ML23345A067

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Technical Specifications Bases Manual
ML23345A067
Person / Time
Site: Susquehanna 
Issue date: 11/28/2023
From:
Susquehanna
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML23345A067 (1)


Text

Page 1 of 2

MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2023-14481

USER INFORMATION:

GERLACH*ROSEY M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 542-3194

TRANSMITTAL INFORMATION:

TO: GERLACH*ROSEY M 11/28/2023 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.

ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.

TSB2 - TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL

REMOVE MANUAL TABLE OF CONTENTS DATE: 11/02/2023

ADD MANUAL TABLE OF CONTENTS DATE: 11/27/2023

CATEGORY: DOCUMENTS TYPE: TSB2 l.\\JUV. L;0 1 L;UL;..:>

Page 2 of 2

ID: TEXT 3.6.1.4 REMOVE: REV: 2

ADD: REV: 3

ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS@ X3171 OR X3194 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.

SSES MANUAL

Manual Name: TSB2

.nual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL

Table Of Contents Issue Date: 11/27/2023 Procedure Name Rev Issue Date Change ID Change Number TEXT LOES 138 01/03/2019

Title:

LIST OF EFFECTIVE SECTIONS

TEXT TOC 25 03/05/2019

Title:

TABLE OF CONTENTS

TEXT 2.1.1 7 03/30/2023

Title:

SAFETY LIMITS (SLS) REACTOR CORE SLS

TEXT 2.1. 2 1

EXT 3.0 5

Title:

LIMITING CONDITION FOR

01/15/2023

TEXT 3.1.4 5 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES '

TEXT 3.1. 5 2 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS

TEXT 3.1. 6 6 01/15/2023

Title:

REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL

Page 1 of 8 Report Date: 11/27/23 SSES MANUAL

Manual Name: TSB2

Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL

  • TEXT 3.1. 7 5 01/05/2023

Title:

REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM

TEX'+. 3.1. 8 4 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES

TEXT 3.2.1 6 03/31/2021

Title:

POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR}

TEXT 3.2.2 6 03/30/2023

Title:

POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)

TEXT 3.2.3 4 03/31/2021

Title:

POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE LHGR

TEXT 3.3.1.1 7 01/05/2023 *

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION

TEXT 3.3.1.2 4 01/23/2018

Title:

INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION

TEXT 3.3.2.1 6 01/15/2023

Title:

INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION

TEXT 3.3.2.2 4 01/05/2023

Title:

INSTRUMENTATION FEEDWATER MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION

TEXT 3.3.3.1 9 11/16/2016

Title:

INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION

TEXT 3.3.3.2 2 11/16/2016

Title:

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM

TEXT 3.3.4.1 3 01/05/2023

Title:

INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATION.

Page 2 of 8 Report Date: 11/27/23 SSES MANUAL

Manual Name: TSB2

.anual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL

TEXT 3.3.4.2 2 01/05/2023

Title:

INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT) INSTRUMENTATION

TEXT 3.3.5.1 8 01/05/2023

Title:

INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION

TEXT 3.3.5.2 3 03/18/2021

Title:

REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL INSTRUMENTATION

TEXT 3.3.5.3 1 01/05/2023

Title:

UNIT 1 REACTOR PRESSURE VESSEL WIC TS CHANGES

TEXT 3.3.6.1 10 01/05/2023

Title:

INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION

.EXT 3.3.6.2 6 03/05/2019

Title:

INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION

TEXT 3.3.7.1 4 03/05/2019

Title:

INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM INSTRUMENTATION

TEXT 3.3.8.1 7 01/05/2023

Title:

INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION

TEXT 3.3.8.2 1 11/16/2016

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING

TEXT 3.4.1 6 03/31/2021

Title:

REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING

TEXT 3.4.2 4 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) JET PUMPS

TEXT 3.4.3 3 01/13/2012

Title:

REACTOR COOLANT SYSTEM (RCS) SAFETY/RELIEF VALVES (S/RVS)

Page 3 of 8 Report Date: 11/27/23 SSES MANUAL

Manual Name: TSB2

Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL

TEXT 3.4.4 1 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE

TEXT 3.4.5 3 03/10/2010

Title:

REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE

TEXT 3.4.6 5 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION

TEXT 3.4.7 3 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITY

TEXT 3.4.8 3 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM

- HOT SHUTDOWN TEXT 3.4.9 2 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM *

- COLD SHUTDOWN

TEXT 3.4.10 6 05/14/2019

Title:

REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS

TEXT 3.4.11 1 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURE

TEXT 3.5.1 9 01/05/2023

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS) REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ECCS OPERATING TEXT 3.5.2 7 06/09/2022

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS) REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ECCS OPERATING TEXT 3.5.3 7 01/05/2023

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS) REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ECCS OPERATING

Page 4 of 8 Report Date: 11/27/23 SSES MANUAL

Manual Name: TSB2

.anual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL

TEXT 3.6.1.1 6 11/16/2016

Title:

PRIMARY CONTAINMENT

TEXT 3.6.1.2 3 01/05/2023

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK

TEXT 3.6.1.3 20 01/05/2023

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)

TEXT 3.6.1.4 3 11/27/2023

Title:

CONTAINMENT SYSTEMS CONTAINMENT PRESSURE

TEXT 3.6.1.5 2 11/16/2016

Title:

CONTAINMENT SYSTEMS DRYWELL AIR TEMPERATURE

.EXT 3.6.1.6 2 01/05/2023

Title:

CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS

TEXT 3.6.2.1 3 11/16/2016

Title:

CONTAINMENT SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE

TEXT 3.6.2.2 2 03/05/2019

Title:

CONTAINMENT SYSTEMS SUPPRESSION POOL WATER LEVEL

TEXT 3.6.2.3 3 01/05/2023

Title:

CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING

TEXT 3.6.2.4 2 01/05/2023

Title:

CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY

TEXT 3.6.3.1 2 06/13/2006

Title:

CONTAINMENT SYSTEMS INTENTIONALLY LEFT BLANK

TEXT 3.6.3.2 4 08/02/2021

Title:

CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM

Page 5 of 8 Report Date: 11/27/23 SSES MANUAL

Manual Name: TSB2

Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL

TEXT 3.6.3.3 3 09/2~/2017

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION

TEXT 3.6.4.1 17 12/16/2020

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT

TEXT 3.6.4.2 14 03/05/2019

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)

TEXT 3.6.4.3 7 03/05/2019

Title:

CONTAINMENT SYSTEMS STANDBY GAS TREATMENT SYSTEM

TEXT 3.7.1 10 01/05/2023

Title:

PLANT SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THE ULTIMATE HEAT SINK (UHS)

TEXT 3.7.2 6 01/05/2023

Title:

PLANT SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM

  • TEXT 3.7.3 4 03/05/2019

Title:

PLANT SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY {CREOAS) SYSTEM

TEXT 3.7.4 2 03/05/2019

Title:

PLANT SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM

TEXT 3.7.5 2 11/16/2016

Title:

PLANT SYSTEMS MAIN CONDENSER ~FFGAS

TEXT 3.7.6 4 11/i6/2016

Title:

PLANT SYSTEMS MAIN TURBINE BYPASS SYSTEM

TEXT 3.7.7 2 11/16/2016

Title:

PLANT SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL

TEXT 3.7.8 1 11/16/2016

Title:

MAINE TURBINE PRESSURE REGULATION SYSTEM

Page 6 of 8 Report Date: 11/27/23 SSES MANUAL

Manual Name: TSB2

.anual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL

TEXT 3.8.1 17 01/05/2023

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES OPERATING

TEXT 3.8.2 2 03/18/2021

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES - SHUTDOWN

TEXT 3.8.3 7 08/07/2019

Title:

ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL LUBE OIL AND STARTING AIR

TEXT 3. 8.4 5 01/05/2023

Title:

ELECTRICAL POWER SYSTEMS DC SOURCES - OPERATING

TEXT 3.8.5 2 03/05/2019

Title:

ELECTRICAL POWER SYSTEMS DC SOURCES - SHUTDOWN

.EXT 3.8.6 2 11/16/2016 Ti.tle: ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERS

TEXT 3.8.7 9 01/05/2023

Title:

ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - OPERATING

TEXT 3.8.8 2 03/05/2019

Title:

ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS SHUTDOWN

TEXT 3.9.1 1 11/16/2016

Title:

REFUELING OPERATIONS REFUELING EQUIPMENT INTERLOCKS

TEXT 3.9.2 2 11/16/2016

Title:

REFUELING OPE~TIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK

TEXT 3.9.3 1 11/16/2016

Title:

REFUELING OPERATIONS CONTROL ROD POSITION

TEXT 3.9.4 0 11/18/2002

Title:

REFUELING OPERATIONS CONTROL ROD POSITION INDICATION

Page 7 of 8 Report Date: 11/27/23 SSES MANUAL

Manual Name: TSB2

Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL

  • TEXT 3.9.5 1
  • 11/16/2016

Title:

REFUELING OPERATIONS CONTROL ROD OPERABILITY - REFUELING

TEXT 3.9.6 2 11/16/2016

Title:

REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL

TEXT 3.9.7 l 11/16/2016

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - HIGH WATER LEVEL

TEXT 3.9.8 1 11/16/2016

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - LOW WATER LEVEL

TEXT 3.10.1 2 03/05/2019

Title:

SPECIAL OPERATIONS INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION

TEXT 3.10.2 1 11/16/2016 *

Title:

SPECIAL OPERATIONS REACTOR MODE SWITCH INTERLOCK TESTING

TEXT 3.10.3 1 11/16/2016

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - HOT SHUTDOWN

TEXT 3.10.4 1 11/16/2016

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - COLD SHUTDOWN

TEXT 3.10.5 l 11/16/2016

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD DRIVE (CRD) REMOVAL - REFUELING

TEXT 3.10.6 1 11/16/2016

Title:

SPECIAL OPERATIONS MULTIPLE CONTROL ROD WITHDRAWAL REFUELING

TEXT 3.10.7 2 03/31/2021

Title:

SPECIAL OPERATIONS CONTROL ROD TESTING OPERATING

3.10.8 4 03/31/2021

Title:

SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST - REFUELING

  • Page 8 of 8 Report Date: 11/27/23 Rev. 3 Containment Pressure B 3.6.1.4
  • B 3.6 CONTAINMENT SYSTEMS

B 3.6.1.4 Containment Pressure

BASES

BACKGROUND The containment pressure is limited during normal operations to preserve the initial conditions assumed in the accident analysis for a Design Basis Accident (OBA) or loss of coolant accident (LOCA).

APPLICABLE Primary containment performance is evaluated for the entire spectrum of SAFETY break sizes for postulated LOCAs (Ref. 1 ). Among the inputs to the OBA is ANALYSES the initial primary containment internal pressure (Ref. 1 ). Analyses assume an initial containment pressure of-1.0 to 2.0 psig. This limitation ensures that the safety analysis remains valid by maintaining the expected initial conditions and ensures that the peak LOCA contain merit internal pressure does not exceed the maximum allowable.

The maximum calculated containment pressure occurs during the reactor blowdown phase of the OBA, which assumes an instantaneous recirculation line break. The calculated peak containment pressure for this limiting event is 48.6 psig (Ref. 1 ).

  • The minimum containment pressure occurs during an inadvertent spray

actuation. The calculated minimum drywell pressure for this limiting event is -4.72 psig. (Ref. 1)

Containment pressure satisfies Criterion 2 of the NRC Policy Statement.

(Ref. 2)

LCO In the event of a OBA, with an initial containment pressure -1.0 to 2.0 psig, the resultant peak containment accident pressure will be maintained below the containment design pressure. The containment pressure is defined to include both the drywell pressure and the suppression chamber pressure.

(Ref. 1)

APPLICABILITY In MODES 1, 2, and 3, a OBA-could cause a release of radioactive material to primary containment. In MODES 4 and 5, the probability and consequences of these events are reduced due to the pressure and temperature limitations of these MODES. Therefore, maintaining containment pressure within limits is not required in MODE 4 or 5.

SUSQUEHANNA - UNIT 2 3.6-40 Rev. 3 Containment Pressure B 3.6.1.4

BASES ACTIONS

With containment pressure not within the limit of the LCO, containment pressure must be restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Required Action is necessary to return operation to within the bounds of the primary containment analysis. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is consistent with the ACTIONS of LCO 3.6.1.1, "Primary Containment," which requires that primary containment be restored to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

8.1 and 8.2

If containment pressure cannot be restored to within limit within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.1.4.1 REQUIREMENTS

  • Verifying that containment pressure is within limit ensures that unit operation remains within the limit assumed in the primary containmer:it analysis. The Surveillance Frequency is controlled under the Surveiliance Frequency Control Program.

REFERENCES 1. FSAR, Section 6.2.

2. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).

SUSQUEHANNA - UNIT 2 3.6-41 Rev. 3 Containment Pressure B 3.6.1.4

BASES

THIS PAGE INTENTIONALLY LEFT BLANK

SUSQUEHANNA - UNIT 2 3.6-42