Text

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. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN " NUCLEAR A SOUTHERN COMPANY DEC 1 5 2015 Docket Nos.: 50-32 1 50-366 NL-14-1 075 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-001 Edwin I. Hatch Nuclear Plant License Amendment Request for Adoption of TSTF-423-A, Rev. 1 Technical 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 to Selected Required End States for BWR Plants." Additionally, the proposed amendment would modify the TS Required Actions 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.* Attachment 1 provides a description and assessment of the proposed change, the requested confirmation of applicability, and plant-specific verifications.

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

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

In accordance with 10 CFR 50.91 (a)(1), "Notice for public comment," the analysis about the issue of no significant hazards consideration (NSHC) using the standards 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 this letter 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 Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.This letter contains Commitments, which are listed in Attachment

2. If you have any questions, please contact Ken McElroy at (205) 992-7369.Respectfully sbitd C. R. Pierce Regulatory Affairs Director CRP/RMJ Sworn to and subscribed before me this .j__ day of I ?t., 2015./Notary Public My commission expires: /6 -i- 1.ot" Attachments:

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

2. Summary of Regulatory Commitments

3. Markup Pages of Existing TS and Bases Showing Proposed Changes 4. Revised (Clean) TS Pages U. S. Nuclear Regulatory Commission NL-14-1075 Page 3 cc: Southern Nuclear Operatingi Company Mr. S. E. Kuczynski, Chairman, President

& CEO Mr. D. G. Bost, Executive Vice President

& Chief Nuclear Officer Mr. D. R. Vineyard, Vice President

-Hatch Mr. M. D. Meier, Vice President

-Regulatory Affairs Mr. D. R. Madison, Vice President

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

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

-Hatch State of Georgia Mr. J. H. Turner, Environmental Director Protection Division Edwin I. Hatch Nuclear Plant License Amendment Request for Adoption of TSTF-423-A, Rev. 1, Technical Specifications End States, NEDC-32988-A, Attachment 1 Assessment 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 Changes 1.0 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 and NPF-5, respectively.

The proposed amendment would, modify the HNP Technical Specifications (TS) to incorporate risk-inform requirements regarding selected Required Action end states. Additionally, it would modify the TS Required Actions 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 changes are 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 (ADAMS Accession Number ML093570241) (Reference I). The Federal Register notice published on February 18, 2011 (76 FR 34) (Reference

2) announced the availability of this TS improvement as part of the consolidated line item improvement process (CLIIP).2.0 Assessment

2.1 Applicability

of Topical R5eport NEDC-32988-A.

TSTF-423.

and Model Safety 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 part of the CLIIP. SNC has concluded that the information provided in the TR NEDC-32988 and TSTF-423, and the NRC staff's model safety evaluation are applicable 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. On November 27, 2012, the NRC published a Federal Register Notice stating that RG 1.182 has been withdrawn and the subject matter has been incorporated into RG 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." RG 1.160 endorses NUMARC 93-01, Revision 4A, dated April 2011.SNC assesses the risk of maintenance activities consistent with the guidance in RG 1.160. Therefore, the justification for adoption of TSTF-423 continues to be applicable.

'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'S model 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 be different between the generic Improved Standard Technicail Specifications (ISTS)A1-1 Attachment 1Ito NL-14-1 075 Assessment 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 2 specific TS; however, the justification for the proposed mode change remains directly applicable.

Additionally, in some cases there may be content differences between the ISTS and HNP TS due to plant-specific or historical reasons. These variations 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 for ISTS 3.4.3. As such, the changes identified in TSTF-423-A, Revision I for ISTS 3.4.3 are not suitable for adoption under the CLIIP process and are not 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 ISTS Conditions E and F. The changes identified in TSTF-423-A, Revision 1 for ISTS 3.5.1, new Condition G are therefore incorporated into HNP Unit 1 and 2 TS 3.5.1 as new Condition E, and references to Conditions E and F are omitted. Similarly, changes identified in TSTF-423-A for ISTS 3.5.1, new Condition H are incorporated into HNP Unit I and 2 TS 3.5.1, new Condition F. The End state Completion Time for modified Conditions E and F in HNP Unit 1 and 2 TS 3.5.1 are consistent with those evaluated in TR 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 TS 3.6.1.6).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 for one inoperable LLS valve, and it is not being proposed to be added by this amendment request. Requirements for two or more LLS valves inoperable are provided in ISTS Condition B, and reflected in TSTF-423-A, Revision 1 as new Condition C. This new Condition C is equivalent to HNP TS 3.6.1.6 Condition A. As such, the changes identified in TSTF-423-A, Revision 1 for ISTS 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 C The 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 gas treatment (SGT) subsystem is inoperable.

For HNP, the Unit 1 and 2 SGT Systems each consist of two fully redundant subsystems, each with its own set of dampers, charcoal filter train, and controls.

The Unit 1 and Unit 2 SOT Systems are shared between Units 1 and 2, and the SOT System on both units automatically start and operate in response to actuation signals A1-2 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 the system.As a result of the ability to share the four HNP Unit 1 and Unit 2 SGT subsystems between units, additional combinations of SGT equipment inoperability are possible that are not reflected in ISTS 3.6.4.3, and the requirements in ISTS 3.6.4.3, Condition A are represented in HNP Unit 1 and 2 TS 3.6.4.3 as Conditions A and B. This difference results in renumbering of the Conditions in HNP Unit 1 and 2 TS 3.6.4.3 relative to those in TSTF-423-A.

Changes identified in TSTF-423-A, Revision 1 for ISTS 3.6.4.3, Condition B are incorporated into the HNP Unit 1 and 2 TS 3.6.4.3, Condition C. The changes identified in TSTF-423-A for ISTS 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 HNP Unit I and 2 TS 3.6.4.3 are consistent with those evaluated in TR NEDC-32988, and provided in TSTF-423-A, Revision 1.6. ISTS TS 3.7.2, Plant Service Water and Ultimate Heat Sink, Conditions C and G (HNP TS 3.6.1.6. Conditions E and G)HNP TS 3.7.2, Conditions B and 0, provide requirements when one plant service water turbine building isolation valve is inoperable in one or each plant service water (PSW) subsystem.

These Conditions reflect plant-specific features of the HNP Unit 1 and 2 design, and ISTS 3.7.2 does not include similar Conditions.

Additionally, ISTS TS 3.7.2 includes Conditions for inoperability of cooling tower fans (Condition C) and ultimate heat sink water temperature (Condition D) that are not included or necessary in the HNP Unit 1 and 2 TS due to plant-specific differences in the PSW system design.*These differences result in renumbering of the Conditions in HNP TS 3.7.2 relative 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 and 2 TS 3.7.5, Condition E, and plant-specific Conditions B and 0 are adopted within this Condition.

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

The end state Completion Time for modified 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) system design consists of two 100% control room AC subsystems.

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

With one control room AC subsystem inoperable, the two remaining control room AC subsystems provide 100% of the required capacity.

With two subsystems inoperable, control room AC capability is diminished, but remains capable of providing 50% of the required capacity.This plant-specific design difference, and the historical licensing basis for HNP Units 1 and 2 are reflected in HNP Unit 1 and 2 TS 3.7.5.

Attachment 1Ito NL-14-1 075 Assessment 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 end state Completion Time for modified Conditions D in HNP Unit 1 and 2 TS 3.7.5 are consistent with those evaluated in TR NEDC-32988, and provided in TSTF-423-A, Revision 1.ISTS 3.7.5 Condition D provides actions when both (all) control room AC subsystems are inoperable.

The analogous Condition was removed from HNP Unit 1 and 2 TS 3.7.5 in license amendment 270/2 14 (ADAMS Accession No. ML14279A261), with the adoption of changes described in TSTF-477.

The changes identified in TSTF-423-A, Revision 1 for ISTS 3.7.5, Condition D are therefore not incorporated into HNP Unit 1 and 2 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 that provided in TSTF.-423-A, Revision 1 for ISTS 3.8.1. HNP Unit I and 2 TS 3.8.1 provides an additional condition (Condition C) for inoperability of one required diesel generator (DG) on the opposite unit that does not appear in ISTS 3.8.1. HNP Unit I and 2 TS 3.8.1 also provides an add itionaJ condition (Condition G) for the situation where there are no DGs capable of providing power to any low pressure coolant injection valve load centers that does not appear in ISTS 3.8.1. Additionally, ISTS 3.8.1 includes 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 HNP licensing basis.These differences result in renumbering of the Conditions in HNP TS 3.8.1 relative 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 and 2 TS 3.8.1, Condition H, and plant-specific Conditions C and G are adopted within this Condition.

The end state Completion Time for modified Condition 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 that provided 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 that render one or more DG or station service DC electrical subsystems inoperable, including battery or charger inoperability.

End state requirements are provided in ISTS 3.8.4, Condition D when the requirements of Condition A, B, or C are not met for a station service DC electrical 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 when conditions exist that render a OG or station service DC electrical subsystem inoperable.

End state requirements are provided in ISTS 3.8.4, Condition 0 when the requirements of Condition A, B, or C are not met for a station service DC electrical subsystem, and ISTS 3.8.4, Condition E provides actions when the requirements of Condition A, B, or C are not met for a DG DC 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 end state Completion Time for modified Condition D in HNP Unit 1 and 2 TS 3.8.4 is consistent with those evaluated in TR NEDC-32988, and provided in TSTF-423-A, Revision 1.10. ISTS TS 3.8.7, Inverters

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

The changes identified in TSTF-423-A, Revision 1 for ISTS TS 3.8.7 are therefore not adopted.11. ISTS TS 3.8.9, Distribution Systems -Operatingq, Condition D (HNP TS 3.8.7. Condition E)The structure and content of Conditions in HNP TS 3.8.7 differs from that provided 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 DC electrical power distribution subsystems is inoperable, or one or more AC vital buses is inoperable.

End state requirements are provided in ISTS 3.8.9, Condition D when the requirements of Conditions A, B, or C are not 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 DC electrical power distribution subsystem inoperable.

End state requirements are provided in HNP TS 3.8.7, Condition E when the requirements of Condition 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 end state Completion Time for modified Condition E in HNP Unit 1 and 2 TS 3.8.7 is consistent with those evaluated in TR NEDC-32988, and provided 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 HNP Unit 2 was licensed to the requirements of 10 CFR 50, Appendix A, GDC, HNP Unit 1 was not. The HNP Unit 1 construction permit was received under the 70 general 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-14-1 075 Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications 10 CFR 50, Appjendix A, General Design Criteria Criterion 17, "Electric Power Systems," states: An onsite electric power system and an offsite electric power system shall be provided to permit functioning of structures, systems, and components important to safety. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to assure that (1) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences and (2) the core is cooled and containment integrity and other vital functions are maintained in the event of postulated accidents.

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

A switchyard common to both circuits is acceptable.

Each of these circuits shall be designed to be available in sufficient time following a loss of all onsite alternating current power supplies and the other offsite electric power circuit, to assure that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded.

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

Provisions shall be included to minimize the probability of losing electric power 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 power from the transmission network, or the loss of power from the onsite electric 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 of power shall be provided to permit the required functioning of the protection systems.A1-6 Attachment 1Ito NL-1 4-1 075 Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications

3.0 Regqulatory

Analysis 3.1 No Si~qnificant Hazards Consideration Southern Nuclear Corporation (SNC) has evaluated the proposed changes to the TS using the criteria in 10 CFR 50.92 and has determined that the proposed changes do not involve a significant hazards consideration.

Description of Amendment Request: A change is proposed to the TS for HNP, Units I and 2, consistent with TSTF-423, Revision 1, to allow, for some systems, entry into hot shutdown rather than cold shutdown to repair equipment, if risk is assessed and managed consistent with the program in place for complying with the requirements of 10 CFR 50.65(a)(4).

Changes proposed in TSTF-423 will be made to the TS 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 no significant hazards consideration is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response:

No The proposed change allows a change to certain required end states when the TS Completion Times for remaining in power operation will be exceeded.

Most of the requested technical specification (TS) changes are to permit an end state of hot shutdown (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 a short interval, (2) entry is initiated by inoperability of a single train of equipment or a restriction on-a plant operational parameter, unless otherwise stated in the applicable TS, and (3) the primary purpose is to correct the initiating condition and return to power operation as soon as is practical.

Risk insights from both the qualitative and quantitative risk assessments were used in specific TS assessments.

Such assessments are documented in Section 6 of topical report NEDC-32988-A, Revision 2, "Technical Justification to Support Risk Informed Modification to Selected Required Action End States for BWR Plants." They provide an integrated discussion of deterministic and probabilistic issues, focusing on specific TSs, which are used to support the proposed TS end state and associated restrictions.

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

Therefore, the probability of an accident previously evaluated is A1-7 Attachment 1Ito NL-14-1 075 Assessment of Proposed Change, Confirmation of Applicability, and Plant-Specific Verifications not significantly increased, if at all. The consequences of an accident after adopting TSTF-423 are no different than the consequences 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 a requirement to assess and manage the risk introduced by this change will further minimize possible concerns.Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

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

Response:

No The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be installed).

If risk is assessed and managed, allowing a change to certain required end states when the TS Completion Times for remaining in power operation are exceeded (i.e., entry into hot shutdown rather than cold shutdown to repair equipment) will not introduce new failure modes or effects and will not, in the absence of other unrelated failures, lead to an accident whose consequences exceed the consequences of accidents previously evaluated.

The addition of a requirement to assess and manage the risk introduced by this change and the commitment by the licensee to adhere to the guidance in TSTF-IG-05-02, "Implementation Guidance for TSTF-423, Revision 1, 'Technical Specifications End States, NEDC-32988-A,'" will further minimize possible concerns.Thus, based on the above, this change does not create the possibility of a new or different kind of accident from an accident previously evaluated.

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

No The proposed change allows, for some systems, entry into hot shutdown rather than cold shutdown to repair equipment, if risk is assessed and managed. The Boiling Water Reactor Owners'Group's risk assessment approach is comprehensive and follows NRC staff guidance as documented in Regulatory Guides (RG)1.174 and 1.177. In addition, the analyses show that the criteria of the three-tiered approach for allowing TS changes are met. The risk impact of the proposed TS changes was assessed following the three-tiered approach recommended in RG 1.177. A risk A1-8 Attachment i to NL-14-1 075 Assessment 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 the requested change involves no significant hazards consideration, as set forth in 10 CFR 50.92(c), "Issuance of Amendment." 3.2 Verifications, Commitments, and Additional Information Needed SNO 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 the new requirements.

Implementation of TSTF-423 requires that risk be managed and assessed, and the configuration risk management program is adequate to satisfy this requirement.

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

Finally, SNC has a Bases Control Program 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 or use of a facility component located within the restricted area, as defined in 10g CFR Part 20, and would change an inspection or surveillance requirement.

However, the proposed change does not involve significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 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 the Proposed Models for Plant-Specific Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1,'Technical Specifications End States, NEDC-32988-A,'

for Boiling Water Reactor Plants Using the Consolidated Line Item Improvement A1-9 Attachment i to NL-14-1 075 Assessment 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 for BWR Plants," December 2002 (ADAMS Package Accession No.ML0301 70090).4. NRC Model Safety Evaluation of TSTF-423, Revision 1, dated February 2, 2011 (ADAMS Accession No. ML1 02730688).

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

Any other statements in this submittal represent intended or planned actions. They are provided for information purposes and are not considered to be regulatory commitments.

REGULATORY COMMITMENTS DUE DATE / EVENT 1. 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 and Resource 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 the exception that SNO will follow Regulatory Guide (RG) 1.160 in lieu of RG 1.182, and SNC will follow Revision 4A of NUMARO 93-01 in lieu of Revision 3 of NUMARO 93-01.A2-1 Edwin I. Hatch Nuclear Plant License Amendment Request for Adoption of TSTF-423-A, Rev. 1, Technical Specifications End States, NEDC-32988-A, Attachment 3 Markup Pages of Existing TS and Bases Showing Proposed Changes RPS Electric Power Monitoring 3.3.8.2 3.3 INSTRUMENTATION 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LCO 3.3.8.2 APPLICABILITY:

Two RPS electric power monitoring assemblies shall be OPERABLE for each 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 cell containing one or more fuel assemblies or with both residual heat removal (RHR) shutdown cooling (SDC) isolation valves open.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both inservice A.1 Remove associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power supplies with one inservice power electric power monitoring supply(s) from service.assembly inoperable.

B. One or both inservice B.1 Remove associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months power supplies with both inservice power electric power monitoring supply(s) from service.assemblies inoperable.

C. Required Action and C. Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.* ~II Jl-#l __'-.......NOTE----LCO 3.0.4.a is not applicable when entering MODE 3.tconiinueo)

HATCH UNIT 1 336 3.3-69 RPS Electric Power Monitoring 3.3.8.2 INo change. Included for information only.ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to fully Immediately associated Completion insert all insertable Time of Condition A or B control rods in core not met in MODE 4 or 5 cells containing one or with any control rod more fuel assemblies.

withdrawn from a core cell containing one or more fuel AND assemblies or with both RHR SDC isolation valves D.2.1 Initiate action to restore Immediately open. one electric power monitoring assembly to OPERABLE status for inservice power supply(s) supplying required instrumentation.

O__R D.2.2 Initiate action to isolate Immediately the RHR SDC.HATCH UNIT 1 3.3-70 HATC UNI 1 33-70Amendment No. 266 I ECCS -Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS -Operating LCO 3.5.1 Each 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 ADS valves are not required to be OPERABLE with reactor steam dome pressure < 150 psig.--.......NOTE----LCO 3.0.4.a is not applicable when entering MODE 3.ACTIONS 'N LCO 3.0.4.b is not applicable to HPCI. l CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 \ Restore low pressure 7 days injection/spray subsystem

\ ECCS injection/spray inoperable, subsystem to OPERABLE status.B. Required Action and B.1 BVe in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met.B.2 n, MODE 4. C. HPCI System inoperable.

C.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months means RCIC System is OPERABLE.AND C.2 Restore HPCI System 14 days to OPERABLE status.I (continued)

HATCH UNIT 1 3.5-1 HATH NI 13-1Amc,.d,,c,.t ,N'. 246j ECCS -Operating 3.5.1 ACTIONS (continued)

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

N REQUIRED ACTION [COMPLETION TIME)perable.eECCS uibsystem F Two or more ADS valves inoperable.

to OPERABLE status.O__R D.2 Restore low pressure ECCS injection/spray subsystem to OPERABLE status.MODE 3.ANDreactor steam dome pressure to-<150 psig.tr LCO 3.0.3.72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 72 hours 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours T.rn^ of C^ndition C or D ftekfrL,, ,t.I I I~3 m-I.Two or more low pressure ECCS injection/spray subsystems inoperable.

O._R HPCI System and two or more ADS valves inoperable.

Immediately HATCH UNIT 1 .-3.5-2 TS 3.5.1 -Condition E Insert E. 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 System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LCO 3.5.3 APPLICABILITY:

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 TIME A. RCIC System inoperable.

A.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months means high pressure coolant injection (HPCI)-.......NOTE ........System is OPERABLE.LCO 3.0.4.a is not AND applicable when entering MODE 3. Restore RCIC System 14 days*----------------------to OPERABLE status.B. Required Action and B.1 in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion

_____________

Time not met. {N HATCH UNIT 1 3.5-9 HATCH NIT Nu,. 246 Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.7 3.6 CONTAINMENT SYSTEMS 3.6.1.7 Reactor Building-to-Suppression Chamber Vacuum Breakers LCO 3.6.1.7 APPLICABILITY:

OPERABLE.MODES 1, 2, and 3.ACTIONS-NOTE-Separate Condition entry is allowed for each line.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more lines with one A.1 Close the open vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months reactor building-to-breaker.suppression chamber vacuum breaker not closed.B. One or more lines with two B.1 Close one open 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reactor building-to-vacuum breaker.suppression chamber vacuum breakers not closed.C. One line with one or more C.1 Restore the vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months reactor building-to-breaker(s) to suppression chamber OPERABLE status.vacuum breakers inoperable for opening.

with one or more ~ ~tore all vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reactor building-to-breakers in one line to suppression chamber OPERABLE status.vacuum breakers inoperable for opening.~INSERT -TS 3.6.1.7 Condition D (continued)

HATCH UNIT 1 3.6-17 HAT H NI I .6 17AuieidiieiL N o. 1951 TS 3.6.1.7 -Condition D Insert D. 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 Breakers 3.6.1.7 ACTIONS (continued)

CONDITION Action and I-Associated Completion Time not met.{of Condition A, B, or E REQUIRED ACTION COMPLETION TIME 4.AND Be in MODE 3.Be in MODE 4.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.1--------------

NOTES- ------1. Not required to be met for vacuum breakers that are open during Surveillances.

2. Not required to be met for vacuum breakers open when performing their intended function.Verify each vacuum breaker is closed.In accordance with the Surveillance Frequency Control Program SR 3.6.1.7.2 Perform a functional test of each vacuum breaker. In accordance with the Inservice Testing Program SR 3.6.1.7.3 Verify the opening setpoint of each vacuum In accordance with breaker is < 0.5 psid. the Surveillance Frequency Control Program HATCH UNIT 1 3.6-18 HATC UNI 1 36-18Amondmont No. 266{

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

MODES 1, 2, and 3.ACTIONS ________CONDITION REQUIRED ACTION COMPLETION TIME A. One required suppression A.1 Restore one vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months chamber-to-drywell vacuum breaker to OPERABLE breaker inoperable for status.opening.~~suppression chamber- EI 1se the open vacuum 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to-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 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months L INSERT -TS 3.6.1.8I ICondition B HATCH UNIT 1 361 3.6-19 TS 3.6.1.8. -Condition B Insert B. Required Action and B.1-----NOTE--

-associated Completion LCO 3.0.4.a is not applicable Time of Condition A not when entering MODE 3.met.Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months RHR Suppression Pool Cooling 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 APPLICABILITY:

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

A.1 Restore RHR suppression pool cooling subsystem to OPERABLE status.7 days B. RHR suppression pool S cooling subsystems inoperable.

I ieuiredi Action and associated Completion Time Rot met.' Condition C/INSERT -TS 3.6.2.3/Condition B BA Rsore one RHR suppression pool cooling subsystem to OPERABLE status.8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months si LU.Be n MODE 3.BinMODE 4.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling In accordance with subsystem manual, power operated, and automatic the Surveillance valve in the flow path that is not locked, sealed, or Frequency Control otherwise secured in position is in the correct Program position or can be aligned to the correct position.(continued)

HATCH UNIT 1 362 3.6-25 TS 3.6.2.3 -Condition B Insert B. 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 Spray 3.6.2.4 3.6 CONTAINMENT SYSTEMS 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray LCO 3.6.2.4 APPLICABILITY:

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

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

LO3.0.4,a is not 0 .2 De i MODE 4. 36-hour J lapplicable when entering MODE 3.SURVEILLANCEREQUIREMENTS________

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

HATCH UNIT 1 3.6-27 HATC UNT-1 l6-7 A 1 l II. 2CC/.LS./

Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 APPLICABILITY:

The secondary containment shall be OPERABLE.-~NOTE----

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

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

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

AND________________________

_______________________(continued)

HATCH UNIT 1 3.6-34 HATCH UNIT 1 3.6-34 Amcndmcnt Nc. 256 I Secondary Containment 3.6.4.1 No change. Included for information only.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)

C.2 Suspend CORE Immediately ALTERATIONS.

AND C.3 Initiate action to Immediately suspend OPDR Vs.SURVEILLANCEREQUIREMENTS________

SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify all secondary containment equipment In accordance with hatches are closed and sealed. the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify one secondary containment access door in In accordance with each access opening is closed, the Surveillance Frequency Control Program SR 3.6.4.1.3--------------------NOTE-------------

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

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

HATCH UNIT 1 3.6-35 HATC UNI 1 36-35Amendment No. 266 SGT System 3.6.4.3 No change. Included for information only.3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 APPLICABILITY:

The Unit 1 and Unit 2 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 TIME A. One required Unit 1 SOT A.1 Restore required Unit 1 30 days from subsystem inoperable SOT subsystem to discovery of failure to while: OPERABLE status. meet the LCO 1. Four SOT subsystems required OPERABLE, and 2. Unit 1 reactor building-to-tefueling floor plug not installed.

B. One required Unit 2 SGT B.1 Restore required SOT 7 days subsystem inoperable, subsystem to OPERABLE status. AND O__R_30 days from One required Unit 1 SGT discovery of failure to subsystem inoperable for meet the LCO reasons other than Condition A.(continued)

HATCH UNIT 1 3.6-40 HATC UNI 1 36-40Amendment No. 256 I

-NOTE-LCO 3.0.4.a is not applicable when entering MODE 3.SGT System 3.6.4.3 ACTIONS (continued)

CONDITION REUIRED ACTION COMPLETION TIME C. Required Action and C.1 in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B AN not 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 B not met during movement of irradiated fuel assemblies in D.1 Place remaining Immediately the secondary containment, OPERABLE SGT during CORE subsystem(s) in ALTERATIONS, or during operation.

OPDR Vs.O__R D.2.1 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS."-NOTE----LCO 3.0.4.a is notAN applicable when entering D23 Iiit cint meitl MODE 3._ D23 IiitacintImeael E. Two or more required SGT E.1 subsystems inoperable in MODE 1, 2, or 3. W4--(e n ODE 3.I ,1 (continued)

HATCH UNIT 1 3.6-41 HATCH.UNIT.1.3.6-41 II SGT System 3.6.4.3 No change. Included for information only.ACTIONS (continued)

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

subsystems inoperable LCO 3.0.3 is not during movement of applicable.

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

AND F.2 Suspend CORE Immediately ALTERATIONS.

AND F.3 Initiate action to Immediately suspend 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 Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance with with the Ventilation Filter Testing Program (VFTP). the VFTP SR 3.6.4.3.3 Verify each required SGT subsystem actuates on In accordance with an actual or simulated initiation signal. the Surveillance Frequency Control Program HATCH UNIT 1 3.6-42 HATC UNI 1 36-42Amendment No. 266 RHRSW System 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System LCO 3.7.1 Two RHRSW subsystems shall be OPERABLE.APPLICABILITY:

MODES 1, 2, and 3.ACTIONS_________________

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

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

HATCH UNIT 137-3.7-1 TS 3.7.1 -Condition D Insert D. Required Action and associated Completion Time of Condition A, B, or C 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 System 3.7.1 ACTIONS (continued)

CONDITION

] REQUIRED ACTION COMPLETION TIME Both RHRSW subsystems inoperable for reasons other than Condition B.-----------------

NOTE-----Enter applicable Conditions and Required Actions of LCO 3.4.7 for RHR shutdown cooling made inoperable by RHRSW System.Eli-Restore one RHRSW subsystem to OPERABLE status.8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months sRequired Action and Ei associated Completion Ti me ln ot met.Iof Condition E 4 4 Be in MODE 3.AN~12 hours 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Be in MODE 4.SURVEILLANCE REQUIREMENTS

_______SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify each RHRSW manual, power operated, and In accordance with automatic valve in the flow path, that is not locked, the Surveillance sealed, or otherwise secured in position, is in the Frequency Control correct position or can be aligned to the correct Program position.HATCH UNIT 13.-3.7-2 PSW System and UHS 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Plant Service Water (PSWV) System and Ultimate Heat Sink (UHS)LCO 3.7.2 APPLICABILITY:

Two PSW subsystems and UHS shall be OPERABLE.MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One PSW pump inoperable.

A.1 Restore PSW pump to 30 days OPERABLE status.B. One PSW turbine building B.1 Restore PSW turbine 30 days isolation valve inoperable, building isolation valve to OPERABLE status.C. One PSW pump in each C.1 Restore one PSW 7 days subsystem inoperable, pump to OPERABLE status.D. One PSW turbine building D.1 Restore one PSW 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months isolation valve in each turbine building subsystem inoperable, isolation valve to OPERABLE status.\'INSERT -TS 3.7.2 Condition E (continued)

HATCH UNIT 1 3.7-3 HATC UNI 1 Nu. 246 TS 3.7.2 -Condition E Insert E. Required Action and E. 1 --NOTE-................

associated Completion LCO 3.0.4.a is not applicable Time of Condition A, B, C, when entering MODE 3.or 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 UHS 3.7.2 ACTIONS (continued)

CONDITION

{ REQUIRED ACTION JCOMPLETION TIME One PSW subsystem inoperable for reasons other than Conditions A and B.-~~NOTES---

1.Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources -Operating," for diesel generator made inoperable by PSW System.2. Enter applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System -Hot Shutdown," for RHR shutdown cooling made inoperable by P3W System.Restore the PSW subsystem to OPERABLE status.72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months IG.11--Required Action and associated Completion Time of Condition

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

HATCH UNIT 137-3.7-4 MCREC System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Main Control Room Environmental Control (MCREC) System No change. Included for information only.LCO 3.7.4 Two MCREC subsystems shall be OPERABLE.-- -------NOTE-----------....................................

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

MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MCREC subsystem A.1 Restore MCREC 7 days inoperable for reasons subsystem to other than Condition 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. AND B.2 Verify mitigating actions 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ensure ORE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.AND B.3 Restore ORE boundary 90 days to OPERABLE status.(continued)

HATCH UNIT 1 3.7-8 HATC UNI 1 37-8Amendment No. 268

-.......NOTE -LCO 3.0.4.a is not applicable when entering MODE 3.............

JICREC System 3.7.4 ACTIONS (continued)

CONDITION R UEDACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B IN not 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 met during movement of irradiated fuel assemblies in D.1 Place OPERABLE Immediately the secondary containment, MCREC subsystem in during CORE pressurization mode.ALTERATIONS, or during OPDRVs. OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND D.2.2 Suspend CORE Immediately

________________ALTERATIONS.-NOTE----LCOG 3.0.4.a is not AND_lapplicable when entering MODE 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 System 3.7.4 No change. Included for information only.I AIR.TINN.q (pnnfinl r T CONDITION REQUIRED ACTION COMPLETION TIME F. Two MCREC subsystems inoperable during movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDR Vs.OR One or more MCREC subsystems inoperable due to an inoperable CRE boundary during movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs.-NOTE-----..........

LCO 3.0.3 is not applicable.

F.1 Suspend movement of irradiated fuel assemblies in the secondary containment.

AND Immediately Immediately Immediately F.2 Suspend CORE ALTERATIONS.

AND F.3 Initiate action to suspend OPDRVs..L. I. ________________________

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each MCREC subsystem

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

HATCH UNIT 1 3.7-10 HATC UNI 1 37-10Amendment No. 268 Control Room AC System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Control Room Air Conditioning (AC) System No change. Included for information only.LCO 3.7.5 APPLICABILITY:

Three control room AC subsystems shall be OPERABLE.MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).ACTIONS ___________

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

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

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

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

HATCH UNIT 1 3.7-12 HATC UNI I 37-12Amendment No. 270

-NOTE-.......

ILCO 3.0O4.a is not Iapplicable when entering IMODE 3.Control Room AC System 3.7.5 AC COND~lITION XREQUIRED ACTION COMPLETION TIME D. Required Action and D. 1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B, or AD-C not met in MODE 1, 2, or I 3.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 of irradiated fuel assemblies in E.1 Place OPERABLE Immediately the secondary containment, control room AC during CORE subsystems in ALTERATIONS, or during operation.

OPDR Vs.OR_E.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND E.2.2 Suspend CORE Immediately ALTERATIONS.

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

HATCH UNIT 1 371 3.7-13 Main Condenser Offgas 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Main Condenser Offgas LCO 3.7.6 APPLICABILITY:

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

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Gross gamma activity rate A.1 Restore gross gamma 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the noble gases not activity rate of the noble within limit, gases to within limit.B. Required Action and B.1 Isolate all main steam 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion lines.Time not met.____ ___ ____ ___ OR LCO 3.0.4.a is not B.2 Isolate SJAE. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Sapplicable when entering MODE 3. ORR[ e in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B.3JEm r HATCH UNIT 1 3.7-16 HATCH UNI 1 3.7-16Amenid 1 1 ent Nc.-9 AC Sources -Operating 3.8.1 3.8 LECTICALPOWE SYSEMSNo change. Included for 3.8 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 network and 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 Standby Gas Treatment (SGT) subsystem required by LCO 3.6.4.3,"'SGT System;" e. One qualified circuit between the offsite transmission network and the 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 pressure coolant injection (LPCI) valve load center; and g. One qualified circuit between the offsite transmission network and the applicable onsite Class 1 E AC electrical power distribution subsystems needed tQ support each Unit I LPCI valve load center required by LCO 3.5.1, "ECCS -Operating." APPLICABILITY:

MODES 1, 2, and 3.HATCH UNIT 1 3.8-1 HATC UNI 1 38-1Amendment No. 211 AC Sources -Operating 3.8.1 No change. Included for information only.ACTIONS LCO 3.0.4.b is not applicable to DGs.CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

OPERABLE required offsite circuits.

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

AND A.3 Restore required offsite 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months circuit to OPERABLE ,status. AND 17 days from discovery of failure to meet LCO 3.8.1.a, b, or c B. One Uniti1 or the swing B.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months DG inoperable.

OPERABLE required offsite circuit(s).

AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND_________________________(continued)

HATCH UNIT 1 3.8-2 HATC UNI I 38-2Amendment No. 246 AC Sources -Operating 3.8.1 No change. Included for information only.ACTIONS CONDITION REQUIRED ACTION (COMPLETION TIME B. (continued)

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

by AND B.3.1 Determine OPERABLE DG(s) are not inoperable due to common cause failure.O__R B.3.2 Perform SR 3.8.1.2.a for OPERABLE DG(s).AND B.4 Restore DG to OPERABLE status.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition B concurrent with inoperability of redundant required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 hours 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for a Unit 1 DC with the swing DG not inhibited or maintenance restrictions not met AND 14 days for a Unit 1 DC with the swing DC inhibited from automatically aligning to Unit 2 and maintenance restrictions met AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for the swing diesel with maintenance restrictions not met (continued)

HATCH UNIT 1 3.8-3 HATC UNI I 38-3Amendment No. 259 AC Sources -Operating 3.8.1 No change. Included for information only.I ACTIONS CONDITION IREQUIRED ACTION jCOMPLETION TIME B. (continued)

B.4 (continued)

AND 14 days for the swing diesel with maintenance restrictions met AND 17 days from discovery of failure to meet LCO 3.8.1.a, b, or c C. One required Unit 2 DG inoperable C.1 Perform SR 3.8.1.1 for OPERABLE required offsite circuit(s).

AND C.2 AND C.3.1 Declare required feature(s), supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable.

Determine OPERABLE DG(s) are not inoperable due to common cause failure.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition C concurrent with in operability of redundant required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 hours OR C.3.2 Perform SR 3.8.1.2.a for OPERABLE DG(s).(continued)

HATCH UNIT 1 3.8-4 HATC UNI I 38-4Amendment No. 259 AC Sources -Operating 3.8.1 No change. Included for information only. I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)

AND C.4 Restore required DG to 7 days with the OPERABLE status. swing DG not inhibited or.maintenance restrictions not met AND 14 days with the swing DG inhibited from automatically aligning to Unit 1 and maintenance restrictions met D. 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 D power available concurrent with inoperable when the inoperability of redundant required redundant required feature(s) are feature(s) inoperable.

AND D.2 Restore all but one 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months required offsite circuit to OPERABLE status.E. One required off~site circuit------NOTE---------L.....

inoperable.

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

HATCH UNIT 1 3.8-5 HATC UNI I 38-5Amendment No. 259 AC Sources -Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. (continued)

OR E.2 Restore required DG to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE 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 to OPERABLE status G. No DGs capable of G.1 Restore one DG 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months supplying power to any capable of supplying Unit 1 LPCI valve load power to Unit 1 LPCI center. valve load center to OPERABLE status.H. Required Action and H.1 in MODE 3.I 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time of Condition A, B, C,AN D, 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 entering OR / MODE 3.Two or more required offsite circuits and one required___________________

_DG________inoperable.____I

__________________

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

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

MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Swing DG DC electrical A.1 Restore DG DC 7 days power subsystem electrical power inoperable due to subsystem to performance of SR 3.8.4.7 OPERABLE status.or SR 3.8.4.8.OR_One or more required Unit 2 DG DC electrical power subsystems inoperable.(continued)

HATCH UNIT 1 3.8-26 HATC UNI 1 38-26Amendment No. 227 DC Sources -Operating 3.8.4 ACTIONS (continued)

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

/LCO 3.0.4.a is not power subsystem r--applicable when entering inoperable for reasonsMOE3 other than Condition A. MD3 C. One Unit 1 station service C.1 \ Restore station service 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DC electrical power \ DC electrical power subsystem inoperable, subsystem to OPERABLE status.D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time of Condition A, B, AN or C not met.E. Two or more DC electrical E.1 Enter LCO 3.0.3. Immediately power subsystems inoperable that result in a loss of function.HATCH UNIT 1 382 3.8-27 Distribution Systems -Operating 3.8.7 3.8 LECRICL PWERSYSEMSNo change. Included for 3.8 LECRICA POER SSTES linformation only.3.8.7 Distribution Systems -Operating LCO 3.8.7 The following AC and DC electrical power distribution subsystems shall be 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; and b. Unit 2 AC and DC electrical power distribution subsystems needed to support equipment required to be OPERABLE by LCO 3.6.4.3, "Standby Gas Treatment (SGT) System," and LCO 3.8.1, "AC Sources -Operating." APPLICABILITY:

MODES 1, 2, and 3.ACTIONS ___________

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 7 days Unit 2 AC or DC electrical Unit 2 AC and DC power distribution subsystem(s) to subsystems inoperable.

OPERABLE status.(continued)

HATCH UNIT 1 3.8-36 HATC UNI I 38-36Amendment No. 227 Distribution Systems -Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. 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 power electrical power distribution distribution subsystem AND subsystems inoperable, to OPERABLE status.16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO 3.8.7.a C. One or more (Unit 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 AND subsystems inoperable.

OPERABLE status.16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO 3.8.7.a 0. One Unit 1 station service D.1 Restore Unit 1 station 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DC electrical power service DC electrical distribution subsystem power distribution AND inoperable, subsystem to OPERABLE status. 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO 3.8.7.a E. Required Action and associated Completion Time of Condition A, B, C, or D not met.F. Two or more electrical power distribution subsystems inoperable that result in a loss of function.E.1 e nDMOE 3.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Enter LCO 3.0.3.Immediately LCO 3.0.4.a is not applicable when entering MODE 3.HATCH UNIT 1 383 3.8-37 I RPS Electric Power Monitoring 3.3.8.2 3.3 INSTRUMENTATION 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LCO 3.3.8.2 APPLICABILITY:

Two RPS electric power monitoring assemblies shall be OPERABLE for each 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 cell containing one or more fuel assemblies or with both residual heat removal (RHR) shutdown cooling (SDC) isolation valves open.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both inservice A.1 Remove associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power supplies with one inservice power electric power monitoring supply(s) from service.assembly inoperable.

B. One or both inservice B.1 Remove associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months power supplies with both inservice power electric power monitoring supply(s) from service.assemblies inoperable.

C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.in MODE 3.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 536-huurts pe vi IVRJLJL '*.(continued)

-NOTE----LCO 3.0.4.a is not applicable when entering MODE 3.HATCH UNIT 2 3.3-69 HATH UIT 3.-69Amondmon'zt Noc. 210j I RPS Electric Power Monitoring 3.3.8.2 No change. Included for information only.ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to fully Immediately associated Completion insert all insertable Time of Condition A or B control rods in core not met in MODE 4 or 5 cells containing one or with any control rod more fuel assemblies.

withdrawn from a core cell containing one or more fuel AND assemblies or with both RHR SDC isolation valves D.2.1 Initiate action to restore Immediately open. one electric power monitoring assembly to OPERABLE status for inservice power supply(s) supplying required instrumentation.

O__8R D.2.2 Initiate action to isolate Immediately the RHR SDC.HATCH UNIT 2 3.3-70 HATC UNI 2 33-70Amendment No. 210 I ECCS -Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS -Operating LCO 3.5.1 Each 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 ADS valves are not required to be OPERABLE with reactor steam dome pressure < 150 psig.APPLICABILITY:

ACTIONS-~~NOTE-----

ILCO 3.0.4.a is not lapplicable when entering IMODE 3.

LCO 3.0.4.b is not applicable to HPCI.CONDITION

/REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 \Restore low pressure 7 days injection/spray subsystem ECCS injection/spray inoperable, subsystem to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met.C. HPCI System inoperable.

C.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months means RCIC System is OPERABLE.AND C.2 Restore HPCI System 14 days to OPERABLE status.(continued)

I HATCH UNIT 2351 3.5-1 ECCS -Operating 3.5.1 ACTIONS (continued)

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

Ei~Two or more AD: N REQUIRED ACTION [COMPLETION TIME 3perable.e ECCS uibsystem D.I Restore HPCI System to OPERABLE status.OR D.2 Restore low pressure ECCS injection/spray subsystem to OPERABLE status.1 in MODE 3.AND E1 " duce reactor steam dome pressure to< 150 psig.72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 72 hours S valves 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

T;1 1 e ~.,f C~,d;t;c~

C ~r C 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Enter LCO 3.0.3.Two or more low pressure ECCS injection/spray subsystems inoperable.

OR HPCI System and two or more ADS valves inoperable.

Immediately HATCH UNIT 2 3.5-2 HATC UNT 23.52 Anerirnnt G.

TS 3.5.1 -Condition E Insert E. 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 System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.APPLICABILITY:

MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.ACTIONS-----------I4 LCo 3.0.4.b is not applicable to RCIC.CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable.

A.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months means high pressure coolant injection (H PCI)NOTE............System is OPERABLE.LCO 3.0.4.a is not AND applicable when entering MODE 3. Restore RCIC System 14 days*----------------------to OPERABLE status.B. Required Action and B.1 "Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. N HATCH UNIT 2 3.5-10 HATCH UITI2I35-10 A IIImcI INcl. 210 Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.7 3.6 CONTAINMENT SYSTEMS 3.6.1.7 Reactor Building-to-Suppression Chamber Vacuum Breakers LCO 3.6.1.7 APPLICABILITY:

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

'IJu I Separate Condition entry is allowed for each line.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more lines with one A.1 Close the open vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months reactor building-to-breaker.suppression chamber vacuum breaker not closed.B. One or more lines with two B.1 Close one open 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reactor building-to-vacuum breaker.suppression chamber vacuum breakers not closed.C. One line with one or more C.1 Restore the vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months reactor building-to-breaker(s) to suppression chamber OPERABLE status.vacuum breakers inoperable for opening.lines with one or more EJ etore all vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reactor building-to-breakers in one line to suppression chamber OPERABLE status.vacuum breakers inoperable for opening./ pINSERT- TS 3.6.1.7I ICondition DI (continued)

HATCH UNIT 2 361 3.6-17 TS 3.6.1.7 -Condition D Insert D. 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 Breakers 3.6.1.7 ACTIONS (continued)

CONDITION REQUIRED ACTION [COMPLETION TIME Action and Associated Completion Timr, 7 1 not met.Iof Condition A, B, or E Be in MODE 3.AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours Be in MODE 4.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.1--------------

NOTES--------

1. Not required to be met for vacuum breakers that are open during Surveillances.

2. Not required to be met for vacuum breakers open when performing their intended function.Verify each vacuum breaker is closed.In accordance with the Surveillance Frequency Control Program SR 3.6.1.7.2 Perform a functional test of each vacuum breaker. In accordance with the Inservice Testing Program SR 3.6.1.7.3 Verify the opening setpoint of each vacuum In accordance with breaker is < 0.5 psid. the Surveillance Frequency Control Program HATCH UNIT 2 3.6-18 HATCH UNIT 2 3.6-18 Amcncirncnt NG. 210 Charles R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN " NUCLEAR A SOUTHERN COMPANY DEC 1 5 2015 Docket Nos.: 50-32 1 50-366 NL-14-1 075 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-001 Edwin I. Hatch Nuclear Plant License Amendment Request for Adoption of TSTF-423-A, Rev. 1 Technical 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 to Selected Required End States for BWR Plants." Additionally, the proposed amendment would modify the TS Required Actions 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.* Attachment 1 provides a description and assessment of the proposed change, the requested confirmation of applicability, and plant-specific verifications.

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