ML20197C829

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Proposed Tech Specs,Revising Remote Shutdown Surveillances & Limiting Conditions for Operation
ML20197C829
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 10/24/1986
From:
GEORGIA POWER CO.
To:
Shared Package
ML20197C818 List:
References
TAC-63570, TAC-63571, NUDOCS 8611070056
Download: ML20197C829 (35)
v • d • e


Text

0 TABLE OF CONTENTS SCction Section Page 1.0 DEFINITIONS 1. 0-1 SAFETY LIMITS LIMITING SAFETY SYSTEM SETTINGS 1.1. FUEL CLADDING INTEGRITY 2.1. FUEL CLADDING INTEGRITY 1.1 -1 A. Reactor Pressure >800 psia A. Trip Settings 1.1 -1 and Core Flow >10% of Rated B. Core Thermal Power Limit (Reactor 1.1 -1 Pressure 5 800 psia C. Power Transient 1.1 -1 D. Reactor Water Level (Hot or Cold 1.1-2 Shutdown Condition)

B. Reactor Water Level Trip Settings 1.1-5 Which Initiate Core Standby Cooling Systems (CSCS) 1.2. REACTOR COOLANT SYSTEM INTEGRITY 2.2. REACTOR COOLANT SYSTEM INTEGRITY 1. 2-1 l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.1. REACTOR PROTECTION SYSTEM 4 .1. REACTOR PROTECTION SYSTEM 3.1 -1 A. Sources of a Trip Signal Which A. Test and Calibration Requirements 3 .1 -1 Initiate a Reactor Scram for the RPS B. Core Maximum Fraction of Limiting B. Core Maximum Fraction of Limiting 3.1 -1 Power Density (CMFLPD) Power Density (CMFLPD)

C. RPS Response Time 3.2. PROTECTIVE INSTRUMENTATION 4.2. PROTECTIVE INSTRUMENTATION 3. 2-1 l A. Instrumentation Which Initiates A. Instrumentation Which Initiates 3 . 2-1 Reactor Vessel and Primary Reactor Vessel and Primary Containment Isolation -

Containment Isolation B. Instrumentation Which Initiates B. Instrumentation Which Initiates 3.2-1 or Controls HPCI or Controls HPCI C. Instrumentation Which Initiates C. Instrumentation Which Initiates 3.2-1 l or Controls RCIC or Controls RCIC D. Instrumentation Which Initiates D. Instrumentation Which Initiates . 3. 2-1 or Controls ADS or Controls ADS HATCH - UNIT 1 fhkiO gC 321 i Proposed TS/0078q/8630-0 p PDR l

O SICITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 4.2. PROTECTIVE INSTRL' MENTATION (CONT') 3. 2-1 3.2. PROTECTIVE INSTRUMENTATION (CONT')

E. Instrumentation Which Initiates E. Instrumentation Which 3.2-1 or Controls the LPCI Mode of RHR Initiates or Controls the LPCI Mode of RHR F. Instrumentation Which Initiates F. Instrumentation Which In- 3.2-1 or Controls Core Spray Otiates or Controls Core Spray G. Neutron Monitoring Instrumentation G. Neutron Monitoring Instru- 3.2-1 Which Initiates Control Rod Blocks mentation Which Initiates Control Rod Blocks H. Radiation Monitoring Systems H. Radiation Monitoring Systems 3.2-1 Which Limit Radioactivity Release Which Limit Radioactivity Release I. Instrumentation Which Initiates I. Instrumentation Which Ini- 3. 2 -1 Recirculation Pump Trip tiates Recirculation Pump Trip J. Instrumentation Which Monitors J. Instrumentation Which Mon- 3.2-1 Leakage Into The Drywell itors Leakage Into The Dry-well K. Instrumentation Which Provides K. Instrumentation Which Provides 3.2-1 Surveillance Information Surveillance Information L. Instrumentation Which Initiates L. Instrumentation Which Initiates 3.2-1 the Disconnection of Offsite the Disconnection of Offsite Power Sources Power Sources

0. Instrumentation Which Initiates M. Instrumentation Which Initiates 3.2-1 Energization of Onsite Power Energization of Onsite Power Sources Sources N. Instrumentation Which Arms Low N. Instrumentation Which Arms Low 3.2-1 Low Set S/RV System Low Set S/RV System O. Instrumentation Which Monitors 0. Instrumentation Which Monitors 3. 2-1 Components Controlled From the Components Controlled From the Remote Shutdown Panel Remote Shutdown Panel 3.3. REACTIVITY CONTROL 4.3. REACTIVITY CONTROL 3. 3-1 A. Core Reactivity Margin A. Core Reactivity Margin 3.3-1
8. Inoperable Control Rods 8. Operable Control Rod Exercise 3.3-1 Requirements C. Control Rod Drive System C. Control Rod Drive System 3.3-2
0. Minimum Count Rate for D. Minimum Count Rate for 3.5-4 Rod Withdrawal Rod Withdrawal E. Rod Worth Inventory E. Rod Worth Inventory 3.3-4 Determination Dete rmination F. Operation With a Limiting F. Operation With a Limiting 3.3-5 Control Rod Pattern Control Rod Pattern HATCH - UNIT 1 11 Proposed TS/0078q/8630-0

4 S'ction Section PaSe LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3. REACTIVITY CONTROL (CONT') 4.3. REACTIVITY CONTROL (CONT')

G. Limiting the Worth of a G. Limiting the Worth of a 3.3-5 Control Rod Below 20% Control Rod Below 20%

Rated Thermal Power Rated Thermal Power H. Shutdown Requirements 3.3-7 3.4. STANDBY LIQUID CONTROL SYSTEM 4.4. STANDBY LIQUID CONTROL SYSTEM 3.4-1 A. Normal System Availability A. Normal Operational Tests 3.4-1

8. Operating with Inoperable B. Surveillance with Inoperable 3.4-2 Components Components C. Sodium Pentaborate Solution C. Sodium Pentaborate Solution 3.4-2 D. Shut down Requirements 3.4-3 3.5. CORE AND CONTAINMENT COOLING 4.5. CORE AND CONTAINMENT COOLING 3.5-1 SYSTEMS SYSTEMS A. Core Spray (CS) System A. Core Spray (CS) System 3.5-1 B. Residual Heat Removal (RHR) B. Residual Heat Removal (RHR) 3.5-2 System (LPCI and Containment System (LPCI 49d Containment Cooling Mode) Cooling Mode)

C. RHR Service Water System C. RHR Service Water System 3.5-5 D. High Pressure Coolant Injection D. High Pressure Coolant In- 3.5-6 (HPCI) System jection (HPCI) System E. Reactor Core Isolation Cooling E. Reactor Core Isolation 3.5-7 (RCIC) System Cooling (RCIC) System F. Automatic Depressurization F. Automatic Depressurization 3.5-9 System (ADS) System (ADS)

G. Minimum Core and Containment G. Surveillance of Core and 3.5-10 Cooling Systems Availability Containment Cooling Systems H. Maintenance of Filled Discharge H. Maintenance of Filled 3.5-10 Pipes Discharge Pipes l

I. Minimum River Flow I. Minimum River Flow 3.5-11 J. Plant Service Water System J. Plant Service Water System 3.5-12 K. Equipment Area Coolers K. Equipment Area Coolers 3.5-13 L. Remote Shutdown Panel L. Remote Shutdown Panel 3.5-13a HATCH - UNIT 1 iii Proposed TS/00784/8630-0

SURVEILLANCE REQUIRENENTS

. LIMITING CONDITIONS FOR OPERATION 4.6. PRIMARY SYSTEM 800NDARY 3. 6-1 3.6. PRIMARY SYSTEM BOUNDARY A. Reactor Coolant Heatup 3.6-1 A. Reactor Coolant Heatup and Cooldown and Cooldown Reactor Vessel Temperature B. Reactor Vessel Temperature 3.6-1 B.

and Pressure and Pressure C. Reactor Vessel Head Stud 3.6-2 C. Reactor Vessel Head Stud Tensioning Tensioning D. Idle Recirculation Loop 3.6-2 D. Idle Recirculation Loop Startup Startup Recirculation Pump Start E. Re' circulation Pump Start 3.6-3 E.

Reactor Coolant Chemistry F. Reactor Coolant Chemistry 3.6-4 F.

G. Reactor Coolent Leakag'e 3.6-7 G. Reactor Coolant Leakage H. Relief / Safety Valves 3.6-9 l H. Relief / Safety Valves Jet Pumps 3.6-9b l I. Jet Pumps I.

J. Recirculation Pump Speeds 3.6-9b l J. Recirculation Pump Speeds K. Structural Integrity 3.6-10 K. Structural Integrity L. Snubbers 3. 6-10a L. Snubbers 4.7. 03NTAINMENT SYSTEMS 3.7-1 3.7. CONTAIN#ENT SYSTEMS A. Primary containment 3.7-1 A. Primary Containment B. Standby Gas Treatment System B. Standby Gas Treatment System 3.7-1Cb l Secondary Containment C. $ccondary Containment 3.7-12 C.

D. Primary Containment 3.7-13

0. Primary Containment Isolation Valves Isolation Yalves 4.8. RADI0 ACTIVE MATERIALS 3.8-1 3.8. RADIOACTIVE MATERIALS A. Miscellaneous Radioactive 3. 8-1 A. Miscellaneous Radioactive Materials Sources Materials Sources 4.9. AUXILIARY ELECTRICAL SYSTEMS 3.9-1 3.9. AUXILIARY ELECTRICAL SYSTEh5 A. Auxiliary Electrical 3.9-1 A. Requirements for Reactor Startup Systems Equipment iv Proposed TS/0078q/8630-0 HATCH - UNIT 1

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9. AUXILIARY ELECTRICAL SYSTEMS (CONT'0) 4.9. AUXILIARY ELECTRICAL SYSTEMS (CONT'0)

B. Requirements for Continued B. Requirements for continued 3.9-4a l Operation With Inoperable Components Operation Without Inoperable Components C. Diesel Generator Requirements 3.9-6 (Reactor in the Shutdown or Refuel Mode)

D. Electric Power Monitoring for the D. Electric Power Monitoring for 3.9-6a [

Reactor Protection System Reactor Protection System l-3.10. REFUELING 4.10. REFUELING 3.10-1 A. Refueling Interlocks A. Refueling Interlocks 3.10-1 B. Fuel Loading 3.10-1 C. Core Monitoring During Core C. Core Monitoring During Core 3.10-2 Alternations Alternations D. Spent Fuel Pool Water Level 0. Spent Fuel Pool Water Level 3.10-2 E. Control Rod Drive Maintenance E. Control Rod Drive Maintenance 3.10-2 F. Reactor Building Cranes F. Reactor Building Cranes 3.10-4 G. Spent Fuel Cask Lifting G. Spent Fuel Cask Lifting 3.10-5 Trunnions and Yoke Trunnions and Yoke H. Time Limitation 3.10-5 I. Crane Travel - Spent Fuel Storage 1. Crane Travel - Spent Fuel Storage 3.10-5 Pool Pool 3.11. FUEL RODS 4.11. FUEL R005 3.11-1 A. Average Planar Linear Heat A. Average Planar Linear Heat 3.11-1 Generation Rate (APLHGR) Generation Rate (APLHGR)

B. Linear Heat Generation Rate B. Linear Heat Generation Rate 3.11-1 (LHGR) (LHGR)

C. Minimum Critical Power C. Minimum Critical Power 3.11-2 l Ratio (MCPR) Ratio (MCPR)

D. Reporting Requirements 3.11-2a l 3.12. MAIN CONTROL ROOM ENVIRONMENTAL 4.12. MAIN CONTROL ROOM ENVIRONMENTAL 3.12-1 SYSTEM SYSTEM A. Ventilation System Operability A. Ventilation System Tests 3.12-1 B. Isolation Valve Operability B. Isolation Valve 3.12-2 and Closing Time Testing C. Radiation Monitors C. Radiation Monitors 3.12-3

0. Shutdown Requirements 3.12-3 E. Chlorine Monitors E. Chlorine Monitors 3.1. 2-3 3.13. FIRE PROTECTION SYSTEMS 4.13. FIRE PROTECTION SYSTEMS

- l HATCH - UNIT 1 v Froposed TS/00784/B630-0

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. Section Section Page LIMITING CONDITIONS FOR OPERATION SURVEILLANCE SE0VIREMENTS 3.14 RADI0 ACTIVE EFFLUENT 4.14 RADI0 ACTIVE EFFLUENT INSTRUMENTATION INSTRUMENTATION 3.15 RADI0 ACTIVE EFFLUENT 4.15 RADIOACTIVE EFFLUENT

. CONCENTRATION AND DOSE CONCENTRATION AND DOSE 3.16 ENVIRONNENTAL 4.16 ENVIRONMENTAL MONITORING PROGRAM MONITORING PROGRAM 5.0 MAJOR DESIGN FEATURES 5.0-1 A. Site 5.0-1 B. Reactor Core 5.0-1 C. Reactor Vessel 5.0-1 D. Containment 5.0-1 E. Fuel Storage 5.0-1 F. Seismic Design 5.0-2 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 Responsibility 6-1 6.2 Organization 6-1 6.3 Unit Staff Qualifications 6-6 6.4 Training 6-6 6.5 Review and Audit 6-6 6.6 Reportable Occurrence Action 6-12 4 6.7 Safety Limit Violation 6-12 l 6.8 Procedures 6-13 6.9 Reporting Requirements 6-14 l 6.10 Record Retention 6-18 l 6.11 Radiation Protection Program 6-20 )

6.12 High Radiation Area 6-20 6.13 Integrity of Systems Outside Containment 6-21 6.14 Iodine Monitoring 6-21 6.15 Environmental Qualification 6-22 6.16 Post-Accident Sampling and Analysis 6-23 6.17 Offsite Dose Calculation Manual 6-23 t

i

. HATCH - UNIT 1 vi Proposed TS/007eq/8630-0 I

LIST OF TABLES Page Table Title Frequency Notations 1.0-11 1.1 Reactor Protection System (RPS) Instrumentation 3.1 -3 3.1 -1 Requirements Reactor Protection System (PRS) Instrumentation 3.1 -7 4.1 -1 Functional Test, Functional Test Minimum Frequency, and Calibration Minimum Frequency

3. 2-1 Instrumentation Which Initiates Reactor Vessel 3.2-2 and Primary Containment Isolation Instrumentation Which Initiates or Controls 3.2-5 3.2-2 HPCI 3.2-3 Instrumentation Which Initiates or Controls 3.2-8 RCIC 3.2-4 Instrumentation Which Initiates or Controls 3.2-10 ADS 3.2-5 Instrumentation Which Initiates or Controls 3.2-11 the LPCI Mode of RHR 3.2-6 Instrumentation Which Initiates or Controls 3.2-14 Core Spray 3.2-7 Neutron Monitoring Instrume'.'ation Which 3.2-15 l Initiates Control Rod Blocks ,

l 3.2-8 Radiation Monitoring Systems Which Limit 3.2-18 i Radioactivity Release 3.2-9 Instrumentation Which Initiates Recirculation 3.2-20 Pump Trip 3.2-10 Instrumentation Which Monitors Leakage into 3.2-21 g

the Drywell l 3.2-22 3.2-11 Instrumentation Which Provides Surveillance

- Information 3.2-12 Instrumentation Which Initiates the 3.2-23b l Disconnection of Offsite Power Sources 3.2-13 Instrumentation Which Initiates Energization 3.2-23c l of Onsite Power Sources 3.2-14 Instrumentation Which Arms Low Low Set S/RV System 3.2-23d 3.2-15 Instrumentation Which Monitors Components Controlled 3.2-23e from the Remote Shutdown Panel HATCH - UNIT 1 vii Proposed TS/0078q/8630-0 l

. LIST OF TABLES (Continued)

Table Title Page 4 . 2 -1 Check, Functional Test, and Calibration Minimum 3.2-24 Frequency for Instrumentation Which Initiates Reactor Vessel and Primary Containment Isolation 4.2-2 Check, Functional Test, and Calibration Minimum 3.2-27 Frequency for Instrumentation Which Initiates or Controls HPCI 4.2-3 Check, Functional Test, and Calibration Minimum 3.2-30 Frequency for Instrumentation Which Initiates or Controls RCIC

4. 2 -4 Check, Functional Test, and Calibration Minimum 3.2-33 Frequency for Instrumentation Which Initiates or Controls ADS 4.2-5 Check, Functional Test, and Calibration Minimum 3.2-35 Frequency for Instrumentation Which Initiates or Controls the LPCI Mode of RHR 4.2-6 Check, Functional Test, and Calibration Minimum 3.2-38 Frequency for Instrumentation Which Initiates or Controls Core Spray 4.2-7 Check, Functional Test, and Calibration Minimum 3.2-40 Frequency for Neutron Monitoring Instrumentation Which Initiates Control Rod Blocks 4.2-8 Check, Functional Test, and Calibration Minimum 3.2-42 Frequency for Radiation Monitoring Systems Which Limit Radioactivity Release 4.2-9 Check and Calibration Minimum Frequency for 3.2-45 Instrumentation Which Initiates Recirculation Pump Trip 4.2-10 Check, Functional Test, and Calibration Minimum 3.2-46 Frequency for Instrumentation Which Monitors Leakage into the Drywell 4.2-11 Check and Calibration Minimum Frequency for 3.2-48 Instrumentation Which Provides Surveillance Information 4.2-12 Instrumentation Which Initiates the 3. 2-49a Disconnection of Of fsite Power Sources 4.2-13 Instrumentation Which Initiates Energization 3.2-49b by Onsite Power Sources 4.2-14 Check, Functional Test, and Calibration Minimum 3. 2-49 c Frequency for Instrumentation Which Arms the Low Low Set S/RV System 4.2-15 Check and Calibration Minimum Frequency for 3.2-49d-Instrumentation Which Monitors Components Controlled From the Remote Shutdown Panel HATCH - UNIT 1 viii Proposed TS/00784/8630-0

LIST OF TABLES (Concluded)

Table Title Page 3.7-1 Primary Containment Isolation Valves 3.7-16 3.7-2 Testable Penetrations with Double 0-Ring Seals 3.7-21 3.7-3 Testable Penetrations with Testable Bellows 3.7-22 3.7-4 Primary. Containment Testable Isolation Valves 3.7-23 3.13-1 Fire Detectors 3.13-2 3.13-2 Fire Hose Stations 3.13-9 3.14.1-1 Radioactive Liquid Effluent Monitoring 3.14-2" Instrumentation 3.14.2-1 Radioactive Gaseous Effluent Monitoring 3.14-7 Instrumentation 4.14.1-1 Radioactive Liquid Effluent Monitoring 3.14-4 Instrumentation Surveillance Requirements 4.14.2-1 Radioactive Gaseous Effluent Monitoring 3.14-11 Instrumentation Surveillance Requirements 4.15.1-1 Radioactive Liquid Effluent Sampling and 3.15-2 Analysis Program 4.15.2-1 Radioactive Gaseous Waste Sampling and 3.15-10 Analysis Program 3.16.1-1 Radiological Environmental Monitoring Program 3.16-4 3.16.1-2 Reporting Levels for Radioactivity Concentra- 3.16-7 tions in Environmental Samples 4.16.1-1 Lower Limit of Detection 3.16-8 6.2.2-1 Minimum Shift Crew Composition 6-4 6.9.1.7-1 Environmental Radiological Monitoring Program 6-15b Summary l 6.9.2-1 Special Reporting Requirements 6-19 HATCH - UNIT 1 ix Proposed TS/0078q/8630-0

LIST OF FIGURES ,

Fiqure Title 1.1 -1 Core Thermal Power Safety Limit Versus Core Flow Rate 2.1 -1 Reactor Vessel Water Levels 4.1 -1 Graphical Aid for the Selection of an Adequate Interval Between Tests 4.2-1 System Unavailability 3.4-1 Sodium Pentabcrate Solution Volume Versus Concentration Requirements 3.4-2 Sodium Pentaborate Solution Temperature Versus Concentration Requirements

3. 6-1 Pressure versus Minimum Temperature for Pressure Tests, Such as Required by ASME Section XI 3.6-2 Pressure versus Minimum Temperature for Non-Nuclear Heatup/Cooldown and Low Power Physics Test 3.6-3 Pressure versus Minimum Temperature for Core Critical Operation other than Low Power Physics Tests (Includes 40*F Margin Required by 10CFR50 Appendix G) 3.6-4 Deleted 3.6-5 Thermal Power Limitations During Operation with less Than Tuo Reactor Coolant System Recirculation Loops in Operation 3.11-1 (Sheet 1) Limiting Value for APLHGR (Fuel Type 3) 3.11-1 (Sheet 2) Limiting Value for APLHGR (Fuel Types 1 and 2) 3.11-2 deleted 3.11-3 Kg Factor 3.15-1 Unrestricted Area Boundary l
6. 2.1 -1 Offsite Organization 6.2.2-1 Unit Organization HATCH - UNIT 1 x Proposed TS/0078q/8630-0

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2 PROTECTIVE INSTRUMENTATION 4.2 PROTECTIVE INSTRUMENTATION Applicability ADDlicability The Limiting Conditions for Operation The Surveillance Requirements apply to the plant instrumentation apply to the instrumentation which performs a protective function, which performs a protective function.

Objective Objective The objective of the Limiting Condi- The objective of the Surveillance tions for Operation is to assure the Requirements is to specify the type operability of protective instrumen- and frequency of surveillance to tation. be applied to protective instru-mentation.

Specifications Specifications The Limiting Conditions for Operation The check, functional test, and of the protective instrumentation af- calibration minimum frequency for fecting each of the following protec- protective instrumentation affect- ,

tive actions shall be as indicated in ing each of the following protec-the corresponding LCO table. tive actions shall be as indicated in the corresponding SR table.

Protective Action LCO Table SR Table A. Initiates Reactor Vessel 3.2-1 4.2-1 and Containment Isolation B. Initiates or Controls HPCI 3.2-2 4.2-2 C. Initiates or Controls RCIC 3.2-3 4.2-3

0. Initiates or Controls ADS 3.2-4 4.2-4 E. Initiates or Controls the 3.2-5 4.2-5 LPCI Mode of RHR F. Initiates or Controls Core 3.2-6 4.2-6 Spray G. Initiates Control Rod Blocks 3.2-7 4.2-7 H. Limits Radioactivity Release 3.2-8 4.2-8 I. Initiates Recirculation Pump 3.2-9 4.2-9 Trip J. Monitors Leakage Into the 3.2-10 4.2-10 Drywell .

K. Provides Surveillance 3.2-11 4.2-11 Information L. Initiates Disconnection of 3.2-12 4.2-12 Offsite Power Sources M. Initiates Energization by 3.2-13 4.2-13 Onsite Power Sources N. Arms the Low Low Set S/RV 3.2-14 4.2-14 System O. Monitors Components Controlled 3.2-15 4.2-15  ;

From the Remote Shutdown Panel i

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.L. Remote Shutdown Panel -4.5.L. Remote Shutdown Panel The Remote Shutdown Panel (the The Remote Shutdown Panel shall be Panel) shall be operable with the demonstrated Operable at least once capability of remotely bringing per 18 months during shutdown witl.

the reactor to and maintaining the the head removed from the reactor reactor in a Cold Shutdown condition vessel by: i I following loss of control from or  ;

habitability of the Main Control 1. Switching control from the Main l Room. The Panel shall be continuously Control Room to the Panel

  • and I monitored whenever control is at the verifying that:

. Panel.

a. All valves controlled from Acolicability the Panel, except the safety /

relief valves, can be opened i Conditions 1, 2, and 3. and closed with the centrols  !

at the Panel, Actions I

b. All pumps controlled from the
1. With the Resote Shutdown Panel Panel, except the RCIC pump, inoperable, restore the Panel to can be started and stopped operable status within 30 days or with the controls at the Panel,  ;

be in at least Hot Shutdown within and  ;

the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the following 24 c. The safety / relief valves con-hours. trolled from the Panel can be opened and closed with the

2. With a component controlled from controls at the Panel by the Remote Shutdown Panel inoperable verifying that their solenoid for reasons unrelated to the Panel, valves actuate.

the component's appropriate Limiting Condition for Operation Action 2. Switching control from the Panel to statement shall be followed, and the Main Control Room following Specification 3.5.L.1 is not completion ** of the above tests applicable, and verifying that:

a. All valves controlled from the Panel, except the safety / relief valves, can be opened with the controls in the Main Control Room,
b. All pumps controlled from the Panel, except the RCIC pump, can be started and stopped with the controls in the Main Control Room, and
c. The safety / relief valves con-trolltd from the Panel be i

opened and closed with the controls in the Main Control Room by verifying that their solenoid valves actuate.

  • When control is at the Panel during the test, the Panel shall be continuously monitored.
    • This shall be done immediately following the ccepletion of the tests required by Specification 4.5.L.1 and the return of control to the Main Control Room, except for those components not required to be operable. For those components not required to be operable, this requirement may be satisfied by operability tests perforned af ter the test of Specification 4.5.L.1 and before the component is i declared operable. This operability test must involve the direct use of Main j Control Room controls, d

HATCH - UNIT 1 3. 5-13a Proposed TS/00004/0630-0

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I i HATCH - UNIT 1 3.5-13b Proposed TS/0080q/8630-0 1

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BASES FOR LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3.5.J/4.5.J Plant Service Water System The Plant Service Water (PSW) system consists of two subsystems (divisions) of two pumps each and a separate standby service water pump system for diesel generator 18. During normal full power operation the two subsystems function as a 3 out of 4 pump cross connected system supplying cooling water to the turbine ano reactor building cooling i systems. In the event of an accident signal, non safety-related cooling loads are iso-lated and the PSW pumps in the two subsystems supply cooling water to diesel generators

' 1A and 1C, the reactor building cooling system and the control room air conditioners, while the standby service water pump is available to automatically supply cooling water to diesel generator 1B should it be needed. Additionally, diesel 18 has a manual back-up water supply available from the Unit 1 Division 1 or Division 2 PSW subsystems so

' that during maintenance on the standby diesel service water pump, either division of the PSW system can manually be aligned to supply cooling water to the 18 diesel. The two subsystems and the standby service water pump system are split in th( accident mode for greater reliability with one pump in each of the two subsystems automatically starting while a start signal from diesel generator 18 initiates standby service water pump operation. Only one of the Division 1 PSW pumps and one of the Division 2 PSW pumps are required for cooling diesel generators l A and 1C, respectively, while the standby ser-vice water pump provides adequate cooling water to diesel generator 18. In the event that the standby service water pump is inoperable, the HNP-1 Division 1-Division 2 intertie supply piping can be aligned to cool the IB diesel. In this condition, one PSW

. pump is capable of supplying the cooling requirements for the reactor building cooling system, the control room air conditioners, and the 1 A,1B, and 1C diesel generators.

The PSW system can supply all power generation systems at full load and the diesel

generators with redundancy if one PSW pump and/or the standby service water pump are incperable. Hence, a 60-day outage time is justified if the standby service water pump
is inoperable since all four PSW pumps are available (divisional intertie to 1B diesel required). In addition, a 30-day outage is justified if one PSW pump is inoperable, or if one PSW pump and the standby service water pump are inoperable (divisional intertie to 18 diesel required). Should two PSW pumps (or one subsystem) become inoperable, or should two PSW pumps (or one subsystem) and the standby service water pump become incperable (division intertie to 18 diesel required) plant operation will probably only continue at less than full power. However, safety-related loads are still adequately powered for these conditions. Therefore, a 7 day outage time is justified for such

! events.

1 K. Engineering Safety Features EauiDment Area Coolers The equipment area cooler in each pump compartment is capable of providing adequate j ventilation flow and cooling. Engineering analyses indicate that the temperature rise in safeguard compartments without adequate ventilation flow or cooling is such that continued operation of the safeguard equipment or associated auxiliary equip-l ment cannot be assured.

The surveillance and testing of the equipment area coolers in each of their various odes is accomplished during the testing of the equipment served by these coolers.

The testing is adequate to assure the operability of the equipment area coolers.

HATCH - UNIT 1 3.5-21 Proposed TS/0080q/8630-0

. BASES FOR LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS L. Remote Shutdown Panel The Remote Shutdown Panel (the Panel), located on the 130 f t elevation of the Reactor Building, provides the operator with the capability of bringing the reactor to the Cold Shutdown condition from rated power operation in the event the Main Control Room (MCR) becomes uninhabitable or control from the MCR is lost. The Panel is designed to comply with the requirements of Safety Class 3, Seismic Category I, and Quality Group C. The Panel also meets the requirements of General Design Criterion 19 of 10 CFR 50, Appendix A.

The Panel has controls and instrumentation necessary for the control of the RCIC system, one loop of the RHR (Shutdown Cooling) system, the discharge valve in one loop of the Recirculation system, the CRD system, one RHRSW subsystem, one loop of the PSW system, and two safety / relief valves. The Panel also has instrumentation for monitoring RHR and RCIC flow, reactor vessel water level and pressure, drywell temperature and pressure, and torus water level and temperature. The operability and surveillance requirements for Panel instrumentation are given in Technical Specifications Table 3.2-15 and 4.2-15, respectively. These requirements ensure that the instrumentation necessary to properly control the above systems / components and monitor key plant parameters is operable when the Panel is required to be operable. The operability and surveillance requirements for the Panel controls are given in this Specification. These requirements ensure that the Panel is available should it be needed. When the reactor is in the Cold Shutdown Condition,'the Panel is not needed and, therefore, is not required to be operable. Testing to ensure that the Panel can fulfill its design function is performed at least once per 18 months during Shutdown, with the head off of the reactor vessel. This allows for complete testing of the Panel's control without impacting safe plant operation or required equipment operability by the switching of control f rom the MCR to the Panel during plant operation. By performing the test during Shutdown with the head removed f rom the reactor vessel, the least number of systems is required to be operable, and safe testing of the Panel is ensured.

M. References

1. FSAR Section 6, Core Standby Cooling System.
2. HNP-2 PSAR Appendix I, Conformance to NRC Interim Acceptance Criteria for  !

Emergency Core Cooling Systems.

3. 10 CFR 50, Appendix A General Design Criterion 19.
4. 10 CFR 50.48, Fire Protection.

HATCH - UNIT 1 3.5-22 Proposed TS/0080q/8630-0 l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY......... ..................................... 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN.......................................... 3/4 1-1 3/4.1.2 REACTIVITY AN0MALIES..................................... 3/4 1-2 3/4.1.3 CONTROL RODS Control Rod Operability.................................. 3/4 1-3 Control Rod Maximum Scram Insertion Times................ 3/4 1-5 Control Rod Average Scram Insertion Times................ 3/4 1-6 ,

Four Control Rod Group Scram Insertion Times............. 3/4 1-7 Control Rod Scram Accumulators........................... 3/4 1-8 Control Rod Drive Coupling............................... 3/4 1-9 Control Rod Position Indication.......................... 3/4 1-11 Control Rod Drive Housing Support........................ 3/4 1-13 3/4.1.4 CONTROL R00 PROGRAM CONTROLS Rod Worth Minimizer...................................... 3/4 1-14 Rod Sequence Control System.............................. 3/4 1-15 Rod Block Monitor........................................ 3/4 1-17 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM............................ 3/4 1-18 3/4.1.6 SCRAM DISCHARGE VOLUME VENT AND DRAIN VALVES............. 3/4 1-21 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR. LINEAR HEAT GENERATION RATE. . . . . . . . . . . . . . . 3/4 2-1 3/4 2.2 APRM SETP0INTS........................................... 3/4 2-5 l 3/4.2.3 MINIMUM CRITICAL POWER RATI0............................. 3/4 2-6 3/4.2.4 LINEAR HEAT GENERATION RATE.............................. 3/4 2-8 HATCH-UNIT 2 IV Proposed TS/0082q/8630-0 t

. INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-24 3/4.3.4 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-33 3/4.3.5 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION 3/4 3-37 3/4.3.6 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-43 Seismic Monitoring Instrumentation 3/4 3-47 Remote Shutdown Monitoring Instrumentation 3/4 3-50 Post-Accident Monitoring Instrumentation 3/4 3-53 Source Range Monitors 3/4 3-56 Traversing Incore Probe System 3/4 3-57 Chlorine Detectors 3/4 3-58 Fire Detection Instrumentation 3/4 3-59 Radioactive Liquid Effluent Instrumentation 3/4 3-60a Radioactive Gaseous Effluent Instrumentation 3/4 3-60f 3/4.3.7 TURBINE OVERSPEED PROTECTION SYSTEM 3/4 3-61 3/4.3.8 DEGRADED STATION VOLTAGE PROTECTION INSTRUMENTATION 3/4 3-63 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops 3/4 4-1 '

Jet Pumps 3/4 4-2 Idle Recirculation Loop Startup 3/4 4-3 HATCH-UNIT 2 V -Proposed TS/0082q/8630-0 l

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE REACTOR COOLANT SYSTEM (Continued) 3/4.4.2 SAFETY / RELIEF VALVES 3/4 4-4 Safety / Relief Valves Low-Low Set Function 3/4 4-4a 3/4 4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems 3/4 4-5 Operational Leakage 3/4 4-6 3/4.4.4 CHEMISTRY 3/4 4-7 3/4.4.5 SPECIFIC ACTIVITY 3/4 4-10 3/4.4.6 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System 3/4 4-13 Reactor Steam Dome 3/4 4-18 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES 3/4 4-19 3/4.4.8 STRUCTURAL INTEGRITY 3/4 4-20 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 HIGH PRESSURE COOLANT INJECTION SYSTEM 3/4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM 3/4 5-3 3/4.5.3 LOW PRESSURE CORE COOLING SYSTEMS Core Spray System 3/4 5-4 Low Pressure Coolant Injection System 3/4 5-7 3/4.5.4 SUPPRESSION CHAMBER 3/4 5-9 HATCH-UNIT 2 VI Proposed TS/0082q/8630-0

~

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY-CONTAINMENT Primary Containment Integrity....................... .... 3/4 6-1 Primary Containment Leakage.............................. 3/4 6-3 Primary Containment Air Lock............................. 3/4 6-6 MSIV Leakage Control System.............................. 3/4 6-7 Primary Containment Structural Integrity. . . . . . . . . . . . . . . . . 3/4 6-8 Primary Containment Internal Pressure.................... 3/4 6-9 Drywell Average Air Temperature.......................... 3/4 6-10 3/4.6.2 DEPRESSURIZATION SYSTEMS Suppression Chamber...................................... 3/4 6-11 Suppression Pool Cooling................................. 3/4 6-14 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES..................... 3/4 6-15 3/4.6.4 VACUUM RELIEF Suppression Chamber - Drywell Vacuum Breakers. . . . . . . . . . . . 3/4 6-33 Reactor Building - Suppression Chamber Vacuum Breakers............................................... 3/4 6-35 3/4.6.5 SECONDARY CONTAINMENT Secondary Containment Integrity.......................... 3/4 6-36 Secondary Containment Automatic Isolation Dampers. . . . . . . . 3/4 6-37 )

3/4.6.6 CONTAINMENT ATMOSPHERE CONTROL l Standby Gas Treatment System............................. 3/4 6-40 Primary Containment Hydrogen Recombiner Systems. . . . . . . . . . 3/4 6-43 Primary Containment Hydrogen Mixing System............... 3/4 6-44 Primary Containment Oxygen Concentration................. 3/4 6-45 l

Primary Containment Purge System......................... 3/4 6-46 HATCH-UNIT 2 VII Proposed TS/0082q/8603-0 1

. [NDEX

. LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System. . . . . . . . . . . . . . . 3/4 7-1 Service Water Systems.................................... 3/4 7-3 3/4.7.2 MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM. . . . . . . . . . . 3/4 7-6 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM. . . . . . . . . . . . . . . . . . . 3/4 7-9 3/4.7.4 SNUBBERS................................................. 3/4 7-11 3/4.7.5 S EALED SOURC E CONTAMINATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-19 3/4.7.6 FIRE SUPPRESSION SYSTEMS Fi re Suppre s si on Wate r System. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-21 S p r i n k l e r Sy s t em s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-25 Low Pressure CO 2

Systems................................. 3/4 7-27 Fire Hose Stations....................................... 3/4 7-28 3/4.7.7 PENETRATION FIRE BARRIERS................................ 3/4 7-30 3/4.7.8 SETTLEMENT OF C LASS I STRUCTURES . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-31 3/4.7.9 REMOTE SHUTDOWN PANEL.................................... 3/4 7-33 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES A.C. Sources-Operating................................... 3/4 8-1 A.C. Sources-Shutdown.................................... 3/4 8-9 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating............................ 3/4 8-10 A.C. Distribution - Shutdown............................. 3/4 8-12 0.C. Distribution - Operating............................ 3/4 8-13 D.C. Distribution - Shutdown............................. 3/4 8-16 A.C. Circuits Inside Primary Containment................. 3/4 8-17 Primary Containment Penetration Conductor Overcurrent Protective Devices........................... 3/4 8-18 Electric Power Monitoring For Reactor Protection System.. 3/4 8-24 HATCH-UNIT 2 .VIII Proposed TS/0082q/8630-0

INDEX LIMITING CONDITIONS FOR OPERATIONAL AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.10 SPECIAL TEST EXCEPTIONS (Continued) 3/4.10.5 HIGH PRESSURE COOLANT INJECTION SYSTEM. . . . . . . . . . . . . . . . . . . 3/4 10-5 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration............................................ 3/4 11-1 Dose..................................................... 3/4 11-4 Liquid Waste Treatment................................... 3/4 11-7 Li q u i d Hol dup Ta n ks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 11-8 3/4.11.2 GASEOUS EFFLUENTS Dose Rate................................................ 3/4 11-9 Dose, Noble Gases........................................ 3/4 11-13 Dose, Radioiodines, Radioactive Material................. 3/4 11-14 in Particulate Form, and Radionuclide Other than Noble Gases Gaseous Radwaste Treatment............................... 3/4 11-15 Total Dose............................................... 3/4 11-16 Explosive Gas Mixture.................................... 3/4 11-18 Main Condenser........................................... 3/4 11-19 3/4.11.3 SOLID RADI0 ACTIVE WASTE.................................. 3/4 11-20 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING.................... 3/4 12-1 l

l i

I HATCH-UNIT 2 IXa Proposed TS/0082q/8630-0

INDEX BASES SECTION PAGE 3/4.0 A P P L I C AB I L I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 / 4 0- 1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN..................................... B 3/4 1-1 3/4.1.2 REACTIVITY AN0MALIES................................ B 3/4 1-1 3/4.1.3 CONT RO L R00 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 1-2 3/4.1.4 CONTROL R00 PROGRAM CONTR0LS . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM....................... B 3/4 1-4 3/4.1.6 SCRAM DISCHARGE VOLUME VENT ORAIN VALVES. . . . . . . . . . . . B 3/4 1-5 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.............................................. B 3/4 2-1 3/4.2.2 APRM SETP0lNTS...................................... B 3/4 2-3 3/4.2.3 MINIMUM CRITICAL POWER RATI0........................ B 3/4 2-3 3/4.2.4 LI N EAR H EAT G EN E RAT I ON RAT E . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 2-5 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION..................................... B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION................. B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION..................................... B 3/4 3-2 3/4.3.4 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION........................... B 3/4 3-3 3/4.3.5 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION..................................... B 3/4 3-3 3/4.3.6 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation................ B 3/4 3-3 Seismic Monitoring Instrumentation.................. B 3/4 3-3 HATCH-UNIT 2 X Proposed TS/0082q/8630-0

INDEX BASES SECTION PAGE INSTRUMENTATION (Continued)

Remote Shutdown Monitoring.......................... B 3/4 3-3 Instrumentation Post-Accident Monitoring............................ B 3/4 3-4 Instrumentation Source Range Monitors............................... B 3/4 3-4 Traversing Incore Probe System...................... B 3/4 3-4 Chlorine Detectors.................................. B 3/4 3-4 Fi re Detec t. ion Instrumentation . . . . . . . . . . . . . . . . . . . . . . B 3/4 3-4 Radioactive Liquid Effluent Instrumentation..................................... B 3/4 3-5 Radioactive Gaseous Effluent Instrumentation..................................... B 3/4 3-5 3/4.3.7 TURBINE OVERSPEED PROTECTION SYSTEM................. B 3/4 3-5 3/4.3.8 DEGRADED STATION VOLTAGE PROTECTION INSTRUMENTATION..................................... B 3/4 3-Sa 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYS1EM................................ B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES................................ B 3/4 4-1 Low-Low Set System.................................. B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems........................... B 3/4 4-2 Operational Leakage................................. B 3/4 4-2 3/4.4.4 CHEMISTRY........................................... B 3/4 4-2 ,

3/4.4.5 SPECIFIC ACTIVITY................................... B 3/4 4-3 l 1

3/4.4.6 PRESSURE / TEMPERATURE LIMITS......................... B 3/4 4-4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES.................... B 3/4 4-6 HATCH-UNIT 2 XI Proposed TS/0082q/8630-0

INDEx BASES SECTION PAGE REACTOR COOLANT SYSTEM (Continued) 3/4.4.8 STRUCTURAL INTEGRITY................................ B 3/4 4-6 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 HIGH PRESSURE COOLANT INJECTION SYSTEM. . . . . . . . . . . . . . B 3/4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM................... B 3/4 5-1 3/4.5.3 LOW PRESSURE CORE COOLING SYSTEMS Core Spray System................................... B 3/4 5-2 Low Pressure Coolant Injection System............... B 3/4 5-3 3/4.5.4 SUPPRESSION CHAMBER................................. B 3/4 5-3 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT INTEGRITY Primary Containment Integrity....................... B 3/4 6-1 Primary Containment Leakage.......... .............. B 3/4 6-1 Prima ry Contai nment Ai r Lock. . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-1 MSIV Leakage Control System......................... B 3/4 6-2 Primary Containment Structural Integrity........................................... B 3/4 6-2 Primary Containment Internal Pressure............... B 3/4 6-2 Drywell Average Air Temperature..................... B 3/4 6-2 3/4.6.2 DEPRESSURIZATION SYSTEMS............................ B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES................ B 3/4 6-4 3/4.6.4' VACUUM RELIEF....................................... B 3/4 6-5 3/4.6.5 SECONDARY CONTAINMENT............................... B 3/4 6-5 3/4.6.6 CONTAINMENT ATMOSPHERE CONTR0L...................... B 3/4 6-5 Prima ry Contai nment Purge System. . . . . . . . . . . . . . . . . . . . B 3/4 6-6 HATCH-UNIT 2 XII Proposed TS/0082q/8630-0

l ZNDEX l l

. BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS............................... B 3/4 7-1 3/4.7.2 MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM...................................... B 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM.............................................. B 3/4 7-1 3/4.7.4 SNUBBERS............................................ B 3/4 7-2 3/4.7.5 SEALED SOURCE CONTAMINATION......................... B 3/4 7-3 3/4.7.6 FIRE SUPPRESSION SYSTEMS............................ B 3/4 7-3 3/4.7.7 P EN ET RATION FI RE BARRI ERS . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-4 3/4.7.8 SETTLEMENT OF CLASS I STRUCTURES.................... B 3/4 7-4 3/4.7.9 R EMOTE SHUTDOWN PANEL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-4 l

3/4.8 ELECTRICAL POWER SYSTEMS.................................... B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 R EACTO R MODE SWI TC H . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.2 INSTRUMENTATION..................................... B 3/4 9-1 3/4.9.3 CONTROL R0D P0SITION................................ B 3/4 9-1 3/4.9.4 DECAY TIME.......................................... B 3/4 9-1 3/4.9.5 SECONDARY CONTAINMENT............................... B 3/4 9-1 3/4.9.6 COMMUNICATIONS...................................... B 3/4 9-2 3/4.9.7 CRANE AND HOIST OPERABILITY......................... B 3/4 9-2 3/4.9.8 CRANE TRAVEL-SPENT FUEL STORAGE P00L. . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.9 WATER LEVEL - REACTOR VESSEL AND and WATER LEVEL - SPENT FUEL STORAGE 3/4.9.10 P00L................................................ B 3/4 9-2 3/4.9.11 CONTROL R00 REM 0 VAL................................. B 3/4 9-2 3/4.9.12 REACTOR COOLANT CIRCU LATION. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-3 HATCH-UNIT 2 XIII Proposed TS/0082q/8630-0

INDEX BASES i

SECTION PAGE 1

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY....................... B 3/4 10-1 3/4.10.2 R00 SEQUENCE CONTROL SYSTEM......................... B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS...................... B 3/4 10-1 3/4.10.4 REC I RCU LATION L00 P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 i 3/4.11 RADIOACTIVE EFFLUENTS

. 3/4.11.1 LIQUID EFFLUENTS Concentration....................................... B 3/4 11-1 Dose................................................ B 3/4 11-1 Li q u i d Wa s te T re a tme n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11-2 Li qu id Hol dup Ta n ks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS Dose Rate........................................... B 3/4 11-2 Dose, Noble Gases................................... B 3/4 11-3 Dose, Radioiodines, Radioactive Material in Particulate Form, and Radionuclide Other than Noble Gases................. B 3/4 11-4 Gaseous Waste Treatment............................. B 3/4 11-5 l Dose................................................ B 3/4 11-5 l Explosive Gas Mixture............................... B 3/4 11-5 Main Condenser...................................... B 3/4 11-5 3/4.11.3 SOLID RADIOACTIVE WASTE............................. B 3/4 11-6 HATCH-UNIT 2 XIIIa Proposed TS/0082q/8630-0 1

1

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area................................................ 5-1 Low Population Zone........................................... 5-1 5.2 CONTAINMENT 4

Configuration................................................. 5-1 Design Temperature and Pressure............................... 5-1 5.3 REACTOR CORE Fuel Assemb11es............................................... 5-1 Control Rod Assemblies........................................ 5-3 j 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature............................... 5-3 Volume........................................................ 5-3 5.5 METEOROLOGICAL TOWER LOCATION................................. 5-3 5.6 FUEL STORAGE Criticality................................................... 5-3 Drainage...................................................... 5-4 Capacity...................................................... 5-4 Fuel Storage.................................................. 5-4 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT.......................... 5-4 1

HATCH-UNIT 2 XIV Proposed TS/0082q/8630-0

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.13 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT. . . . . . . . . . . . . . . . . . . . . 6-19 6.14 IODINE MONITORING............................................ 6-20 6.15 ENVIRONMENTAL QUALIFICATION.................................. 6-21 6.16 POST-ACCIDENT SAMPLING AND ANALYSIS.......................... 6'-22 6.17 0FFSITE DOSE CALCULATION MANUAL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-22 l

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1 HATCH-UNIT 2 XVII Proposed TS'/0082q/8630-0

PLANT SYSTEMS 3/4.7.9 REMOTE SHUTDOWN PANEL LIMITING CONDITION FOR OPERATION 3.7.9 The Remote Shutdown Panel (the Panel) shall be OPERABLE with the capability

._ of remotely bringing the reactor to and maintaining the reactor in a COLD SHUTDOWN condition following loss of control from or habitability of the Main Control Room.

The Panel shall be continuously monitored whenever control is at the Panel.

APPLICABILITY: Conditions 1, 2, and 3.

ACTION:

a. With the Remote Shutdown Panel inoperable, restore the Panel to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
b. With a component controlled from the Remote Shutdown Panel i inoperable for reasons unrelated to the Panel, the component's appropriate LIMITING CONDITION FOR OPERATION ACTION statement shall be followed, and Specification 3.7.9.a is not applicable. ,

SURVEILLANCE REQUIREMENTS 4.7.9 The Remote Shutdown Panel shall be demonstrated OPERABLE at least once per 18 months during shutdown with the head removed from the reactor vessel by:

a. Switching control from the Main Control Room to the Panel
  • and verifying that:
1. All valves controlled from the Panel, except the safety /

relief valves, can be opened and closed with the controls at the Panel,

2. All pumps controlled from the Panel, except the RCIC pump, can l be started and stopped with the controls at the Panel, and
3. The safety / relief valves controlled from the Panel can be opened and closed with the controls at the Panel by verifying that their solenoid valves ac+.uate.

"When control is at the Panel during the test, the Panel shall be continuously monitored.

HATCH - UNIT 2 3/4 7-33 Proposed TS/0083q/8630-0

1 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. Switching control from the Panel to the Main Control Room following ' completion
  • of the above tests and verifying that:
1. All valves controll6d from the Panel, except the safety / relief valves, can be opened ard closed with the controls in the Main Control Room,
2. All pumps controlled from the Panel, except the RCIC pump, can be started and stopped with the controls in the Main Control Room, and
3. The safety / relief valves controlled from the Panel can be opened and closed with the controls in the Main Control Room by verifying that their solenoid valves actuate.

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  • This shall be done immediately following the completion of the tests required by Specification 4.7.9.a and the return of control to the Main Control Room except for those components not required to be OPERABLE. For those components not required to be OPERABLE, this requirement may be satisfied by operability tests performed after the test of Specification 4.7.9.a and before the component is declared OPERABLE. This operability test must involve the direct use of Main Control Room controls.

I HATCH - UNIT 2 3/4 7-34 Proposed TS/0083q/8630-0

PLANT SYS1 EMS BASES 3/4.7.7 PENETRATION FIRE RARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.

During periods of time when the barriers are not functional, a contin-uous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status unless the OPERABILITY of the fire detection instruments, providing coverage of the fire detection zones on each side of the non-functional barriers, has been demonstrated.

3/4.7.8 SETTLEMENT OF CLASS 1 STRUCTURES In order to assure that settlement does not exceed predicted and allowable settlement values, a program has been established to conduct a survey at the site.

The allowable total and differential settlement values are based on original settlement predictions. In establishing these tabulated values, an assumption is made that pipe and conduit connections have been designed to safely withstand the stresses which vould develop due to total and differential settlement.

3/4.7.9 REMOTE SHUTDOWN PANEL The Remote Shutdown Panel (the Panel), located on the 130 ft elevation of the Reactor Building, provides the operator with the capability of bringing the reactor to the COLD SHUTOOWN condition from rated power operation in the event the Main Control Room (MCR) becomes uninhabitable or control from the MCR is lost. The Panel is designed to comply with the requirements of Safety Class 3, Seismic Category I, and Quality Group C. The Panel also meets the requirements of General Design Criterion of 10 CFR 50, Appendix A.

The Panel has controls and instrumentation necessary for the control of l the RCIC system, one loop of the RHR (Shutdown Cooling) system, the discharge valve in one loop of the Recirculation system, the CRD system, one RHRSW subsystem, one loop of the PSW system, and two safety / relief valves. The ,

Panel also has instrumentation for monitoring RHR and RCIC flow, reactor I vessel water level and pressure, drywell temperature and pressure, and torus l

HATCH - UNIT 2 B 3/4 7-4 Proposed TS/0083q/8630-0

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PLANT SYSTEMS BASES REMOTE SHUTDOWN PANEL (Continued) water level and temperature. The operability and surveillance requirements for Panel instrumentation are given in Technical Specifications Tables

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3.3.6.3-1 and 4.3.6.3-1, respectively. These requirements ensure that the instrumentation necessary to properly control the above systems / components and monitor key plant parameters is OPERABLE when the Panel is required to be OPERABLE. The operability and surveillance requirements for the Panel controls are given in this Specification. These requirements ensure that the Panel is available should it be needed. When the reactor is in the COLD SHUTDOWN condition, the Panel is not needed and,therefore, is not required to be OPERABLE. Testing to ensure that the Panel can fulfill its design functions is performed at least once per 18 months during shutdown with the head off of the reactor vessel. This. allows for complete testing of the Panel's controls without impacting safe plant operation or required equipment operability by the switching of control from the MCR to the Panel during plant operation. By performing the test during shutdown with the head removed from the reactor vessel, the least number of systems is required to be OPERABLE, and safe testing of the Panel is ensured.

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