NL-21-0160, License Amendment Request to Remove Table of Contents from Technical Specifications

From kanterella
(Redirected from ML21173A064)
Jump to navigation Jump to search
License Amendment Request to Remove Table of Contents from Technical Specifications
ML21173A064
Person / Time
Site: Hatch, Vogtle, Farley  Southern Nuclear icon.png
Issue date: 06/22/2021
From: Gayheart C
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-21-0160
Download: ML21173A064 (34)
v • d • e


Text

Cheryl A. Gayheart 3535 Colonnade Parkway Regulatory Affairs Director Birmingham, AL 35243 205 992 5316 tel 205 992 7601 fax cagayhea@southernco.com June 22, 2021 Docket Nos.: 50-348 50-321 50-424 NL-21-0160 50-364 50-366 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant - Units 1 and 2 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Remove Table of Contents from Technical Specifications Ladies and Gentlemen:

Pursuant to 10 CFR 50.90, Southern Nuclear Operating Company (SNC) is submitting a request for an amendment to the Technical Specifications (TS), for Joseph M. Farley Nuclear Plant (FNP) Unit 1 Renewed Facility Operating License NPF-2 and Unit 2 Renewed Facility Operating License NPF-8, Edwin I Hatch Nuclear Plant (HNP) Unit 1 Renewed Facility Operating License DPR-57 and Unit 2 Renewed Facility Operating License NPF-5, and Vogtle Electric Generating Plant (VEGP) Unit 1 Renewed Facility Operating License NPF-68 and Unit 2 Renewed Facility Operating License NPF-81.

This request is to revise the operating licenses to remove the table of contents from the FNP, HNP, and VEGP TS and remove the effective page list from the HNP TS and place them under licensee control.

The Enclosure provides a description of the proposed change. Attachments 1a through 1d provide the existing TS pages marked up to show the proposed change.

This letter contains no regulatory commitments.

SNC requests approval of the proposed license amendment by June 30, 2022 with the amendment being implemented within 60 days of issuance.

U. S. Nuclear Regulatory Commission NL-21-0160 Page 2 In accordance with 10 CFR 50.91, a copy of this application, with enclosures, is being provided to the designated State of Alabama and State of Georgia officials.

If you have any questions, please contact Jamie Coleman at 205.992.6611.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the

___ day of June 2021.

Respectfully submitted, Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company CAG/kgl/cg

Enclosure:

Description and Assessment Attachments:

1a. FNP Units 1 and 2 Proposed Technical Specification Changes (Mark-up) 1b. HNP Unit 1 Proposed Technical Specification Changes (Mark-up) 1c. HNP Unit 2 Proposed Technical Specification Changes (Mark-up) 1d. VEGP Units 1 and 2 Proposed Technical Specification Changes (Mark-up) cc: Regional Administrator, Region ll NRR Project Manager - Farley, Hatch, Vogtle 1 & 2 Senior Resident Inspector - Farley, Hatch, Vogtle 1 & 2 Director, Alabama Office of Radiation Control Director, Environmental Protection Division - State of Georgia RTYPE: CGA02.001

Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant - Units 1 and 2 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Remove Table of Contents from Technical Specifications Enclosure Description and Assessment

Enclosure - Description and Assessment

1.0 DESCRIPTION

In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Southern Nuclear Operating Company (SNC) is requesting an amendment to the Technical Specifications (TS) for the renewed facility operating licenses for Joseph M.

Farley Nuclear Plant (FNP) Units 1 and 2, Edwin I. Hatch Nuclear Plant (HNP) Units 1 and 2, and Vogtle Electric Generating Plant (VEGP) Units 1 and 2. This request is to revise the operating licenses to remove the table of contents from the FNP, HNP, and VEGP TS and remove the effective page list from the HNP TS and place them under licensee control. The TOC and effective page list (HNP only) are not being eliminated and will be published with the TS. However, following approval of this license amendment request, revisions to the TOC and effective page list (HNP only) will be made under licensee control and without Nuclear Regulatory Commission (NRC) review and approval.

2.0 PROPOSED CHANGE

S The proposed change would revise the operating licenses to remove the TOC from the FNP, HNP, and VEGP TS and remove the effective page list from the HNP TS and place them under licensee control.

The TOC, and the effective page list (HNP only), for the TS are not being eliminated, rather, following approval of this license amendment request, responsibility for maintenance and issuance of updates to the TS TOC, and the effective page list (HNP only), will transfer from the NRC to SNC. The TOC, and the effective page list (HNP only), will no longer be included in the NRC issued TS and as such will no longer be part of the TS (Appendix A to the operating license). The TOC and effective page list (HNP only) for the TS will be maintained under SNC control. Changes to the TOC and effective page list (HNP only) will then be revised by SNC in conjunction with the implementation of future NRC approved TS amendments.

Placing the TOC, and the effective page list (HNP only), under licensee control eliminates the regulatory burden of submitting TOC pages, and the effective page list (HNP only), for NRC review and allows timely administrative corrections and improvements to the TOC, and the effective page list (HNP only), without NRC review and approval.

3.0 TECHNICAL ANALYSIS

The TOC and effective page list do not meet the criteria specified in 10 CFR 50.36 requiring their inclusion within a plant's TS. 10 CFR 50.36(b) states:

"Each license authorizing operation of a production or utilization facility of a type described in § 50.21 or § 50.22 will include technical specifications. The technical specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34."

10 CFR 50.36(c) states the "Technical specifications will include items in the following categories." Review of 10 CFR 50.36 indicates that a TOC or an effective page list was not listed in the regulation as one of the categories.

The TOC references the page number of each specification in the TS and does not contain any technical information required by 10 CFR 50.36. The effective page list provides the revision number for each page in the TS and does not contain any technical information required by 10 E-1

Enclosure - Description and Assessment CFR 50.36. Since the TOC and effective page list do not include information required to be in the TS by 10 CFR 50.36, inclusion of a TOC and effective page list within the TS is optional.

Removal of the TOC and effective page list (HNP only) from the TS is an administrative change and is acceptable.

Additionally, the "Writer's Guide for Plant-Specific Improved Technical Specifications

(Reference 1) was reviewed for guidance. The writer's guide refers to the TOC as "Technical Specification Front Matter," which also includes the title page and effective page list. These portions of the TS are described as not part of the TS and, therefore, are under licensee control as proposed for the TOC and effective page list (HNP only) in this amendment request.

The TS TOC, and the effective page list (HNP only), will be maintained under SNC control.

Changes to the TOC and effective page list (HNP only) will then be revised by SNC in conjunction with the implementation of future NRC approved TS amendments.

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements 10 CFR 50.36 contains requirements for what is to be included in a licensee's TS. The TOC and effective page list, which contains only administrative information, is not required to be in the TS per the requirements of 10 CFR 50.36.

4.2 Precedent x Exelon Generating Company license amendment was issued on December 18, 2019, Issuance of Amendments to Remove Table of Contents from Technical Specifications.

(Reference 2)

This license amendment approved the removal of the TOC from the TS of several plants in the Exelon fleet, similar to this request to remove the TOC from several plants in the SNC fleet.

x Point Beach Nuclear Plant license amendment was issued on October 11, 2011, Issuance of Amendment re: Request to Remove the Table of Contents from the Technical Specifications. (Reference 3)

This license amendment approved the removal of the TOC from the Point Beach TS, similar to this request.

4.3 No Significant Hazards Evaluation Southern Nuclear Operating Company (SNC) is requesting an amendment to the Technical Specifications (TS) for the renewed facility operating licenses for Joseph M. Farley Nuclear Plant (FNP) Units 1 and 2, Edwin I. Hatch Nuclear Plant (HNP) Units 1 and 2, and Vogtle Electric Generating Plant (VEGP) Units 1, and 2. This request is to revise the operating licenses to remove the table of contents (TOC) from the TS and the effective page list (HNP only). The TOC and effective page list are not being eliminated and will be published with the TS. However, following approval of this license amendment request, revisions to the TOC and effective page list (HNP only) will be made under licensee control and without Nuclear Regulatory Commission review and approval.

E-2

Enclosure - Description and Assessment 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, as discussed 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 is administrative and affects control of documents. The TOC and the effective page list (HNP only) provide the page number and revision of the specifications in the TS. Transferring control of changes to the TOC and the effective page list (HNP only) to the licensee does not affect the operation, physical configuration, or function of plant equipment or systems. It does not impact the initiators or assumptions of analyzed events; nor does it impact the mitigation of accidents or transient events. The change has no effect on the probability or consequences of an accident.

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 is administrative and does not alter the plant configuration, require installation of new equipment, alter assumptions about previously analyzed accidents, or impact the operation or function of plant equipment or systems.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

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

Response: No The proposed change is administrative. The TOC and effective page list are not required by regulation to be included in the operating license or the TS. Removal of the TOC, and the effective page list (HNP only) from NRC revision control does not impact any safety assumptions or have the potential to reduce a margin of safety as described in the TS Bases. No change in the technical content of the TS is involved.

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.

4.4 Conclusions E-3

Enclosure - Description and Assessment In conclusion, based on considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or the health and safety of the public.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes requirements with respect to the format of the license or otherwise makes editorial, corrective or other minor revisions. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10)(v). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.

6.0 REFERENCES

1. Technical Specifications Task Force, TSTF-GG-05-01, "Writer's Guide for Plant-Specific Improved Technical Specifications," dated June 2005. (ML060720511)
2. Letter from NRC to Exelon Generation Company, dated December 18, 2019, Issuance of Amendments to Remove Table of Contents from Technical Specifications.

(ML19302E700)

3. Letter from NRC to NextEra, dated October 11, 2011, Issuance of Amendment re:

Request to Remove the Table of Contents from the Technical Specifications.

(ML112640016)

E-4

Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant - Units 1 and 2 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Remove Table of Contents from Technical Specifications Attachment 1.a FNP Units 1 and 2 Proposed Technical Specification Changes (Mark-up)

TABLE OF CONTENTS 1.0 USE AND APPLICATION .............................................................................. 1.1-1 1.1 Definitions .............................................................................................. 1.1-1 1.2 Logical Connectors ................................................................................ 1.2-1 1.3 Completion Times .................................................................................. 1.3-1 1.4 Frequency .............................................................................................. 1.4-1 2.0 SAFETY LIMITS (SLs) ................................................................................... 2.0-1 2.1 SLs ........................................................................................................ 2.0-1 2.2 SL Violations .......................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ............... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ............................. 3.0-3 3.1 REACTIVITY CONTROL SYSTEMS...................................................... 3.1.1-1 3.1.1 SHUTDOWN MARGIN (SDM) ........................................................ 3.1.1-1 3.1.2 Core Reactivity ............................................................................... 3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC) ..................................... 3.1.3-1 3.1.4 Rod Group Alignment Limits ........................................................... 3.1.4-1 3.1.5 Shutdown Bank Insertion Limits ..................................................... 3.1.5-1 3.1.6 Control Bank Insertion Limits .......................................................... 3.1.6-1 3.1.7 Rod Position Indication ................................................................... 3.1.7-1 3.1.8 PHYSICS TESTS Exceptions MODE 2 ..................................... 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS ........................................................... 3.2.1-1 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) ............................................ 3.2.1-1 N

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F+ ) ........................... 3.2.2-1 3.2.3 AXIAL FLUX DIFFERENCE (AFD) ................................................ 3.2.3-1 3.2.4 QUADRANT POWER TILT RATIO (QPTR).................................... 3.2.4-1 3.3 INSTRUMENTATION............................................................................. 3.3.1-1 3.3.1 Reactor Trip System (RTS) Instrumentation ................................... 3.3.1-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation......................................................................... 3.3.2-1 3.3.3 Post Accident Monitoring (PAM) Instrumentation ........................... 3.3.3-1 3.3.4 Remote Shutdown System ............................................................. 3.3.4-1 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation......................................................................... 3.3.5-1 3.3.6 Containment Purge and Exhaust Isolation Instrumentation......................................................................... 3.3.6-1 3.3.7 Control Room Emergency Filtration/Pressurization System (CREFS) Actuation Instrumentation .......................................... 3.3.7-1 3.3.8 Penetration Room Filtration (PRF) System Actuation Instrumentation......................................................................... 3.3.8-1 Farley Units 1 and 2 i Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

TABLE OF CONTENTS 3.4 REACTOR COOLANT SYSTEM (RCS) ................................................. 3.4.1-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits .................................................. 3.4.1-1 3.4.2 RCS Minimum Temperature for Criticality ...................................... 3.4.2-1 3.4.3 RCS Pressure and Temperature (P/T) Limits ................................. 3.4.3-1 3.4.4 RCS Loops MODES 1 and 2 ...................................................... 3.4.4-1 3.4.5 RCS Loops MODE 3 .................................................................. 3.4.5-1 3.4.6 RCS Loops MODE 4 .................................................................. 3.4.6-1 3.4.7 RCS Loops MODE 5, Loops Filled ............................................. 3.4.7-1 3.4.8 RCS Loops MODE 5, Loops Not Filled ....................................... 3.4.8-1 3.4.9 Pressurizer ..................................................................................... 3.4.9-1 3.4.10 Pressurizer Safety Valves .............................................................. 3.4.10-1 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ...................... 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP) System ........... 3.4.12-1 3.4.13 RCS Operational LEAKAGE ........................................................... 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ................................. 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation........................................ 3.4.15-1 3.4.16 RCS Specific Activity ...................................................................... 3.4.16-1 3.4.17 Steam Generator (SG) Tube Integrity ............................................. 3.4.17-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ............................ 3.5.1-1 3.5.1 Accumulators ................................................................................. 3.5.1-1 3.5.2 ECCS Operating......................................................................... 3.5.2-1 3.5.3 ECCS Shutdown ........................................................................ 3.5.3-1 3.5.4 Refueling Water Storage Tank (RWST).......................................... 3.5.4-1 3.5.5 Seal Injection Flow ......................................................................... 3.5.5-1 3.5.6 ECCS Recirculation Fluid pH Control System ................................ 3.5.6-1 3.6 CONTAINMENT SYSTEMS ................................................................... 3.6.1-1 3.6.1 Containment ................................................................................... 3.6.1-1 3.6.2 Containment Air Locks ................................................................... 3.6.2-1 3.6.3 Containment Isolation Valves ......................................................... 3.6.3-1 3.6.4 Containment Pressure .................................................................... 3.6.4-1 3.6.5 Containment Air Temperature ........................................................ 3.6.5-1 3.6.6 Containment Spray and Cooling Systems ...................................... 3.6.6-1 3.6.7 Hydrogen Recombiners .................................................................. 3.6.7-1 3.6.8 Hydrogen Mixing System (HMS) .................................................... 3.6.8-1 3.6.9 Reactor Cavity Hydrogen Dilution System ...................................... 3.6.9-1 3.6.10 Containment Sump......................................................................... 3.6.10-1 3.7 PLANT SYSTEMS ................................................................................. 3.7.1-1 3.7.1 Main Steam Safety Valves (MSSVs) .............................................. 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs)............................................. 3.7.2-1 Farley Units 1 and 2 ii Amendment No. 232 (Unit 1)

Amendment No. 229 (Unit 2)

TABLE OF CONTENTS 3.7.3 Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves ...................... 3.7.3-1 3.7.4 Atmospheric Relief Valves (ARVs) ................................................. 3.7.4-1 3.7.5 Auxiliary Feedwater (AFW) System ................................................ 3.7.5-1 3.7.6 Condensate Storage Tank (CST) ................................................... 3.7.6-1 3.7.7 Component Cooling Water (CCW) System ..................................... 3.7.7-1 3.7.8 Service Water System (SWS) ......................................................... 3.7.8-1 3.7.9 Ultimate Heat Sink (UHS) ............................................................... 3.7.9-1 3.7.10 Control Room Emergency Filtration/Pressurization System (CREFS) ...................................................................... 3.7.10-1 3.7.11 Control Room Air Conditioning System (CRACS) ........................... 3.7.11-1 3.7.12 Penetration Room Filtration (PRF) System ..................................... 3.7.12-1 3.7.13 Fuel Storage Pool Water Level ....................................................... 3.7.13-1 3.7.14 Fuel Storage Pool Boron Concentration ......................................... 3.7.14-1 3.7.15 Spent Fuel Assembly Storage ........................................................ 3.7.15-1 3.7.16 Secondary Specific Activity ............................................................. 3.7.16-1 3.7.17 Cask Storage Area Boron Concentration Cask Loading Operations ............................................................................... 3.7.17-1 3.7.18 Spent Fuel Assembly Storage Cask Loading Operations ............ 3.7.18-1 3.7.19 Engineered Safety Feature (ESF) Room Coolers ........................... 3.7.19-1 3.8 ELECTRICAL POWER SYSTEMS ......................................................... 3.8.1-1 3.8.1 AC Sources Operating ................................................................ 3.8.1-1 3.8.2 AC Sources Shutdown ................................................................ 3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ....................................... 3.8.3-1 3.8.4 DC Sources Operating ................................................................ 3.8.4-1 3.8.5 DC Sources Shutdown ............................................................... 3.8.5-1 3.8.6 Battery Cell Parameters.................................................................. 3.8.6-1 3.8.7 Inverters Operating ..................................................................... 3.8.7-1 3.8.8 Inverters Shutdown ..................................................................... 3.8.8-1 3.8.9 Distribution Systems Operating................................................... 3.8.9-1 3.8.10 Distribution Systems Shutdown .................................................. 3.8.10-1 3.9 REFUELING OPERATIONS .................................................................. 3.9.1-1 3.9.1 Boron Concentration....................................................................... 3.9.1-1 3.9.2 Nuclear Instrumentation.................................................................. 3.9.2-1 3.9.3 Containment Penetrations .............................................................. 3.9.3-1 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation High Water Level................................................. 3.9.4-1 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation Low Water Level ................................................. 3.9.5-1 3.9.6 Refueling Cavity Water Level.......................................................... 3.9.6-1 4.0 DESIGN FEATURES ............................................................................. 4.0-1 4.1 Site Location ................................................................................. 4.0-1 4.2 Reactor Core.................................................................................. 4.0-1 Farley Units 1 and 2 iii Amendment No. 176 (Unit 1)

Amendment No. 169 (Unit 2)

TABLE OF CONTENTS 4.3 Fuel Storage .......................................................................................... 4.0-1 5.0 ADMINISTRATIVE CONTROLS .................................................................... 5.1-1 5.1 Responsibility ......................................................................................... 5.1-1 5.2 Organization ........................................................................................... 5.2-1 5.3 Unit Staff Qualifications .......................................................................... 5.3-1 5.4 Procedures............................................................................................. 5.4-1 5.5 Programs and Manuals .......................................................................... 5.5-1 5.6 Reporting Requirements ........................................................................ 5.6-1 5.7 High Radiation Area ............................................................................... 5.7-1 Farley Units 1 and 2 iv Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant - Units 1 and 2 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Remove Table of Contents from Technical Specifications Attachment 1.b HNP Unit 1 Proposed Technical Specification Changes (Mark-up)

HATCH UNIT 1 TECHNICAL SPECIFICATIONS EFFECTIVE PAGE LIST Unless noted otherwise, all pages are Amendment No. 195.

PAGE AMENDMENT PAGE AMENDMENT 1.1-2 200 3.6-1 200 1.1-4 214 3.6-2 200 2.0-1 219 3.6-6 200 3.1-17 217 3.6-12 200 3.1-19 204 3.6-14 201 3.3-1 213 3.6-15 204 3.3-2 214 3.6-16 208 3.3-3 213 3.6-33 198 3.3-4 213 3.6-34 198 3.3-5 214 3.7-8 225 3.3-6 213 3.7-9 225 3.3-7 214 3.7-10 225 3.3-8 213 3.8-1 211 3.3-9 214 3.8-2 211 3.3-17 206 3.8-3 through 3.8-40 227 3.3-19 210 3.10-17 205 3.3-27 214 3.10-18 205 3.3-28 214 4.0-2 220 3.3-29 214 5.0-10 223 3.3-30 196 5.0-11 223 3.3-32 197 5.0-12 223 3.3-52 216 5.0-15 224 3.3-57 216 5.0-16 226 3.3-61 197 5.0-17 200 3.4-1 213 5.0-18 203 3.4-2 213 5.0-20 215 3.4-3 213 3.4-6 204 3.4-7 208 3.4-20 206 3.4-21 206 3.4-22 222 3.4-23 222 3.4-24 222 3.4-25 197 3.5-1 204 3.5-2 204 3.5-3 211 3.5-4 204 3.5-5 208 3.5-7 202 3.5-10 197 Note: Amendment No. 199 is associated with issuance of the Plant Hatch Environmental Protection Plan.

HATCH UNIT 1 i Amendment No. 227

TABLE OF CONTENTS 1.0 USE AND APPLICATION .......................................................................... 1.1-1 1.1 Definitions ................................................................................................... 1.1-1 1.2 Logical Connectors ..................................................................................... 1.2-1 1.3 Completion Times ....................................................................................... 1.3-1 1.4 Frequency .................................................................................................. 1.4-1 2.0 SAFETY LIMITS (SLs) ............................................................................... 2.0-1 2.1 SLs ............................................................................................................. 2.0-1 2.2 SL Violations............................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .......... 3.0-1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ......................... 3.0-3 3.1 REACTIVITY CONTROL SYSTEMS .......................................................... 3.1-1 3.1.1 SHUTDOWN MARGIN (SDM) .................................................................... 3.1-1 3.1.2 Reactivity Anomalies .................................................................................. 3.1-4 3.1.3 Control Rod OPERABILITY ........................................................................ 3.1-5 3.1.4 Control Rod Scram Times........................................................................... 3.1-9 3.1.5 Control Rod Scram Accumulators ............................................................... 3.1-12 3.1.6 Rod Pattern Control .................................................................................... 3.1-15 3.1.7 Standby Liquid Control (SLC) System......................................................... 3.1-17 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves............................. 3.1-23 3.2 POWER DISTRIBUTION LIMITS ............................................................... 3.2-1 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ...... 3.2-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) .......................................... 3.2-2 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) ............................................ 3.2-4 3.3 INSTRUMENTATION ................................................................................. 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation ..................................... 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation ........................................... 3.3-10 3.3.2.1 Control Rod Block Instrumentation ............................................................. 3.3-15 3.3.2.2 Feedwater and Main Turbine Trip High Water Level ................................... 3.3-21 Instrumentation 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ........................................ 3.3-23 3.3.3.2 Remote Shutdown System ......................................................................... 3.3-26 (continued)

HATCH UNIT 1 i Amendment No. 266

TABLE OF CONTENTS (continued) 3.3 INSTRUMENTATION (continued) 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation ............ 3.3-28 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation .............................................. 3.3-31 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation......................... 3.3-34 3.3.5.2 RPV Water Inventory Control Instrumentation ............................................ 3.3-44 3.3.5.3 Reactor Core Isolation Cooling (RCIC) System Instrumentation ................. 3.3-47 3.3.6.1 Primary Containment Isolation Instrumentation........................................... 3.3-51 3.3.6.2 Secondary Containment Isolation Instrumentation ...................................... 3.3-60 3.3.6.3 Low-Low Set (LLS) Instrumentation ............................................................ 3.3-64 3.3.7.1 Main Control Room Environmental Control (MCREC) System Instrumentation ..................................................................................... 3.3-68 3.3.8.1 Loss of Power (LOP) Instrumentation ......................................................... 3.3-70 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring ...................... 3.3-73 3.4 REACTOR COOLANT SYSTEM (RCS) ..................................................... 3.4-1 3.4.1 Recirculation Loops Operating .................................................................... 3.4-1 3.4.2 Jet Pumps .................................................................................................. 3.4-3 3.4.3 Safety/Relief Valves (S/RVs) ...................................................................... 3.4-5 3.4.4 RCS Operational LEAKAGE ....................................................................... 3.4-7 3.4.5 RCS Leakage Detection Instrumentation .................................................... 3.4-9 3.4.6 RCS Specific Activity .................................................................................. 3.4-11 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System -

Hot Shutdown ....................................................................................... 3.4-13 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System -

Cold Shutdown ..................................................................................... 3.4-16 3.4.9 RCS Pressure and Temperature (P/T) Limits.............................................. 3.4-18 3.4.10 Reactor Steam Dome Pressure .................................................................. 3.4-25 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), RPV WATER INVENTORY CONTROL AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM..................................................................................................... 3.5-1 3.5.1 ECCS - Operating ....................................................................................... 3.5-1 3.5.2 RPV Water Inventory Control...................................................................... 3.5-6 3.5.3 RCIC System .............................................................................................. 3.5-10 3.6 CONTAINMENT SYSTEMS ....................................................................... 3.6-1 3.6.1.1 Primary Containment .................................................................................. 3.6-1 3.6.1.2 Primary Containment Air Lock .................................................................... 3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ........................................... 3.6-7 3.6.1.4 Drywell Pressure ........................................................................................ 3.6-13 3.6.1.5 Drywell Air Temperature ............................................................................. 3.6-14 (continued)

HATCH UNIT 1 ii Amendment No. 290

TABLE OF CONTENTS (continued) 3.6 CONTAINMENT SYSTEMS (continued) 3.6.1.6 Low-Low Set (LLS) Valves.......................................................................... 3.6-15 3.6.1.7 Reactor Building-to-Suppression Chamber Vacuum Breakers .................... 3.6-17 3.6.1.8 Suppression Chamber-to-Drywell Vacuum Breakers .................................. 3.6-19 3.6.2.1 Suppression Pool Average Temperature .................................................... 3.6-21 3.6.2.2 Suppression Pool Water Level .................................................................... 3.6-24 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling .......................... 3.6-25 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ............................ 3.6-27 3.6.2.5 Residual Heat Removal (RHR) Drywell Spray ............................................ 3.6.29 3.6.3.1 Containment Atmosphere Dilution (CAD) System ....................................... 3.6-31 3.6.3.2 Primary Containment Oxygen Concentration .............................................. 3.6-33 3.6.4.1 Secondary Containment ............................................................................. 3.6-34 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ...................................... 3.6-37 3.6.4.3 Standby Gas Treatment (SGT) System ...................................................... 3.6-40 3.7 PLANT SYSTEMS...................................................................................... 3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System.......................... 3.7-1 3.7.2 Plant Service Water (PSW) System and Ultimate Heat Sink (UHS) ............ 3.7-3 3.7.3 Diesel Generator (DG) 1B Standby Service Water (SSW) System ............. 3.7-6 3.7.4 Main Control Room Environmental Control (MCREC) System .................... 3.7-8 3.7.5 Control Room Air Conditioning (AC) System............................................... 3.7-12 3.7.6 Main Condenser Offgas .............................................................................. 3.7-16 3.7.7 Main Turbine Bypass System ..................................................................... 3.7-18 3.7.8 Spent Fuel Storage Pool Water Level ......................................................... 3.7-19 3.7.9 Turbine Building Ventilation (TB HVAC) Exhaust System Fans .................. 3.7-20 3.8 ELECTRICAL POWER SYSTEMS............................................................. 3.8-1 3.8.1 AC Sources - Operating .............................................................................. 3.8-1 3.8.2 AC Sources - Shutdown.............................................................................. 3.8-20 3.8.3 Diesel Fuel Oil and Transfer, Lube Oil, and Starting Air .............................. 3.8-23 3.8.4 DC Sources - Operating.............................................................................. 3.8-26 3.8.5 DC Sources - Shutdown ............................................................................. 3.8-31 3.8.6 Battery Cell Parameters .............................................................................. 3.8-35 3.8.7 Distribution Systems - Operating ................................................................ 3.8-40 3.8.8 Distribution Systems - Shutdown ................................................................ 3.8-43 3.9 REFUELING OPERATIONS ...................................................................... 3.9-1 3.9.1 Refueling Equipment Interlocks .................................................................. 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock ....................................................... 3.9-3 3.9.3 Control Rod Position ................................................................................... 3.9-4 3.9.4 Control Rod Position Indication ................................................................... 3.9-5 3.9.5 Control Rod OPERABILITY - Refueling ...................................................... 3.9-7 (continued)

HATCH UNIT 1 iii Amendment No. 287

TABLE OF CONTENTS (continued) 3.9 REFUELING OPERATIONS (continued) 3.9.6 Reactor Pressure Vessel (RPV) Water Level .............................................. 3.9-8 3.9.7 Residual Heat Removal (RHR) - High Water Level ..................................... 3.9-9 3.9.8 Residual Heat Removal (RHR) - Low Water Level ...................................... 3.9-11 3.10 SPECIAL OPERATIONS............................................................................ 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation ...................................... 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing ....................................................... 3.10-3 3.10.3 Single Control Rod Withdrawal - Hot Shutdown .......................................... 3.10-5 3.10.4 Single Control Rod Withdrawal - Cold Shutdown ........................................ 3.10-8 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ................................ 3.10-12 3.10.6 Multiple Control Rod Withdrawal - Refueling ............................................... 3.10-14 3.10.7 Control Rod Testing - Operating ................................................................. 3.10-16 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling .......................................... 3.10-18 4.0 DESIGN FEATURES.................................................................................. 4.0-1 4.1 Site ............................................................................................................. 4.0-1 4.2 Reactor Core .............................................................................................. 4.0-1 4.3 Fuel Storage ............................................................................................... 4.0-2 5.0 ADMINISTRATIVE CONTROLS ................................................................ 5.0-1 5.1 Responsibility ............................................................................................. 5.0-1 5.2 Organization ............................................................................................... 5.0-2 5.3 Unit Staff Qualifications .............................................................................. 5.0-5 5.4 Procedures ................................................................................................. 5.0-6 5.5 Programs and Manuals ............................................................................... 5.0-7 5.6 Reporting Requirements ............................................................................. 5.0-20 5.7 High Radiation Area.................................................................................... 5.0-24 (continued)

HATCH UNIT 1 iv Amendment No. 287

TABLE OF CONTENTS (continued)

LIST OF TABLES 1.1-1 MODES ...................................................................................................... 1.1-6 3.1.4-1 Control Rod Scram Times........................................................................... 3.1-11 3.3.1.1-1 Reactor Protection System Instrumentation ................................................ 3.3-7 3.3.1.2-1 Source Range Monitor Instrumentation....................................................... 3.3-14 3.3.2.1-1 Control Rod Block Instrumentation ............................................................. 3.3-20 3.3.3.1-1 Post Accident Monitoring Instrumentation ................................................... 3.3-25 3.3.5.1-1 Emergency Core Cooling System Instrumentation ...................................... 3.3-39 3.3.5.2-1 Reactor Core Isolation Cooling System Instrumentation ............................. 3.3-47 3.3.6.1-1 Primary Containment Isolation Instrumentation........................................... 3.3-52 3.3.6.2-1 Secondary Containment Isolation Instrumentation ...................................... 3.3-59 3.3.6.3-1 Low-Low Set Instrumentation ..................................................................... 3.3-63 3.3.8.1-1 Loss of Power Instrumentation.................................................................... 3.3-68 3.8.6-1 Battery Cell Parameter Requirements......................................................... 3.8-31 LIST OF FIGURES 3.1.7-1 Sodium Pentaborate Solution Volume Versus Concentration Requirements ....................................................................................... 3.1-21 3.1.7-2 Sodium Pentaborate Solution Temperature Versus Concentration Requirements ....................................................................................... 3.1-22 3.4.1-1 Deleted ....................................................................................................... 3.4-3 3.4.9-1 Pressure/Temperature Limits for Inservice Hydrostatic and Inservice Leakage Tests ...................................................................................... 3.4-22 3.4.9-2 Pressure/Temperature Limits for Non-Nuclear Heatup, Low Power Physics Tests, and Cooldown Following a Shutdown ............................ 3.4-23 3.4.9-3 Pressure/Temperature Limits for Criticality ................................................. 3.4-24 4.1-1 Site and Exclusion Area Boundaries and Low Population Zone .................. 4.0-3 HATCH UNIT 1 v Amendment No. 266

Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant - Units 1 and 2 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Remove Table of Contents from Technical Specifications Attachment 1.c HNP Unit 2 Proposed Technical Specification Changes (Mark-up)

HATCH UNIT 2 TECHNICAL SPECIFICATIONS EFFECTIVE PAGE LIST Unless noted otherwise, all pages are Amendment No. 135.

PAGE AMENDMENT PAGE AMENDMENT 1.1-3 141 3.5-1 145 1.1-4 155 3.5-2 145 2.0-1 167 3.5-3 152 3.1-17 158 3.5-4 145 3.1-19 145 3.5-5 150 3.3-1 154 3.5-7 143 3.3-2 155 3.5-10 138 3.3-3 154 3.6-1 141 3.3-4 154 3.6-2 141 3.3-5 155 3.6-6 141 3.3-6 154 3.6-12 141 3.3-7 166 3.6-14 142 3.3-8 154 3.6-15 145 3.3-9 155 3.6-16 150 3.3-17 146 3.6-34 139 3.3-19 151 3.6-35 139 3.3-27 155 3.7-8 168 3.3-28 155 3.7-9 168 3.3-29 155 3.7-10 168 3.3-30 136 3.8-1 152 3.3-32 138 3.8-2 152 3.3-37 137 3.8-3 through 3.8-40 169 3.3-38 137 3.10-17 146 3.3-39 137 3.10-18 146 3.3-40 137 4.0-2 161 3.3-50 137 5.0-10 164 3.3-52 157 5.0-11 164 3.3-57 157 5.0-12 164 3.3-61 138 5.0-15 165 3.4-1 154 5.0-16 155 3.4-2 154 5.0-17 141 3.4-3 154 5.0-18 144 3.4-6 145 5.0-20 156 3.4-7 150 3.4-20 147 3.4-21 147 3.4-22 163 3.4-23 163 3.4-24 163 3.4-25 136 Notes: Amend No. 140 is associated with issuance of the Plant Hatch EPP.

Amend No. 149 supersedes Amend No. 148, which addresses Cycle 13.

HATCH UNIT 2 i Amendment No. 169

TABLE OF CONTENTS 1.0 USE AND APPLICATION .......................................................................... 1.1-1 1.1 Definitions ................................................................................................... 1.1-1 1.2 Logical Connectors ..................................................................................... 1.2-1 1.3 Completion Times ....................................................................................... 1.3-1 1.4 Frequency .................................................................................................. 1.4-1 2.0 SAFETY LIMITS (SLs) ............................................................................... 2.0-1 2.1 SLs ............................................................................................................. 2.0-1 2.2 SL Violations............................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .......... 3.0-1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ......................... 3.0-3 3.1 REACTIVITY CONTROL SYSTEMS .......................................................... 3.1-1 3.1.1 SHUTDOWN MARGIN (SDM) .................................................................... 3.1-1 3.1.2 Reactivity Anomalies .................................................................................. 3.1-4 3.1.3 Control Rod OPERABILITY ........................................................................ 3.1-5 3.1.4 Control Rod Scram Times........................................................................... 3.1-9 3.1.5 Control Rod Scram Accumulators ............................................................... 3.1-12 3.1.6 Rod Pattern Control .................................................................................... 3.1-15 3.1.7 Standby Liquid Control (SLC) System......................................................... 3.1-17 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves............................. 3.1-22 3.2 POWER DISTRIBUTION LIMITS ............................................................... 3.2-1 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ...... 3.2-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) .......................................... 3.2-2 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) ............................................ 3.2-4 3.3 INSTRUMENTATION ................................................................................. 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation ..................................... 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation ........................................... 3.3-10 3.3.2.1 Control Rod Block Instrumentation ............................................................. 3.3-15 3.3.2.2 Feedwater and Main Turbine Trip High Water Level ................................... 3.3-21 Instrumentation 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ........................................ 3.3-23 3.3.3.2 Remote Shutdown System ......................................................................... 3.3-26 (continued)

HATCH UNIT 2 i Amendment No. 210

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation ..................................................................................... 3.3-28 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation .............................................. 3.3-31 3.3.5.1 Emergency Core Cooling System (ECCS)

Instrumentation ..................................................................................... 3.3-34 3.3.5.2 RPV Water Inventory Control Instrumentation ............................................ 3.3-44 3.3.5.3 Reactor Core Isolation Cooling (RCIC) System Instrumentation ..................................................................................... 3.3-47 3.3.6.1 Primary Containment Isolation Instrumentation........................................... 3.3-51 3.3.6.2 Secondary Containment Isolation Instrumentation ...................................... 3.3-60 3.3.6.3 Low-Low Set (LLS) Instrumentation ............................................................ 3.3-64 3.3.7.1 Main Control Room Environmental Control (MCREC) System Instrumentation ..................................................................................... 3.3-68 3.3.8.1 Loss of Power (LOP) Instrumentation ......................................................... 3.3-70 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring ............................................................................................. 3.3-73 3.4 REACTOR COOLANT SYSTEM (RCS) ..................................................... 3.4-1 3.4.1 Recirculation Loops Operating .................................................................... 3.4-1 3.4.2 Jet Pumps .................................................................................................. 3.4-3 3.4.3 Safety/Relief Valves (S/RVs) ...................................................................... 3.4-5 3.4.4 RCS Operational LEAKAGE ....................................................................... 3.4-7 3.4.5 RCS Leakage Detection Instrumentation .................................................... 3.4-9 3.4.6 RCS Specific Activity .................................................................................. 3.4-11 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ........................................................................ 3.4-13 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown....................................................................... 3.4-16 3.4.9 RCS Pressure and Temperature (P/T) Limits.............................................. 3.4-18 3.4.10 Reactor Steam Dome Pressure .................................................................. 3.4-25 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ....................................................................... 3.5-1 3.5.1 ECCS - Operating ....................................................................................... 3.5-1 3.5.2 RPV Water Inventory Control...................................................................... 3.5-7 3.5.3 RCIC System .............................................................................................. 3.5-11 (continued)

HATCH UNIT 2 ii Amendment No. 235

TABLE OF CONTENTS (continued) 3.6 CONTAINMENT SYSTEMS ....................................................................... 3.6-1 3.6.1.1 Primary Containment .................................................................................. 3.6-1 3.6.1.2 Primary Containment Air Lock .................................................................... 3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ........................................... 3.6-7 3.6.1.4 Drywell Pressure ........................................................................................ 3.6-13 3.6.1.5 Drywell Air Temperature ............................................................................. 3.6-14 3.6.1.6 Low-Low Set (LLS) Valves.......................................................................... 3.6-15 3.6.1.7 Reactor Building-to-Suppression Chamber Vacuum Breakers .................... 3.6-17 3.6.1.8 Suppression Chamber-to-Drywell Vacuum Breakers .................................. 3.6-19 3.6.2.1 Suppression Pool Average Temperature .................................................... 3.6-21 3.6.2.2 Suppression Pool Water Level .................................................................... 3.6-24 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling .......................... 3.6-25 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ............................ 3.6-27 3.6.2.5 Residual Heat Removal (RHR) Drywell Spray ............................................ 3.6-29 3.6.3.1 (Deleted).....................................................................................................

3.6.3.2 Primary Containment Oxygen Concentration .............................................. 3.6-31 3.6.3.3 Drywell Cooling System Fans ..................................................................... 3.6-32 3.6.4.1 Secondary Containment ............................................................................. 3.6-33 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ...................................... 3.6-36 3.6.4.3 Standby Gas Treatment (SGT) System ...................................................... 3.6-39 3.7 PLANT SYSTEMS...................................................................................... 3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System.......................... 3.7-1 3.7.2 Plant Service Water (PSW) System and Ultimate Heat Sink (UHS) ..................................................................... 3.7-3 3.7.3 Diesel Generator (DG) 1B Standby Service Water (SSW)

System.................................................................................................. 3.7-6 3.7.4 Main Control Room Environmental Control (MCREC) System .................... 3.7-8 3.7.5 Control Room Air Conditioning (AC) System............................................... 3.7-12 3.7.6 Main Condenser Offgas .............................................................................. 3.7-16 3.7.7 Main Turbine Bypass System ..................................................................... 3.7-18 3.7.8 Spent Fuel Storage Pool Water Level ......................................................... 3.7-20 3.7.9 Turbine Building Ventilation (TB HVAC) Exhaust System Fans .................. 3.7-21 3.8 ELECTRICAL POWER SYSTEMS............................................................. 3.8-1 3.8.1 AC Sources - Operating .............................................................................. 3.8-1 3.8.2 AC Sources - Shutdown.............................................................................. 3.8-20 3.8.3 Diesel Fuel Oil and Transfer, Lube Oil, and Starting Air ..................................................................................... 3.8-23 3.8.4 DC Sources - Operating.............................................................................. 3.8-26 3.8.5 DC Sources - Shutdown ............................................................................. 3.8-31 (continued)

HATCH UNIT 2 iii Amendment No. 210

TABLE OF CONTENTS 3.8 ELECTRICAL POWER SYSTEMS (continued) 3.8.6 Battery Cell Parameters .............................................................................. 3.8-35 3.8.7 Distribution Systems - Operating ................................................................ 3.8-40 3.8.8 Distribution Systems - Shutdown ................................................................ 3.8-43 3.9 REFUELING OPERATIONS ...................................................................... 3.9-1 3.9.1 Refueling Equipment Interlocks .................................................................. 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock ....................................................... 3.9-3 3.9.3 Control Rod Position ................................................................................... 3.9-5 3.9.4 Control Rod Position Indication ................................................................... 3.9-6 3.9.5 Control Rod OPERABILITY - Refueling ...................................................... 3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level .............................................. 3.9-9 3.9.7 Residual Heat Removal (RHR) - High Water Level ..................................... 3.9-10 3.9.8 Residual Heat Removal (RHR) - Low Water Level ...................................... 3.9-12 3.10 SPECIAL OPERATIONS............................................................................ 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation ...................................... 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing ....................................................... 3.10-3 3.10.3 Single Control Rod Withdrawal - Hot Shutdown .......................................... 3.10-5 3.10.4 Single Control Rod Withdrawal - Cold Shutdown ........................................ 3.10-8 3.10.5 Single Control Rod Drive (CRD)

Removal - Refueling ............................................................................. 3.10-12 3.10.6 Multiple Control Rod Withdrawal - Refueling ............................................... 3.10-14 3.10.7 Control Rod Testing - Operating ................................................................. 3.10-16 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling .......................................... 3.10-18 4.0 DESIGN FEATURES.................................................................................. 4.0-1 4.1 Site ............................................................................................................. 4.0-1 4.2 Reactor Core .............................................................................................. 4.0-1 4.3 Fuel Storage ............................................................................................... 4.0-2 (continued)

HATCH UNIT 2 iv Amendment No. 232

TABLE OF CONTENTS (continued) 5.0 ADMINISTRATIVE CONTROLS ................................................................ 5.0-1 5.1 Responsibility ............................................................................................. 5.0-1 5.2 Organization ............................................................................................... 5.0-2 5.3 Unit Staff Qualifications .............................................................................. 5.0-5 5.4 Procedures ................................................................................................. 5.0-6 5.5 Programs and Manuals ............................................................................... 5.0-7 5.6 Reporting Requirements ............................................................................. 5.0-20 5.7 High Radiation Area.................................................................................... 5.0-24 (continued)

HATCH UNIT 2 v Amendment No. 232

TABLE OF CONTENTS (continued)

LIST OF TABLES 1.1-1 MODES ...................................................................................................... 1.1-6 3.1.4-1 Control Rod Scram Times........................................................................... 3.1-11 3.3.1.1-1 Reactor Protection System Instrumentation ................................................ 3.3-7 3.3.1.2-1 Source Range Monitor Instrumentation....................................................... 3.3-14 3.3.2.1-1 Control Rod Block Instrumentation ............................................................. 3.3-20 3.3.3.1-1 Post Accident Monitoring Instrumentation ................................................... 3.3-25 3.3.5.1-1 Emergency Core Cooling System Instrumentation ...................................... 3.3-39 3.3.5.2-1 Reactor Core Isolation Cooling System Instrumentation ............................. 3.3-47 3.3.6.1-1 Primary Containment Isolation Instrumentation........................................... 3.3-52 3.3.6.2-1 Secondary Containment Isolation Instrumentation ...................................... 3.3-59 3.3.6.3-1 Low-Low Set Instrumentation ..................................................................... 3.3-63 3.3.8.1-1 Loss of Power Instrumentation.................................................................... 3.3-68 3.8.6-1 Battery Cell Parameter Requirements......................................................... 3.8-36 LIST OF FIGURES 3.1.7-1 Sodium Pentaborate Solution Volume Versus Concentration Requirements ................................................................ 3.1-20 3.1.7-2 Sodium Pentaborate Solution Temperature Versus Concentration Requirements ................................................................ 3.1-21 3.4.1-1 Deleted ....................................................................................................... 3.4-3 3.4.9-1 Pressure/Temperature Limits for Inservice Hydrostatic and Inservice Leakage Tests ................................................................ 3.4-22 3.4.9-2 Pressure/Temperature Limits for Non-Nuclear Heatup, Low Power Physics Tests, and Cooldown Following a Shutdown ........................................................................................... 3.4-23 3.4.9-3 Pressure/Temperature Limits for Criticality ................................................. 3.4-24 4.1-1 Site and Exclusion Area Boundaries and Low Population Zone ..................................................................................................... 4.0-3 HATCH UNIT 2 vi Amendment No. 210

Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant - Units 1 and 2 Edwin I. Hatch Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 License Amendment Request to Remove Table of Contents from Technical Specifications Attachment 1.d VEGP Units 1 and 2 Proposed Technical Specification Changes (Mark-up)

TABLE OF CONTENTS 1.0 USE AND APPLICATION ..................................................................... 1.1-1 1.1 Definitions ............................................................................................. 1.1-1 1.2 Logical Connectors ............................................................................... 1.2-1 1.3 Completion Times ................................................................................. 1.3-1 1.4 Frequency ............................................................................................. 1.4-1 2.0 SAFETY LIMITS (SLs) ......................................................................... 2.0-1 2.1 SLs ....................................................................................................... 2.0-1 2.2 SL Violations ......................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .... 3.0-1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ................... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS .................................................... 3.1.1-1 3.1.1 SHUTDOWN MARGIN (SDM) .............................................................. 3.1.1-1 3.1.2 Core Reactivity ..................................................................................... 3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC)............................................ 3.1.3-1 3.1.4 Rod Group Alignment Limits ................................................................. 3.1.4-1 3.1.5 Shutdown Bank Insertion Limits ............................................................ 3.1.5-1 3.1.6 Control Bank Insertion Limits ................................................................ 3.1.6-1 3.1.7 Rod Position Indication ......................................................................... 3.1.7-1 3.1.8 PHYSICS Tests Exceptions - MODE 2 ................................................. 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS.......................................................... 3.2.1-1 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) (FQ Methodology) ....................... 3.2.1-1 N

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor ( F+ ) .................................. 3.2.2-1 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset ..................... 3.2.3-1 Control (RAOC) Methodology) 3.2.4 QUADRANT POWER TILT RATIO (QPTR) .......................................... 3.2.4-1 (continued)

Vogtle Units 1 and 2 i Amendment No. 107 (Unit 1)

Amendment No. 85 (Unit 2)

TABLE OF CONTENTS 3.3 INSTRUMENTATION ........................................................................... 3.3.1-1 3.3.1 Reactor Trip System (RTS) Instrumentation.......................................... 3.3.1-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation ............................................................................. 3.3.2-1 3.3.3 Post Accident Monitoring (PAM) Instrumentation .................................. 3.3.3-1 3.3.4 Remote Shutdown System .................................................................... 3.3.4-1 3.3.5 4.16 kV ESF Bus Loss of Power (LOP) Instrumentation........................ 3.3.5-1 3.3.6 Containment Ventilation Isolation Instrumentation................................. 3.3.6-1 3.3.7 Control Room Emergency Filtration System (CREFS)

Actuation Instrumentation .............................................................. 3.3.7-1 3.3.8 High Flux at Shutdown Alarm (HFASA) ................................................. 3.3.8-1 3.4 REACTOR COOLANT SYSTEM (RCS) ............................................... 3.4.1-1 3.4.1 RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits ....................................................... 3.4.1-1 3.4.2 RCS Minimum Temperature For Criticality ............................................ 3.4.2-1 3.4.3 RCS Pressure and Temperature (P/T) Limits ........................................ 3.4.3-1 3.4.4 5&6/RRSV02'(6DQG ............................................................. 3.4.4-1 3.4.5 RCS Loops 02'( ......................................................................... 3.4.5-1 3.4.6 5&6/RRSV02'( ......................................................................... 3.4.6-1 3.4.7 5&6/RRSV02'(/RRSV)LOOHG .................................................... 3.4.7-1 3.4.8 5&6/RRSV02'(/RRSV1RW)LOOHG .............................................. 3.4.8-1 3.4.9 Pressurizer............................................................................................ 3.4.9-1 3.4.10 Pressurizer Safety Valves ..................................................................... 3.4.10-1 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ............................ 3.4.11-1 3.4.12 Cold Overpressure Protection Systems (COPS) ................................... 3.4.12-1 3.4.13 RCS Operational LEAKAGE ................................................................. 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ....................................... 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation .............................................. 3.4.15-1 3.4.16 RCS Specific Activity............................................................................. 3.4.16-1 3.4.17 Steam Generator (SG) Tube Integrity ................................................... 3.4.17-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) .......................... 3.5.1-1 3.5.1 Accumulators ........................................................................................ 3.5.1-1 3.5.2 (&&62SHUDWLQJ ................................................................................ 3.5.2-1 3.5.3 (&&66KXWGRZQ................................................................................ 3.5.3-1 3.5.4 Refueling Water Storage Tank (RWST) ................................................ 3.5.4-1 3.5.5 Seal Injection Flow ................................................................................ 3.5.5-1 3.5.6 Recirculation Fluid pH Control System .................................................. 3.5.6-1 (continued)

Vogtle Units 1 and 2 ii Amendment No. 144 (Unit 1)

Amendment No. 124 (Unit 2)

TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS.................................................................. 3.6.1-1 3.6.1 Containment ......................................................................................... 3.6.1-1 3.6.2 Containment Air Locks .......................................................................... 3.6.2-1 3.6.3 Containment Isolation Valves ................................................................ 3.6.3-1 3.6.4 Containment Pressure .......................................................................... 3.6.4-1 3.6.5 Containment Air Temperature ............................................................... 3.6.5-1 3.6.6 Containment Spray and Cooling Systems ............................................. 3.6.6-1 3.6.7 Deleted ................................................................................................ 3.6.7-1 3.7 PLANT SYSTEMS ................................................................................ 3.7.1-1 3.7.1 Main Steam Safety Valves (MSSVs) ..................................................... 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs) ................................................... 3.7.2-1 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves............................................................................... 3.7.3-1 3.7.4 Atmospheric Relief Valves (ARVs) ........................................................ 3.7.4-1 3.7.5 Auxiliary Feedwater (AFW) System....................................................... 3.7.5-1 3.7.6 Condensate Storage Tank (CST) - (Redundant CSTs) ......................... 3.7.6-1 3.7.7 Component Cooling Water (CCW) System ........................................... 3.7.7-1 3.7.8 Nuclear Service Cooling Water (NSCW) System .................................. 3.7.8-1 3.7.9 Ultimate Heat Sink (UHS) ..................................................................... 3.7.9-1 3.7.10 Control Room Emergency Filtration System (CREFS) - Both Units Operating ............................................................................. 3.7.10-1 3.7.11 Control Room Emergency Filtration System (CREFS) - One Unit Operating ............................................................................... 3.7.11-1 3.7.12 Control Room Emergency Filtration System (CREFS) - Both Units Shutdown ............................................................................. 3.7.12-1 3.7.13 Piping Penetration Area Filtration and Exhaust System (PPAFES) ......................................................................... 3.7.13-1 3.7.14 Engineered Safety Features (ESF) Room Cooler and Safety Related Chiller System ....................................................... 3.7.14-1 3.7.15 Fuel Storage Pool Water Level ............................................................. 3.7.15-1 3.7.16 Secondary Specific Activity ................................................................... 3.7.16-1 3.7.17 Fuel Storage Pool Boron Concentration ................................................ 3.7.17-1 3.7.18 Fuel Assembly Storage in the Fuel Storage Pool .................................. 3.7.18-1 (continued)

Vogtle Units 1 and 2 iii Amendment No. 158 (Unit 1)

Amendment No. 140 (Unit 2)

TABLE OF CONTENTS 3.8 ELECTRICAL POWER SYSTEMS ....................................................... 3.8.1-1 3.8.1 AC 6RXUFHV2SHUDWLQJ ....................................................................... 3.8.1-1 3.8.2 $&6RXUFHV6KXWGRZQ ...................................................................... 3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, Starting Air, and Ventilation .............................................................................. 3.8.3-1 3.8.4 '&6RXUFHV2SHUDWLQJ ...................................................................... 3.8.4-1 3.8.5 '&6RXUFHV6KXWGRZQ ...................................................................... 3.8.5-1 3.8.6 Battery Parameters ............................................................................... 3.8.6-1 3.8.7 ,QYHUWHUV2SHUDWLQJ ............................................................................ 3.8.7-1 3.8.8 ,QYHUWHUV6KXWGRZQ............................................................................ 3.8.8-1 3.8.9 'LVWULEXWLRQ6\VWHPV2SHUDWLQJ ......................................................... 3.8.9-1 3.8.10 'LVWULEXWLRQ6\VWHPV6KXWGRZQ ......................................................... 3.8.10-1 3.9 REFUELING OPERATIONS ................................................................. 3.9.1-1 3.9.1 Boron Concentration ............................................................................. 3.9.1-1 3.9.2 Unborated Water Source Isolation Valves ............................................. 3.9.2-1 3.9.3 Nuclear Instrumentation ........................................................................ 3.9.3-1 3.9.4 Containment Penetrations ..................................................................... 3.9.4-1 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation

+LJK:DWHU/HYHO ....................................................................... 3.9.5-1 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation

/RZ:DWHU/HYHO ........................................................................ 3.9.6-1 3.9.7 Refueling Cavity Water Level ................................................................ 3.9.7-1 4.0 DESIGN FEATURES ............................................................................ 4.0-1 4.1 Site ....................................................................................................... 4.0-1 4.2 Reactor Core ........................................................................................ 4.0-1 4.3 Fuel Storage ......................................................................................... 4.0-2 5.0 ADMINISTRATIVE CONTROLS ........................................................... 5.1-1 5.1 Responsibility ........................................................................................ 5.1-1 5.2 Organization ......................................................................................... 5.2-1 5.3 Unit Staff Qualifications ......................................................................... 5.3-1 5.4 Procedures ........................................................................................... 5.4-1 5.5 Programs and Manuals ......................................................................... 5.5-1 5.6 Reporting Requirements ....................................................................... 5.6-1 5.7 High Radiation Area .............................................................................. 5.7-1 (continued)

Vogtle Units 1 and 2 iv Amendment No. 133 (Unit 1)

Amendment No. 112 (Unit 2)

TABLE OF CONTENTS (continued)

LIST OF TABLES 1.1-1 MODES ................................................................................................ 1.1-7 3.3.1-1 Reactor Trip System Instrumentation .................................................... 3.3.1-14 3.3.2-1 Engineered Safety Feature Actuation System Instrumentation ............................................................................. 3.3.2-9 3.3.3-1 Post Accident Monitoring Instrumentation ............................................. 3.3.3-6 3.3.4-1 Remote Shutdown System Instrumentation and Controls ..................... 3.3.4-3 3.3.6-1 Containment Ventilation Isolation Instrumentation................................. 3.3.6-5 3.3.7-1 CREFS Actuation Instrumentation......................................................... 3.3.7-6 3.7.1-1 Maximum Allowable Power Range Neutron Flux High Trip Setpoint with Inoperable Main Steam Safety Valves...................... 3.7.1-3 3.7.1-2 Main Steam Safety Valve Lift kSettings ................................................. 3.7.1-4 (continued)

Vogtle Units 1 and 2 v Amendment No. 144 (Unit 1)

Amendment No. 124 (Unit 2)

LIST OF FIGURES 2.1.1-1 Reactor Core Safety Limits ................................................................... 2.0-2 3.4.16-1 Reactor Coolant Dose Equivalent I-131 Reactor Coolant Specific Activity Limit Versus Percent of Rated Thermal Power with the Reactor Coolant Specific

$FWLYLW\!&LJUDP'RVH(TXLYDOHQW,-131.................................. 3.4.16-4 3.7.18-1 Vogtle Unit 1 Burnup Credit Requirements for All Cell Storage ............................................................................. 3.7.18-3 3.7.18-2 Vogtle Unit 2 Burnup Credit Requirements for All Cell Storage ............................................................................. 3.7.18-4 4.3.1-1 Vogtle Units 1 and 2 Empty Cell Checkerboard Storage Configurations .................................................................. 4.0-6 4.3.1-2 Vogtle Unit 2 3x3 Checkerboard Storage Configuration ....................... 4.0-7 4.3.1-3 Vogtle Units 1 and 2 Interface Requirements (All Cell to Checkerboard Storage) ................................................ 4.0-8 4.3.1-4 Vogtle Unit 2 Interface Requirements (Checkerboard Storage Interface) ................................................. 4.0-9 4.3.1-5 Vogtle Unit 2 Interface Requirements (3x3 Checkerboard to All Cell Storage) ......................................... 4.0-10 4.3.1-6 Vogtle Unit 2 Interface Requirements (3x3 to Empty Cell Checkerboard Storage) ................................... 4.0-11 4.3.1-7 Vogtle Unit 1 IFBA Credit Requirements for All Cell Storage ............................................................................. 4.0-12 4.3.1-8 Vogtle Unit 2 Burnup Credit Requirements for 3-out-of-4 Storage ......................................................................... 4.0-13 4.3.1-9 Vogtle Unit 2 IFBA Credit Requirements for Center Assembly for 3x3 Storage ............................................................. 4.0-14 4.3.1-10 Vogtle Unit 2 Burnup Credit Requirements for Peripheral Assemblies for 3x3 Storage ............................................................................. 4.0-15 5.5.6-1 Deleted.

Vogtle Units 1 and 2 vi Amendment No. 147 (Unit 1)

Amendment No. 127 (Unit 2)

Retrieved from "https://kanterella.com/w/index.php?title=NL-21-0160,_License_Amendment_Request_to_Remove_Table_of_Contents_from_Technical_Specifications&oldid=3408960"