ML19282B741

Technical Requirements Manual, Part 2 of 2

ML19282B741
Person / Time
Site:	Hatch
Issue date:	09/26/2019
From:	Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML19282B739	List: ML19282B730 ML19282B736 ML19282B741 ML19282B743 NL-19-1124, Submittal of Revision 37 to Updated Final Safety Analysis Report, Fire Hazard Analysis Changes, Technical Specification Bases Changes, Technical Requirements Manual Changes, 10CFR50.59 Summary Report and Revised Nrc
References
NL-19-1124
Download: ML19282B741 (200)

Text

HATCH UNIT 1 TRM T 11.0-1 T 11.0 LOSS OF FUNCTION DIAGRAMS A. Purpose Loss of Function Diagrams (LFDs) provide a means for evaluating the affects of the loss of one or more instrument channels on the capability of the associated instrument logic to perform its intended safety function. In fulfilling this purpose, the LFDs provide the following:

The number of channels associated with a given instrument function.

The configuration of the instrument channels in the trip systems.

The number and combinations of channels required to be operable in order for instrument function capability to be maintained.

B. General Rules for Use:

LFDs are channel-based, that is, they are designed to be used to determine instrument function capability given a loss of one or more channels. For the purposes of determining loss of function, the LFDs show what constitutes a channel. However, in identifying the beginning and end of a channel for the purpose of determining channel functional test scope, the LFD should not be used for this purpose; instead, the TRM definition Channel Functional Test Scope should be used.

As in typical elementary logic, the energy trace is from the sensor to the actuated device. Consequently, inoperability of a component in the energy trace can directly or indirectly affect the ability of a downstream component in the trace to function. However, the opposite is not always true; that is, the downstream component since it does not provide input to the upstream component does not affect the ability of the upstream component to function. As such, loss of a component anywhere other than in the channel cannot in all cases be traced back to evaluate the affect of the loss on a channel(s). Consequently, since the LFDs are channel-based, in such cases, the LFD cannot be used to determine instrument function capability. Instead, the elementary logic must be consulted to determine the affect of the loss on the supported system.

LFDs are designed to be used with the instrumentation specifications found in the Technical Specifications, the TRM, and the ODCM. Typically, an LFD is provided for each instrumentation specification line item. However, some instruments provide more than one instrument function and an LFD may not provide sufficient information to ascertain all of the functions provided by the instrument. In order to identify all instrument functions performed by a particular instrument, Table 10.1-1, Master Equipment Cross Reference, Sorted by MPL, must be consulted. For a given MPL, this sort will identify all LFDs for the instrument functions that are served by the instrument.

The complete logic from sensor to the actuation logic/actuated device is not reflected in the LFDs. A dashed line is used to denote cases where the logic

HATCH UNIT 1 TRM T 11.0-2 was not included. Elementary diagrams used to develop the LFD are referenced on the LFD in the event information on the omitted logic is needed.

The drawings show the channels and the trip logics associated with a particular instrument function and how the channels and the trip logics are related in the trip systems.

The LFDs are ordered alphabetically by the system abbreviation and then sequentially by the sketch number.

The LFD sketches are condensed elementaries and, therefore, the same rules of use that apply to elementaries also apply to the LFDs.

The loss of function statement typically found at the bottom of the LFD identifies the channel combinations required to be operable in order for instrument function capability as defined in the instrumentation specification to be maintained. In some cases, the associated instrument specification contains an action statement that requires tripping the inoperable channel within a prescribed period of time. The LFD takes credit for this requirement in that it specifies for these cases that in order for instrument function to be maintained, the prescribed combinations of channels must be either operable or maintained in the tripped condition.

The following is a list of abbreviations and their meanings used in the drawings that may be unfamiliar to the user:

AU - Alarm Unit EPM - RPS Electric Power Monitoring ITU - Indicating Trip Unit LRM - Log Radiation Monitor MTU - Master Trip Unit PRM - Process Radiation Monitoring PS - Pressure Switch RWLH - Reactor Water Level High RIS - Radiation Indicating Switch SAU - Single Alarm Unit STU - Slave Trip Unit

T 11.0 LOSS OF FUNCTION DIAGRAMS LIST OF DIAGRAMS Diagram No.

Title Revision No.

HATCH UNIT 1 TRM T 11.0-i Revision 60 LFD-1-CRB-01 (1 sheet)

TS 3.3.2.1-1, Item 1.a, Control Rod Block, Rod Block Monitor, Low Power Range - Upscale 12 LFD-1-CRB-02 (1 sheet)

TS 3.3.2.1-1, Item 1.b, Control Rod Block, Rod Block Monitor, Intermediate Power Range - Upscale 12 LFD-1-CRB-03 (1 sheet)

TS 3.3.2.1-1, Item 1.c, Control Rod Block, Rod Block Monitor, High Power Range - Upscale 12 LFD-1-CRB-04 (1 sheet)

TS 3.3.2.1-1, Item 1.d, Control Rod Block, Rod Block Monitor - Inop 12 LFD-1-CRB-05 (1 sheet)

TS 3.3.2.1-1, Item 1.e, Control Rod Block, Rod Block Monitor - Downscale 12 LFD-1-CRB-06 (1 sheet)

N/A 12 LFD-1-CRB-07 (1 sheet)

TS 3.3.2.1-1, Item 2, Control Rod Block, Rod Worth Minimizer LFD-1-CRB-08 (1 sheet)

TS 3.3.2.1-1, Item 3, Control Rod Block, Reactor Mode Switch - Shutdown Position LFD-1-CRB-09 (1 sheet)

TRM T3.3.2-1, Item 1.a, Control Rod Block Instrumentation, SRM - Detector Not Full In 60 LFD-1-CRB-10 (1 sheet)

TRM T3.3.2-1, Item 1.b, Control Rod Block Instrumentation, SRM - Upscale 60 LFD-1-CRB-11 (1 sheet)

TRM T3.3.2-1, Item 1.c, Control Rod Block Instrumentation, SRM - Inoperative 60 LFD-1-CRB-12 (1 sheet)

TRM T3.3.2-1, Item 1.d, Control Rod Block Instrumentation, SRM - Downscale 60 LFD-1-CRB-13 (1 sheet)

TRM T3.3.2-1, Item 2.a, Control Rod Block Instrumentation, IRM - Detector Not Full In 60 LFD-1-CRB-14 (1 sheet)

TRM T3.3.2-1, Item 2.b, Control Rod Block Instrumentation, IRM - Upscale 60 LFD-1-CRB-15 (1 sheet)

TRM T3.3.2-1, Item 2.c, Control Rod Block Instrumentation, IRM - Inoperative 60

List of Diagrams (Continued)

Diagram No.

Title Revision No.

HATCH UNIT 1 TRM T 11.0-ii Revision 113 LFD-1-CRB-16 (1 sheet)

TRM T3.3.2-1, Item 2.d, Control Rod Block Instrumentation, IRM - Downscale 60 LFD-1-CRB-17 (1 sheet)

TRM T3.3.2-1, Item 3.a, Control Rod Block Instrumentation, APRM - Simulated Thermal Power -

Upscale 60 LFD-1-CRB-18 (1 sheet)

TRM T3.3.2-1, Item 3.b, Control Rod Block Instrumentation, APRM - Simulated Thermal Power -

Upscale (Setdown) 60 LFD-1-CRB-19 (1 sheet)

TRM T3.3.2-1, Item 3.c, Control Rod Block Instrumentation, APRM - Inoperative 60 LFD-1-CRB-20 (1 sheet)

TRM T3.3.2-1, Item 3.d, Control Rod Block Instrumentation, APRM - Neutron Flux - Downscale 60 LFD-1-CRB-21 (1 sheet)

TRM T3.3.2-1, Item 3.e, Control Rod Block Instrumentation, APRM - Low LPRM Count 60 LFD-1-CRB-22 (1 sheet)

TRM T3.3.2-1, Item 3.f, Control Rod Block Instrumentation, APRM - Reactor Recirculation Flow -

Upscale 60 LFD-1-CRB-23 (1 sheet)

TRM T3.3.2-1, Item 4, Control Rod Block Instrumentation, SDV Level - High 60 LFD-1-ECCS-01 (1 sheet)

TS 3.3.5.1-1, Item 1.a, Core Spray System RWL - Low Low Low, Level 1 6

LFD-1-ECCS-02 (1 sheet)

TS 3.3.5.1-1, Item 1.b, Core Spray System Drywell Pressure - High 93 LFD-1-ECCS-03 (1 sheet)

TS 3.3.5.1-1, Item 1.c & TS 3.3.5.2-1, Item 1.a, Core Spray System Reactor Steam Dome Pressure - Low 113 LFD-1-ECCS-04 (1 sheet)

TS 3.3.5.1-1, Item 1.d & TS 3.3.5.2-1, Item 1.b, Core Spray System Core Spray Pump Discharge Flow - Low 113 LFD-1-ECCS-05 (1 sheet)

TS 3.3.5.1-1, Item 2.a, LPCI System RWL - Low Low Low, Level 1 6

LFD-1-ECCS-06 (1 sheet)

TS 3.3.5.1-1, Item 2.b, LPCI System Drywell Pressure - High 93

List of Diagrams (Continued)

Diagram No.

Title Revision No.

HATCH UNIT 1 TRM T 11.0-iii Revision 113 LFD-1-ECCS-07 (1 sheet)

TS 3.3.5.1-1, Item 2.c & TS 3.3.5.2-1, Item 2.a, LPCI System Reactor Steam Dome Pressure - Low 113 LFD-1-ECCS-08 (1 sheet)

TS 3.3.5.1-1, Item 2.d, LPCI System Reactor Steam Dome Pressure - Low Recirc Disch Valve Permissive LFD-1-ECCS-09 (1 sheet)

TS 3.3.5.1-1, Item 2.e, LPCI System Reactor Vessel Shroud, Level 0 LFD-1-ECCS-10 (1 sheet)

TS 3.3.5.1-1, Item 2.f, LPCI System LPCI Pump Start - Time Delay Relay LFD-1-ECCS-11 (1 sheet)

TS 3.3.5.1-1, Item 2.g & TS 3.3.5.2-1, Item 2.b, LPCI System LPCI Pump Discharge Flow - Low (Bypass) 113 LFD-1-ECCS-12 (1 sheet)

TS 3.3.5.1-1, Item 3.a, HPCI System RWL - Low Low, Level 2 6

LFD-1-ECCS-13 (1 sheet)

TS 3.3.5.1-1, Item 3.b, HPCI Initiation Drywell Pressure - High 93 LFD-1-ECCS-14 (1 sheet)

TS 3.3.5.1-1, Item 3.c, HPCI System Reactor Vessel Water Level - High, Level 8 LFD-1-ECCS-15 (1 sheet)

TS 3.3.5.1-1, Item 3.d, HPCI System Condensate Storage Tank Level - Low LFD-1-ECCS-16 (1 sheet)

TS 3.3.5.1-1, Item 3.e, HPCI System Suppression Pool Water Level - High LFD-1-ECCS-17 (1 sheet)

TS 3.3.5.1-1, Item 3.f, HPCI System HPCI Pump Disch Flow - Low (Bypass)

LFD-1-ECCS-18 (1 sheet)

TS 3.3.5.1-1, Item 4.a/5.a, ADS Trip System RWL - Low, Low, Low - Level 1 6

LFD-1-ECCS-19 (1 sheet)

TS 3.3.5.1-1, Item 4.b/5.b, ADS Trip System Drywell Pressure - High 93 LFD-1-ECCS-20 (1 sheet)

TS 3.3.5.1-1, Item 4.c/5.c, ADS Trip System ADS Initiation Timer LFD-1-ECCS-21 (1 sheet)

TS 3.3.5.1-1, Item 4.d/5.d, ADS Trip System RWL - Low, Level 3 (Confirmatory)

List of Diagrams (Continued)

Diagram No.

Title Revision No.

HATCH UNIT 1 TRM T 11.0-iv Revision 104 LFD-1-ECCS-22 (1 sheet)

TS 3.3.5.1-1, Item 4.e/5.e, ADS Trip System Core Spray Pump Discharge Press - High LFD-1-ECCS-23 (1 sheet)

TS 3.3.5.1-1, Item 4.f/5.f, ADS Trip System LPCI Pump Discharge Pressure - High LFD-1-ECCS-24 (1 sheet)

TS 3.3.5.1-1, Item 4.g/5.g, ADS Trip System ADS Low Water LVL Actuation Timer LFD-1-ECCS-25 (1 sheet)

TRM T3.3.5-1, Item 2, HPCI Turbine Trip HPCI Turbine Exhaust Pressure - High 60 LFD-1-ECCS-26 (1 sheet)

TRM T3.3.5-1, Item 3, HPCI Turbine Trip HPCI Pump Suction Pressure - Low 60 LFD-1-ECCS-27 (1 sheet)

TRM T3.3.5-1, Item 5, RCIC Turbine Trip RCIC Turbine Exhaust Pressure - High 104 LFD-1-ECCS-28 (1 sheet)

TRM T3.3.5-1, Item 6, RCIC Turbine Trip RCIC Pump Suction Pressure - Low 60 LFD-1-ECCS-29 (1 sheet)

TRM T3.3.5-1, Items 7.a and 7.b, RCIC Pump Discharge Flow - High, Low 82 LFD-1-EPM-01 TS 3.3.8.2, RPS Electric Power Monitor Trips 33 (1 sheet)

LFD-1-LLS-01 (2 sheets)

TS 3.3.6.3-1, Item 1, Low-Low Set Instrumentation -

Reactor Steam Dome Pressure - High 103 LFD-1-LLS-02 (2 sheets)

TS 3.3.6.3-1, Item 2, Low-Low Set Instrumentation -

Low-Low Set Pressure Setpoints 103 LFD-1-LLS-03 (2 sheets)

TS 3.3.6.3-1, Item 3, Low-Low Set Instrumentation -

Tailpipe Pressure Switch 103 LFD-1-LOP-01 (3 sheets)

TS 3.3.8.1-1, Items 1.a and 1.b, 4.16 kV Emergency Bus, Loss of Voltage and Time Delay LFD-1-LOP-02 (3 sheets)

TS 3.3.8.1-1, Items 2.a and 2.b, 4.16 kV Emergency Bus, Degraded Voltage and Time Delay

List of Diagrams (Continued)

Diagram No.

Title Revision No.

HATCH UNIT 1 TRM T 11.0-v Revision 93 LFD-1-LOP-03 (1 sheet)

TS 3.3.8.1-1, Items 3.a and 3.b, 4.16 KV Emergency Bus, Degraded Voltage Annunciation and Time Delay 63 LFD-1-MCREC-01 (1 sheet)

TS 3.3.7.1, MCREC System Initiation Control Room Air Inlet Radiation - High LFD-1-MCREC-02 (1 sheet)

TRM T3.3.7-1, Item 1, MCREC System Instrumentation, Reactor Vessel Water Level - Low Low Low, Level 1 60 LFD-1-MCREC-03 (1 sheet)

TRM T3.3.7-1, Item 2, MCREC System Instrumentation, Drywell Pressure - High 93 LFD-1-MCREC-04 (1 sheet)

TRM T3.3.7-1, Item 3, MCREC System Instrumentation, Main Steam Line Flow - High 60 LFD-1-MCREC-05 (1 sheet)

TRM T3.3.7-1, Item 4, MCREC System Instrumentation, Refueling Floor Area Radiation - High 60 LFD-1-MCREC-06 (1 sheet)

TRM T3.3.7-1, Item 5, MCREC System Instrumentation, Main Control Room Intake Radiation -

Downscale LFD-1-MSLR-01 (2 sheets)

TRM T3.3.11, Main Steam Line Radiation High - High 0/60 LFD-1-PCIS-01 (2 sheets)

TS 3.3.6.1-1, Item 1.a, Main Steam Line Isolation -

Reactor Vessel Water Level - Low Low Low, Level 1 LFD-1-PCIS-02 (2 sheets)

TS 3.3.6.1-1, Item 1.b, Main Steam Line Isolation -

Main Steam Line Pressure - Low LFD-1-PCIS-03 (2 sheets)

TS 3.3.6.1-1, Item 1.c, Main Steam Line Isolation -

Main Steam Line Flow - High LFD-1-PCIS-04 (2 sheets)

TS 3.3.6.1-1, Item 1.d, Main Steam Line Isolation -

Condenser Vacuum - Low LFD-1-PCIS-05 (2 sheets)

TS 3.3.6.1-1, Item 1.e, Main Steam Line Isolation -

Main Steam Tunnel Temperature - High

List of Diagrams (Continued)

Diagram No.

Title Revision No.

HATCH UNIT 1 TRM T 11.0-vi Revision 93 LFD-1-PCIS-06 (4 sheets)

TS 3.3.6.1-1, Item 1.f, Main Steam Line Isolation -

Turbine Building Area Temperature - High LFD-1-PCIS-07 (1 sheet)

TS 3.3.6.1-1, Item 2.a, Primary Containment Isolation, Reactor Vessel Water Level - Low, Level 3 20 LFD-1-PCIS-08 (1 sheet)

TS 3.3.6.1-1, Item 2.b, Primary Containment Isolation, Drywell Pressure - High 33 LFD-1-PCIS-09 (1 sheet)

TS 3.3.6.1-1, Item 2.c, Primary Containment Isolation, Drywell Radiation - High LFD-1-PCIS-10 (1 sheet)

TS 3.3.6.1-1, Item 2.d, Primary Containment Isolation, Reactor Building Exhaust Radiation - High 24 LFD-1-PCIS-11 (1 sheet)

TS 3.3.6.1-1, Item 2.e, Primary Containment Isolation, Refueling Floor Exhaust Radiation - High 53 LFD-1-PCIS-12 (1 sheet)

TS 3.3.6.1-1, Item 3.a, HPCI System Isolation - HPCI Steam Line Flow - High LFD-1-PCIS-13 (1 sheet)

TS 3.3.6.1-1, Item 3.b, HPCI System Isolation - HPCI Steam Supply Line Pressure - Low LFD-1-PCIS-14 (1 sheet)

TS 3.3.6.1-1, Item 3.c, HPCI System Isolation - HPCI Turbine Exhaust Diaphragm Pressure - High LFD-1-PCIS-15 (1 sheet)

TS 3.3.6.1-1, Item 3.d, HPCI System Isolation -

Drywell Pressure - High 93 LFD-1-PCIS-16 (1 sheet)

TS 3.3.6.1-1, Item 3.e, HPCI System Isolation - HPCI Pipe Penetration Room Temperature - High LFD-1-PCIS-17 (1 sheet)

TS 3.3.6.1-1, Items 3.f and 3.g, HPCI System Isolation

- Suppression Pool Area Ambient Temperature - High, and Suppression Pool Area Temperature - Time Delay Relays LFD-1-PCIS-18 N/A LFD-1-PCIS-19 (1 sheet)

TS 3.3.6.1-1, Items 3.h and 3.g, HPCI System Isolation - Suppression Pool Area Differential Temperature - High, and Suppression Pool Area Temperature - Time Delay Relays

List of Diagrams (Continued)

Diagram No.

Title Revision No.

HATCH UNIT 1 TRM T 11.0-vii Revision 113 LFD-1-PCIS-20 (1 sheet)

TS 3.3.6.1-1, Item 3.i, HPCI System Isolation -

Emergency Area Cooler Temperature - High LFD-1-PCIS-21 (1 sheet)

TS 3.3.6.1-1, Item 4.a, RCIC System Isolation RCIC Steam Line Flow - High LFD-1-PCIS-22 (1 sheet)

TS 3.3.6.1-1, Item 4.b, RCIC System Isolation RCIC Steam Supply Line Pressure - Low LFD-1-PCIS-23 (1 sheet)

TS 3.3.6.1-1, Item 4.c, RCIC System Isolation RCIC Turbine Exhaust Diaphragm Pressure - High LFD-1-PCIS-24 (1 sheet)

TS 3.3.6.1-1, Item 4.d, RCIC System Isolation Drywell Pressure - High LFD-1-PCIS-25 (1 sheet)

TS 3.3.6.1-1, Items 4.e and f, RCIC System Isolation RCIC Suppression Pool Ambient Area Temperature -

High, and Suppression Pool Area Temperature - Time Delay Relays LFD-1-PCIS-26 N/A LFD-1-PCIS-27 (1 sheet)

TS 3.3.6.1-1, Items 4.f and g, RCIC System Isolation Suppression Pool Area Temperature Time Delay Relays, and RCIC Suppression Pool Area Differential Temperature - High LFD-1-PCIS-28 (1 sheet)

TS 3.3.6.1-1, Item 4.h, RCIC System Isolation Emergency Area Cooler Temperature - High LFD-1-PCIS-29 (1 sheet)

TS 3.3.6.1-1, Item 5.a, RWCU System Isolation Area Temperature - High LFD-1-PCIS-30 (2 sheets)

TS 3.3.6.1-1, Item 5.b, RWCU System Isolation Area Ventilation Differential Temperature - High LFD-1-PCIS-31 (1 sheet)

TS 3.3.6.1-1, Item 5.c, RWCU System Isolation SLC System Initiation LFD-1-PCIS-32 (1 sheet)

TS 3.3.6.1-1, Item 5.d & TS 3.3.5.2-1, Item 4.a, RWCU System Isolation Reactor Vessel Water Level - Low Low, Level 2 113 LFD-1-PCIS-33 (1 sheet)

TS 3.3.6.1-1, Item 6.a, RHR SDC System Isolation, Reactor Steam Dome Pressure - High

List of Diagrams (Continued)

Diagram No.

Title Revision No.

HATCH UNIT 1 TRM T 11.0-viii Revision 113 LFD-1-PCIS-34 (1 sheet)

TS 3.3.6.1-1, Item 6.b & TS 3.3.5.2-1, Item 3.a, RHR SDC System Isolation, Reactor Vessel Water Level -

Low, Level 3 113 LFD-1-PRM-01 (1 sheet)

ODCM 2-1, Item 1, Liquid Radwaste Effluent Line Radiation High LFD-1-PRM-02 (1 sheet)

ODCM 3-1, Item 1.a, Reactor Building Vent Stack Monitoring System, Radiation High LFD-1-PRM-03 (1 sheet)

TRM T3.3.8-1, Item 1, Offgas System Isolation Post-Treatment Radiation Upscale 60 LFD-1-PRM-04 (1 sheet)

TRM T3.3.8-1, Item 2, Offgas System Isolation Post-Treatment Radiation Monitor Downscale 60 LFD-1-PRM-05 (1 sheet)

ODCM 3-1, Item 3.a, Main Stack Monitoring System, Noble Gas Activity Monitor 104 LFD-1-RCIC-01 (1 sheet)

TS 3.3.5.3-1, Item 1, RCIC System Reactor Vessel Water Level - Low Low, Level 2 113 LFD-1-RCIC-02 (1 sheet)

TS 3.3.5.3-1, Item 2, RCIC System Reactor Vessel Water Level - High, Level 8 113 LFD-1-RCIC-03 (1 sheet)

TS 3.3.5.3-1, Item 3, RCIC System Condensate Storage Tank Level - Low 113 LFD-1-RCIC-04 (1 sheet)

TS 3.3.5.3-1, Item 4, RCIC System Suppression Pool Water Level - High 113 LFD-1-RPS-01 (1 sheet)

TS 3.3.1.1-1, Item 1.a, Reactor Protection System Instrumentation - IRM Neutron Flux - High LFD-1-RPS-02 (1 sheet)

TS 3.3.1.1-1, Item 1.b, Reactor Protection System Instrumentation - IRM Inop LFD-1-RPS-03 (1 sheet)

TS 3.3.1.1-1, Item 2.a, Reactor Protection System Instrumentation - APRM Neutron Flux - High (Setdown) 12

List of Diagrams (Continued)

Diagram No.

Title Revision No.

HATCH UNIT 1 TRM T 11.0-ix Revision 66 LFD-1-RPS-04 (1 sheet)

TS 3.3.1.1-1, Item 2.b, Reactor Protection System Instrumentation - Simulated Thermal Power -High 12 LFD-1-RPS-05 (1 sheet)

TS 3.3.1.1-1, Item 2.c, Reactor Protection System Instrumentation - Neutron Flux - High 12 LFD-1-RPS-06 (1 sheet)

TS 3.3.1.1-1, Item 2.d, Reactor Protection System Instrumentation - APRM Inop 12 LFD-1-RPS-07 (1 sheet)

TS 3.3.1.1-1, Item 2.e, Reactor Protection System Instrumentation - APRM Two-out-of-Four Voter Circuit 12 LFD-1-RPS-07a (1 sheet)

TS 3.3.1.1-1, Item 2.f, Reactor Protection System Instrumentation - OPRM Upscale 26 LFD-1-RPS-08 (1 sheet)

TS 3.3.1.1-1, Item 3, Reactor Protection System Instrumentation - Reactor Vessel Steam Dome Pressure - High LFD-1-RPS-09 (1 sheet)

TS 3.3.1.1-1, Item 4, Reactor Protection System Instrumentation - Reactor Vessel Water Level - Low, Level 3 LFD-1-RPS-10 (1 sheet)

TS 3.3.1.1-1, Item 5, Reactor Protection System Instrumentation - Main Steam Isolation Valve - Closure LFD-1-RPS-11 (1 sheet)

TS 3.3.1.1-1, Item 6, Reactor Protection System Instrumentation, Drywell Pressure - High LFD-1-RPS-12 (1 sheet)

TS 3.3.1.1-1, Item 7.a, Reactor Protection System Instrumentation - Scram Discharge Volume Water Level - High, Resistance Temperature Detector LFD-1-RPS-13 (1 sheet)

TS 3.3.1.1-1, Item 7.b, Reactor Protection System Instrumentation - Scram Discharge Volume Water Level - High, Float Switch LFD-1-RPS-14 (1 sheet)

TS 3.3.1.1-1, Item 8, Reactor Protection System Instrumentation - Turbine Stop Valve - Closure 66 LFD-1-RPS-15 (1 sheet)

TS 3.3.1.1-1, Item 9, Reactor Protection System Instrumentation - Turbine Control Valve Fast Closure, Trip Oil Pressure - Low 33

List of Diagrams (Continued)

Diagram No.

Title Revision No.

HATCH UNIT 1 TRM T 11.0-x Revision 33 LFD-1-RPS-16 (1 sheet)

TS 3.3.1.1-1, Item 10, Reactor Protection System Instrumentation, Reactor Mode Switch - Shutdown Position LFD-1-RPS-17 (1 sheet)

TS 3.3.1.1-1, Item 11, Reactor Protection System Instrumentation, Manual Scram LFD-1-RPS-18 (1 sheet)

TS SR 3.3.1.1.11, Reactor Protection System Instrumentation Bypass, Items 8 and 9 33 LFD-1-RPT-01 (1 sheet)

TS 3.3.4.1.a.1, EOC-RPT, TSV Closure LFD-1-RPT-02 (1 sheet)

TS 3.3.4.1.a.2, EOC-RPT, TCV Fast Closure LFD-1-RPT-03 (1 sheet)

TS 3.3.4.2.a, Reactor Vessel Water Level -

ATWS-RPT Level 6

LFD-1-RPT-04 (1 sheet)

TS 3.3.4.2.b, ATWS-RPT, Reactor Steam Dome Pressure - High LFD-1-RPT-05 (1 sheet)

TS SR 3.3.4.1.2, EOC-RPT Instrumentation Bypass Below 28 Percent Power 33 LFD-1-RWLH-01 (1 sheet)

TS 3.3.2.2, Feedwater and Main Turbine Trip High Water Level Instrumentation LFD-1-SCIS-01 (1 sheet)

TS 3.3.6.2-1, Item 1, Reactor Vessel Water Level -

Low Low, Level 2 LFD-1-SCIS-02 (1 sheet)

TS 3.3.6.2-1, Item 2, Drywell Pressure - High LFD-1-SCIS-03 (1 sheet)

TS 3.3.6.2-1, Item 3, Secondary Containment Isolation Reactor Building Exhaust Radiation - High LFD-1-SCIS-04 (1 sheet)

TS 3.3.6.2-1, Item 4, R/F Exhaust Radiation - High

HATCH UNIT 1 TRM T 12.0-1 Revision 1 T 12.0 Safety Function Determination Program 1.0 Introduction This document outlines the Plant Hatch Safety Function Determination Program (SFDP), provides guidance for evaluating the impact of failure to meet multiple Technical Specifications (TS) Limiting Conditions for Operation (LCOs), and gives appropriate actions for a loss of safety function. The SFDP is required by TS Section 5.5.10.

2.0 Loss of Safety Function

2.1 Background

LCO 3.0.2 directs that if an LCO is not met, its associated Required Actions shall be performed. LCO 3.0.6 provides exception to LCO 3.0.2 for a supported system, structure, or component (SSC) by allowing only the support SSC LCO Actions to be performed if the supported SSC is inoperable solely because its support SSC is inoperable.

If a support SSC is inoperable and a loss of safety function does not exist, the Required Actions for the support SSC address the Condition, and the supported SSC Required Actions do not have to be performed. This recognizes that the plant may no longer satisfy single failure criteria and that all of the supported SSC may not meet the definition of OPERABILITY.

Appropriate compensation is made by performance of the support system Required Actions.

2.2 Use of LCO 3.0.6 Upon determination that a TS required support SSC is inoperable, the decision may be made to use LCO 3.0.6 for the supported SSCs. A loss of safety function determination shall be performed using the flow chart shown in Attachment 1 as a guide. Attachment 2 provides examples of appropriate determinations. The allowances given by LCO 3.0.6 can be taken only if no loss of safety function exists.

2.3 Actions for a Loss of Safety Function If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. These may be the Required Actions specified for the loss of safety function or LCO 3.0.3.

HATCH UNIT 1 TRM T 12.0-2 Revision 1 2.4 SSC OPERABILITY OPERABILITY determinations precede entry into the SFDP and thus, are not a direct part of the SFDP. OPERABILITY of an SSC is determined using the definition given in TS 1.1, along with the guidance of SR 3.0.1. When equipment that is not addressed in TS is degraded or nonconforming, the impact on TS SSC OPERABILITY shall also be assessed.

3.0 Guidance for Safety Function Determination TS 5.5.10 states that a loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analyses cannot be performed. For the purpose of this program a graduated approach may be taken for determining the safety function of the supported SSC. This approach, detailed below, is graduated from most to least conservative. Even if the least conservative method is used, the requirements of TS 5.5.10 will be met. In determining whether a loss of safety function has occurred, at least one of these methods must be used.

Method 1: Redundant Train(a)

For this method, the safety function is assumed to be the system function.

Confirm the OPERABILITY of the corresponding redundant supported SSC(s).

If one or more of the redundant SSCs are found to be inoperable, a loss of safety function may exist. The appropriate actions for a loss of function may be taken or alternatively, one of the following methods may be used.

Method 2: LCO Function In certain cases, multiple systems with diverse individual functions are specified under one LCO statement; i.e., in one TS. For these, the safety function may be considered to be broader than the individual system function--it is the TS LCO function, not the system function.

An example of this is the TS for ECCS Operating, in which four different systems are included. In this case, the function as stated in the Bases,... to cool the core during a LOCA, may be the safety function to be considered in the SFDP.

If a loss of LCO function is determined to exist, the appropriate actions for a loss of safety function may be taken. Alternatively, the following method may be used.

(a) The term train may be interchanged with subsystem or division.

HATCH UNIT 1 TRM T 12.0-3 Revision 1 Method 3: Safety Analysis In this approach, the function of the SSC in the FSAR accident analyses is considered to be the safety function. If the SSC in question is not credited in the analyses, or if the accident function it performs is intact, then no loss of safety function exists. However, if the function is lost, then the actions for a loss of safety function must be taken.

4.0 Additional Requirements and Information 4.1 Non-TS SSCs A situation may exist where a TS support SSC provides support to an SSC not addressed in TS, which may in turn support a supported SSC addressed in TS. The interrelationships between TS and non-TS support and supported SSCs shall be considered in the loss of safety function determination.

4.2 Subsequent Inoperabilities While taking the Required Actions of the support SSC as allowed by LCO 3.0.6, the impact of subsequent additional SSC inoperabilities on previous SFDP evaluations shall be considered.

5.0 Extending Supported SCS Completion Times 5.1 Singular Support SSC Inoperability When entering the supporting SSC Required Actions as allowed by LCO 3.0.6, the Completion Times for the supported SSCs might potentially be extended longer than their allowed Required Action Completion Times if they are shorter than those of the support SSC. If there is no loss of safety function, it is acceptable to extend the Completion Time of the supported SSC an amount equal to but not exceeding the Completion Time of its support SSC.

5.2 Multiple Support SSC Inoperabilities Once a supported SSC LCO is not met solely based on a support SSC inoperability, subsequent support SSC inoperabilities have additional limitations. This is to ensure that the supported LCO will not be in a situation of not being met for an inappropriate amount of time.

Provided there is no loss of function, the Required Actions of the support SSC Condition(s) continue to apply to each additional failure, with Completion Times based on initial entry into the particular support SSC Condition. However, when a subsequent support SSC is discovered to be inoperable or not within limits, the overall time that the supported SSC LCO is not met shall be limited to the more restrictive of either:

a. The first support SSC Completion Time, plus an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; or

HATCH UNIT 1 TRM T 12.0-4 Revision 1

b. The subsequent support SSC Completion Time as measured from discovery of the subsequent inoperability.

To apply this Completion Time extension, two criteria must first be met. The subsequent support SSC inoperability.

a. Must exist concurrently with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

Should this extended Completion Time expire with the subsequent support SSC remaining inoperable or not within limits, the Completion Time for the subsequent support SSC inoperable Condition shall be considered expired. The Required Actions defined for that Condition shall be entered.

Examples regarding Completion Time tracking are included in Attachment 2.

6.0 Conclusions Regarding the Use of LCO 3.0.6 The exception permitted by LCO 3.0.6 is justified as follows. The actions necessary to ensure safe operation of the plant are specified in the support SSC LCO Required Actions and the SFDP requires evaluation of loss of safety function. The SFDP directs that appropriate actions be taken if a loss of safety function exists. This approach eliminates the confusion and inconsistency associated with entry into multiple LCO Conditions and Required Actions.

HATCH UNIT 1 TRM T 12.0-5 Revision 5 ATTACHMENT 1 (Sheet 1 of 2)

HATCH UNIT 1 TRM T 12.0-6 ATTACHMENT 1 (Sheet 2 of 2)

HATCH UNIT 1 TRM T 12.0-7 ATTACHMENT 2 SCENARIO NO. 1: At 0100, with Unit 2 in RUN, the Unit 2 4160V F bus (a.k.a.

swing bus) is determined to be inoperable. No other TS SSC inoperabilities exist.

The 4160V F bus is a support SSC, addressed by TS LCO 3.8.7. Required Action C requires restoring the bus to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

The following is the loss of function determination for the supported systems:

RHR Pumps 2C and 2D: For LCO 3.5.1, because Core Spray, ADS, and HPCI are OPERABLE, no loss of safety function exists.

RHR Pumps 2C and 2D: For LCO 3.6.2.3, suppression pool cooling is not considered inoperable because only one pump per subsystem is required.

RHR Pumps 2C and 2D: For LCO 3.6.2.4, suppression pool spray is not considered inoperable because only one pump per subsystem is required.

RHR Pump 2C: For LCO 3.7.1, because the other subsystem is OPERABLE, no loss of safety function exists.

PSW Pumps 2C and 2D: For LCO 3.7.2, because PSW can perform its safety function with one pump per subsystem, no loss of safety function exists.

CRD Pump 2B: This is a non-TS SSC, but it supports control rods, TS LCO 3.1.3. With redundant CRD pumps operable, the safety function of the control rods is not affected.

Diesel Bldg. MCC 1B (1R24S026): This is part of the 4160V F bus subsystem, addressed by TS 3.8.7. This supports distribution cabinet 1K (1R24S030) and ultimately the DG 1B. The DG 1B is inoperable, and LCO 3.8.1 Condition B required several different actions with Completion Times ranging from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 7 days. With redundant DGs OPERABLE, no loss of safety function exists.

==

Conclusions:==

No loss of safety function exists. LCO 3.0.6 may be entered with a completion time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore the inoperable bus to OPERABLE status, beginning at 0100.

HATCH UNIT 1 TRM T 12.0-8 Revision 35 SCENARIO NO. 2: At 0500, with Unit 2 in RUN, Reactor Vessel Water Level-Low Low Low (Level 1) channels A, B, and C are determined to be inoperable. This leaves only channel D operable.

This instrumentation supports ECCS by providing initiation for Core Spray, LPCI and ADS; and, also, supports initiation of the DGs and isolation of the PSW Turbine Building valves. Since all these supported functions require at least two channels, entry must be made into the Required Actions for LCO 3.3.5.1.

These Actions directly specify declaring supported features inoperable (due to loss of initiation capability in both Divisions). As stated in LCO 3.0.6, when the support SSC Required Actions provide direction for supported SSCs, the applicable supported SSC Conditions and Required Actions shall be entered. This effectively precludes the use of LCO 3.0.6 in determining the completion time for the supported SSCs.

==

Conclusions:==

The LCO 3.3.5.1 Required Actions should be performed, as well as those for all the inoperable supported systems. The SFDP will not be entered, because LCO 3.0.6 cannot be used.

SCENARIO NO. 4-A: At 0100, with Unit 2 in MODE 1, the Unit 2 RHRSW A Pump becomes inoperable. The RHRSW crosstie valves are tagged for maintenance. No other TS SSC inoperabilities exist.

The RHRSW system is a support SSC, addressed by TS LCO 3.7.1. Required Action A for one inoperable RHRSW pump is to restore the pump to OPERABLE status within 30 days. The bases for this specification state that an RHRSW subsystem is considered operable when 2 pumps are OPERABLE with an OPERABLE flow path. With the A pump inoperable, the A subsystem of RHRSW is inoperable.

The following is the loss of function determination for the supported systems:

RHR Suppression Pool Cooling: LCO 3.6.2.3 requires two subsystems to be OPERABLE for suppression pool cooling. The Bases for this LCO state that an RHR suppression pool cooling subsystem is OPERABLE with one RHR pump, the heat exchanger, and associated piping. Therefore, the inoperability of RHRSW subsystem A causes suppression pool cooling subsystem A to be inoperable.

This is Condition A, with a Required Action Completion Time of 7 days. However, because suppression pool cooling subsystem B is OPERABLE, no loss of safety function exists. The Completion Time for suppression pool cooling may be extended to 30 days (from the time of discovery of RHRSW pump A being inoperable; i.e., 0100).

RHR Suppression Pool Spray: LCO 3.6.2.4 requires 2 subsystems to be OPERABLE for suppression pool spray. The Bases for this LCO state that an RHR suppression pool spray subsystem is OPERABLE with one RHR pump, the heat exchanger, and associated piping. Therefore, the inoperability of RHRSW subsystem A causes suppression pool spray subsystem A to be inoperable.

This is Condition A, with a Required Action Completion Time of 7 days. However,

HATCH UNIT 1 TRM T 12.0-9 Revision 35 because subsystem B is operable, no loss of safety function exists. The Completion Time for suppression pool spray may be extended to 30 days.

SCENARIO 4-B: At 29 days, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the initial inoperability of RHRSW pump A, with the pump remaining inoperable, RHRSW pump C is found to be inoperable. At 29 days 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, RHR SW pump A is restored to OPERABLE status. RHRSW pump C remains inoperable.

With the second RHRSW pump inoperability, Condition C has been entered for LCO 3.7.1. Note that the Completion Time clock for Condition A is still running.

Condition C requires that the RHRSW subsystem be restored to OPERABLE status within 7 days. The two SSCs supported by RHRSW continue to have their B subsystems OPERABLE, so no loss of safety function exists.

When the RHRSW pump A is restored to OPERABLE status, the LCO 3.7.1 Condition C is exited, but the Condition A clock is still running due to the inoperability of RHRSW pump C. Under the provisions of Section 1.3 of the Technical Specifications, the Completion Time for RHRSW pump C is 31 days from the initial inoperability, i.e., the inoperability of pump A. Therefore, the Completion Times for the supported SSCs may also be extended to 31 days measured from the same starting point.

HATCH UNIT 1 TRM C-i TECHNICAL REQUIREMENTS MANUAL APPENDIX C HNP UNITS 1 AND 2 OFFSITE DOSE CALCULATION MANUAL SPECIFICATIONS ACTIVE PAGE LIST Page Version No.

2-1 25 2-2 25 2-3 25 2-4 25 2-5 25 2-6 25 3-1 25 3-2 25 3-3 25 3-4 25 3-5 25 3-6 25 3-7 25 3-8 25 3-9 25 10-1 25 10-2 25 10-3 25 10-4 25 10-5 25 10-6 25 10-7 25

HNP ODCM 2-1 Version 25 1/18 CHAPTER 2 LIQUID EFFLUENTS 2.1 LIMITS OF OPERATION The following Liquid Effluent Controls implement requirements established by Technical Specifications Section 5.0. Terms printed in all capital letters are defined in Chapter 10.

2.1.1 Liquid Effluent Monitoring Instrumentation Control In accordance with Technical Specification 5.5.4.a, the radioactive liquid effluent monitoring instrumentation channels shown in Table 2-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits specified in Section 2.1.2 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Section 2.3.

2.1.1.1 Applicability As shown in Table 2-1.

2.1.1.2 Actions With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, declare the channel inoperable, or change the setpoint to a conservative value.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2-1. NOTE: One instrument channel may be inoperable for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to perform required surveillances prior to entering other applicable ACTIONS. Otherwise, restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report, per Technical Specification 5.6.3, why this inoperability was not corrected in a timely manner.

Entry into an Operational Mode or other specified CONDITION shall be made if, as a minimum, the requirements of Technical Specifications LCO 3.0.4 are met.

2.1.1.3 Surveillance Requirements Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2-2.

HNP ODCM 2-2 Version 25 1/18 2.1.1.4 Basis The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Section 2.3 to ensure that the alarm/trip will occur prior to exceeding the limits of Section 2.1.2. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

HNP ODCM 2-3 Version 25 1/18 Table 2-1 Radioactive Liquid Effluent Monitoring Instrumentation Instrument OPERABILITY Requirementsa Minimum Channels OPERABLE Applicabilityb ACTION

1. Gross Radioactivity Monitors Providing Automatic Termination of Release Liquid Radwaste Effluent Line 1

(1) 100

2. Gross Radioactivity Monitors not Providing Automatic Termination of Release Service Water System Effluent Line 1

(2) 101

3. Flowrate Measurement Devicesc

a. Liquid Radwaste Effluent Line 1

(1) 102

b. Discharge Canal 1

(1), (2) 102

4. Differential Pressure Measurement Devices Service Water System to Closed Cooling Water System 1

At all times 103

5. Groundwater Outfall Instrumentation

a. Auto Sampler at Y22N008A 1

At all times 104

b. Flow Totalizer at Y22N008A 1

At all times 105 a.

All requirements in this Table apply to each unit.

b.

Applicability of requirements is as follows:

(1)Whenever the radwaste discharge valves are not locked closed.

(2)Whenever the Service Water System pressure is below the Closed Cooling Water System pressure, or P indication is not available.

c.

Pump curves may be used to estimate flow; in such cases, ACTION statement 102 is not required.

HNP ODCM 2-4 Version 25 1/18 Table 2-1 (contd)

Notation for Table 2 ACTION Statements ACTION 100 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Section 2.1.2.3, and b.

At least two technically qualified individuals independently verify the discharge line valving and verify the release rate calculations.

Otherwise, suspend release of radioactive effluents via this pathway. If the channel remains inoperable for over 30 days, an explanation of the circumstances must be included in the next Radioactive Effluent Release Report.

ACTION 101 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that once per shift grab samples are collected and analyzed for gross radioactivity at a MINIMUM DETECTABLE CONCENTRATION no higher than 1 % 10-7&Ci/mL. If the channel remains inoperable for over 30 days, an explanation of the circumstances must be included in the next Radioactive Effluent Release Report.

ACTION 102 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that the flowrate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. If the channel remains inoperable for over 30 days, an explanation of the circumstances must be included in the next Radioactive Effluent Release Report.

ACTION 103 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, assure that the Service Water System effluent monitor is OPERABLE.

ACTION 104 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, obtain daily grab samples and composite for weekly tritium, monthly gamma, and quarterly Sr 89/90 analyses.

ACTION 105 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, estimate outfall flow rate daily. If the channel remains inoperable for over 30 days, an explanation of the circumstances must be included in the next Radioactive Effluent Release Report.

HNP ODCM 2-5 Version 25 1/18 Table 2-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements INSTRUMENT Surveillance Requirementsa CHANNEL CHECK SOURCE CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST

1. Gross Radioactivity Monitors Providing Automatic Termination of Release Liquid Radwaste Effluent Line Db Pe R

Qc

2. Gross Radioactivity Monitors not Providing Automatic Termination of Release Service Water System Effluent Line Db M

R Qf

3. Flowrate Measurement Devices

a. Liquid Radwaste Effluent Line Db,d NA 18 M Q

b.

Discharge Canal Db,d NA 18 M Q

4. Differential Pressure Measurement Devices Service Water System to Closed Cooling Water System D

NA R

NA

5. Groundwater Outfall Instrumentation

a. Auto Samplers at (1)

Y22N008A Wg NA NA NA

b. Flow Totalizer at Y22N008A Wg NA NA NA a.

All requirements in this Table apply to each unit.

b.

During releases via this pathway.

c.

In addition to the basic functions of a CHANNEL FUNCTIONAL TEST (Section 10.2), the CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:

(1)

Instrument indicates measured levels above the alarm/trip setpoint; (2)

Instrument indicates an isolation on high alarm; or (3)

Instrument controls are not set in operate mode.

d.

CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once daily on any day on which CONTINUOUS, periodic, or BATCH releases are made.

e.

The SOURCE CHECK shall consist of verifying that the instrument is reading on scale.

Hatch ODCM Table 2-2 (contd)

Notation for Table 2 Surveillance Requirements 2-6 Version 25 1/18 f.

In addition to the basic functions of a CHANNEL FUNCTIONAL TEST (Section 10.2), the CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

(1)

Instrument indicates measured levels above the alarm setpoint; (2)

Instrument indicates a downscale failure; or (3)

Instrument controls are not set in operate mode.

g.

CHANNEL CHECK shall consist of verifying indication of operability at least once weekly during sample collection.

HNP ODCM 3-1 Version 25 1/18 CHAPTER 3 GASEOUS EFFLUENTS 3.1 LIMITS OF OPERATION The following Limits of Operation implement requirements established by Technical Specifications Section 5.0. Terms printed in all capital letters are defined in Chapter 10.

3.1.1 Gaseous Effluent Monitoring Instrumentation Control In accordance with Technical Specification 5.5.4., the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Section 3.1.2.a are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Section 3.3.

3.1.1.1 Applicability These limits apply as shown in Table 3-1.

3.1.1.2 Actions With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, declare the channel inoperable, or restore the setpoint to a value that will ensure that the limits of Section 3.1.2.a are met.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3-1. NOTE: One instrument channel may be inoperable for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to perform required surveillances prior to entering other applicable ACTIONS. Otherwise, restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report, per Technical Specification 5.6.3, why this inoperability was not corrected in a timely manner.

Entry into an Operational Mode or other specified CONDITION shall be made if, as a minimum, the requirements of Technical Specifications LCO 3.0.4 are met.

3.1.1.3 Surveillance Requirements Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 3-2.

HNP ODCM 3-2 Version 25 1/18 3.1.1.4 Basis The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Section 3.3 to ensure that the alarm/trip will occur prior to exceeding the limits of Section 3.1.2.a. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

HNP ODCM 3-3 Version 25 1/18 Table 3-1 Radioactive Gaseous Effluent Monitoring Instrumentation Instrument Minimum Channels OPERABLE Applicability ACTION

1. Reactor Building Vent Stack Monitoring System (Each Unit)

a. Noble Gas Activity Monitorc 1

(a) 105

b. Iodine Sampler Cartridge 1

(a) 107 c.

Particulate Sampler Filter 1

(a) 107

d. Effluent System Flowrate Measurement Device 1

(a) 104

e. Sampler Flowrate Measurement Device 1

(a) 104

2. Recombiner Building Ventilation Monitoring System

a. Noble Gas Activity Monitorc 1

(a) 105

b. Iodine Sampler Cartridge 1

(a) 107 c.

Particulate Sampler Filter 1

(a) 107

d. Effluent System Flowrate Measurement Device 1

(a) 104

e. Sampler Flowrate Monitor 1

(a) 104

3. Main Stack Monitoring System

a. Noble Gas Activity Monitorc 1

(a) 105

b. Iodine Sampler Cartridge 1

(a) 107 c.

Particulate Sampler Filter 1

(a) 107

d. Effluent System Flowrate Measurement Device 1

(a) 104

e. Sampler Flowrate Measurement Device 1

(a) 104

4. Condenser Offgas Pretreatment Monitor (Each Unit)

a. Noble Gas Activity Monitor 1

(b) 108

a. During radioactive releases via this pathway.

b. During operation of the main condenser air ejector.

c.

Monitor must be capable of responding to a MINIMUM DETECTABLE CONCENTRATION of 1 % 10-4 &Ci/mL.

HNP ODCM 3-4 Version 25 1/18 Table 3-1 (contd)

Notation for Table 3-1.

ACTION 104 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flowrate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. If the number of channels OPERABLE remains less than required by the minimum channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next Radioactive Effluent Release Report.

ACTION 105 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken daily and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With the number of main stack monitoring system channels OPERABLE less than required by the minimum channels OPERABLE requirement, immediately suspend drywell purge. If the number of channels OPERABLE remains less than required by the minimum channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next Radioactive Effluent Release Report.

ACTION 107 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided samples are continuously collected with auxiliary equipment for periods on the order of 7 days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the end of the sampling period. If the number of channels OPERABLE remains less than required by the minimum channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next Radioactive Effluent Release Report.

ACTION 108 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:

a.

The offgas treatment system is not bypassed; and b.

The offgas post-treatment monitor (D11-K615) or the main stack monitor (D11-K600) is OPERABLE; and c.

Perform Technical Specification SR 3.7.6.1 every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Otherwise, enter Condition "A" of Technical Specification LCO 3.7.6.

If the number of channels OPERABLE remains less than required by the minimum channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next Radioactive Effluent Release Report.

HNP ODCM 3-5 Version 25 1/18 Table 3-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements INSTRUMENT CHANNEL CHECK SOURCE CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST

1. Reactor Building Vent Stack Monitoring System (Each Unit)

a. Noble Gas Activity Monitor Da M

R Qc

b. Iodine Sampler Cartridge Wa,d NA NA NA c.

Particulate Sampler Filter Wa,d NA NA NA

d. Effluent System Flowrate Measuring Device Da NA R

Q

e. Sampler Flowrate Measuring Device Da NA R

Q

2. Recombiner Building Ventilation Monitoring System

a. Noble Gas Activity Monitor Da M

R Qc

b. Iodine Sampler Cartridge Wa,d NA NA NA c.

Particulate Sampler Filter Wa,d NA NA NA

d. Effluent System Flowrate Measuring Device Da NA R

Q

e. Sampler Flowrate Measuring Device Da NA R

Q

3. Main Stack Monitoring System

a. Noble Gas Activity Monitor Da M

R Qc

b. Iodine Sampler Cartridge Wa,d NA NA NA c.

Particulate Sampler Filter Wa,d NA NA NA

d. Effluent Flowrate Monitor Da NA R

Q

e. Sampler Flowrate Monitor Da NA R

Q

4. Condenser Offgas Pretreatment Monitor (Each Unit)

a. Noble Gas Activity Monitor Db M

R Qc a.

Requirement applies during releases via this pathway.

b.

Requirement applies during operation of the main condenser air ejector.

c.

In addition to the basic functions of a CHANNEL FUNCTIONAL TEST (Section 10.2), the CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

(1)

Instrument indicates measured levels above the alarm/trip setpoint.

(2)

Circuit failure occurs.

(3)

Instrument indicates a downscale failure.

HNP ODCM 3-6 Version 25 1/18 d.

The CHANNEL CHECK shall consist of verifying sampler flow and the presence of the collection device (i.e., particulate filter or charcoal cartridge, etc.) at the weekly changeout.

3.1.2 Gaseous Effluent Dose Rate Control In accordance with Technical Specifications 5.5.4.c and 5.5.4.g, the licensee shall conduct operations so that the dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 10-1) are limited as follows:

a.

For noble gases: Less than or equal to a dose rate of 500 mrem/y to the total body and less than or equal to a dose rate of 3000 mrem/y to the skin, and b.

For Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem/y to any organ.

3.1.2.1 Applicability This limit applies at all times.

3.1.2.2 Actions With a dose rate due to radioactive material released in gaseous effluents exceeding the limit stated in Section 3.1.2, immediately decrease the release rate to within the stated limit.

Entry into an Operational Mode or other specified CONDITION shall be made if, as a minimum, the requirements of Technical Specifications LCO 3.0.4 are met.

3.1.2.3 Surveillance Requirements The dose rates due to radioactive materials in areas at or beyond the SITE BOUNDARY due to releases of gaseous effluents shall be determined to be within the above limits, in accordance with the methods and procedures in Section 3.4.1, by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-3.

3.1.2.4 Basis This control is provided to ensure that gaseous effluent dose rates will be maintained within the limits that historically have provided reasonable assurance that radioactive material discharged in gaseous effluents will not result in a dose to a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, exceeding the limits specified in Appendix I of 10 CFR Part 50, while allowing operational flexibility for effluent releases. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.

HNP ODCM 3-7 Version 25 1/18 The dose rate limit for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days specifically applies to dose rates to a child via the inhalation pathway.

This control applies to the release of gaseous effluents from all reactors at the site.

HNP ODCM 3-8 Version 25 1/18 Table 3-3 Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Type Sampling and Analysis Requirementsa Sampling FREQUENCY Minimum Analysis FREQUENCY Type of Activity Analysis MINIMUM DETECTABLE CONCENTRATION (MDC)

(&Ci/mL)

Environmental Release Points

1. Main Stack

2. Reactor Building Vent (Each Unit)

3. Recombiner Building Ventb Mc Grab Sample Mc PRINCIPAL GAMMA EMITTERS H-3 1 E-4 1 E-6 CONTINUOUSe Wd Charcoal or Silver Zeolite Sample I-131 I-133 1 E-12 1 E-10 CONTINUOUSe Wd Particulate Sample PRINCIPAL GAMMA EMITTERS 1 E-11 CONTINUOUSe M

COMPOSITE Particulate Sample Gross Alpha 1 E-11 CONTINUOUSe Q

COMPOSITE Particulate Sample Sr-89, Sr-90 1 E-11 a.

Terms printed in all capital letters are defined in Chapter 10. When unusual circumstances result in a MINIMUM DETECTABLE CONCENTRATION higher than required, the reasons shall be documented in the next Radioactive Effluent Release Report.

b.

The Recombiner Building Vent serves Unit 1. Sample analysis results and associated source terms must be assigned to Unit 1 for the purpose of release accountability and dose calculations.

c.

Sampling and analyses for PRINCIPAL GAMMA EMITTERS shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a one-hour period. The more frequent sampling and analysis requirement applies only if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant and the Main Stack Noble Gas Activity Monitor reading have both increased by a factor of 3.

HNP ODCM 3-9 Version 25 1/18 Table 3-3 (contd)

Notation for Table 3-3 d.

Sampling shall be performed weekly, and analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing (or after removal from sampler). Sampling shall also be performed once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a one-hour period, with analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding MINIMUM DETECTABLE CONCENTRATIONs may be increased by a factor of 10. The more frequent sampling and analysis requirement applies only if analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant and the Main Stack Noble Gas Activity Monitor reading have both increased by a factor of 3.

e.

The ratio of the sample flowrate to the sampled stream flowrate shall be known for the time period covered by each dose or dose rate calculation made in accordance with controls specified in Sections 3.1.2, 3.1.3, and 3.1.4.

HNP ODCM 10-1 Version 25 1/18 CHAPTER 10 DEFINITIONS OF EFFLUENT CONTROL TERMS The terms defined in this chapter are used in the presentation of the above chapters. These terms are shown in all capital letters to indicate that they are specifically defined.

10.1 TERMS SPECIFIC TO THE ODCM The following terms are used in the ODCM, but are not found in the Technical Specifications:

BATCH RELEASE A BATCH RELEASE is the discharge of wastes of a discrete volume. Prior to sampling for analyses, each liquid batch shall be isolated and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

COMPOSITE SAMPLE A COMPOSITE SAMPLE is one which contains material from multiple waste releases, in which the quantity of sample is proportional to the quantity of waste discharged, and in which the method of sampling employed results in a specimen that is representative of the wastes released. Prior to analyses, all liquid samples that are to be aliquotted for a COMPOSITE SAMPLE shall be mixed thoroughly, in order for the COMPOSITE SAMPLE to be representative of the effluent release.

When assessing the consequences of a waste release at the pre-release or post-release stage, the most recent available COMPOSITE SAMPLE results for the applicable release pathway may be used.

CONTINUOUS RELEASE A CONTINUOUS RELEASE is the discharge of wastes of a non-discrete volume, e.g.,

from a volume within a system that has an input flow during the continuous release.

FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of surveillance requirements shall correspond to the intervals defined below, with a maximum allowable extension not to exceed 25% of the surveillance interval.

NOTATION FREQUENCY S (Once per shift)

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D (Daily)

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W (Weekly)

At least once per 7 days.

M (Monthly)

At least once per 31 days.

Q (Quarterly)

At least once per 92 days.

SA (Semi-annually)

At least once per 184 days.

18M At least once per 18 months.

R (Refueling)

At least once per 24 months.

S/U (Startup)

Prior to each reactor startup.

NA Not Applicable.

P (Prior)

Completed prior to each release.

HNP ODCM 10-2 Version 25 1/18 GASEOUS RADWASTE TREATMENT SYSTEM The GASEOUS RADWASTE TREATMENT SYSTEM is the offgas holdup system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

LIQUID RADWASTE TREATMENT SYSTEM A LIQUID RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive materials in liquid effluents by systematic collection, retention, and processing through filtration, evaporation, separation and/or ion exchange treatment.

This system consists of at least one collection tank, one evaporator or demineralizer system, one post-treatment tank and associated components providing for treatment flow and functional control.

MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS For the purposes of the ODCM, MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS include the following changes to such systems:

(1)

Major changes in process equipment, components, structures, or effluent monitoring instrumentation as described in the Final Safety Analysis Report (FSAR) or as evaluated in the Nuclear Regulatory Commission staff's Safety Evaluation Report (SER) (e.g., deletion of evaporators and installation of demineralizer);

(2)

Changes in the design of radwaste treatment systems that could significantly increase quantities of effluents released from those previously considered in the FSAR and SER; (3)

Changes in system design which may invalidate the accident analysis as described in the SER (e.g., changes in tank capacity that would alter the curies released); or (4)

Changes in system design that could potentially result in a significant increase in occupational exposure of operating personnel (e.g., use of temporary equipment without adequate shielding provisions).

MEMBER(S) OF THE PUBLIC1 A MEMBER OF THE PUBLIC shall be an individual in a controlled area or an UNRESTRICTED AREA. However, an individual is not a MEMBER OF THE PUBLIC during any period in which the individual receives an occupational dose. This category may include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

MILK ANIMAL A MILK ANIMAL is a cow or goat that is producing milk for human consumption.

1 The italicized terms in this definition, which are not otherwise used in this ODCM, shall have the definitions assigned to them by 10 CFR 20.1003.

HNP ODCM 10-3 Version 25 1/18 MINIMUM DETECTABLE CONCENTRATION The MINIMUM DETECTABLE CONCENTRATION (MDC) is defined, for purposes of the controls in this ODCM, as the smallest concentration of radioactive material in a sample that will yield a net count above system background and that will be detected with 95-percent probability, with only 5-percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation, the MDC for a given radionuclide is determined as follows (Reference 17):

t 6

b s

b s

e Y

10 x

2.22 V

E t

1 t

1 R

3.29 t

2.71 MDC

88 9

=

)

)

+

(10.1) where:

MDC

=

the a priori MINIMUM DETECTABLE CONCENTRATION (Ci per unit mass or volume).

Rb

=

the background counting rate, or the counting rate of a blank sample, as appropriate (counts per minute).

ts

=

the length of the sample counting period (minutes).

tb

=

the length of the background counting period (minutes).

E

=

the counting efficiency (counts per disintegration)

V

=

the sample size (units of mass or volume).

2.22 % 106 =

the number of disintegrations per minute per &Ci.

Y

=

the fractional radiochemical yield, when applicable.

=

the radioactive decay constant for the given radionuclide (h-1). Values of used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 26.

t

=

for effluent samples, the elapsed time between the midpoint of sample collection and the time of counting (h); for environmental samples, the elapsed time between the end of sample collection and the time of counting (h).

Typical values of E, V, Y, and t should be used in the calculation. It should be recognized that the MDC is defined as an a priori (before the fact) limit representing the capability of a measurement system, and not as an a posteriori (after the fact) limit for a particular measurement.

HNP ODCM 10-4 Version 25 1/18 PRINCIPAL GAMMA EMITTERS The PRINCIPAL GAMMA EMITTERS for which the MINIMUM DETECTABLE CONCENTRATION (MDC) limit applies include exclusively the following radionuclides:

For liquid radioactive effluents: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an MDC of 5 x 10-6 &Ci/mL.

For gaseous radioactive effluents: In noble gas releases, Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-138; and in particulate releases, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.

For environmental media: The gamma emitters specifically listed in Table 4-3.

These lists do not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report, the Annual Radiological Environmental Operating Report, or other applicable report(s).

OPERATIONAL CONDITION An OPERATIONAL CONDITION shall be any one inclusive combination of Mode Switch position and average reactor coolant temperature, as defined in Table 1.1-1 of the Technical Specifications.

REACTOR MODE The REACTOR MODE is established by the Mode Switch position. The four Mode Switch positions are REFUEL, SHUTDOWN, START & HOT STANDBY, and RUN.

(See Technical Specifications Table 1.1-1 for definitions of these MODES.)

SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by Georia Power Company as shown in Figure 10-1.

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

UNRESTRICTED AREA The UNRESTRICTED AREA shall be any area access to which is neither limited nor controlled by the licensee, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

HNP ODCM 10-5 Version 25 1/18 10.2 TERMS DEFINED IN THE TECHNICAL SPECIFICATIONS The following terms are defined in the Technical Specifications, Section 1.1. Because they are used throughout the Limits of Operation sections of the ODCM, they are presented here for convenience. In the event of discrepancies between the definitions below and those in the Technical Specifications, the Technical Specification definitions shall take precedence.

ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output, such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by any means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 EQUIVALENT (microcuries/gram) that alone would produce the same Committted I-131 Effective Dose Equivalent as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, 1988.

OPERABLE (or OPERABILITY)

A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, division, component or device to perform its specified safety

HNP ODCM 10-6 Version 25 1/18 function(s) are also capable of performing their related support function(s).

RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2804 MWt.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.