ML18094A350

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Proposed Tech Specs,Revising Electrical Power Sys
ML18094A350
Person / Time
Site: Salem  PSEG icon.png
Issue date: 04/14/1989
From:
Public Service Enterprise Group
To:
Shared Package
ML18094A349 List:
References
NUDOCS 8904250234
Download: ML18094A350 (28)
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I l ELECTRICAL POWER SYSTEMS 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.3.1 All containment penetration conductor overcurrent protective devices required to provide thermal protection of penetrations shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and* 4.

ACTION:

With one or more of the required containment penetration conductor overcurrent protective device(s) inoperable:

a.

Restore the protective device(s) to OPERABLE status or de-energize the circuit(s) by tripping either the primary or backup protective device, or racking out or removing the primary or backup device within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the affected system or component inoperable, and verify the primary or backup protective device to be tripped, or the primary or backup device racked out or removed at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their primary or backup protective device tripped, or which have the primary or backup device racked out or removed, or

b.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.8.3.1 All required containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:

a.

At least once per 18 months:

1.

For at least one 4.16 KV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated OPERABLE at least once per 72 months, by performance of:

SALEM - UNIT 1 (a)

A CHANNEL CALIBRATION of the associated protective relays, and (b)

An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed.

3/4 8-14

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2.

By verifying the OPERABILITY of the required molded case and lower voltage circuit breakers, by selecting and functionally testing a representative sample of at least 10% of all the circuit breakers of that type.

Circuit breakers selected for functional testing shall be selected on a rotating basis.

The functional test shall consist of injecting a current input at the specified setpoint to each selected circuit breaker and verifying that each circuit breaker-functions as designed.

Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.

For each circuit breaker found inoperable during the functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

3.

By visually inspecting a representative of at least 20% of all fuses installed to thermally protect electrical penetrations to verify that the installed fuse is the size and type specified for that application.

Additionally, the above sample will be verified to be functional by voltage or resistance measurements, or by equipment operability checks.

Fuses shall be selected on a rotating basis.

For each fuse found to be the wrong size or type or is functionaly inoperable, an additional representative sample of 10% shall be inspected as specified above until no further discrepancies are found or all fuses have been inspected or functionally tested.

b.

At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.

SALEM - UNIT 1 3/4 8-15

ELECTRICAL POWER SYSTEMS BASES 3/4.8.1 AND 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will b available to supply the safety related equipment required for 1) the safe; shutdown of the facility, and 2) the mitigation and control of accident conditions within the facility.

The minimum specified independent and redundant A.C. and D:c. power sources and distribution systems satisfy tr requirements of General Design Criterion 17 of Appendix "A" to 10 CFR Pa:

  • 50.

The ACTION requirements specified for the levels of degradation of*,1e power sources provide restriction upon continued facility operation commensurate with the level of degradation.

The OPERABILITY of the po~

sources are consistent with the initial condition assumptions of the a,'.ident analyses and are based upon maintaining at least one redundant set of I /site I

A.C. and D.C. power sources and associated distribution systems OPERAJ

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during accident conditions coincident with an assumed loss of offsit~',ower and single failure of the other onsite A.C. source.

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The OPERABILITY of the minimum specified A.C. and D.C. power sc associated distribution systems during shutdown and refueling ensur(

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/ces and

'that 1) the facility can bemaintained in the shutdown or refueling conditi, for I

extended time periods, and 2) sufficient instrumentation and contrc I

capability is available for moni taring and maintaining the unit sti 1us.

The Surveillance Requirements for demonstrating the OPERABILJ' diesel generators is based upon the recommendations of Regulatory/

"Selection of Diesel Generator Set Capacity for Standby Power Sup' March 10, 1971, and Guide 1. 108, "Periodic Testing Diesel Genera1 as Onsite Electric Power Systems at Nuclear Power Plants," *Revis*

. August 1977.

/

3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES I

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[ of the uide 1. 9,

.ies, 11 c Units Used n 1, Containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary *and backup overcurrent protection circuit breakers and fuses during periodic surveillance.

The surveillance frequency applicable to molded case circuit breakers and.

lower voltage circuit breakers provides assurance of breaker reliability by testing at least one representative sample of each manufacturer's brand of molded case and lower voltage circuit breakers.

Each manufacturer's molded case circuit breakers and lower voltage circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers are tested.

If a wide variety exists within any manufacturer's brand of molded case or lower voltage circuit breakers, it is necessary to further divide that manufacturer's breakers into groups and treat each group as a separate type of breaker for surveillance purposes.

SALEM - UNIT 1 B 3/4 8-1

ELECTRICAL POWER SYSTEMS BASES (Continued)

Visual inspection and operability checks of fuses provide assurance of the fuses ability to protect containment electrical penetrations.

Destructive testing of fuses is not considered necessary since it is industry knowledge that the reaction time of fuses will not increase or otherwise degrade in the non-conservative direction, since their operation is not dependent on mechanical motion.

A 20% rotating representative sample assures that all fuses are inspected periodically.

A list of the required containment penetration conductor overcurrent protective devices, with information on location, size and equipment powered by the protective circuit is maintained in the UFSAR.

The list is limited to those overcurrent devices installed for the purpose of keeping circuit fault current below the penetration rating. It does not apply to other overcurrent devices which protect penetrations where fault currents are less than the sustained rating of the penetration.

This is consistent with the requirements of IEEE 741-1986 which states that no special consideration is required to protect electrical penetrations that can indefinitely withstand the maximum fault current available.

Setpoints are controlled by plant procedures and drawings and any additions, deletions or modifications to the containment penetration conductor overcurrent protective devices list is governed by Section 50.59 of 10 CFR Part 50.

SALEM - UNIT 1 B 3/4 8-2

ELECTRICAL POWER SYSTEMS 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.3.1 All containment penetration conductor overcurrent protective devices required to provide thermal protection of penetrations shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more of the required containment penetration conductor overcurrent protective device(s) inoperable:

a.

Restore the protective device(s) to OPERABLE status or de-energize the circuit(s) by tripping either the primary or backup protective device, or racking out or removing the primary or backup device within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the affected system or component inoperable, and verify the primary or backup protective device to be tripped, or the primary or backup device racked out or removed at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their primary or backup protective device tripped, or which have the primary or backup device racked out or removed, or

b.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.8.3.l All required containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:

a.

At least once per 18 months:

1.

For at least one 4.16 KV reactor coolant pump circuit, such that all reactor coolant pump circuits are demonstrated OPERABLE at least once per 72 months, by performance of:

(a)

A CHANNEL CALIBRATION of the associated protective relays, and (b)

An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed.

SALEM - UNIT 2 3/4 8-16

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2.

By verifying the OPERABILITY of the required molded case and lower voltage circuit breakers, by selecting and functionally testing a representative sample of at least 10% of all the circuit breakers of that type.

Circuit breakers selected for functional testing shall be selected on a rotating basis.

The functional test shall consist of injecting a current input at the specified setpoint to each selected circuit breaker and verifying that each circuit breaker functions as designed.

Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.

For each circuit breaker found inoperable during the functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

3.

By visually inspecting a representative of at least 20% of all fuses installed to thermally protect electrical penetrations to verify that the installed fuse is the size and type specified for that application.

Additionally, the above sample will be verified to be functional by voltage or resistance measurements, or by equipment operability checks.

Fuses shall be selected on a rotating basis.

For each fuse found to be the wrong size or type or is functionally inoperable, an additional representative sample of 10% shall be inspected as specified above until no further discrepancies are found or all fuses have been inspected or functionally tested.

b.

At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer 1 s recommendations.

SALEM - UNIT 2 3/4 8-17

1.

SALEM - UNIT 2 TABLE 3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES DELETED 3/4 8-18 Amendment No.

ELECTRICAL POWER SYSTEMS BASES 3/4.8.1 AND 3/4.8.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for 1) the safe shutdown of the facility, and 2) the mitigation and control of accident conditions within the facility.

The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criterion 17 of Appendix "A" to 10 CFR Part 50.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation.

The OPERABILITY of the power sources are consistent with the initial condition assumptions of the accident analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C. source.

The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods, and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status.

The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators is based upon the recommendations of Regulatory Guide 1.9, "Selection of Diesel Generator Set Capacity for Standby Power Supplies,"

March 10, 1971, and Guide 1.108, "Periodic Testing Diesel Generator Units Used as Onsite Elec'tric Power System1'? at Nuclear Power Plants," Revision 1, August 1977.

3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers and* fuses during periodic surveillance.

The surveillance frequency applicable to molded case circuit breakers and lower voltage circuit breakers provides assurance of breaker reliability by testing at least one representative sample of each manufacturer's brand of molded case and lower voltage circuit breakers.

Each manufacturer's molded case circuit breakers and lower voltage circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers are tested. If a wide variety exists within any manufacturer's brand of molded case or lower voltage circuit breakers, it is necessary to further divide that manufacturer's breakers into groups and treat each group as a separate type of breaker for surveillance purposes.

SALEM - UNIT 2 B 3/4 8-1

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ELECTRICAL POWER SYSTEMS BASES (Continued)

Visual inspection and operability checks of fuses provide assurance of the fuses ability to protect containment electrical penetrations.

A 20%

rotating representative sample assures that all fuses are inspected.

periodically.

A list of the required containment penetration conductor overcurrent protective devices, with information on location, size and equipment powered br the protective *cfrcuTC is maintained in' the UFSAR.' -The l:ist is limited to those overcurrent devices installed for the purpose of keeping circuit fault current below the penetration rating. It does not apply to other overcurrent devices which protect penetrations where fault currents are less than the sustained rating of the penetration..This is consistent with the requirements of IEEE 741-1986 which states that no special consideration is required*to protect electrical penetrations that can indefinitely withstand the maximum fault current available._ Setpoints are controlled by plant procedures and draw~ngs and any additions, deletions or modifications to the containment penetration conductor overcurrent protective devices list is governed by Section 50.59 of 10 CFR Part 50.

SALEM-- UNIT 2 B 3/4 8-2

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INDEX DEFINITIONS

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SECTION 1.0 DEFINITIONS DEFINED TERMS....

ACTION AXIAL FLUX DIFFERENCE.

CHANNEL CALIBRATION.

CHANNEL CHECK....

CHANNEL FUNCTIONAL TEST CONTAINMENT INTEGRITY CONTROLLED LEAKAGE CORE ALTERATION...

DOSE EQUIVALENT I-131 E-AVERAGE DISINTEGRATION ENERGY ENGINEERED SAFETY FEATURE RESPONSE TIME FREQUENCY NOTATION FULLY WITHDRAWN.........

GASEOUS RADWASTE TREATMENT SYSTEM IDENTIFIED LEAKAGE MEMBER(S) OF THE PUBLIC....

OFFSITE DOSE CALCULATION MANUAL (ODCM)

OPERABLE - OPERABILITY OPERATIONAL MODE PHYSICS TESTS PRESSURE BOUNDARY LEAKAGE..

PROCESS CONTROL PROGRAM (PCP)

PURGE-PURGING QUADRANT POWER TILT RATIO..

RATED THERMAL POWER.....

REACTOR TRIP SYSTEM RESPONSE TIME REPORTABLE OCCURRENCE SHUTDOWN MARGIN SITE BOUNDARY.

SOLIDIFICATION SOURCE CHECK STAGGERED TEST BASIS THERMAL POWER....

UNIDENTIFIED LEAKAGE UNRESTRICTED AREA..

VENTILATION EXHAUST TREATMENT SYSTEM VENTING...............

SALEM - UNIT 1 I

Amendment No *.

PAGE 1-1 1-1 1-1 1-1 1-1 1-1 1-2 1-2 1-2 1-2 1-3 1-3 1-3 1-3 1-3 1-3 1-4 1-4 1-4 1-4 1-5 1-5 1-5 1-5 1-5 1-5 1-6 1-6 1-6 1-6 1-6 1-6 1-6 1-7 1-7 1-7 1-7 1-7

INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS

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SECTION 2.1 SAFETY LIMITS Reactor Core Reactor Coolant System-Pressure 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Trip System Instrumentation Setpoints BASES PAGE 2-1 2-1 2-4

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SECTION 2.1 SAFETY LIMITS Reactor Core..........

Reactor Coolant System Pressure 2.2 LIMITING SAFETY SYSTEM SETTINGS PAGE B 2-1 B 2-2 Reactor Trip System Instrumentation Setpoints

...... B 2-3 SALEM - UNIT 1 II Amendment No.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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SECTION 3/4.0 APPLICABILITY 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - Tavg > 200°F Shutdown Margin - Tavg ~ 200°F Boron Dilution Moderator Temperature Coefficient.

Minimum Temperature for Criticality 3/4.1.2 BORATION SYSTEMS Flow Paths - Shutdown Flow Paths - Operating Charging Pump - Shutdown Charging Pump - Operating Boric Acid Transfer Pumps - Shutdown Boric Acid Transfer Pumps - Operating Borated Water Sources - Shutdown Borated Water Sources - Operating 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height Position Indicating Systems Rod Drop Time.......

Shutdown Rod Insertion Limit Control Rod Insertion Limits SALEM - UNIT 1 III PAGE 3/4 0-1 3/4 1-1 3/4 1-3 3/4 1-4 3/4 1-5 3/4 1-6 3/4 1-7 3/4 1-8 3/4 1-10 3/4 1-11 3/4 1-12 3/4 1-13 3/4 1-14 3/4 1-16 3/4 1-18 3/4 1-20 3/4 1-21 3/4 1-22 3/4 1-23 Amendment No.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE..

3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR 3/4.2.4 QUADRANT POWER TILT RATIO 3/4.2.5 DNB PARAMETERS 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION..............

3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation Movable Incore Detectors Seismic Instrumentation Meteorological Instrumentation Remote Shutdown Instrumentation Fire Detection Instrumentation Accident Monitoring Instrumentation Radioactive Liquid Effluent Monitoring Instrumentation..

Radioactive Gaseous Effluent Monitoring Instrumentation..

3/4 2-1 3/4 2-5 3/4 2-9 3/4 2-11 3/4 2-13 3/4 3-1 3/4 3-14 3/4 3-35 3/4 3-39 3/4 3-AO 3/4 3-43 3/4 3-46 3/4 3-49 3/4 3-53 3/4 3-58 3/4 3-64 SALEM - UNIT 1 IV Amendment No.

INDEX LIMITING CONDITIONS FOR OPERATION AND_SURVEILLANCE REQUIREMENTS

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SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation Hot Standby.

Hot Shutdown Cold Shutdown 3/4.4.2.1 SAFETY VALVES - SHUTDOWN 3/4.4.2.2 SAFETY VALVES - OPERATING 3/4.4~3 RELIEF VALVES.

3/4.4.4 PRESSURIZER.

3/4.4.5 STEAM GENERATORS 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection System Operational Leakage...

Pressure Isolation Valves 3/4.4.7 CHEMISTRY........

3/4.4.8 SPECIFIC ACTIVITY....

3/4.4.9 PRESSURE/TEMPERATURE LIMITS Reactor Coolant System Pressurizer......

Overpressure Protection Systems 3/4.4.10 STRUCTURAL INTEGRITY ASME Code Class 1, 2, and 3 Components 3/4.4.11 INTENTIONALLY BLANK.

3/4 4-1 3/4 4-2 3/4 4-3 3/4 4-3b 3/4 4-4 3/4 4-4a 3/4 4-5 3/4 4-6 3/4 4-7 3/4 4-14 3/4 4-15 3/4 4-16a 3/4 4-17 3/4 4-20 3/4 4-24 3/4 4-29 3/4 4-30 3/4 4-32 3/4 4-34 3/4.4.12 HEAD VENTS......................

3/4 4-35 SALEM - UNIT 1 v

Amendment No..

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS.

3/4.5.2 ECCS SUBSYSTEMS - Tavg ~ 350°F 3/4.5.3 ECCS SUBSYSTEMS - Tavg < 350°F 3/4.5.4 BORON INJECTION SYSTEM Boron Injection Tank Heat Tracing....

3/4.5.5 REFUELING WATER STORAGE TANK 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity Containment Leakage Containment Air Locks Internal Pressure Air Temperature Containment Structural Integrity Containment Ventilation System.

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System..

Spray Additive System Containment Cooling System 3/4.6.3 CONTAINMENT ISOLATION VALVES 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers...

Electric Hydrogen Recombiners SALEM - UNIT 1 VI Amendment No.

  • 3/4 5-1 3/4 5-3 3/4 5-6 3/4 5-7 3/4 5-8 3/4 5-9 3/4 6-1 3/4 6-2 3/4 6-5 3/4 6-6 3/4 6-7 3/4 6-8 3/4 6-8a 3/4 6-9 3/4 6-10 3/4 6-11 3/4 6-12 3/4 5-18 3/4 6-19

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

~========================================================================

SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves.......

Auxiliary Feedwater System Auxiliary Feed Storage Tank Activity Main Steam Line Isolation Valves 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION 3/4.7.3 COMPONENT COOLING WATER SYSTEM

. 3/4.7.4 SERVICE WATER SYSTEM 3/4.7.5 FLOOD PROTECTION 3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM....

3/4.7.7 AUXILIARY BUILDING EXHAUST AIR FILTRATION SYSTEM 3/4.7.8 SEALED SOURCE CONTAMINATION 3/4.7.9 SNUBBERS 3/4.7.10 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System Spray and/or Sprinkler System Low Pressure C02 Systems Fire Hose Stations 3/4.7.11 PENETRATION FIRE BARRIERS SALEM - UNIT 1 VII 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/.4 3/4 3/4 3/4 3/4 3/4 3/4 Amendment No.

7-1 7-5 7-7 7-8 7-10 7-14 7-15 7-16 7-17 7-18 7-22 7-26 7-28 7-34 7-37 7-39 7-40 7-42

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

=============================================================

SECTION PAGE 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES Operating..

Shutdown 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating..

A.C. Distribution - Shutdown 125-Volt D.C. Distribution - Operating 125-Volt D.C. Distribution - Shutdown 28-Volt D.C. Distribution - Operating.

28-Volt D.C. Distribution - Shutdown 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES SALEM - UNIT 1 VIII 3/4 8-1 3/4 8-5 3/4 8-6 3/4 8-7 3/4 8-8 3/4 8-10 3/4 8-11 3/4 8-13 3/4 8-14 Amendment No. --,

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION 3/4.9.2 INSTRUMENTATION.

3/4.9.3 DECAY TIME 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS 3/4.9.5 COMMUNICATIONS 3/4.9.6 MANIPULATOR CRANE 3/4.9.7 CRANE TRAVEL - FUEL HANDLING AREA 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION All Water Levels Low Water Level 3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM...

3/4.9.10 WATER LEVEL - REACTOR VESSEL 3/4.9.11 STORAGE POOL WATER LEVEL..

3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...

3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS 3/4.10.3 PHYSICS TESTS 3/4.10.4 NO FLOW TESTS SALEM - UNIT 1 IX 3/4 9-1 3/4 9-2 3/4 9-3 3/4 9-4 3/4 9-5 3/4 9-6 3/4 9-7 3/4 9-8 3/4 9-8a 3/4 9-9 3/4 9-10 3/4 9-11 3/4 9-12 3/4 10-1 3/4 10-2 3/4 10-3 3/4 10-4 Amendment No.

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

=============================================================

SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration......

Dose Liquid Radwaste Treatment Liquid Holdup Tanks 3/4.11.2 GASEOUS EFFLUENTS Dose Rate...

~

Dose-Noble Gases Dose-Iodine-131, Tritium, and Radionuclides in Particulate Form Gaseous Radwaste Treatment.

Explosive Gas Mixture Gas Storage Tanks...

3/4.11.3 SOLID RADIOACTIVE WASTE 3/4.11.4 TOTAL POSE 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM 3/4.12.2 LAND USE CENSUS..

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM SALEM - UNIT 1 x

Amendment No.

3/4 11-1 3/4 11-5 3/4 11-6 3/4 11-7 3/4 11-8 3/4 11-12 3/4 11-13 3/4 11-14 3/4 11-15 3/4 11-18 3/4 11-17 3/4 11-18 3/4 12-1 3/4 12-11 3/4 12-:13

INDEX BASES

=============================================================

SECTION 3/4.0 APPLICABILITY 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL 3/4.1.2 BORATION SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE..

3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR and AND 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR 3/4.2.4 QUADRANT POWER TILT RATIO 3/4.2.5 DNB PARAMETERS SALEM - UNIT 1 XI PAGE B 3/4 0-1 B 3/4 1-1 B 3/4 1-3 B 3/4 1-4 B 3/4 2-1 B 3/4 2-4 B 3/4 2-5 B 3/4 2-5 Amendment No..

I I

I I INDEX BASES

=============================================================

SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 PROTECTIVE INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES (ESF)

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION

~

3/4.4.2 SAFETY VALVES 3/4.4.3 RELIEF VALVES 3/4.4.4 PRESSURIZER 3/4.4.5 STEAM GENERATORS 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE.

3/4.4.7 CHEMISTRY 3/4.4.8 SPECIFIC ACTIVITY 3/4.4.9 PRESSURE/TEMPERATURE LIMITS 3/4.4.10 STRUCTURAL INTEGRITY....

B 3/4 3-1 B 3/4 3-1 B 3/4 3-1 B 3/4 4-1 B 3/4 4-la B 3/4 4-la B 3/4 4-2 B 3/4 4-2 B 3/4 4-3 B 3/4 4-4 B 3/4 4-5 B 3/4 4-6 B 3/4 4-11 3/4.4.11 INTENTIONALLY BLANK................. B 3/4 4-11 3/4.4.12 HEAD VENTS.....................

B 3/4 4-11 SALEM - UNIT 1 XII Amendment No.

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INDEX BASES

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SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 3/4. 5.2 and 3/4.5.3 ACCUMULATORS..

ECCS SUBSYSTEMS 3/4.5.4 BORON INJECTION SYSTEM...

3/4.5.5 REFUELING WATER STORAGE TANK (RWST) 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES 3/4.6.4 COMBUSTIBLE GAS CONTROL SALEM - UNIT 1 XIII B 3/4 5-1 B 3/4 5-1 B 3/4 5-2 B 3/4 5-2 B 3/4 6-1 B 3/4 6-3 B 3/4 6-3 B 3/4 6-4 Amendment No.

INDEX BASES

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SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION B 3/4 7-1 B 3/4 7-4 B 3/4 7-4 3/4.7.3 COMPONENT COOLING WATER SYSTEM 3/4.7.4 SERVICE WATER SYSTEM 3/4.7.5 FLOOD PROTECTION..

3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM....

3/4.7.7 AUXILIARY BUILDING EXHAUST AIR FILTRATION SYSTEM.....

3/4.7.8 SEALED SOURCE CONTAMINATION 3/4.7.9 SNUBBERS 3/4.7.10 FIRE SUPPRESSION SYSTEMS 3/4.7.11 PENETRATION FIRE BARRIERS 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES and AND 3/ 4. 8*. 2 ONSITE POWER DISTRIBUTION SYSTEMS B 3/4 7-4 B 3/4 7-5

........ B 3/4 7-5 B 3/4 7-5 B 3/4 7-5 B 3/4 7-6 B 3/4 7-7 B 3/4 7-7 B 3/4 8-1 3/4.8.3 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES B 3/4 8-1 SALEM - UNIT 1 XIV Amendment No..

I INDEX BASES

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SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION B 3/4 9-1 3/4.9.2 INSTRUMENTATION B 3/4 9-1

. 3/4.9.3

  • DECAY TIME B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS B 3/4 9-1 3/4.9.5
  • coMMUNICATIONS B 3/4 9-1 3/4.9.6 MANIPULATOR CRANE B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...........

3/4.9.9 CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM.......

3/4.9.10 WATER LEVEL - REACTOR VESSEL and AND 3/ 4. 9.11 STORAGE POOL 3/4.9.12 FUEL HANDLING AREA VENTILATION SYSTEM 3/4.10*

SPECIAL TEST EXCEPTIONS 3/4.10.1. SHUTDOWN MARGIN...........

1/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS 3/4.10.3 PHYSICS TESTS.

3/4.10.4 NO FLOW TESTS.

SALEM - UNIT 1 xv B 3/4 9-2 B 3/4 9-2 B 3/4 9-3 B 3/4 9-3 B 3/4. 10-1 B 3/4 10-1 B 3/4 10-1 B 3/4 10-1 Amendment No.-

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I INDEX BASES

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SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTE 3/4.11.4 TOTAL DOSE 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4~12.1 MONITORING PROGRAM 3/4.12.2 LAND USE CENSUS

. 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM SALEM - UNIT 1 XVI B 3/4 11-1 B 3/4 11-3 B 3/4 11-6 B 3/4 11-7 B 3/4 12-1 B 3/4 12-1 B 3/4 12-2 Amendment No *.

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INDEX DESIGN FEATURES

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SECTION 5.1 SITE Exclusion Area Low Population Zone 5.2 CONTAINMENT Configuration Design Pressure and Temperature 5.3 REACTOR CORE Fuel Assemblies Control Rod Assemblies 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature Volume............

5.5 METEOROLOGICAL TOWER LOCATION 5.6 FUEL STORAGE Criticality Drainage...

Capacity..

5.7 COMPONENT CYCLIC OR ~RANSIENT LIMIT SALEM - UNIT 1 XVII PAGE 5-1 5-1

'5-1 5-4 5-4 5-4 5-4 5-4 5-5 5-5 5-5 5-5 5-6 Amendment No,,

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I INDEX ADMINISTRATIVE CONTROLS

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SECTION 6.1 RESPONSIBILITY 6.2 ORGANIZATION Off site Facility Staff......

Shift Technical Advisor 6.3 FACILITY STAFF QUALIFICATION 6.4 TRAINING....

6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE 6.5.2 Function Composition Alternates Meeting Frequency Quorum.....

Responsibilities Review Process Authority Record NUCLEAR SAFETY REVIEW Function Composition Consultants Off-Site Review Group Review Audits On-Site Safety Review Group Responsibilities Authority.........

SALEM - UNIT 1 XVIII PAGE 6-1 6-1 6-1 6-6 6-6 6-6 6-7 6-7 6-7 6-7 6-7.a 6-8 6-9 6-9 6-9 6-9 6-9 6-9a 6-9a 6-9a 6-10 6-11 6-11 6-11 Amendment No. -----..

ADMINISTRATIVE CONTROLS

  • INDEX
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SECTION 6.5.3

. TECHNICAL REVIEW AND CONTROL 6.6 REPORTABLE EVENT ACTION 6.7 SAFETY LIMIT VIOLATION 6.8 PROCEDURES AND PROGRAMS 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS 6.9.2 SPECIAL REPORTS

6.13 PROCESS CONTROL PROGRAM 6.14 OFFSITE DOSE CALCULATION MANUAL 6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.16 ENVIRONMENTAL QUALIFICATION SALEM - UNIT 1 XIX PAGE 6-12 6-12a 6-12a 6-13 6-15 6-19 6-19 6-21 6-21 6-22 6-22 6-23 6-24 Amendment No.

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