in MODE 4.12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s36 hoursSURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.1

NOTES- ------1. Not required to be met for vacuumbreakers that are open duringSurveillances.

2. Not required to be met for vacuumbreakers open when performing theirintended function.

Verify each vacuum breaker is closed.In accordance withthe Surveillance Frequency ControlProgramSR 3.6.1.7.2 Perform a functional test of each vacuum breaker.

In accordance withthe Inservice Testing ProgramSR 3.6.1.7.3 Verify the opening setpoint of each vacuum In accordance withbreaker is < 0.5 psid. the Surveillance Frequency ControlProgramHATCH UNIT 13.6-18HATC UNI 1 36-18Amondmont No. 266{

Suppression Chamber-to-Drywell Vacuum Breakers3.6.1.83.6 CONTAINMENT SYSTEMS3.6.1.8 Suppression Chamber-to-Drywell Vacuum BreakersLCO 3.6.1.8Ten suppression chamber-to-drywell vacuum breakers shall beOPERABLE for opening.ANDTwelve suppression chamber-to-drywell vacuum breakers shall beclosed, except when performing their intended function.

APPLICABILITY:

MODES 1, 2, and 3.ACTIONS ________CONDITION REQUIRED ACTION COMPLETION TIMEA. One required suppression A.1 Restore one vacuum 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months schamber-to-drywell vacuum breaker to OPERABLEbreaker inoperable for status.opening.~~suppression chamber-EI1se the open vacuum 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months sto-drywell vacuum breaker breaker.not closed.,,D.11Required Action and Be in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s~associated Completion

/Time r,°t met"A DJ~f '--0f onitin j 1-4.[Be in MODE 4. 36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months sL INSERT -TS 3.6.1.8IICondition BHATCH UNIT 1 3613.6-19 TS 3.6.1.8.

-Condition B InsertB. Required Action and B.1-----NOTE--

-associated Completion LCO 3.0.4.a is not applicable Time of Condition A not when entering MODE 3.met.Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RHR Suppression Pool Cooling3.6.2.33.6 CONTAINMENT SYSTEMS3.6.2.3 Residual Heat Removal (RHR) Suppression Pool CoolingLCO 3.6.2.3APPLICABILITY:

Two RHR suppression pool cooling subsystems shall be OPERABLE.

MODES 1, 2, and 3.ACTIONSCONDITION I REQUIRED ACTION ICOMPLETION TIMEA. One RHR suppression poolcooling subsystem inoperable.

A.1Restore RHRsuppression poolcooling subsystem toOPERABLE status.7 daysB. RHR suppression poolS cooling subsystems inoperable.

I ieuiredi Action andassociated Completion Time Rot met.' Condition C/INSERT -TS 3.6.2.3/Condition BBA Rsore one RHRsuppression poolcooling subsystem toOPERABLE status.8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months siLU.Be n MODE 3.BinMODE 4.12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s36 hoursSURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling In accordance withsubsystem manual, power operated, and automatic the Surveillance valve in the flow path that is not locked, sealed, or Frequency Controlotherwise secured in position is in the correct Programposition or can be aligned to the correct position.

(continued)

HATCH UNIT 1 3623.6-25 TS 3.6.2.3 -Condition B InsertB. Required Action and BA-----NOTE-

associated Completion LCO 3.0.4.a is not applicable Time of Condition A not when entering MODE 3.met.Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RHR Suppression Pooi Spray3.6.2.43.6 CONTAINMENT SYSTEMS3.6.2.4 Residual Heat Removal (RHR) Suppression Pool SprayLCO 3.6.2.4APPLICABILITY:

Two RHR suppression pool spray subsystems shall be OPERABLE.

MODES 1, 2, and 3.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One RHR suppression pool A.1 Restore RHR 7 daysspray subsystem suppression pool sprayinoperable, subsystem toOPERABLE status.B. Two RHR suppression pool B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months spray subsystems suppression pool sprayinoperable, subsystem toOPERABLE status.C. Required Action and C.1 ../Be in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sassociated Completion

/Time not met.-NOTE------

LO3.0.4,a is not 0 .2 De i MODE 4. 36-hour Jlapplicable when enteringMODE 3.SURVEILLANCEREQUIREMENTS________

SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify each RHR suppression pool spray In accordance withsubsystem manual, power operated, and the Surveillance automatic valve in the flow path that is not locked, Frequency Controlsealed, or otherwise secured in position is in the Programcorrect position or can be aligned to the correctposition.

(continued)

HATCH UNIT 13.6-27HATC UNT-1 l6-7 A 1l II. 2CC/.LS./

Secondary Containment 3.6.4.13.6 CONTAINMENT SYSTEMS3.6.4.1 Secondary Containment LCO 3.6.4.1APPLICABILITY:

The secondary containment shall be OPERABLE.

-~NOTE----

LCO 3.0.4.a is notapplicable when enteringMODE 3.MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel--(OPDRVs).

ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. Secondary containment Restore secondary 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sinoperable in MODE 1, 2, \ containment toor 3. OPERABLE status.B. Required Action and B.1 "Be in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sassociated Completion Time of Condition A notmet.C. Secondary containment C.1------NOTE-------....

inoperable during LCO 3.0.3 is notmovement of irradiated fuel applicable.

assemblies in thesecondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuelOPDRVs. assemblies in thesecondary containment.

AND________________________

_______________________(continued)

HATCH UNIT 13.6-34HATCH UNIT 1 3.6-34 Amcndmcnt Nc. 256 I Secondary Containment 3.6.4.1No change. Included forinformation only.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEC. (continued)

C.2 Suspend CORE Immediately ALTERATIONS.

ANDC.3 Initiate action to Immediately suspend OPDR Vs.SURVEILLANCEREQUIREMENTS________

SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment equipment In accordance withhatches are closed and sealed. the Surveillance Frequency ControlProgramSR 3.6.4.1.2 Verify one secondary containment access door in In accordance witheach access opening is closed, the Surveillance Frequency ControlProgramSR 3.6.4.1.3--------------------NOTE-------------

The number of standby gas treatment (SGT)subsystem(s) required for this Surveillance isdependent on the secondary containment configuration, and shall be one less than thenumber required to meet LCO 3.6.4.3, "StandbyGas Treatment (SGT) System,"

for the givenconfiguration.

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

Frequency ControlProgram(continued)

HATCH UNIT 13.6-35HATC UNI 1 36-35Amendment No. 266 SGT System3.6.4.3No change. Included forinformation only.3.6 CONTAINMENT SYSTEMS3.6.4.3 Standby Gas Treatment (SGT) SystemLCO 3.6.4.3APPLICABILITY:

The Unit 1 and Unit 2 SGT subsystems required to support LCO 3.6.4.1,"Secondary Containment,"

shall be OPERABLE.

MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel(OPDRVs).

ACTIONS ___________

CONDITION REQUIRED ACTION COMPLETION TIMEA. One required Unit 1 SOT A.1 Restore required Unit 1 30 days fromsubsystem inoperable SOT subsystem to discovery of failure towhile: OPERABLE status. meet the LCO1. Four SOT subsystems required

OPERABLE, and2. Unit 1 reactor building-to-tefueling floor plugnot installed.

B. One required Unit 2 SGT B.1 Restore required SOT 7 dayssubsystem inoperable, subsystem toOPERABLE status. ANDO__R_30 days fromOne required Unit 1 SGT discovery of failure tosubsystem inoperable for meet the LCOreasons other thanCondition A.(continued)

HATCH UNIT 13.6-40HATC UNI 1 36-40Amendment No. 256 I

-NOTE-LCO 3.0.4.a is notapplicable when enteringMODE 3.SGT System3.6.4.3ACTIONS (continued)

CONDITION REUIRED ACTION COMPLETION TIMEC. Required Action and C.1 in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sassociated Completion Time of Condition A or B ANnot met in MODE 1, 2, or 3.0.2 De in ,vDE 4.D. Required Action and---------NOTE-----

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A or Bnot met during movement ofirradiated fuel assemblies in D.1 Place remaining Immediately the secondary containment, OPERABLE SGTduring CORE subsystem(s) inALTERATIONS, or during operation.

OPDR Vs.O__RD.2.1 Suspend movement of Immediately irradiated fuelassemblies insecondary containment.

ANDD.2.2 Suspend CORE Immediately ALTERATIONS."

-NOTE----LCO 3.0.4.a is notANapplicable when entering D23 Iiit cint meitlMODE 3._ D23 IiitacintImeael E. Two or more required SGT E.1 subsystems inoperable inMODE 1, 2, or 3. W4--(e n ODE 3.I ,1(continued)

HATCH UNIT 13.6-41HATCH.UNIT.1.3.6-41 II SGT System3.6.4.3No change. Included forinformation only.ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIMEF. Two or more required SGT F.1---------NOTE------

subsystems inoperable LCO 3.0.3 is notduring movement of applicable.

irradiated fuel assemblies inthe secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuelOPDRVs. assemblies insecondary containment.

ANDF.2 Suspend CORE Immediately ALTERATIONS.

ANDF.3 Initiate action to Immediately suspend OPDRVs.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each required SGT subsystem for In accordance with> 15 continuous minutes.

the Surveillance Frequency ControlProgramSR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance withwith the Ventilation Filter Testing Program (VFTP). the VFTPSR 3.6.4.3.3 Verify each required SGT subsystem actuates on In accordance withan actual or simulated initiation signal. the Surveillance Frequency ControlProgramHATCH UNIT 13.6-42HATC UNI 1 36-42Amendment No. 266 RHRSW System3.7.13.7 PLANT SYSTEMS3.7.1 Residual Heat Removal Service Water (RHRSW) SystemLCO 3.7.1Two RHRSW subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.ACTIONS_________________

___CONDITION REQUIRED ACTION COMPLETION TIMEA. One RHRSW pump A.1 Restore RHRSW pump 30 daysinoperable, to OPERABLE status.B. One RHRSW pump in each B.1 Restore one RHRSW 7 dayssubsystem inoperable, pump to OPERABLEstatus.C. One RHRSW subsystem-------------NOTE--------

inoperable for reasons Enter applicable Conditions andother than Condition A. Required Actions of LCO 3.4.7,"Residual Heat Removal (RHR)Shutdown Cooling System -HotShutdown,"

for RHR shutdowncooling tnade inoperable byRHRSW System.C.1 Restore RHRSW 7 dayssubsystem toOPERABLE status.

-TS 3.7.1Condition D(continued)

HATCH UNIT 137-3.7-1 TS 3.7.1 -Condition D InsertD. Required Action andassociated Completion Time of Condition A, B, orC not met.D.1----NOTE---

LCO 3.0.4.a is not applicable when entering MODE 3.Be in MODE 3.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RHRSW System3.7.1ACTIONS (continued)

CONDITION

] REQUIRED ACTION COMPLETION TIMEBoth RHRSW subsystems inoperable for reasonsother than Condition B.-----------------

NOTE-----

Enter applicable Conditions andRequired Actions of LCO 3.4.7for RHR shutdown cooling madeinoperable by RHRSW System.Eli-Restore one RHRSWsubsystem toOPERABLE status.8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months sRequired Action and Eiassociated Completion Ti me ln ot met.Iof Condition E4 4Be in MODE 3.AN~12 hours36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months sBe in MODE 4.SURVEILLANCE REQUIREMENTS

_______SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify each RHRSW manual, power operated, and In accordance withautomatic valve in the flow path, that is not locked, the Surveillance sealed, or otherwise secured in position, is in the Frequency Controlcorrect position or can be aligned to the correct Programposition.

HATCH UNIT 13.-3.7-2 PSW System and UHS3.7.23.7 PLANT SYSTEMS3.7.2 Plant Service Water (PSWV) System and Ultimate Heat Sink (UHS)LCO 3.7.2APPLICABILITY:

Two PSW subsystems and UHS shall be OPERABLE.

MODES 1, 2, and 3.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One PSW pump inoperable.

A.1 Restore PSW pump to 30 daysOPERABLE status.B. One PSW turbine building B.1 Restore PSW turbine 30 daysisolation valve inoperable, building isolation valveto OPERABLE status.C. One PSW pump in each C.1 Restore one PSW 7 dayssubsystem inoperable, pump to OPERABLEstatus.D. One PSW turbine building D.1 Restore one PSW 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sisolation valve in each turbine buildingsubsystem inoperable, isolation valve toOPERABLE status.\'INSERT

-TS 3.7.2Condition E(continued)

HATCH UNIT 13.7-3HATC UNI 1 Nu. 246 TS 3.7.2 -Condition E InsertE. Required Action and E. 1 --NOTE-................

associated Completion LCO 3.0.4.a is not applicable Time of Condition A, B, C, when entering MODE 3.or D not met.Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months PSW System and UHS3.7.2ACTIONS (continued)

CONDITION

{ REQUIRED ACTION JCOMPLETION TIMEOne PSW subsystem inoperable for reasonsother than Conditions Aand B.-~~NOTES---

1.Enter applicable Conditions and Required Actions ofLCO 3.8.1, "AC Sources -Operating,"

for dieselgenerator made inoperable by PSW System.2. Enter applicable Conditions and Required Actions ofLCO 3.4.7, "Residual HeatRemoval (RHR) ShutdownCooling System -HotShutdown,"

for RHRshutdown cooling madeinoperable by P3WSystem.Restore the PSWsubsystem toOPERABLE status.72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sIG.11--Required Action andassociated Completion Time of Condition

~Be in MODE 3.AND12 hours36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months sBe in MODE 4.O._RRBoth PSW subsystems inoperable for reasonsother than Conditions Cand D.OR_UHS inoperable.

HATCH UNIT 137-3.7-4 MCREC System3.7.43.7 PLANT SYSTEMS3.7.4 Main Control Room Environmental Control (MCREC) SystemNo change. Included forinformation only.LCO 3.7.4Two MCREC subsystems shall be OPERABLE.

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

The main control room envelope (ORE) boundary may be opened intermittently underadministrative control.APPLICABILITY:

MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel(OPDRVs).

ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One MCREC subsystem A.1 Restore MCREC 7 daysinoperable for reasons subsystem toother than Condition B. OPERABLE status.B. One or more MOREC B.1 Initiate action to Immediately subsystems inoperable due implement mitigating to inoperable CRE actions.boundary in MODE 1, 2,or3. ANDB.2 Verify mitigating actions 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sensure ORE occupantexposures toradiological,

chemical, and smoke hazards willnot exceed limits.ANDB.3 Restore ORE boundary 90 daysto OPERABLE status.(continued)

HATCH UNIT 13.7-8HATC UNI 1 37-8Amendment No. 268

-.......NOTE -LCO 3.0.4.a is notapplicable when enteringMODE 3.............

JICREC System3.7.4ACTIONS (continued)

CONDITION R UEDACTION COMPLETION TIMEC. Required Action and C.1 Be in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sassociated Completion Time of Condition A or B INnot met in MODE 1, 2, or 3.".2 Do in M,'ODE 4.3hor]D. Required Action and---------NOTE-----

associated Completion Time LCO 3.0.3 is not applicable.

of Condition A not metduring movement ofirradiated fuel assemblies in D.1 Place OPERABLE Immediately the secondary containment, MCREC subsystem induring CORE pressurization mode.ALTERATIONS, or duringOPDRVs. ORD.2.1 Suspend movement of Immediately irradiated fuelassemblies in thesecondary containment.

ANDD.2.2 Suspend CORE Immediately

________________ALTERATIONS.

-NOTE----

LCOG 3.0.4.a is not AND_lapplicable when enteringMODE 3. D.2.3 Initiate action to Immediatelysuspend OPDRVs.E. Two MCREC subsystems E.1 " lEntor LCO 3.0.3. ,,,,,,.,,,,

inoperable in MODE 1, 2,or 3 for reasons other than _ _Condition B. Be inMODE 3+"-- 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

HATCH UNIT 13.-3.7-9 MCREC System3.7.4No change. Included forinformation only.IAIR.TINN.q (pnnfinl r TCONDITION REQUIRED ACTIONCOMPLETION TIMEF. Two MCREC subsystems inoperable duringmovement of irradiated fuelassemblies in thesecondary containment, during COREALTERATIONS, or duringOPDR Vs.OROne or more MCRECsubsystems inoperable dueto an inoperable CREboundary during movementof irradiated fuel assemblies in the secondary containment, during COREALTERATIONS, or duringOPDRVs.-NOTE-----..........

LCO 3.0.3 is not applicable.

F.1 Suspend movement ofirradiated fuelassemblies in thesecondary containment.

ANDImmediately Immediately Immediately F.2Suspend COREALTERATIONS.

ANDF.3Initiate action tosuspend OPDRVs..L. I. ________________________

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREC subsystem

> 15 minutes.

In accordance withthe Surveillance Frequency ControlProgramSR 3.7.4.2 Perform required MCREC filter testing in In accordance withaccordance with the Ventilation Filter Testing the VFTPProgram (VFTP).SR 3.7.4.3 Verify each MCREC subsystem actuates on an In accordance withactual or simulated initiation signal. the Surveillance Frequency ControlProgram(continued)

HATCH UNIT 13.7-10HATC UNI 1 37-10Amendment No. 268 Control Room AC System3.7.53.7 PLANT SYSTEMS3.7.5 Control Room Air Conditioning (AC) SystemNo change. Included forinformation only.LCO 3.7.5APPLICABILITY:

Three control room AC subsystems shall be OPERABLE.

MODES 1, 2, and 3,During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel(OPDRVs).

ACTIONS ___________

CONDITION REQUIRED ACTION COMPLETION TIMEA. One control room AC A.1 Restore control room 30 dayssubsystem inoperable.

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

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

< 90°F.ANDC.2 Restore one control 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sroom AC subsystem toOPERABLE status.(continued)

HATCH UNIT 13.7-12HATC UNI I 37-12Amendment No. 270

-NOTE-.......

ILCO 3.0O4.a is notIapplicable when enteringIMODE 3.Control Room AC System3.7.5ACCOND~lITION XREQUIRED ACTIONCOMPLETION TIMED. Required Action and D. 1 Be in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sassociated Completion Time of Condition A, B, or AD-C not met in MODE 1, 2, or I3.D.. 9 nMD4.E. Required Action and---------------NOTE-------

associated Completion LCO 3.0.3 is not applicable.

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

during movement ofirradiated fuel assemblies in E.1 Place OPERABLE Immediately the secondary containment, control room ACduring CORE subsystems inALTERATIONS, or during operation.

OPDR Vs.OR_E.2.1 Suspend movement of Immediately irradiated fuelassemblies in thesecondary containment.

ANDE.2.2 Suspend CORE Immediately ALTERATIONS.

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

HATCH UNIT 1 3713.7-13 Main Condenser Offgas3.7.63.7 PLANT SYSTEMS3.7.6 Main Condenser OffgasLCO 3.7.6APPLICABILITY:

The gross gamma activity rate of the noble gases measured at the maincondenser evacuation system pretreatment monitor station shall be< 240 mCi/second.

MODE 1,MO DES 2 and 3 with any main steam line not isolated and steam jet airejector (SJAE) in operation.

ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. Gross gamma activity rate A.1 Restore gross gamma 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sof the noble gases not activity rate of the noblewithin limit, gases to within limit.B. Required Action and B.1 Isolate all main steam 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sassociated Completion lines.Time not met.____ ___ ____ ___ ORLCO 3.0.4.a is not B.2 Isolate SJAE. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sSapplicable when enteringMODE 3. ORR[ e in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sB.3JEm rHATCH UNIT 13.7-16HATCH UNI 1 3.7-16Amenid 11ent Nc.-9 AC Sources -Operating 3.8.13.8 LECTICALPOWE SYSEMSNo change. Included for3.8 LECRICL POER YSTMS information only.3.8.1 AC Sources -Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission networkand the Unit 1 onsite Class 1 E AC Electrical Power Distribution System;b. Two Unit 1 diesel generators (DGs);c. T-he swing DG;d. One Unit 2 DG capable of supplying power to one Unit 2 StandbyGas Treatment (SGT) subsystem required by LCO 3.6.4.3,"'SGT System;"e. One qualified circuit between the offsite transmission network andthe Unit 2 onsite Class 1 E AC Electrical Power Distribution subsystem(s) needed to support the Unit 2 SGT subsystem(s) required by LCO 3.6.4.3;f. Two D~s (any combination of Unit 2 DGs and the swing DG),each capable of supplying power to one Unit 1 low pressurecoolant injection (LPCI) valve load center; andg. One qualified circuit between the offsite transmission network andthe applicable onsite Class 1 E AC electrical power distribution subsystems needed tQ support each Unit I LPCI valve load centerrequired by LCO 3.5.1, "ECCS -Operating."

APPLICABILITY:

MODES 1, 2, and 3.HATCH UNIT 13.8-1HATC UNI 1 38-1Amendment No. 211 AC Sources -Operating 3.8.1No change. Included forinformation only.ACTIONSLCO 3.0.4.b is not applicable to DGs.CONDITION REQUIRED ACTION COMPLETION TIMEA. One required offsite circuit A.1 Perform SR 3.8.1.1 for 1 hourinoperable.

OPERABLE requiredoffsite circuits.

ANDOnce per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months sthereafter ANDA.2 Declare required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery feature(s) with no offsite of no offsite power toPower available one 4160 V ESF businoperable when the concurrent withredundant required inoperability offeature(s) are redundant requiredinoperable, feature(s)

ANDA.3 Restore required offsite 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months scircuit to OPERABLE,status.

AND17 days fromdiscovery of failure tomeet LCO 3.8.1.a, b,or cB. One Uniti1 or the swing B.1 Perform SR 3.8.1.1 for 1 hourDG inoperable.

OPERABLE requiredoffsite circuit(s).

ANDOnce per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months sthereafter AND_________________________(continued)

HATCH UNIT 13.8-2HATC UNI I 38-2Amendment No. 246 AC Sources -Operating 3.8.1No change. Included forinformation only.ACTIONSCONDITION REQUIRED ACTION (COMPLETION TIMEB. (continued)

B.2 Declare requiredfeature(s),

supported the inoperable DG,inoperable when theredundant requiredfeature(s) areinoperable.

byANDB.3.1 Determine OPERABLEDG(s) are notinoperable due tocommon cause failure.O__RB.3.2 Perform SR 3.8.1.2.a for OPERABLE DG(s).ANDB.4 Restore DG toOPERABLE status.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition Bconcurrent withinoperability ofredundant requiredfeature(s) 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s24 hours72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for aUnit 1 DC withthe swing DG notinhibited ormaintenance restrictions not metAND14 days for aUnit 1 DC withthe swing DCinhibited fromautomatically aligning toUnit 2 andmaintenance restrictions metAND72 hours for the swingdiesel withmaintenance restrictions not met(continued)

HATCH UNIT 13.8-3HATC UNI I 38-3Amendment No. 259 AC Sources -Operating 3.8.1No change. Included forinformation only.IACTIONSCONDITION IREQUIRED ACTION jCOMPLETION TIMEB. (continued)

B.4 (continued)

AND14 days for the swingdiesel withmaintenance restrictions metAND17 days fromdiscovery of failure tomeet LCO 3.8.1.a, b,or cC. One required Unit 2 DGinoperable C.1 Perform SR 3.8.1.1 forOPERABLE requiredoffsite circuit(s).

ANDC.2ANDC.3.1Declare requiredfeature(s),

supported bythe inoperable DG,inoperable when theredundant requiredfeature(s) are inoperable.

Determine OPERABLEDG(s) are not inoperable due to common causefailure.1 hourANDOnce per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months sthereafter 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition Cconcurrent within operability ofredundant requiredfeature(s) 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s24 hoursORC.3.2 Perform SR 3.8.1.2.a forOPERABLE DG(s).(continued)

HATCH UNIT 13.8-4HATC UNI I 38-4Amendment No. 259 AC Sources -Operating 3.8.1No change. Included forinformation only. IACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEC. (continued)

ANDC.4 Restore required DG to 7 days with theOPERABLE status. swing DG notinhibited or.maintenance restrictions not metAND14 days with theswing DG inhibited from automatically aligning to Unit 1 andmaintenance restrictions metD. Two or more required D.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from discovery off~site circuits inoperable, feature(s) with no off~site of Condition Dpower available concurrent withinoperable when the inoperability ofredundant required redundant requiredfeature(s) are feature(s) inoperable.

ANDD.2 Restore all but one 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months srequired offsite circuit toOPERABLE status.E. One required off~site circuit------NOTE---------L.....

inoperable.

Enter applicable Conditions andRequired Actions of LCO 3.8.7,AND "Distribution Systems -Operating,"

when Condition E isOne required DC entered with no AC power sourceinoperable, to one 4160 V ESF bus.E.1 Restore required off~site 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months scircuit to OPERABLEstatus.(continued)

HATCH UNIT 13.8-5HATC UNI I 38-5Amendment No. 259 AC Sources -Operating 3.8.1ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIMEE. (continued)

ORE.2 Restore required DG to 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sOPERABLE status.F. Two or more (Unit 1 and F.1 Restore all but one 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months swing) DGs inoperable.

Unit 1 and swing DGs toOPERABLE statusG. No DGs capable of G.1 Restore one DG 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months supplying power to any capable of supplying Unit 1 LPCI valve load power to Unit 1 LPCIcenter. valve load center toOPERABLE status.H. Required Action and H.1 in MODE 3.I 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sAssociated Completion Time of Condition A, B, C,AND, E, F, or G not met.One or more required 1.1A Enter LCO 3.0.3. Immediately offsite circuits and two or ___________

more required DGs / l.......NOTE-----

inoperable.

/ LCO 3.0.4.a is not when enteringOR / MODE 3.Two or more requiredoffsite circuits and onerequired___________________

_DG________inoperable.____I

__________________

HATCH UNIT 1 .-3.8-6 DC Sources -Operating 3.8.43.8 ELECTRICAL POWER SYSTEMS3.8.4 DC Sources -Operating No change. Included forinformation only.LCO 3.8.4The following DC electrical power subsystems shall be OPERABLE:

a. The Unit 1 Division 1 and Division 2 station service DCelectrical power subsystems;

b. The Unit 1 and the swing DGs DC electrical powersubsystems; andc. The Unit 2 DG DC electrical power subsystems needed tosupport the equipment required to be OPERABLE byLCO 3.6.4.3, "Standby Gas Treatment (SGT) System,"and LCO 3.8.1, "AC Sources -Operating."

APPLICABILITY:

MODES 1, 2, and 3.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. Swing DG DC electrical A.1 Restore DG DC 7 dayspower subsystem electrical powerinoperable due to subsystem toperformance of SR 3.8.4.7 OPERABLE status.or SR 3.8.4.8.OR_One or more requiredUnit 2 DG DC electrical power subsystems inoperable.

(continued)

HATCH UNIT 13.8-26HATC UNI 1 38-26Amendment No. 227 DC Sources -Operating 3.8.4ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIMEB. One Unit 1 DG DC B.1 Restore OG DC 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months selectrical power subsystem electrical powerinoperable, subsystem toOPERABLE status.ORR______

-- ---- ---NOTE----Swing DG DC electrical

/LCO 3.0.4.a is notpower subsystem r--applicable when enteringinoperable for reasonsMOE3 other than Condition A. MD3C. One Unit 1 station service C.1 \ Restore station service 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months sDC electrical power \ DC electrical powersubsystem inoperable, subsystem toOPERABLE status.D. Required Action and D.1 Be in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sAssociated Completion Time of Condition A, B, ANor C not met.E. Two or more DC electrical E.1 Enter LCO 3.0.3. Immediately power subsystems inoperable that result in aloss of function.

HATCH UNIT 1 3823.8-27 Distribution Systems -Operating 3.8.73.8 LECRICL PWERSYSEMSNo change. Included for3.8 LECRICA POER SSTES linformation only.3.8.7 Distribution Systems -Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shallbe OPERABLE:

a. Unit 1 AC and DC electrical power distribution subsystems comprised of:1. 4160V essential buses 1lE, 1iF, and 1iG;2. 600 V essential buses 1C and 1D;3. 120/208 V essential cabinets 1A and 1IB;4. 120/208 V instrument buses 1A and 1B;5. 125/250 V DC station service buses 1A and 1iB;6. DG DC electrical power distribution subsystems; andb. Unit 2 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE byLCO 3.6.4.3, "Standby Gas Treatment (SGT) System,"

andLCO 3.8.1, "AC Sources -Operating."

APPLICABILITY:

MODES 1, 2, and 3.ACTIONS ___________

CONDITION REQUIRED ACTION COMPLETION TIMEA. One or more required A.1 Restore required 7 daysUnit 2 AC or DC electrical Unit 2 AC and DCpower distribution subsystem(s) tosubsystems inoperable.

OPERABLE status.(continued)

HATCH UNIT 13.8-36HATC UNI I 38-36Amendment No. 227 Distribution Systems -Operating 3.8.7ACTIONS (continued)

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

OPERABLE status.16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months fromdiscovery of failure tomeet LCO 3.8.7.a0. One Unit 1 station service D.1 Restore Unit 1 station 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months sDC electrical power service DC electrical distribution subsystem power distribution ANDinoperable, subsystem toOPERABLE status. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months fromdiscovery of failure tomeet LCO 3.8.7.aE. Required Action andassociated Completion Time of Condition A, B, C,or D not met.F. Two or more electrical power distribution subsystems inoperable thatresult in a loss of function.

E.1 e nDMOE 3.12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sEnter LCO 3.0.3.Immediately LCO 3.0.4.a is notapplicable when enteringMODE 3.HATCH UNIT 1 3833.8-37I RPS Electric Power Monitoring 3.3.8.23.3 INSTRUMENTATION 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LCO 3.3.8.2APPLICABILITY:

Two RPS electric power monitoring assemblies shall be OPERABLE foreach inservice RPS motor generator set or alternate power supply.MODES 1, 2, and 3,MODES 4 and 5 with any control rod withdrawn from a core cellcontaining one or more fuel assemblies or with both residual heatremoval (RHR) shutdown cooling (SDC) isolation valves open.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One or both inservice A.1 Remove associated 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months spower supplies with one inservice powerelectric power monitoring supply(s) from service.assembly inoperable.

B. One or both inservice B.1 Remove associated 1 hourpower supplies with both inservice powerelectric power monitoring supply(s) from service.assemblies inoperable.

C. Required Action andassociated Completion Time of Condition A or Bnot met in MODE 1, 2, or 3.in MODE 3.12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s536-huurts pe vi IVRJLJL '*.(continued)

-NOTE----LCO 3.0.4.a is notapplicable when enteringMODE 3.HATCH UNIT 23.3-69HATH UIT 3.-69Amondmon'zt Noc. 210j I RPS Electric Power Monitoring 3.3.8.2No change. Included forinformation only.ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIMED. Required Action and D.1 Initiate action to fully Immediately associated Completion insert all insertable Time of Condition A or B control rods in corenot met in MODE 4 or 5 cells containing one orwith any control rod more fuel assemblies.

withdrawn from a core cellcontaining one or more fuel ANDassemblies or with bothRHR SDC isolation valves D.2.1 Initiate action to restore Immediately open. one electric powermonitoring assembly toOPERABLE status forinservice powersupply(s) supplying requiredinstrumentation.

O__8RD.2.2 Initiate action to isolate Immediately the RHR SDC.HATCH UNIT 23.3-70HATC UNI 2 33-70Amendment No. 210 I ECCS -Operating 3.5.13.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM3.5.1 ECCS -Operating LCO 3.5.1Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six of seven safety/relief valves shall be OPERABLE.

MODE 1,MODES 2 and 3, except high pressure coolant injection (HPCI) and ADSvalves are not required to be OPERABLE with reactor steamdome pressure

< 150 psig.APPLICABILITY:

ACTIONS-~~NOTE-----

ILCO 3.0.4.a is notlapplicable when enteringIMODE 3.

LCO 3.0.4.b is not applicable to HPCI.CONDITION

/REQUIRED ACTION COMPLETION TIMEA. One low pressure ECCS A.1 \Restore low pressure 7 daysinjection/spray subsystem ECCS injection/spray inoperable, subsystem toOPERABLE status.B. Required Action and B.1 Be in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sassociated Completion Time of Condition A notmet.C. HPCI System inoperable.

C.1 Verify by administrative 1 hourmeans RCIC System isOPERABLE.

ANDC.2 Restore HPCI System 14 daysto OPERABLE status.(continued)

IHATCH UNIT 23513.5-1 ECCS -Operating 3.5.1ACTIONS (continued)

D. HPCI System inc~AND~One low ~injection/spray st~inoperable.

Ei~Two or more AD:N REQUIRED ACTION [COMPLETION TIME3perable.

e ECCSuibsystem D.I Restore HPCI Systemto OPERABLE status.ORD.2 Restore low pressureECCS injection/spray subsystem toOPERABLE status.1in MODE 3.ANDE1 " duce reactor steamdome pressure to< 150 psig.72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s72 hoursS valves12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sinoperable.

T;11e ~.,f C~,d;t;c~

C ~r C36 hoursEnter LCO 3.0.3.Two or more low pressureECCS injection/spray subsystems inoperable.

ORHPCI System and two ormore ADS valvesinoperable.

Immediately HATCH UNIT 23.5-2HATC UNT 23.52 Anerirnnt G.

TS 3.5.1 -Condition E InsertE. Required Action and E.1-----NOTE-

associated Completion LCO 3.0.4a is not applicable Time of Condition C or D when entering MODE 3.not met.Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RCIC System3.5.33.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM3.5.3 RCIC SystemLCO 3.5.3The RCIC System shall be OPERABLE.

APPLICABILITY:

MODE 1,MODES 2 and 3 with reactor steam dome pressure

> 150 psig.ACTIONS-----------I4LCo 3.0.4.b is not applicable to RCIC.CONDITION REQUIRED ACTION COMPLETION TIMEA. RCIC System inoperable.

A.1 Verify by administrative 1 hourmeans high pressurecoolant injection (H PCI)NOTE............System is OPERABLE.

LCO 3.0.4.a is not ANDapplicable when enteringMODE 3. Restore RCIC System 14 days*----------------------to OPERABLE status.B. Required Action and B.1 "Be in MODE 3. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sassociated Completion Time not met. NHATCH UNIT 23.5-10HATCH UITI2I35-10 A IIImcI INcl. 210 Reactor Building-to-Suppression Chamber Vacuum Breakers3.6.1.73.6 CONTAINMENT SYSTEMS3.6.1.7 Reactor Building-to-Suppression Chamber Vacuum BreakersLCO 3.6.1.7APPLICABILITY:

OPERABLE.

MODES 1, 2, and 3.ACTIONS---------------------

'IJu ISeparate Condition entry is allowed for each line.CONDITION REQUIRED ACTION COMPLETION TIMEA. One or more lines with one A.1 Close the open vacuum 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sreactor building-to-breaker.suppression chambervacuum breaker not closed.B. One or more lines with two B.1 Close one open 1 hourreactor building-to-vacuum breaker.suppression chambervacuum breakers notclosed.C. One line with one or more C.1 Restore the vacuum 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months sreactor building-to-breaker(s) tosuppression chamber OPERABLE status.vacuum breakersinoperable for opening.lines with one or more EJ etore all vacuum 1 hourreactor building-to-breakers in one line tosuppression chamber OPERABLE status.vacuum breakersinoperable for opening./ pINSERT-TS 3.6.1.7IICondition DI(continued)

HATCH UNIT 2 3613.6-17 TS 3.6.1.7 -Condition D InsertD. Required Action and 0.1- -NOTE- ----associated Completion LCO 3.0.4a is not applicable Time of Condition C not when entering MODE 3.met.Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Reactor Building-to-Suppression Chamber Vacuum Breakers3.6.1.7ACTIONS (continued)

CONDITION REQUIRED ACTION [COMPLETION TIME Action andAssociated Completion Timr,71not met.Iof Condition A, B, or EBe in MODE 3.AND12 hours36 hour4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months sBe in MODE 4.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.1

NOTES--------

1. Not required to be met for vacuumbreakers that are open duringSurveillances.

2. Not required to be met for vacuumbreakers open when performing theirintended function.

Verify each vacuum breaker is closed.In accordance withthe Surveillance Frequency ControlProgramSR 3.6.1.7.2 Perform a functional test of each vacuum breaker.

In accordance withthe Inservice Testing ProgramSR 3.6.1.7.3 Verify the opening setpoint of each vacuum In accordance withbreaker is < 0.5 psid. the Surveillance Frequency ControlProgramHATCH UNIT 23.6-18HATCH UNIT 2 3.6-18 Amcncirncnt NG. 210 Charles R. PierceRegulatory Affairs DirectorSouthern NuclearOperating

Company, Inc.40 Inverness Center ParkwayPost Office Box 1295Birmingham, AL 35242Tel 205.992.7872 Fax 205.992.7601 SOUTHERN "NUCLEARA SOUTHERN COMPANYDEC 1 5 2015Docket Nos.: 50-32 150-366NL-14-1 075U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, D. C. 20555-001 Edwin I. Hatch Nuclear PlantLicense Amendment Request for Adoption of TSTF-423-A, Rev. 1Technical Specification End States, NEDC-32988-A Usin~q the Consolidated Line Item Improvement Process

Reference:

TSTF-423-A, Revision 1, "Technical Specifications End States,NEDC-32988-A,"

dated December 22, 2009.Ladies and Gentlemen:

In accordance with the provisions Title 10 of the Code of Federal Regulations (CFR), Section 50.90, Southern Nuclear Operating Company (SNC) is submitting a request for an amendment to the Hatch Nuclear Plant (HNP), Units 1 and 2,Technical Specifications (TS) to incorporate the NRC-approved, Technical Specification Task Force (TSTF) traveler, TSTF-423-A, Revision 1 (reference).

The proposed change would modify the TS to risk-inform requirements regarding selected Required Action end states by incorporating the Boiling Water Reactor(BWR) Owners' Group (BWROG) approved Topical Report NEDC-32988-A, Revision 2, "Technical Justification to Support Risk-Informed Modification toSelected Required End States for BWR Plants."

Additionally, the proposedamendment would modify the TS Required Actions with a Note prohibiting theuse of limiting condition for operation (LCO) 3.0.4.a when entering the preferred end state (Mode 3) on startup.* Attachment 1 provides a description and assessment of the proposedchange, the requested confirmation of applicability, and plant-specific verifications.

Attachment 2 summarizes the regulatory commitments made in thislicense amendment request.* Attachment 3 provides markup pages of existing TS and Bases to showthe proposed changes.* Attachment 4 provides revised (clean) TS pages.ACL(