ML18031A874

Proposed Tech Spec Revs,Incorporating New Requirements for Radiological Effluent Monitoring,Recording & Reporting Per NUREG-0473

ML18031A874
Person / Time
Site:	Browns Ferry
Issue date:	09/30/1986
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18031A873	List: ML18031A872 ML18031A874
References
RTR-NUREG-0473, RTR-NUREG-473 TAC-63022, TAC-63023, TAC-63024, NUDOCS 8610140295
Download: ML18031A874 (507)

Text

ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION REVISIONS BROVNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 8b10140295 8b0930 PDR ADQCK 05000259 P PDR APPENDIX A TECHNICAL SPECIFICATIONS BROGANS FERRY UNITS 1 AND 2

UNET 1 TABLE OF CONTENTS 0241p

TABLE OF CONTENTS Section Introduction o~~~~~~~~~~~~~~~~ea e no.1.0 Definitions SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 1.1/2.1 1.2/2.2 Fuel Cladding Integrity Reactor Coolant System Integrity.LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 27 3.1/4.1 3.2/4.2 Reactor Protection System Protective Instrumentation

.31 50 A.Primary Containment and Reactor Building Isolation Functions 50 B.Core and Containment Cooling Systems-Initiation and Control 50 C.Control Rod Block Actuation 51 D.Radioactive Liquid Effluent Monitoring Instrumentation 51 E.Drywell Leak Detection.F.Surveillance Instrumentation 52 G.Control Room Isolation.52 H.Flood Protection

.53 I.Meteorological Monitoring Instrumentation 53 J~Seismic Monitoring Instrumentation

.54 K.Radioactive Gaseous Effluent Instrumentation

..Monitoring 54 3.3/4.3 Reactivity Control A.Reactivity Limitations B.Control Rods.C.Scram Insertion Times 120 120 121 124 0241p Section 3.4/4.4 D.Reactivity Anomalies.E.Reactivity Control F.Scram Discharge Volume Standby Liquid Control System A.Normal System Availability

.B.Operation with Inoperable Components

.C.Sodium Pentaborate Solution 125 126'126 135 135 136 137 3.5/4.5 Core and Containment Cooling Systems A.Core Spray System (CSS)B.Residual Heat Removal System (RHRS)(LPCI and Containment Cooling)C.RHR Service Mater System and Emergency Equipment Cooling'Water System (EECWS)D.Equipment Area Coolers E.High Pressure Coolant Injection System (HPCIS)~~o~~~~~~~~~~~~~~143 143 145 151 154 154 F.Reactor Core Isolation Cooling System (RC I CS)~~~~~~~~~~~~~~~~~156 G.Automatic Depressurization System (ADS)~~~~~~~~~~~~~~~~~~157 H.Maintenance of Filled Discharge Pipe.I.Average Planar Linear Heat Generation Rate.J.Linear Heat Generation Rate (LHGR)K.Minimum Critical Power Ratio (MCPR)158 159 159 160 3.6/4.6 L.APRM Setpoints M.Reporting Requirements

.Primary System Boundary 160A 160A 174 A.Thermal and Pressurization Limitations

.174 B.Coolant Chemistry 176 0241p

Section C.Coolant Leakage D.Relief Valves~Pa e No.180 181 E.Jet Pumps F.Recirculation Pump Operation.G.Structural Integrity.H.Seismic Restraints, Supports and Snubbers 3.7/4.7 Containment Systems A.Primary Containment B.Standby Gas Treatment System.C.Secondary Containment D.Primary Containment Isolation Valves E.Control Room Emergency Ventilation

.F.Primary Containment Purge System.G.Containment Atmosphere Dilution System (CAD)181 182 183 185 227 227 236 240 242 244 246 248 H.Containment Atmosphere Monitoring (CAM)Sys H>Analyzer tern 249 3.8/4.8 Radioactive Materials 281 A.Liquid Effluents.B.Airborne Effluents.281 283 C.Radioactive Effluents-Dose 286 D.Mechanical Vacuum Pump.E.Miscellaneous Radioactive Materials Sources 286 287 F.Solid Radwaste.289 3.9/4.9 Auxiliary Electrical System A.Auxiliary Electrical Equipment B.Operation with Inoperable Equipment t C.Operation in Cold Shutdown 3.10/4.10 Core Alterations A.Refueling Interlocks

.292 292'95 298 302 302 0241p Section B.Core Monitoring C.Spent Fuel Pool Water D.Reactor Building Crane 305 306 307 E.Spent Fuel Cask F.Spent Fuel Cask Handling-Refueling Floor.3.11/4.11 Fire Protection Systems A.High Pressure Fire Protection System.B.CO>Fire Protection System.C.Fire Detectors 307 308 315 315 319 320 D.Roving Fire Watch E.Fire Protection Systems inspection F.Fire Protection Organization

.G.Air Masks and Cylinders H.Continuous Fire Watch 321 322 322 323 323 5.0 i.Open'Flames, Welding Cable Spreading Room Major Design Features 5.1 Site Features and Burning in the 323 330 330 5.2 Reactor 5.3 Reactor Vessel 330 330 5.4 Containment 330 6.0 5.5 Fuel Storage.5.6 Seismic Design.Administrative Controls 330 331 332 6.1 Organization

.332 1v 0241p

0 Section 6.2 Review and Audit 6.3 Procedures

6.4 Actions

to be Taken in the Event of a Reportable Occurrence in Plant Operation.~Pa e No.333 338 346 6.5 Actions to be taken in the Limit is Exceeded Event a Safety 346 6.6 Station Operating Records 6.7 Reporting Requirements

6.8 Minimum

Plant Staffing 346 349 358 024lp LIST OF TABLESTitle Surveillance Frequency Notation~Pa e No.7c 3.1.A Reactor Protection System (SCRAM)Instrumentation Requirements

.33 4.1.A Reactor Protection System (SCRAM)Instrumentation Functional Tests Minimum Functional Test Frequencies for Safety Instrumentation and Control Circuits 37 4.1.B Reactor Protection System (SCRAM)Instrument Calibration Minimum Calibration Frequencies for Reactor Protection Instrument Channels.40 3.2.A Primary Containment and Reactor Building Isolation Instrumentation 55 3.2.B Instrumentation that Initiates or Controls the Core and Containment Cooling Systems 62 3.2.C Instrumentation that Initiates Rod Blocks 73 3.2.D Radioactive Liquid Effluent Monitoring Instrumentation 76 Instrumentation that Monitors Leakage Into Drywell 77 3.2.F Surveillance Instrumentation

.78 3.2.G Control Room Isolation Instrumentation

.81 3.2eH Flood Protection Instrumentation 82 3.2.I 3.2eJ Meteorological Monitoring Instrumentation Seismic Monitoring Instrumentation

.83 84 3.2eK Radioactive Gaseous Effluent Monitoring Instrumentation 84A 4.2.A Surveillance Requirements for Primary Containment and Reactor Building Isolation Instrumentation

.85 4.2.B Surveillance Requirements for Instrumentation that Initiate or Control the CSCS 96 4.2.C Surveillance Requirements for Instrumentation that Initiate Rod Blocks 102 4.2.D~~Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.

103 4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation

.104 vi 0241p LIST OF TABLES (Cont'd)Table~~4.2.F Title Minimum Test and Calibration Frequency for Surveillance Instrumentation

~Pa e No.105 4.2.G Surveillance Requirements for Control Room Isolation Instrumentation 106 4.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation

.107 4.2eJ Seismic Monitoring Instrument Surveillance 108 4.2eK Radioactive Gaseous Effluent Instrumentation Surveillance 108A 3.5-1 3.5.I Minimum RHRSW and EECW Pump Assignment MAPLHGR Versus Average Planar Exposure 152a 171, 172, 172a 3.7.A Primary Containment Isolation Valves 250 3.7.B t 3.7.C 3.7.D Testable Penetrations with Double 0-Ring Seals.Testable Penetrations with Testable Bellows Air Tested Isolation Valves 256 257 258 3.7.E Primary Containment.

Isolation Valves which Terminate below the Suppression Pool Water evel L 262 3.7.F Primary Containment Isolation Valves Located inWater Sealed Seismic Class 1 Lines.263 3.7.H Testable Electrical Penetrations

.265 4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start 298a 3.11.A 6.8.A Fire Protection System Hydraulic Requirements Minimum Shift Crew Requirements 324 360 v11 0241p LIST OF ILLUSTRATIONS e~Fi ure 2.1.1 Title APRM Flow Reference Scram and APRM Rod Block Settings a~~a~a a a..a a a a a.a a~~Pa e No.13 2.1-2 APRM Flow Bias Scram Vs.Reactor Core Flow.26-4.1-1 Graphic Aid in the Selection of an Adequate Interval Between Tests 49 4.2-1 System Unavailability 119 3.4-1 Sodium Pentaborate Solution Volume Concentration Requirements

.138 3.4-2 Sodium Pentaborate Solution Temperature Requirements 139 3.5.K-1 MCPR Limits 172b 3.5.2 K~Factor 173 3.6-1 Minimum Temperature

'F Above Change in Transient Temperature 194 Change in Charpy V Transition Temperature Vs.Neutron Exposure 195 4.8.la Gaseous Release Points and Elevations 290 4.8.1b Land Site Boundary.290A 6.1-1 TVA Office of Power Organization for of Nuclear Power Plant Operation 361 6.1-2 Functional Organization 362 6.2-1 6.3-1 Review and Audit Function In-Plant Fire Program Organization

.363 364 v111 0241p UNIT 2 TABLE OF CONTENTS 0241p TABLE OF CONTENTS Section Introduction

.~Pa e No.1.0 Definitions 1.1/2.1 1.2/2.2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS Fuel Cladding Integrity Reactor Coolant System Integrity.LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 27 3.1/4.1 3.2/4.2 Reactor Protection System Protective Instrumentation

.A.Primary Containment and Reactor Building Isolation Functions 31 50 50 B.Core and Containment Cooling Systems-Initiation and Control 50 C.Control Rod Block Actuation 51 D.Radioactive Liquid Effluent Monitoring Instrumentation E.Drywell Leak Detection.F.Surveillance Instrumentation

.G.Control Room Isolation.H.Flood Protection

.51 52 52 53 I.Meteorological Monitoring Instrumentation 53 J.Seismic Monitoring Instrumentation

.54 K.Radioactive Gaseous Effluent Instrumentation Monitoring 54 3.3/4.3 Reactivity Control A.Reactivity Limitations B.Control Rods C.Scram Insertion Times 120 120 121 124 0241p Section 3.4/4.4 3.5/4.5 D.Reactivity Anomalies E.Reactivity Control F.Scram Discharge Volume Standby Liquid Control System A.Normal System Availability

.B.Operation with Inoperable Components C.Sodium Pentaborate Solution Core and Containment Cooling Systems A.Core Spray System (CSS)B.Residual Heat Removal System (RHRS)(LPCI and Containment Cooling)C.RHR Service Water System and Emergency Equipment Cooling"Water System (EECWS)D.Equipment Area Coolers E.High Pressure Coolant Injection System (HPCIS)~~~~~~~~~~~~~~~~~Fa e No.125 126 126 135 135 136 137 143 143 145 151 154 154 F.Reactor Core Isolation Cooling System (RCICS)~~~~~~~~~~~~~~~156 G.Automatic Depressurization System (ADS)~~~~~~~~e~~e~~~~157 H.Maintenance oE Filled Discharge Pipe I.Average Planar Linear Heat Generation R ate.J.Linear Heat Generation Rate (LHGR)K.Minimum Critical Power Ratio (MCPR)158 759 159 160 L.APRM Setpoints 160A 3.6/4.6 M..Reporting Requirements

.Primary System Boundary A.Thermal and Pressurization Limitations

.160A 174 174 B.Coolant Chemistry 176 0241p Section C.Coolant Leakage D.Relief Valves~Pa e No.180 181 3.7/4.7 E.Jet Pumps F.Recirculation Pump Operation.G.Structural Integrity.H.Seismic Restraints, Supports and Snubbers Containment Systems A.Primary Containment 181 182 183 185 227 227 3.8/4.8 B.Standby Gas Treatment System.C.Secondary Containment D.Primary Containment Isolation Valves E.Control Room Emergency Ventilation

.F.Primary Containment Purge System.G.Containment Atmosphere Dilution System (CAD)H.Containment Atmosphere Monitoring (CAM)Syst H>Analyzer Radioactive Materials em 236 240 242 244 246 248 249 281 A.Liquid Effluents.B.Airborne Effluents~~~281 283 C.Radioactive Effluents-Dose~~~286 D.Mechanical Vacuum Pump.E.Miscellaneous Radioactive Materials Sources 286 287 F.Solid Radwaste.289 3.9/4.9 3.10/4.10 Auxiliary Electrical System A.Auxiliary Electrical Equipment B.Operation with Inoperable Equipment C.Operation in Cold Shutdown.Core Alterations A.Refueling Interlocks

.292 292 295 298 302 302 0241p

Section B.Core Monitoring C.Spent Fuel Pool Water D.Reactor Building Crane E.Spent Fuel Cask F.Spent Fuel Cask Handling-Refueling Floor 305 305 307 307 308 3.11/4.11 Fire Protection Systems A.High Pressure Fire Protection System.B.CO>Fire Protection System.C.Fire Detectors.315 315 319~~~~320 D.Roving Fire Watch E.Fire Protection Systems Inspection

.F.Fire Protection Organization

.G.Air Masks and Cylinders H.Continuous Fire Watch 321 322 322 323 323 5.0 I.Open Flames, Welding Spreading Room.Major Design Features 5.1 Site Features and Burning in the Cable 323 330 330 6.0 5.2 Reactor 5.3 Reactor Vessel 5.4 Containment 5.5 Fuel Storage.5.6 Seismic Design.Administrative Controls 6.1 Organization

.6.2 Review and Audit 330 330 330 330 331 332 332 333 1v 0241p

Section 6.3 Procedures

~Fa e No.338 6.4 Actions to be Taken in the Event of a Reportable Occurrence in Plant Operation.346 6.5 Actions to be taken in the Limit is Exceeded Event a Safety 346 6.6 Station Operating Records 6.7 Reporting Requirements

6.8 Hinimum

Plant Staffing 346 349 358 024lp Table 1.1 LIST OF TABLES Title Surveillance Frequency Notation~pa e No.7c 3.1.A Reactor Protection System (SCRAM)Instrumentation Requirements 33'4.1.A Reactor Protection System (SCRAM)Instrumentation Functional Tests Minimum Functional Test Frequencies for Safety Instrumentation and Control Circuits 37 4.1.B Reactor Protection System (SCRAM)Instrument Calibration Minimum Calibration Frequencies for Reactor Protection Instrument Channels 40 3.2.A Primary Containment and Reactor Building Isolation Instrumentation 55 3.2.B Instrumentation that Initiates or Controls the Core and Containment Cooling Systems 62 3.2.C Instrumentation that Initiates Rod Blocks 73 3.2.D Radioactive Liquid Effluent Monitoring Instrumentation 76 3.2.F 3.2.G 3.2eH 3.2.I 3.2.J Instrumentation that Monitors Leakage Into Drywell Surveillance Instrumentation

.Control Room Isolation Instrumentation Flood Protection Instrumentation

.Meteorological Monitoring Instrumentation Seismic Monitoring Instrumentation

.77 78 81 82 83 84 3.2eK Radioactive Gaseous Effluent Monitoring Instrumentation 84A 4.2.A Surveillance Requirements for Primary Containment and Reactor Building Isolation Instrumentation 85 4.2.B Surveillance Requirements for Instrumentation that Initiate or Control the CSCS.89 4.2.C Surveillance Requirements for Instrumentation that Initiate Rod Blocks 102 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.

103 4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation

, 104 vi 0241p Table LIST OF TABLES (:ont'di Title Minimum Test and Calibration Frequency for Surveillance Instrumentation

'105 Surveillance Requirements for Control Room Isolation Instrumentation 106>>'.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation

.'107-'.2.J Seismic Monitoring Instrument Surveillance

.108 4e2.K Radioactive Gaseous Effluent Instrumentation Surveillance

.108A 3.5-1 Minimum RHRSW and EECW Pump Assignment 152a 3.5.I MAPLHGR Versus Average Planar Exposure.171, 172, 3.7.A 3.7.B 3.7.C Primary Containment Isolation Valves Testable Penetrations with Double 0-Ring Seals Testable Penetrations with Testable Bellows 250 256 257 3.7.D Air Tested Isolation Valves 258 3.7.E Primary Containment Isolation Valves which Terminate below the Suppression Pool Water L evel~~~~~~~~~~~~~~~~~~~262 3.7.F Primary Containment Isolation Valves Located in Water Sealed Seismic Class 1 Lines.263 3.7.H 4.9.A.4.C Testable Electrical Penetrations 1 Voltage Relay Setpoints/Diesel Generator Start 265 298a 3.11.A 6.8.A Fire Protect on System Hydraulic Requirements Minimum Shift Crew Requirements 324 360 vii 024lp

LIST OF ILLUSTRATIONS e~Fi ure 2.1.1 Title APRM Flow.Reference Scram and APRM Rod Block S t a ettlngS a a~~~~~~a a~~e a a a~~~Pa e No.13 2.1-2 APRM Flow Bias Scram Vs.Reactor Core Flow.26 4.1-1 Graphic Aid in the Selection of an Adequate Interval Between Tests 49 4.2-1 System Unavai'lability 119 3.4-1'I Sodium Pentaborate Solution Volume Concentration Requirements

.138 3.4-2 Sodium Pentaborate Solution Temperature Requ1rements

.139 3.5.K-1 MCPR Limits a~~~~~~~~a~~~~~~~~~~172a 3.5.2 I Factor K 173 3.6-1 Minimum Temperature

'F Above Change in Transient Temperature 194 3.6-2 Change in Charpy V Transition Temperature Vs.Neutron Exposure 195 4.8.1a Gaseous Release Points and Elevations 290 4.8.1b Land Site Boundary.290A 6.1-1 TVA Office of Power Organization for of Nuclear Power Plant Operation 361 6.1-2 6.2-1 Functional Organization Review and Audit Function 362 363 6.3-1 In-Plant Fire Program Organization

.364 V11 1 0241p BROWNS FERRY NUCLEAR PLANT-UNIT 1&, 2 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS 02429

1.0 DEFINITIONS

(Cont'd)10.~Lo ic-A logic is an arrangement of relays.contacts, and other components that produces a decision output.(a)~Initiatin

-A logic that receive signals from channels and produce decision outputs to the actuation logic.(b)Actuation-A logic that receives signals (either from initiation logic or channels)and produces decision outputs to accomplish a protective action.11.Channel Calibration

-Shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel monitors.The channel calibration shall encompass the entire channel including alarm and/or trip functions and shall include the channel functional test.The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

Non-calibratable components shall be excluded from this requirement, but will be included in channel functional test and source check.12.Channel Functional Test-Shall be: a.Analog Channels-the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b.Bistable channels-the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

13.Source Check-Shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources.0242p

1.0 DEFINITIONS

(Cont'd)Functional Tests-A functional test is the manual operation or initiation of a system, subsystem, or components to verify that it functions within design tolerances (e.g., the manual start of a core spray pump to verify that it runs and that it pumps the required volume of water).X.Shutdown-The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.

Y.En ineered Safe uard-An engineered safeguard is a safety system the actions of which are essential to a safety action required in response to accidents.

Z.Reportable Event-A reportable event shall be any of those conditions specified in section 50.73 to 10 CFR Part 50.Solidification

-Shall be the conversion of radioactive wastes into a form that meets shipping and burial ground requirements..

BB.Offsite Dose Calculation Manual (ODCM)-Shall be a manual describing the environmental monitoring program and the methodology and parameters used in the calculation of release rate limits and offsite doses due to radioactive gaseous and and liquid effluents.

The ODCH will also provide the plant with guidance for establishing alarm/trip setpoints to ensure technical specifications sections 3.8.A.1 and 3.8.B.1 are not exceeded.CC.Pur e or our in-The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is required to purify the containment.

DD.Process Control Pro ram-Shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.EE.Radiolo ical Effluent Manual (REM)-Shall be a manual containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposure to individuals from station operation.

It shall also specify operating guidelines for radioactive waste treatment systems and report content.FF.p~entin-The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required.Vent, used in system names, does not imply a venting process.0242p 7A

1.0 DEFINITIONS

(Cont'd)GG.owned, leased, or otherwise controlled by TVA.HH.Unrestricted Area-Any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for industrial, commercial, institutional, or recreational purposes.Dose E uivalent I-131-The DOSE EQUIVALENT I-131 shall be the concentration of I-131 (in pCi/gm)which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.The thyroid dose conversion factor used for this calculation shall be those listed in Table III of TID-14844"Calculation of Distance Factors for Power and Test Reactor Sites".Gaseous Waste Treatment S stem-The charcoal adsorber vessels installed on the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release.Members of the Public-Shall'include all individuals who by virtue of their occupational status have no formal association with the plant.This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.

This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter restricted areas.LL.Surveillance

-Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements.

Each surveillance Requirement shall be performed within the specified time interval with, (1)A maximum allowable extention not to exceed 25'Io of the surveillance interval, but (2)The combined time entered for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications.

Surveillance requirements do not have to be performed on inoperable eouipment.

0242p 7B Table 1.1 SURVEILLANCE FRE UENCY NOTATION NOTATION S (Shift)D (Daily)W (Weekly)M (Monthly)Q (Quarterly)

SA (Semi-Annually Y (Yearly)R (Refueling)

S/U (Start-Up)

N.A.P (Prior)F~RE UENCY At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.At least once per normal calendar 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day (midnight to midnight).

At least once per 7 days.At least once per 31 days.At least once per 3 months or 92 days.At least once per 6 months or 184 days.At least once per year or 366 days.At least once per operating cycle.Prior to each reactor startup.Not applicable.

Completed prior to each release.7C 0242p

LIMITING CONDITIONS FOR OPERAT10N SURVEILLANCE RE UIREMENTS~3.Q.B Core and Containment Coolin S stems-Initiation 6 Control 4.2.B Core and Containment Coolin S stems-Initiation 6.Control are required to be operable shall be considered operable if they are within the required surveillance testing frequency and there is no reason to suspect that they are inoperable.

C.Control Rod Block Actuation C.Control Rod Block Actuat'ion The limiting conditions of ,.operation for the instrumentation that initiates control rod block are given in Table 3.2.C.Instrumentation shall be functionally tested, calibrated, and checked as indicated in Table 4.2.C.System logic shall be functionally tested as indicated in Table 4.2.C.3.2.D Radioactive Li uid Effluent Monitorin Instrumentation 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation 1.The radioactive liquid effluent monitoring instrumentation listed in Table 3.2.D shall be operable with the applicability as shown in Tables 3.2.D/4.2.D.

Alarm/trip setpoints will be set in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.A.1 are not exceeded.1.Each of the radioactive liquid effluent monitoring instruments shall be demonstrated operable by performance of test in accordance with Table 4.2.D.2.The action required when the'umber of operable channels is less than the minimum channels operable requirement is specified in the notes for Table 3.2.D.Exert best efforts to return the instrument(s) to OPERABLE status within 30 days and if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.51 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.D Radioactive Li uid Effluent~~~~(Con')4.2.D Radioactive Li uid Effluent (Con't)3.With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these specifications.

4.The provisions of specification 1.0.C and 6.7.2 are not applicable.

E.Dr ell Leak Detection'.Dr ell Leak Detection The limiting conditions of operation for the instrumentation that monitors drywell leak detection are given in Table 3.2.E.Instrumentation shall be calibrated and checked as indicated in Table 4.2.E.F.Surveillance Instrumentation F.Surveillance Instrumentation The limiting conditions for the instrumentation that provides surveillance information readouts are given in Table 3.2.F.Instrumentation shall be calibrated and checked as indicated in Table 4.2.F.G.Control Room Isolation G.Control Room Isolation The limiting conditions for instrumentation that isolates the control room and initiates the control room emergency pressurization systems are given in Table 3.2.G.Instrumentation shall be calibrated and checked as indicated in Table 4.2.G.52 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UXREMENTS monitoring listed in shall be all times.The seismic instruments Table 3.2.J operable at 2.With the number of seismic monitoring instruments less than the number listed in Table 3.2.J, restore the inoperable instrument(s) to operable status within 30 days.3.With one or more of the instruments listed in Table 3.2.J inoperable for more than 30 days, submit a Special Report to the Commission pursuant to specification 6.7.3.C within the next 10 days describing the cause of the malfunction and plans for restoring the instruments to operable status.3.2.J Seismic Monitorin Instrumentation

~~~l.4.2.J Seismic Monitorin Instrumentation 1.Each of the seismic monitoring instruments shall be demonstrated operable by performance of tests at the frequencies listed in Table 4.2.J.2.Data shall be retrieved from all seismic instruments actuated during a seismic event and analyzed to determine the magnitude of the vibratory ground motion.A Special Report shall be submitted to the Commission pursuant to specification 6.7.3.D within 10 days describing the magnitude, frequency spectrum, and resultant effect upon plant features important to safety.3.2.K Radioactive Gaseous Effluent Monitorin Instrumentation 4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation The radioactive gaseous effluent monitoring instruments listed in Table 3.2.K shall be operable with the applicability as shown in Tables 3.2.K/4.2.K.

Alarm/trip setpoints will be set in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.B.1 are not exceeded.l.Each of the radioactive gaseous effluent monitoring instruments shall be demonstrated operable by performance of tests in accordance with Table 4.2.K.54 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.K Radioactive Gaseous Effluent Monitorin Instrumentation (Con't)4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation (Con't)2.The action required when the number of operable channels is less than the Minimum Channels Operable requirement is specified in the notes for Table 3.2.K.Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Release Report why the inoperability was not corrected in a timely manner.3.With a radioactive gaseous effluent monitoring channel alarm/trip setpoint less conservative than required by these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these specifications.

4.Both off-gas treatment monitors may be taken out of service for less than one hour for purging of monitors during SI performance.

5.The provisions of specifications 1.0.C and 6.7.2 are not applicable.

54A 0233p

Instrument

'1.LIQUID RADHASTE EFFLUENT MONITOR (RM-90-130) 2.RHR SERVICE HATER MONITOR (RM-90-133,-134)3.RAlJ COOLING HATER MONITOR (RM-90-132) 4.LIQUID RADHASTE EFFLUENT FLOH RATE (77-60 loop excluding fixed in line rotometer)

TABLE 3.2.D Radioactive Li uid Effluent Monitorin Instrumentation Minimum Channels 0 erable I It Action A, B 0240p 76

NOTES FOR TABLE 3.2.D 0"~At all times~'~'~During releases via this pathway"~'-:<During operation of an RHR loop and associated RHR service water system ACTION A During release of radioactive wastes from the radwaste processing system, the following shall be met (1)liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in 3.8.A.l,, (2)if this cannot be met, two independent samples of the tank being discharged shall be analyzed in accordance with the sampling and~analysis program specified in the REM and two qualified station personnel shall independently verify the release rate calculations and check valving before the discharge.

Otherwise, suspend release via this pathway.ACTION B With a radioactive liquid effluent monitoring channel/alarm trip setpoint less conservative than required by these specifications, suspend release via this pathway without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism referred by these specifications.

ACTION C During operation of an RHR loop and associated RHR service water system, the effluent from that unit's service water shall be continuously monitored.

If an installed monitoring system is not available, a temporary monitor or grab samples taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and an analysis of at least an LLDf 1E-7 pCi/ml (gross)or<applicable MPC ratio (y isotopic)shall be used to monitor the effluent.ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continued provided that a temporary monitor is installed or, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for radioactivity with an LLDf 1E-7 jCi/ml (gross)or<applicable MPC ratio (y isotopic).

ACTION E With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continued provided the flow rate 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.Pump curves may be used to estimate flow.ACTION FAlarm/trip setpoints will be calculated in accordance with the guidance given in the Offsite Dose Calculation Manual (ODCM).(1)See REM, TABLE NOTATIONS-TABLE C-l, for the definition of LLD.76A 0242p E 3.2.K Radioactive Gaseous Effluent Monitorin Instrumentation Instrument STACK (RM-90-147A 5 8)a.Noble Gas Monitor b.Iodine Cartridge c.Particulate Filter d.Sampler Flow Abnormal e.Stack Flow (FT, FM, F I-90-271)REACTOR/TURBINE BLDG VENTILATION (RM-90-250) a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter Minimum Channels/Devices 0 erable (1)(1)(1)(1)(1)(1)(1)(1)(1)A licabilit Action A/C B/C B/C D D A/C B/C B/C D 3.5.TURBINE BLDG EXHAUST (RM-90-249, 251)a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter RADHASTE BLDG VENT (RM-90-252) a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter OFF GAS HYDROGEN ANALYZER (H~A, HgB)(1)(1)(1)(1)(1)(1)(1)(1)A/C B/C B/C D A/C B/C B/C D 6.OFF GAS POST TREATMENT a.Noble Gas Activity Monitor (RM-90-265, 266)b.Sample Flow Abnormal (PA-90-262) 0240p 84A NOTES FOR TABLE 3.2.K i'At all times o'<During releases via this pathway~'~':During main condenser offgas treatment system operation ACTION A With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via the affected pathway may continue provided a temporary monitoring system is installed or grab samples are taken and analyzed at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.ACTION B With a number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continued provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7)days and analyzed in accordance with the sampling and analysis program specified in the REH 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.ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for functional testing, calibration, or repair without providing or initiating grab sampling.ACTION D With the number of channels OPERABLE less than required by the Hinimum Channels Operable requirement, effluent releases via this pathway may continue provided the flow rate 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 />.ACTION E With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, operation of main condenser offgas treatment system may continue provided that a temporary monitor is installed or grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.ACTION F With the number of channels OPERABLE less than required by the Hinimum Channels Operable requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 />.Purging during SI performance is not considered a loss of monitoring capability.

84B 0242p TABLE 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation Surveillance Re uirements Instrument 1.LIQUID RADHASTE EFFLUENT MONITOR (RM-90-130) 2.RHR SERVICE HATER MONITOR (RM-90-133,-134)3.RAH COOLING HATER MONITOR (RM-90-132) 4.LIQUID RADHASTE EFFLUENT FLOH RATE (77-60 loop)Instrument Check D(4)D(4)D(4)D(4)Source Check NA Channel Calibration R(5)R(5)R(5)Functional Test Q(1)Q(2)Q(2)Q(3)0240p 103 NOTES FOR TABLE 4.2.D (1)The channel functional test shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint b.Instrument indicates an inoperative/downscale failure c.Instrument controls not set in operate mode (2)The channel functional test shall also demonstrate that control room annunciation occurs if any of the following conditions exist: a~b.c~Instrument indicates measured levels above the alarm/trip setpoint Instrument indicates an inoperative/downscale failure Instrument controls not set in operate mode (3)This functional test shall consist of measuring rate of tank decrease over a period of time and comparing this value with flow rate instrument reading.(4)INSTRUMENT CHECK shall consist of verifying indication during periods of release.INSTRUMENT CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days which continuous, periodic, or batch releases are made.0 (5)The CHANNEL CALIBRATION shall include the use of a known (traceable to National Bureau of Standards Radiation Measurement System)radioactive source(s)positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards (NBS).103A 0242p

TABLE 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance Instrument STACK a.Noble Gas Monitor'b.Iodine Cartridge c.Particulate Filter d.Sampler Flow Abnormal e.Stack Flowmeter Instrument Check Source Check M NA NA NA NA Channel Calibration R()NA NA R R Functional Test Q(Z)NA NA Q Q 2~3.4.5.6.REACTOR/TURBINE BLDG VENT a.Noble Gas Monitor'"'.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter TURBINE BLDG EXHAUST a.Noble Gas Monitor"'.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter RADHASTE BLDG VENT a.Noble Gas Monitor.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter OFF GAS HYDROGEN ANALYZER (HpA, HpB)OFF GAS POST TREATMENT.Noble Gas Activity Monitor b.Sample Flow Abnormal M NA NA NA M NA NA NA M NA NA NA R(1)NA NA R R(1)NA NA R R(1)NA NA R R'"'(I)R Q(2)NA NA Q Q(/)NA NA Q Q(Z)NA NA'Q(a)Q(4)Q(l)0240p 108A

NOTES FOR TABLE 4.2.K (1)The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of Standards Radiation Measurement System)radioactive source(s)positioned in a reproducible geometry with respect to the sensor or using standards that have obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards.

(2)The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint.b.Instrument indicates an inoperative/downscale failure.c.Instrument controls not set in operate mode (stack only).(3)The channel calibration shall include the use of standard gas samples containing a nominal: a.Zero volume percent hydrogen (compressed air)and, b.One volume percent hydrogen, balance nitrogen.(4)The channel functional test shall demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exists: a.Instrument indicates measured level above the alarm/trip setpoint.b.Instrument indicates an inoperative/downscale failure.c.Instrument controls not set in operate mode.The two channels are arranged in a coincidence logic such that 2 upscale, or 1 downscale and 1 upscale or 2 downscale will isolate the offgas line.(5)The noble gas monitor shall have a LLD of lE-5:(Xe 133 Equivalent).

(6)The noble gas monitor shall have a LLD of 1E-6 (Xe 133 Equivalent).

108B 0242p 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 will be calculated in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.This instrumentation also includes provisions for monitoring the concentration of potentially explosive gas mixtures in the offgas holdup system.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.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 in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior.to exceeding the limits of 10 CFR Part 20 Appendix B, Table II, Column 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 50.115A 0242p

4.2 BASES

e there is no true minimum.The curve does have a definite knee and very little reduction in system unavailability is achieved by testing at a shorter interval than computed by the equation for a single channels The best test procedure of all those examined is to perfectly stagger the tests.That is, if the test interval is four months, test one or the other channel every two months.This is shown in Curve No.5.The difference between Cases 4 and 5 is negligible.

There may be other arguments, however, that more strongly support the perfectly staggered tests, including reductions in human error.The conclusions to be drawn are these: 1.A 1 out of n system may be treated the same as a single channel in terms of choosing a test interval;and 2.more than one channel should not be bypassed for testing at any one time.The radiation monitors in the refueling area ventilation duct which initiate building isolation and standby gas treatment operation are arranged in two 1 out of 2 logic systems.The bases given for the rod blocks apply here also and were used ta arrive at the functional testing frequency.

The off-gas post treatment monitors are connected in a 2 out of 2 logic arrangement.

Based on experience with instruments of similar design, a testing interval of once every three months has been found adequate.The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also.The criteria for ensuring the reliability and accuracy of the radioactive gaseous effluent instrumentation is listed in Table 4.2.K.The criteria for ensuring the reliability and accuracy of the radioactive liquid effluent instrumentation is listed in Table 4.2.D.118 0242p LIMITING CONDITIONS FOR OPERATION SURUEILLANCE RE UIREMENTS 3.6 Primar S stem Boundar~~6.Whenever the react or is critical, the limits on activity concentrations in the reactor coolant shall not exceed the equilibrium value of 3.2 pc/gm of does equivalent I-131.4.6 Primar S stem Boundar 6.Additional coolant samples shall be taken whenever the reactor activity exceeds one percent of the equilibrium concentration specified in 3.6.B.6 and one of the following conditions are met: This limit may be exceeded following power transients for a maximum of 48.hours.During this activity transient the iodine concentrations shall not exceed 26 pCi/gm whenever the reactor is critical.The reactor shall not be operated more than 5 percent of its yearly power operation under this exception for the equilibrium activity limits.If the iodine concentration in the coolant exceeds 26 pCi/gm, the reactor shall be shut down, and the steam line isolation valves shall be closed immediately.

a.During startup b.Following a signi'ficant power change~'~~

c.Following an increase in the equilibrium off-gas level exceeding 10,000 pCi/sec (at the steam jet air ejector)within a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.d.Whenever the equilibrium iodine limit specified in 3.6.B.6 is exceeded.The additional coolant liquid samples shall be taken at 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or until a stable iodine concentration below the limiting value (3.2 pCi/gm)is established.

However, at least 3 consecutive samples shall be taken in all cases.An isotopic analysis shall be performed for each sample, and quantitative measurements made to determine the dose equivalent I-131 concentration.

If the total iodine activity of the sample is below 0.32 pCi/gm, an isotopic analysis to determine equivalent I-131 is not required."~'<For the purpose of this section on sampling frequency, a significant power exchange is defined as a change exceeding 15%%d of rated power in less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.179 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials Applies to the release of radioactive liquids and gases from the facility.O~b ective To define the limits and conditions for the release of radioactive effluents to the environs to assure that any.radioactive releases are as low as reasonably achievable and within the limits of 10 CFR Part 20.The specifications except for 3.8.A.l and 3.8.B.1 are exempt from the requirements of definition 1.0.C (Limiting Condition for Operation).

A.Li uid Effluents 1.The concentration of radioactive material released at any time from the site to unrestricted areas (see Figure 4.8-lb)shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity.2.If the limits of 3.8.A.1 are exceeded, appropriate action shall be initiated without delay to bring the release within Applies to the periodic test and record requirements and sampling and monitoring methods used for facility effluents.

~Ob ective To ensure that radioactive liquid and gaseous releases from the facility are maintained within the limits specified by Specifications 3.8.A and 3.8.B.S ecification A.Li uid Effluents 1.Facility records shall be maintained of radioactive concentrations and volume before dilution of each batch of liquid effluent released, and of the average dilution flow and length of time over which each discharge occurred.2.Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with the sampling and analysis program specified in the REM.3..The operation of the automatic isolation valves and discharge tank selection valves shall be checked annually.281 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3.8 Radioactive

Materials 4.8 Radioactive Materials 3.limits.Provide prompt notification to the NRC pursuant to section 6.7.2.The doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas (See Figure 4.8-1b)shall be limited: 4.The results of the analysis of samples collected from release points shall be used with the calculational methodology in the ODCM to assure that the concentrations at the point of release are maintained within the limits of specification 3.8.A.l.4~5.a.During any calendar quarter to<1.5 mrem to the total body and<5 mrem to any organ and, b.During any calendar year to<3 mrem to the total body and<10 mrem to any organ If the limits specified in 3.8.A.3 a 6 b above are exceeded, prepare and submit'Special Report pursuant to Section 6.7.2.The maximum activity to be contained in one liquid radwaste tank or temporary storage tank that can be discharged directly to the environs shall not exceed 10 curies excluding tritium and dissolved/entrained noble gas.5.Cummulative quarterly and yearly dose contributions from liquid effluents shall be determined as specified in the ODCM at least once every 31 days.The quantity of radioactive material contained in any outside liquid radwaste storage tanks shall be determined to be within the above limit by analyzing a'representative sample of the tank's contents at~least once per 7 days when radioactive materials are being added to the tank.6.With radioactive liquid waste exceeding 3.8.A.5 limits, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit.Events leading to this condition must be reported in the next Semiannual Radioactive Effluent Release Report (section F.2 of the REM)282 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTSRadioactive Materials B.Airborne Effluents 4.8 Radioactive Materials B.Airborne Effluents 1.The dose rate at any time to areas at and beyond the site boundary (see Figure 4.8-lb)due to radioactivity released in gaseous effluents from the site shall be limited to the following values: a.The dose rate limit for noble gases shall be<500 mrem/yr to the total body and<3000 mrem/yr to the skin, and b.The dose rate limit for I-131, I-133, H-3, and particulates with greater than eight day half-lives shall be<1500 mrem/yr to any organ.2.If the'limits of 3.8.B.1 are exceeded, appropriate corrective action shall be immediately initiated to bring the release within limits.Provide prompt notification to the NRC pursuant to section 6.7.2.1.The gross 6/y and particulate activity of gaseous wastes released to the environment shall be monitored and recorded.a.For effluent streams having continuous monitoring capability, the activity shall be monitored and flow rate evaluated and recorded to enable release rates of gross radioactivity to be determined at least once per shift using instruments specified in table 3.2.K.b.For effluent streams without continuous monitoring capability, the activity shall be monitored and recorded and the release through these streams controlled to within the limits specified in 3.8.B.2.Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with the sampling and analysis program specified in the REM.Dose rates shall be determined to be within limits of 3.8.B using methods contained in the ODCM.283 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.The air dose to areas at and beyond the site boundary (see Figure 4.8-1b)due to noble gases released in gaseous effluents per unit shall be limited to the following:

3.Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in the ODCM at least once every 31 days.a.During any calendar quarter, to<5 mrad for gamma radiation and<10 mrad for beta radiation; b.During any calendar year, to<10 mrad for gamma radiation and<20 mrad for beta radiation.

lf the calculated air dose exceeds the limits specified in 3.8.B.3 above, prepare and submit a special report pursuant to section 6.7.2.5.The dose to a member of the public from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than 8 days in gaseous effluent released per unit to areas at and beyond the site boundary (see Figure 4.8-1b)shall be limited to the following:

a.To any organ during any calendar quarter to<7.5 mrem;b.To anyorgan during any calendar year to<15 mrem;284 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 6.If the calculated doses exceed the limits oF 3.8.B.5 above, prepare and submit a special report pursuant to section 6.7.2.4.During operation above 25/o power, the position of the charcoal bed bypass valve will be verified daily.7.During operation above 25K power the discharge of the SJAE must be routed through the charcoal adsorbers.

8.With gaseous waste being discharged for more than 7 days without treatment through the charcoal adsorbers, prepare and submit a special report pursuant to section 6.7.2.5.The concentration of hydrogen downstream of the recombiners shall be determined to be within the limits of 3.8.B.9 by continuously monitoring the offgass whenever the SJAE is in service using instruments described in Table 3.2.K.Instrument surveillance requirements are specified in Table 4.2.K.9.Whenever the SJAE is in service, the concentration of hydrogen in the offgas downstream of the recombiners shall be limited to (4'X by volume.10.With the concentration of hydrogen exceeding the limit of 3.8.B.9 above, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.285 0233p LIMITING CONDITIONS FOR OPERATION 3.8.C Radioactive Effluents-Dose SURVEILLANCE RE UIREMENTS 4.8.C Radioactive Effluents-Dose 1.The dose or dose\commitment to a real individual from all uranium fuel cycle sources is limited to<25 mrem to the total body or any organ (except the thyroid, which is limited to<75 mrem)over a period of one calendar year.1.Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with specifications 3.8.A.3, 3.8.B.3, and 3.8.B.5 and the methods in the ODCM.2.With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of specification 3.8.A.3, 3.8.B.3, or 3.8.B.5, prepare and submit a Special Report to the Commission pursuant to specification 6.7.2 and limit the subsequent releases such that the limits of 3 8 C.l are not exceeded.3.8.D Mechanical Vacuum Pum 4.8.D Mechanical Vacuum Pum 1.Each mechanical vacuum pump shall be capable of being automatically isolated and secured on a signal or high radioactivity in the steam lines whenever the main steam isolation valves are open.At least once during each operating cycle verify automatic securing and isolation of the mechanical vacuum pump.2.If the limits of 3.8.D are not met, the vacuum pump shall be isolated.286 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

3.8 Radioactive

Materials 4.8.C Radioactive Materials E.Miscellaneous Radioactive Materials Sources E.Miscellaneous Radioactive Materials Sources 1.Source Leaka e Test 1.Surveillance Re uirement Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of>0.005 microcurie of removable contamination.

Each sealed souce with removable contamination in excess of the above limit shall be immediately withdrawn from use and (a)either decontaminated and repaired, or (b)disposed of in accordance with Commission regulations.

Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an agreement State, as follows: a.Sources in Use Each sealed source, excluding startup sources and flux detectors previously subjected to core flux, containing radioactive material, other than Hydrogen 3, with a halF-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at least once per six months.The leakage test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample.287 0233p LIMITING CONDITIONS FOR OPERATION SURUEILLANCE RE UIREMENTS 4.8.E Miscellaneous Radioactive Materials Sources 1.Surveillance Re uirements b.Stored Sources Not In Use Each sealed source and fission detector not previously subjected to core flux shall be tested prior to use or transfer to another licensee unless tested within the previous six months.Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to use.c.Startu Sources and Fission Detectors Each sealed startup source and fission detector shall be tested prior to being subjected to core flux and following repair or maintenance to the source.2.~Re orts A report shall be prepared and submitted to the Commission on an annual basis if sealed sources or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.

288 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

3.8 Radioactive

Materials 4.8 Radioactive Materials F.Solid Radwaste F.Solid Radwaste 1.The solid radwaste system shall be operated in accordance with a process control program, for the solidification and packaging of wet radioactive wastes to ensure meeting the requirements of 10 CFR 20 and 10 CFR 71 and burial ground requirements prior to shipment of radioactive wastes from the site.1.The Process Control Program shall include surveillance checks necessary to demonstrate compliance with 3.8.F.1.2.With the packaging requirements of 10 CFR 20 or burial ground requirements and/or 10 CFR 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site.289 0233p Switchyard Turbine Building Exhaust Fan (32m)Office Building Service Bldg.Turbine Building ad-4aste Bldg.Reactor Building Stack (180m)Reactor Building Ventilation (40m)Figure 4.8-1a GASEOUS RELEASE POINTS AND ELEVATIONS 290 Figure 4.8-1b LAND SITE BOUNDARY , I//~s~,',~,~,,*'iquid Dlecherae (l)lffueer P<pee)lW M N~N aeewr'It~e">>ppe1u AA t<Alll C II*ee<<4 I mtle 2@!lee 290A

3.8 BASES

Radioactive waste release levels to unrestricted areas should be kept"as low as reasonably achievable" and are not to exceed the concentration limits specified in 10 CFR Part 20.At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the concentration limits specified in 10 CFR Part 20.It is expected that by using this operational flexibility and exerting every effort to keep levels or radioactive materials released as low as reasonably achievable in accordance with criteria established in 10 CFR 50 Appendix I, the annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR Part 20.Specification 3.8.A.l is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1)the Section 11.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2)the limits of 10 CFR Part 20.106(e)to the population.

The concentration limit for noble gases is based upon the assumption that Ze-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)Publication 2.Specification 3.8.A.3 is provided to implement the dose requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50.The Limiting Condition for Operation implements the guides set forth the Section 11.A of Appendix I.Specification 3.8.A.4 action statements provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept"as low as is reasonably achievable".

Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by291 0242p calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.3.8.B AIRBORNE EFFLUENTS Specification 3.8.8.1 is provided to ensure that the dose rate at anytime at the exclusion boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas.The annual dose limits are the doses associated with the concentrations of 10 CFR part 20, Appendix B, Table II, Column 1.These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a member of the public in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).

For members of the public who may at times be within the exclusion area 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 exclusion area boundary.291A 0242p

3.8.B AIRBORNE EFFLUENTS (cont'd)The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to<500 mrem/year to the total body or to<3000 mrem/year to the skin.These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to<1500 mrem/year for the nearest cow to the plant.Specification 3.8.B.2 requires that appropriate correction action(s)be taken to reduce gaseous effluent releases if the limits of 3.8.B.1 are exceeded.Specification 3.8.B.5 dose limits is provided to implement the requirements of Section II.C, III.A, and IV of Appendix I, 10 CFR Part 50.The limiting conditions for operation are the guides set forth in Section II.C of Appendix I.Specification 3.8.B.6 action statement provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methods used for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109,"Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977, NUREG/CR-1004,"A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides", October 1979, and Regulatory Guide 1.111,"Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.The pathways which are examined in the development of these calculations are: 1)individual inhalation of airborne radionuclides, 2)deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3)deposition onto grassy areas where milk animal and meat producing animals graze with consumption of the milk and meat by man, and 4)deposition on the ground with subsequent exposure of man.Specification 3.8.B.6 action statement requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.5.291B 0242p

AIRBORNE EFFLUENTS Specification 3.8.B.7 requires that the offgas charcoal adsor'ber beds be used when specified to treat gaseous effluents prior to their release to the environment.

This provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

Specification 3.8.B.8 requires that a special report be prepared and submitted to explain reasons for any failure to comply with Specification 3.8.B.7.Specification 3.8.B.3 is provided to implement the requirements of Section II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50.The Limiting Condition for Operation implements the guide set forth in Section II.C of Appendix I.Specification 3.8.B.4 action statement provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated.

The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109,"Calculating of Annual Doses to lIan from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1 October 1977, NUREG/CR-1004,"A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides", October 1979 and Regulatory Guide 1.111,"Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.The ODCM equations provided for determining the air doses at the exclusion area boundary will be based upon the historical average atmospheric conditions.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.Specifications 3.8.B.4 requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.3.4.8.A and 4.8.B BASES The surveillance requirements given under Specification 4.8.A and 4.8 B provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release of radioactive materials in the liquid and 291C 0242p

4.8.A and 4.8.B BASES (cont'd)gaseous effluents.

These surveillance requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to~radioactive wastes released to the environment.

Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 6 of these technical specifications.

On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such actions as the Commission deems appropriate.

3.8.C and 4.8.C BASES This specification is provided to meet the dose limitations of 40 CFR 190.The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.For sites containing up to four reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level.The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for the calendar year to be within 40 CFR 190 limits.For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose'contributions from other nuclear fuel cycle facilities at the same site or within a radius of five miles must be considered.

3.8.D and 4.8.D MECHANICAL VACUUM PUMP The purpose of isolating the mechanical vacuum pump line is to limit the release of activity from the main condenser.

During an accident, fission products would be transported from the reactor through the main steam lines to the condenser.

The fission product radioactivity would be sensed by the main steam line radioactivity monitors which initiate isolation.

3.8.E and 4.8.E BASES The limitations on removable contamination for sources requiring leak testing, including alpha emitters, based on 10 CFR 70.39(c)limits for plutonium.

This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group.Those sources which are frequently handled are required to be tested more often than those which are not.Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices)are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

291D 0242p

6.0 ADMINISTRATIVE

CONTROLS k.The radiological environmental monitoring program and the results thereof at least once per 12 months.1.The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev.1, 1974 and Regulatory Guide 4.1, 1975 at least once per 12 months.m.The performance of activities required by the Safeguards Contingency Plan to meet the criteria of 10 CFR 73.40(d)at least once per 12 months.n.The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.o.The Process Control Program and implementing procedures for solidification of wet radioactive wastes at least once per 24 months.p.The Radiological Effluent Manual and implementing procedures at least once per 12 months.9.AUTHORITY The NSRB shall report to and advise the Manager of Power on those areas of responsibility specified in Sections 6.2.A.7 and 6.2.A.8.10.RECORDS Records of NSRB activities shall be prepared, approved and distributed as indicated below: a.Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Manager of Power within 14 days following each meeting.b.Reports of reviews encompassed by Section 6.2.A.7 above, shall be prepared, approved and forwarded to the Manager of Power within 14 days following completion of the review.c.Audit reports encompassed by Section 6.2.A.8 above, shall be forwarded to the Manager of Power and to the management positions responsible for the areas audited within 30 days after completion of the audit.334A 0242p

6.0 ADMINISTRATIVE

CONTROLS j.Review proposed changes to the Radiological Effluent Manual.k.Review adequacy of the Process Control Program and Offsite Dose Calculation Manual at least once every 24 months.1.Review changes to the radwaste treatment systems.A I m.Review of every unplanned onsite release of radioactive material to the.environs including the preparation and forwarding of reports covering evaluation, recommendation, and deposition of the corrective action to prevent recurrence to the Director, Nuclear Power and to the Nuclear Safety Review Board.5 A~uthorit The PORC shall be advisory to the plant superintendent.

6.Records Minutes shall be kept for all PORC meetings with copies sent,to Director, Nuclear Power;Assistant Director of Nuclear Power (Operations);

Chairman, NSRB.p~7.Procedures 0 Written administrative procedures for committee operation shall be prepared and maintained describing the method for submission and content of presentations to the committee, review and approval by members of'committee actions, dissemination of minutes, agenda and scheduling of meetings.337 0242p

6.0 ADMINISTRATIVE

CONTROLS~~~6.3 Procedures A.Detailed written procedures, including applicable checkoff lists covering items listed below shall be prepared, approved and adhered to.1.Normal startup, operation and shutdown of the reactor and of all systems and components involving nuclear safety of the facility.2.Refueling operations.

3.Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks and abnormal reactivity changes.4.Emergency conditions involving potential or actual release of radioactivity.

5.Preventive or corrective maintenance operations which could have an effect on the safety of the reactor.6.Surveillance and testing requi'rements.

7.Radiation control procedures.

8.Radiological Emergency Plan implementing procedures.

9.Plant security program implementing procedures.

10.Fire protection and prevention procedures.

11.Limitations on the amount of overtime worked by individuals performing safety-related functions in accordance with the NRC policy statement on working hours (Generic Letter No.82-12).12.Radiological Effluent Manual implementing procedures.

13.Process Control Program (PCP).14.Offsite Dose Calculation Manual.B.Written procedures pertaining to those items listed above shall be reviewed by PORC and approved by the plant superintendent prior to implementation.

Temporary changes to a procedures which do not change the intent of the approved procedure may be made by a member of the plant staff knowledgeable in the area affected by the procedure except that temporary changes to those items listed above except item 5 require the additional approval of a member of the plant staff who holds a Senior Reactor Operator license on the unit affected.Such changes shall be documented and subsequently reviewed by PORC and approved by the plant superintendent.

338 0242p

6.0 ADMINISTRATIVE

CONTROLS 6.3 Procedures E.ualit Assurance Procedures

-Effluent and Environmental Monitorin Quality Assurance procedures shall be established, implemented, and maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, rev.1, June 1974 and Regulatory Guide 4.1, rev.1, April 1975 or Regulatory Guide 4.15, Dec.1977.340 0242p

6.0 Administrative

Controls 3.Uni ue Re ortin Re uirements A.Radioactive Effluent Release Re ort Deleted.(See REM section F.2)355 0242p

6.0 ADMINISTRATIVE

CONTROLS 6.9 Process Control Pro ram (PCP)1.The PCP shall be approved by the Commission prior to implementation.

2.Changes to the PCP shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change(s)was made.This submittal shall contain: a.Sufficiently detailed information to totally support the change.b.A determination that the change did not change the overall conformance of the solidified product to existing criteria.3.Changes to the PCP shall become effective upon review and acceptance by PORC.6.10 Offsite Dose Calculational Manual (ODCM)1.The ODCM shall be approved by the Commission prior to implementation.

2.Changes to the ODCM shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change(s)was made.This submittal shall contain: a.Sufficiently detailed information to totally support the change.3.Changes to the ODCM shall become effective upon review and acceptance by PORC.6.11 RADIOLOGICAL EFFLUENT MANUAL (REM)1.The REM shall be approved by the Commission prior to implementation.

2.Changes to the REM shall be reviewed by PORC prior to implementation.

3.Changes to the REM shall be approved by the Commission prior to implementation.

359 0242p 0

APPENDIX B TECHNICAL SPECIFICATIONS BROWNS FERRY UNITS 1 AND 2 0242p ENVIRONMENTAL TECHNICAL SPECIFICAITONS FOR BROWNS FERRY NUCLEAR PLANT TABLE OF CONTENTS~pa e No.1.0 DEFINITIONS....................,.......................

Deleted 2.0 LIMITING CONDITIONS FOR OPERATION................

.....Deleted 2.1 Thermal Discharge Limits..........................

2.2 Chemical............

Deleted Deleted 2.2.1 Makeup Water Treatment Plan Demineralizer Regerants..

2.2.2 Chlorine.t Spent Deleted Deleted 3.0 DESIGN FEATURES AND OPERATING PRACTICES................

Deleted 3.1 Chemical Usage.~~~~~~~~~~~~~~~~~~~~~~~~~Deleted 0 3.1.2 Other Chemicals............................

3.2 Land Management.............

3.2.1 Power

Plant Site...........................

Deleted Deleted Deleted 3.1.1 Oils and Hazardous Materials..............

Deleted 3.2.2 Transmission Line Right-of-Way Maintenance.

3.3 Onsite

Meteorological Monitoring..................

Deleted 4.0 ENVIRONMENTAL SURVEILLANCE.............................

Deleted 4.1 Ecological Surveillance...........................

4.1.1 Abiotlc

4 ea.1.2 Blotice~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~4.1.3 Special Studies....................

~....~.-4.2 Radiological Environmental Monitoring Program.....

Deleted Deleted Deleted Deleted Deleted 0242p 0

5.2 Organiratxon..............

5.3 Review

and Audit..........

5.0 ADMINISTRATIVE

CONTROLS......

5.1 Responsibility..........

Deleted Deleted Deleted Deleted 5.4 Action to be Taken if an Ezceeded..............

Environment LCO is~~t~~~~~~~~~~~~~~~~~~~~~~5.5 Procedure.........................

~~~~~~~~5.7 Environmental Records...

~.........................

ables........................

T Figures.~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~5.6 Reporting Requxrements............................

Deleted Deleted Deleted Deleted Deleted Deleted0242p

3.2.2 Transmission

Line Ri ht-of-Wa Maintenance O~b ecbive The sole purpose of this section is to provide reporting requirements (to USNRC)on herbicide usage, if any, for purposes of right-of-way maintenance regarding only those transmission lines under USNRC's jurisdiction for the Browns Ferry Nuclear Plant.S ecification A statement as to whether or not herbicides have been used in maintaining rights-of-way for those transmission lines associated with the Browns Ferry Nuclear Plant shall be provided.If herbicides have been used, a description of the types, volumes, concentrations, manners and frequencies of application, and miles or rights-of-way that have been treated shall be included.Re ortin Re uirements Information as specified above shall be provided in the Annual Operating Report (Appendix A, Section 6.7.l(b)).

Bases Vegetation growth on a transmission line right-of-way must be controlled in such a manner that it will neither interfere with safe and reliable operation of the line or impede restoration of service when outages occur.Vegetation growth is controlled by mechanical cutting and the limited use of herbicides.

Selected chemicals approved by EPA for use as herbicides are assigned (by EPA)label instructions which provide guidance on and procedures for their use.0242p APPENDIX A TECHNICAL SPECIFICATIONS UNIT 3 0243p

UNIT 3 TABLE OF CONTENTS 0243p TABLE OF CONTENTS~Pa e No.Introduction

.1.0 Definitions.

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 1.1/2.1 1.2/2.2 Fuel Cladding Integrity.

Reactor Coolant System Integrity.LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 26 3.1/4.1 3.2/4.2 Reactor Protection System.Protective Instrumentation

...A.Primary Containment and Reactor Building Isolation Functions.

31 49 49 B.Core and Containment Cooling Systems-Initiation and Control 50 C.Control Rod Block Actuation.

50 D.Radioactive Liquid Effluent Monitoring Instruments.

51 E.Drywell Leak Detection.F.Surveillance Instrumentation

.53 53 G.Control Room Isolation.H.Flood Protection

.54 I.Meteorological Monitoring Instrumentation.

J.Seismic Monitoring Instrumentation

.54 56 K.Radioactive Gaseous Effluent Instrumentation.

Monitoring

~~~~~~56A 0 3.3/4.3 Reactivity Control A.Reactivity Limitations B.Control Rods 118 118 122 0243p

Section~Pa e No.C.Scram Insertion Times.128 D.Reactivity Anomalies.

129 E.Reactivity Control F.Scram Discharge Volume.129 129 3.4/4.4 Standby Liquid Control System.137 A.Normal System Availability

.B.Operation with Inoperable Components C.Sodium Pentaborate Solution.137 139 139 3.5/4.5 Core and Containment Cooling Systems.146 A.Core Spray System.B.Residual Heat Removal System (RHRS)(LPCI and Containment Cooling)146 149 C.RHR Service Water System and Emergency Equipment Cooling Water System (EECWS)155 D.Equipment Area Coolers.158 E.High Pressure Coolant Injection System (HPCIS)~~~~~~~~'~~~~~~~~159 F.Reactor Core Isolation Cooling System (RCICS)~~~~~~~~~~~~'~~~160 G.Automatic Depressurization System (ADS)~~~~~~~~~~~~~~~~~161 H.Maintenance of Filled Discharge Pipe.163 I.Average Planar Linear Heat Generation R ate e~~~~~~~~~~~~~~~~165 J.Linear Heat Generation Rate.166 K.Minimum Critical Power Ratio (MCPR).167 L.APRM Setpoints M.Reporting Requirements

.~~~3.6/4.6 Primary System Boundary.A.Thermal and Pressurization Limitations 167A 167A 184 184 0243p Section" B.Coolant Chemistry.

C.Coolant Leakage.D.Relief Valves.E.Jet Pumps.F.Recirculation Pump Operation.G.Structural Integrity.H.Seismic Restraints, Supports, and Snubbers~Pa e No.187 191 192 193 195 196 198 3.7/4.7 Containment Systems.A.Primary Containment.

B.Standby Gas Treatment System.C.Secondary Containment.

D.Primary Containment Isolation Valves.E.Control Room Emergency Ventilation

.F.Primary Containment Purge System G.Containment Atmosphere Dilution System (CAD)231 231 247 251 254 256 258 260 3.8/4'H.Containment Atmosphere Monitoring System H~Analyzer Radioactive Materials.(CAM)261 299 A.Liquid Effluents.B.Airborne Effluents 299 301 C.Radioactive Effluents-Dose.D.Mechanical Vacuum Pumps.E.Miscellaneous Radioactive Materials Sources.304 304 305 F.Solid Radwaste.307 3.9/4.9 Auxiliary Electrical System.A.Auxiliary Electrical Equipment B.Operation with Inoperable Equipment.

316 316 321 0243p Section t'., Operation in Cold Shutdown.3.10/4.10 Core Alterations

.~Fa e No.326 331 A.Refueling Interlocks.

'a B.Core Monitoring

.331 336 C.Spent Fuel Pool Water.D.Reactor Building Crane.E.Spent Fuel Cask.337 338 339 F.Spent Fuel Cask Handling-Refueling loor~~~~~~~~~~~~~~~~F 339 3.11/4.11 Fire Protection Systems.A.High Pressure Fire Protection System.B.CO>Fire Protection System.C.Fire Detectors.

D.Roving Fire Watch.E.Fire Protection Systems Inspections 347 347 351 352 353 354 F.Fire Protection Organization.

354 G.Air Masks and Cylinders H.Continuous Fire Watch.355 355 5.0 I.Open Flames, Welding, Cable Spreading Room.Major Design Features.5.1 Site Features.5.2 Reactor.~and Burning in the~~~355 360 360 360 5.3 Reactor Vessel.360 5.4 Containment 360 5.5 Fuel Storage.5.6 Seismic Design.Administrative Controls.6.1 Organization.

360 361 362 362 1v 0243p LIST OF TABLES Section 1.1 Title Surveillance Frequency Notation.~Pa e No.3.1.A 4.1.A Reactor Protection System (SCRAM)Instrumentation Requirements

.Reactor Protection System.(SCRAM)Instrumentation Functional Tests Minimum Functional Test Frequencies for Safety Instr.and Control Circuits.32 36 4.1.B Reactor Protection System (SCRAM)Instrument Calibration Minimum Calibration Frequencies Reactor Protection Instrument Channels for 39 3.2.A Primary Containment and Reactor Building Isolation Instrumentation.

57 3.2.B Instrumentation that Initiates or Controls the Core and Containment Cooling Systems 64 3.2.C 3.2.D Instrumentation that Initiates Rod Blocks.a Radioactive Liquid Effluent Monitoring Instrumentation.

76 79 3.2.E~~Instrumentation that Monitors Leakage Into Drywell 80 3.2.F Surveillance Instrumentation

.81 3.2.G Control Room Isolation Instrumentation

.84 3.2eH Flood Protection Instrumentation

.85 3.2.I Meteorological Monitoring Instrumentation.

86 3.2eJ Seismic Monitoring Instrumentation

.87 3.2eK Radioactive Gaseous Effluent Monitoring Instrumentation.

87A 4.2.A Surveillance Requirements for Primary Containment and Reactor Building Isolation Instrumentation.

88 4.2.B Surveillance Requirements for Instrumentation that Initiate or Control the CSCS.92 4.2.C Surveillance Requirements for Instrumentation that Initiate Rod Blocks.99 4.2.D~~Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirement 100 v1 0243p

4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation

.101 Minimum Test and Calibration Frequency for Surveillance Instrumentation

.102 4.2.G Surveillance Requirements for Control Room Isolation Instrumentation.

103 4.2.M Minimum Test and Calibration Frequency for Flood Protection Instrumentation

.104 4.2.J Seismic Monitoring Instrument Surveillance Requirements

.105 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance

.105A.3.5.-1 3.5.I Minimum RHRSW and EECW Pump Alignment.

.....156a MAPLHGR vs.Average Planar Exposure.....181, 182, 182a, 182b 3.7.A Primary Containment Isolation Valve.262 3.7.B Testable Penetrations with Double 0-Ring Seals 268 Testable Penetrations with Testable Bellows.269 Air Tested Isolation Valves.270 3.7.E Primary Containment Isolation Valve which Terminate Below the Suppression Pool Water L evel.279 3.7.F Primary Containment Isolation Valve Located in Water Sealed Seismic Class I Lines.280 3.7.G 3.7.H Deleted Testable Electrical Penetrations

.283 4.9.A.4.c Voltage Relay Setpoints/Diesel Generator Start.327 3.11.A Fire Protection System Hydraulic Requirements 355a 6.8.A Minimum Shift Crew Requirements.

390 v11 0243p LIST OF ILLUSTRATIONS t~Fi ure 2.1.1 Title APRM Flow Reference Scram and APRM Rod Block S t a et t lngs~~~~~~~~~~~~~~~~~~~~~Pa e No.14 2.1-2 APRM Flow Bias Scram Vs.Reactor Core-Flow.25 4.1-1 Graphic Aid in the Selection of an Adequate Interval Between Tests.48 4.2-1 3.4-1 System Unavailability.

Sodium Pentaborate Solution Volume Concentration Requirements

.117 141 3.4-2 Sodium Pentaborate Solution Temperature Requirements

.142 3.5.K-1 MCPR Limits.182c 3.5.2 3.6-1 KI Factor vs.Percent Core Flow.Temperature-Pressure Limitations 183 207 Change in Charpy V Transition Temperature Vs.Neutron Exposure~~~~4.8.1.a Gaseous Release Points and Elevations.

208 308 4.8.1.b Site Boundary.309 6.1-1 TVA Office of Power Organization for Operati of Nuclear Power Plants.on 391 6.1-2 Functional Organization.

392 6.2-1 Review and Audit Function.393 6.3-1 In-Plant Fire Program Organization 394 V111 0243p BROWNS FERRY NUCLEAR PLANT-UNIT 3 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS 0244p

0 a protective trip function.A trip system may require one or more'instrument channel trip signals related to one or more plant.parameters in order to initiate trip system action.Initiation of*'rotective action may require the tripping of a single trip system-or the coincident tripping of two trip systems.7.Protective Action-A action initiated by the protective system when a limit is reached.A protective action can be at a channel or system level.8.Protective Function-A system protective action which results from the protective action of the channels monitoring a particular plant condition.

9.Simulated Automatic Acutation-Simulated automatic acutation means applying a simulated signal to the sensor to actuate the circuit in question.10.~Lo ic-A logic is an arrangement of relays, contacts, and other components that produces a decision output.(a)Initiatin-A logic that receives signals from channels and produces decision outputs to the actuation logic.(b)Actuation-A logic that receives signals (either from initiation logic or channels)and produces decision outputs to accomplish a protective action.11.Channel Calibration

-Shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel monitors.The channel calibration shall encompass the entire channel including alarm and/or trip functions and shall include the channel function test.The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

Non-calibratable components shall be excluded from this requirement, but will be included in channel functional.

test and source check.12.'hannel Functional Test-Shall be: 1 Analog Channels-the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b.Bistable channels-the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

13.Source Check-Shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources.0244p 1 W."-Functional Tests-A functional test is the manual operation or.initiation of a system, subsystem, or component to verify that it functions within design tolerances (e.ges the manual start of a ,.core spray pump to verify that it runs and that it pumps the required volume of water).j>>4'e X.Shutdown-The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.

Y.En ineered Safe uard-An engineered safeguard the actions of which are essential to a safety response to accidents.

is a safety system action required in Z.Re ortable Event-A reportable event shall be any of those conditions specified in section 50.73 to 10 CFR Part 50.Solidification

-Shall be the conversion of radioactive wastes into a form that meets shipping and burial ground requirements.

BB.Offsite Dose Calculation Manual (ODCM)-Shall be a manual describing the environmental monitoring program and the methodology and parameters used in the calculation of release rate limits and offsite doses due to radioactive gaseous and liquid effluents.

The ODCM will also provide the plant with guidance for establishing alarm/trip setpoints to ensure technical specifications section 3.8.A.l and 3.8.B.l are not exceeded.CC.Pur e or ur in-The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is required to purify the containment.

DD.Process Control Pro ram-Shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.EE.FF.Radiolo ical Effluent Manual (REM)-Shall be a manual containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposure to individuals from station operation.

It shall also specify operating guidelines for radioactive waste treatment systems and report content.dentin-The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required.Vent, used in system names, does not imply a venting process.7A 0244p

1.0 DEFINITIONS

(Cont'd)f GG.HH.owned, leased, or otherwise controlled by TVA.Unrestricted Area-Any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of'ndividuals from exposure to radiation and radioactive materials or any area within the site boundary used for industrial, commercial, institutional, or recreational purposes.Dose E uivalent I-131-The DOSE EQUIVALENT I-131 shall be the concentration of I-131'in pCi/gm)which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.The thyroid dose conversion factor used for this calculation shall be those listed in Table III of TID-14844"Calculation of Distance Factors for Power and Test Reactor Sites".Gaseous Waste Treatment S stem-The charcoal adsorber vessels installed on the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release.Members of the Public-Shall include all individuals who by virtue of their occupational status have no formal association with the plant.This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.

This category shall not include non-employees such as vending machine servicemen or postmen who, as part of-their formal job function, occasionally enter restricted areas.LL.Surveillance

-Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements.

Each Surveillance Requirement shall be performed within the specified time interval with, (1)A maximum allowable extention not to exceed 25K of the surveillance interval, but (2)The combined time entered for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications.

Surveillance requirements do not have to be performed on inoperable equipment.

7B 0244p

E Table 1.1 SURVEILLANCE FRE UENCY NOTATION 1 NOTATION S (Shift)D (Daily)W (Weekly)M (Monthly)Q (Quarterly)

SA (Semi-Annually)

Y (Yearly)R (Refueling)

S/U (Start-Up)

N.A.P (Prior)~E<EUENCY At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.At least once per normal calendar 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day (midnight to midnight).

At least once per 7 days.At least once per 31 days.At least once per 3 months or 92 days.At least once per 6 months or 184 days.At least once per year or 366 days.At least once per operating cycle.Prior'to each reactor startup.Not applicable.

Completed prior to each release.0244p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2 Protective Instrumentation

4.2 Protective

Instrumentation 3.2.D Radioactive Li uid Effluent Monitorin Instrumentation 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation The radioactive liquid effluent instrumentation listed in Table 3.2.D shall be operable with the applicability as shown in Table 3.2.D/4.2.D.

Alarm/trip setpoints will be set in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.A.1 are not exceeded.l.Each of the radioactive liquid effluent monitoring instruments shall be demonstrated operable by performance of test in accordance with Table 4.2.D.2.The action required when the number of operable channels is less than the minimum channels operable requirement is specified in the notes for Table 3.2.D.Exert best efforts to return the instrument(s) to OPERABLE status within 30 days and if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the.inoperability was not corrected in a timely manner.3.With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these specifications.

4~The provisions of specifications 1.0.C and 6.7.2 are not applicable.

51 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.K Radioactive Gaseous Effluent Monitorin Instrumentation 4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation The radioactive gaseous effluent monitoring instruments listed in Table 3.2.K shall be operable with the applicability as shown in Tables 3.2.K/4.2.K.

-Alarm/trip setpoints will be set in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.B.l are not exceeded.l.Each of the radioactive gaseous effluent monitoring instruments shall be demonstrated operable by performance of tests in accordance with Table 4.2.K..-2.The action required when the number of operable channels is less than the minimum channels operable requirement is specified in the notes for Table 3.2.K.Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Release Report why the inoperability was not corrected in a timely manner.3~With a radioactive gaseous.effluent monitoring channel alarm/trip setpoint less conservative than required by these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these specifications.

4~Both off-gas posttreatment monitors may be taken out-of-service for less than one hour for purging of monitors during SI performance.

5.The provisions of specifications 1.0.C and 6.7.2 are not applicable.

56A 0233p Instrument

'1.LIQUID RADHASTE EFFLUENT MONITOR (RM-90-130) 2.RHR SERVICE HATER MONITOR (RM-90-133,-134)3.RAH COOLING HATER MONITOR (RM-90-132) 4.LIQUID RADHASTE EFFLUENT FLOH RATE (77-60 loop excluding fixed in line rotometer)

TABLE 3.2.D Radioactive Li uid Effluent Monitorin Instrumentation Minimum Channels 0 erable b lit Action A, B 0240p 79 f~

NOTES FOR TABLE 3.2.D>'<At all times>'~'~During releases via this pathway>'o'~'~During operation of an RHR loop and associated RHR service water system ACTION A During release of radioactive wastes from the radwaste processing system, the following shall be met (1)liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in 3.8.A.1, (2)if this cannot be met, two independent samples of t e tank being discharged shall be analyzed in accordance with the sampling and analysis program specified in the REM and two qualified station personnel shall independently verify the release rate calculations and check valving before the discharge.

Otherwise, suspend release via this pathway.ACTION B With a radioactive.

liquid effluent monitoring channel/alarm trip setpoint less conservative than required by these specifications, suspend release via this pathway without'delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism referred by these specifications.

ACTION C During operation of an RHR loop and associated RHR service water system, the effluent from that unit's service water shall be continuously monitored.

If an installed monitoring system is not available, a temporary monitor or grab samples taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and an analysis of at least an LLDf 1E-7'Ci/ml (gross)or (applicable MPC ratio (y isotopic)shall be used to monitor the effluent.ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided that a temporary monitor is installed or, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for radioactivity with an LLDf 1E-7 pCi/ml (gross)or (applicable MPC ratio (y isotopic).

ACTION E With the number of channels OpERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided the flow rate 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.Pump curves may be used to estimate flow.ACTION F Alarm/trip setpoints will be calculated in accordance with the guidance given in the Offsite Dose Calculation Manual (ODCM).(1)See REM, TABLE NOTATIONS-TABLE C-l, for the definition of LLD.79A 0244p 0 s.~.~Radioactive Gaseous Effluent Monitorin Instrumentation Instrument STACK (RM-90-147A 5 B)a.Noble Gas Monitor b.Iodine Cartridge c.Particulate Filter d.Sampler Flow Abnormal e.Stack Flow (FT, FM, FI-90-271)

Minimum Channels/Devices 0 erable (1)(1)(1)(1)(1)A 1 i cab i 1 i t Action A/C 8/C.B/C D D 2.3.4.5.6.REACTOR/TURBINE BLDG VENTILATION (RM-90-250) a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d~Sampler Flowmeter TURBINE BLDG EXHAUST (RM-90-249, 251)a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter RADHASTE BLDG VENT (RM-90-252) a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter OFF GAS HYDROGEN ANALYZER (HgA, HgB)OFF GAS POST TREATMENT a.Noble Gas Activity Monitor (RM-90-265, 266)b.Sample Flow Abnormal (PA-90-262)

(1)(1)(1)(1)(1)(1)(1)(1)(1)~(1)(1)(1)A/C B/C B/C D A/C B/C B/C D A/C 8/C B/C D 0240p 87A NOTES FOR TABLE 3.2.K l~'~At all times>'~'<During releases via this pathway~'~'~~During main condenser offgas treatment system operation ACTION A With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via the affected pathway may continue provided a temporary monitoring system is installed or grab samples are taken and analyzed at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.ACTION B With a 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 sampling equipment for periods on the order of seven (7)days and analyzed in accordance with the sampling and analysis program specified in the REM 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.ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for functional testing, calibration, or repair without providing or initiating grab sampling.t ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement effluent releases via this pathway may continue provided the flow rate 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 />.ACTION E With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, operation of main condenser offgas treatment system may continue provided that a temporary monitor is installed or grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.ACTION F 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 at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 />.Purging during SI performance is not considered a loss of monitoring capability.

87B 02449 TABLE 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation Surveillance Re uirements Instrument 1~LIQUID RADHASTE EFFLUENT MONITOR (RM-90-130) 2.RHR SERVICE HATER MONITOR (RM-90-133,-134)3.RAW COOLING HATER MONITOR (RM-90-132) 4.LIQUID RADHASTE EFFLUENT FLOH RATE (77-60 loop)Instrument Check D(4)D(4)D(4)D(4)Source Check Channel Calibration R(5)R(5)R(5)R Functional Test Q(1)Q(2)Q(2)Q(3).0240p 100 NOTES FOR TABLE 4.2.D (I)The channel functional test shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint b.Instrument indicates an inoperative/downscale failure c.Instrument controls not set in operate mode (2)The channel functional test shall also demonstrate that control room annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm setpoint b.Instrument indicates an inoperative/downscale failure c.Instrument controls not set in operate mode (3)This functional test shall consist of measuring rate of tank decrease over a period of time and comparing this value with flow rate instrument reading.(4)INSTRUMENT CHECK shall consist of verifying indication during periods of release.INSTRUMENT CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days which continuous, periodic, or batch releases are made.(5)The CHANNEL CALIBRATION shall include%he use of a known (traceable to National Bureau of Standards Radiation Measurement System)radioactive source(s)positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards (NBS).100A 0244p TABLE 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance Instrument STACK a.Noble Gas Monitor'b.Iodine Cartridge c.Particulate Filter d.Sampler Flow Abnormal e.Stack Flowmeter Instrument Check D W W D D Source Check M'A NA NA NA Channel Calibration R(1)NA NA R R Functional Test Q(2)NA NA Q Q 2.3.4 5.6.REACTOR/TURBINE BLDG VENT a.Noble Gas Monitor"'.Iodine Sampler c.Particulate Sampler d.Stack Flowmeter TURBINE BLDG EXHAUST a.Noble Gas Monitor"'.Iodine Sampler c.Particulate Sampler d.Stack Flowmeter RADWASTE BLDG VENT a.Noble Gas Monitor"'.Iodine Sampler c.Particulate Sampler d.Stack Flowmeter OFF GAS HYDROGEN ANALYZER (H2A, H2B)OFF GAS POST TREATMENT.Noble Gas Activity Monitor b.Sample Flow Abnormal D D D D M NA NA NA M NA NA NA NA NA NA R"'A NA R R(1)NA NA R R(1)NA NA R R(), R(1)R Q(2)NA NA Q Q(2)NA NA Q Q(2)NA NA Q Q(4)Q(4)Q(2)0240p 105A

I NOTES FOR TABLE 4.2.K~~~(1)The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of Standards Radiation Measurement System)radioactive

, source(s)positioned in a reproducible geometry with respect to the sensor or using standards that have obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards.

C I (2)The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint.b.Instrument indicates an inoperable/downscale failure.c.Instrument controls not set in operate mode (stack only).(3)The channel calibration shall include the use of standard gas samples containing a nominal: a.Zero volume percent hydrogen (compressed air)and, b.One volume percent hydrogen, balance nitrogen.(4)The channel functional test shall demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exists: a.Instrument indicates measured levels above the alarm/tiip setpoint.b.Instrument i.ndicates an inoperative/downscale failure.c.Instrument controls not set in operate mode.The two channels are arranged in a coincidence logic such that 2 upscale, or 1 downscale and 1 upscale or 2 downscale will isolate the offgas line.(5)The noble gas monitor shall have a LLD of 1E-5 (Xe 133 Equivalent).

f (6)The noble gas monitor shall have a LLD of 1E-6 (Xe 133 Equivalent).

105B 0244p Cg I II The operability of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event t and evaluate the response of those features important to safety.This capability is required to permit comparison of the measured response to that used in the design basis for Browns Ferry Nuclear Plant.The instrumentation provided is consistent with specific portions of the recommendations of Regulatory Guide 1.12"Instrumentation for Earthquakes".

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 will be calculated in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.This instrumentation also includes provisions for monitoring the concentration of potentially explosive gas mixtures in the offgas holding system.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.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 in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20 Appendix B, Table II, Column 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 113 0244p

The most likely cause would be to stipulate that one channel be bypassed, tested, and restored, and then immediately following, the second channel be~~~~~~~~~~~~~~~.bypassed, tested, and restored.This is shown by Curve No.4.Note that there is no true minimum.The curve does have a definite knee and very little reduction in system unavailability is achieved by testing at a shorter interval than computed by the equation for a single channel.The best test procedure of all those examined is to perfectly stagger the tests.That is, if the test interval is four months, test one or the other channel every two months.This is shown in Curve No.5.The difference between-Cases 4 and 5 is negligible.

There may be other arguments, however, that more strongly support the perfectly staggered tests, including reductions in human error.The conclusions to be drawn are these: 1.A 1 out of n system may be treated the same as a single channel in terms of choosing a test interval;and 2.more than one channel should not be bypassed for testing at any one time.The radiation monitors in the refueling area ventilation duct which initiate building isolation and standby gas treatment operation are arranged in two 1 out of 2 logic systems.The bases given for the rod blocks apply here also and were used to arrive at the functional testing frequency.

The off-gas post treatment monitors are connected in a 2 out of 2 logic arrangement.

Based on experience with instruments of similar design, a testing interval of once every three t months has been found adequate.The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also.The criteria for ensuring the reliabil'ity and accuracy of the radioactive gaseous effluent instrumentation is listed in Table 4.2.K.The criteria for ensuring the reliability and accuracy of the radioactive liquid effluent instrumentation is listed in Table 4.2.D.116 0244p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS t 3.6 Primar 5.S stem Boundar Whenever the reactor is critical, the limits on activity concentrations in the reactor coolant shall not exceed the equilibrium value of 3.2 pc/gm of dose equivalent I-131.This limit may be exceeded following power transients for a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.During this activity transient the iodine concentrations shall not exceed the equilibrium values by a factor of more than 10 whenever the reactor is critical.The reactor shall not be operated more than 5 percent of its yearly power operation under this exception for the equilibrium activity limits.If the iodine concentration in the coolant exceeds the equilibrium limit by a factor of ten, the reactor shall shutdown, and the steam line isolation valves shall be closed immediately.

4.6 Primar

S'stem Boundar 190 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8.Radioactive Materials 4.8 Radioactive Materials Applies to the release of radioactive liquids and gases from the facility.~Ob ective To define the limits and conditions for the release of radioactive effluents to the environs to assure that any.radioactive releases are as low as reasonably achievable and within the limits of 10 CFR Part 20.The specifications except for 3.8.A.1 and 3.8.B.1 are exempt from the requirements of definition 1.0.C (Limiting Condition for Operation).

A.Li uid Effluents 1.The concentration of radioactive material released at any time from the site to unrestricted areas (see Figure 4.8-1b)shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity.2.If the limits of 3.8.A.l are exceeded, appropriate action shall be initiated without delay to bring the release within Applies to the periodic test and record requirements and sampling and monitoring methods used for facility effluents.

O~b ective To ensure that radioactive liquid and gaseous releases from the facility are maintained within the limits specified by Specifications 3.8.A and 3.8.B.S ecification A.Li uid Effluents 1.Facility records shall be maintained of radioactive concentrations and volume before dilution of each batch of liquid effluent released, and of the average dilution flow and length of time over which each discharge occurred.2.Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with the sampling and analysis program specified in the REM.3.The operation of the automatic isolation valves and discharge tank selection valves shall be checked annually.299 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 i Radioactive Materials limits.Provide prompt notification to the NRC pursuant to section 6.7.2.3.The doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas (See Figure 4.8-1b)shall be limited: 4.8 Radioactive Materials 4.The results of the analysis of samples collected from release points shall be used with the calculational methodology in the ODCM to assure that the concentrations at the point of release are maintained within the limits of specification 3.8.A.1.a.During any calendar quarter to<1.5 mrem to the total body and<5 mrem to any organ and, b.During any calendar year to<3 mrem to the total body and<10 mrem to any organ 4.If the limits specified in 3.8.A.3 a 6 b above are exceeded, prepare and submit Special Report pursuant to Section 6.7.2.5.The maximum activity to be contained in one liquid radwaste tank or temporary storage tank that can be discharged directly to the environs shall not exceed 10 curies excluding tritium and dissolved/entrained noble gas.5.Cummulative quarterly and yearly dose contributions from liquid effluents shall be determined as specified in the ODCM at least once every 31 days.6.The quantity of radioactive material contained in any outside liquid radwaste storage tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.6.With radioactive liquid waste exceeding 3.8.A.5 limits, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit.Events leading to this condition must be reported in the next Semiannual Radioactive Effluent Release Report (section F.2 of the REM)300 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials B.Airborne Effluents 4.8 Radioactive Materials B.Airborne Effluents 1.The dose rate at any time to areas at and beyond the site boundary (see Figure 4.8-1b)due to radioactivity released in gaseous effluents from the site shall be limited to the following values: '.The dose rate limit for noble gases shall be<500 mrem/yr to the total body and<3000 mrem/yr to the skin, and b.The dose rate limit for I-131, I-133, H-3, and particulates with greater than eight day half-lives shall be<1500 mrem/yr to any organ.2.If the'limits of 3.8.B.l are exceeded, appropriate corrective action shall be immediately initiated to bring the release within limits.Provide prompt notification to the NRC pursuant to section 6.7.2.1.The gross 0/y and particulate activity of gaseous wastes released to the environment shall be monitored and recorded.a.For effluent streams having continuous monitoring capability, the activity shall be monitored and flow rate evaluated and recorded to enable release rates of gross radioactivity to be determined at least once per shift using instruments specified in table 3.2.K.b.For effluent streams without continuous monitoring capability, the activity shall be monitored and recorded and the release through these streams controlled to within the limits specified in 3.8.B.2.Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with the sampling and analysis program specified in the REM.Dose rates shall be determined to be within limits of 3.8.B using methods contained in the ODCM.301 0233p

'I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS-3.The air dose to areas at and beyond the site boundary (see Figure 4.8-1b)due to noble gases released in gaseous effluents per unit shall be limited to the following:

3.Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in the ODCM at least once every 31 days.a.During any calendar quarter, to<5 mrad for gamma radiation and<10 mrad for beta radiation; b.During any calendar year, to<10 mrad for gamma radiation and<20 mrad for beta radiation.

4.If the calculated air dose exceeds the limits specified in 3.8.B.3 above, prepare and submit a special report pursuant to section 6.7'.5.The dose to a member of the public from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than 8 days in gaseous effluent released per unit to areas at and beyond the site boundary (see Figure 4.8-1b)shall be limited to the following:

a.To any organ during any calendar quarter to<7.5 mrem;b.To any organ during any calendar year to<15 mrem;302 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 6.If the calculated doses exceed the limits of 3.8.B.5 above, prepare and submit a special'report pursuant to section 6.7.2.4.During operation above 25'X power, the position of the charcoal bed bypass valve will be verified daily.7.During operation above 25K power the discharge of the SJAE must be routed through the charcoal adsorbers.

8.With gaseous waste being discharged for more than 7 days without treatment through the charcoal adsorbers, prepare and submit a special report pursuant to section 6.7.2.5.The concentration of hydrogen downstream of the recombiners shall be determined to be within the limits of 3.8.B.9 by continuously monitoring the offgass whenever the SJAE is in service using instruments described in Table 3.2.K.Instrument surveillance requirements are specified in Table 4.2.K.9.Whenever the SJAE is in service, the concentration of hydrogen in the offgas downstream of the recombiners shall be limited to<4X by volume.10.With the concentration of hydrogen exceeding the limit of 3.8.B.9 above,.restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.303 0233p 0

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8.C Radioactive Effluents-Dose 4.8.C Radioactive Effluents-Dose The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to<25 mrem to the total body or any organ (except the thyroid, which is limited to<75 mrem)over a period of one calendar year.1.Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with specifications 3.8.A.3, 3.8.B.3, and 3.8.B.5 and the methods in the ODCM.2.With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of specification 3.8.A.3, 3.8.B.3, or 3.8.B.5, prepare and submit a Special Report to the Commission pursuant to specification 6.7.2 and limit the subsequent releases such that the limits of 3.8.C.1 are not exceeded.3.8.D Mechanical Vacuum Pum 4.8.D Mechanical Vacuum Pum Each mechanical vacuum pump shall be capable of being automatically isolated and secured on a signal or high radioactivity in the steam lines whenever the main steam isolation valves are open.'t least once during each operating cycle verify automatic securing and isolation of the mechanical vacuum pump.2.If the limits of 3.8.D.1 are not met, the vacuum pump shall be isolated.304 0233p

3.8 LIMITING

CONDITIONS FOR OPERATION Radioactive Materials E.Miscellaneous Radioactive Materials Sources 4.8 SURVEILLANCE RE UIREMENTS Radioactive Materials E.Miscellaneous Radioactive

-.'aterials Sources 1.Source Leaka e Test 1.Surveillance Re uirement Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or.5 microcuries of alpha emitting material shall be free of>0.005 microcurie of removable contamination.

Each sealed source with removable.

contamination in excess of the above limit shall be immediately withdrawn from use and (a)either decontaminated and repaired, or (b)disposed of in accordance with Commission regulations.

Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an agreement State, as follows: a.Sources in Use Each sealed source, excluding startup sources and flux detectors previously subjected to core flux, containing radioactive material, other than Hydrogen 3, with a half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at least once per six months.The leakage test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample.305 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS4.8.E Miscellaneous Radioactive Materials Sources 1.Surveillance Re uirements b.Stored Sources Not In Use Each sealed source and fission detector not previous1y subjected to core flux shall be tested prior to use or transfer to another licensee unless tested within the previous six months.Sealed sources and fission.detectors transferred without a certificate indicating the last test date shall be tested prior to use.c.Startu Sources and Fission Detectors Each sealed startup source and fission detector shall be tested prior to being subjected to core flux and following repair or maintenance to the source.2.~Re orts A report shall be prepared and submitted to the Commission on an annual basis if sealed sources or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.

306 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials'F.Solid Radwaste F.Solid Radwaste 1.The solid radwaste system shall be operated in accordance with a process control program, for the solidification and packaging of wet radioactive wastes to ensure meeting the requirements of 10 CFR 20 and 10 CFR 71 and burial ground requirements prior to shipment of radioactive wastes from the site.1.The Process Control Program shall include surveillance checks necessary to demonstrate

'ompliance with 3.8.F.l.-2.With.the packaging requirements of 10 CFR 20 or burial ground requirements and/or 10 CFR 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site.307 0233p

Switchyard Office Building Service Bldg.Turbine Building Exhaust Pan (32m)Turbine Building Rad-Maste" Bldg.Reactor Building Stack (180m)Reactor Building Ventilation (40m)Pigure 4.8-la GASEOUS RELEASE POINTS AND ELEVATIONS 308

/Ltqutd Dteeherge A>tffueer Ptpee)Q~.eeeefr: f f eer~eu Ill%l fftte 2 fettee 30'

3.8 BASES

Radioactive waste release levels to unrestricted areas should be kept"as low as reasonably achievable" and are not to exceed the concentration limits specified in 10 CFR Part 20.At the same time, these specifications permit the flexibility of operation, compatible with considerations of'ealth and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the concentration limits specified in 10 CFR Part 20.It is expected that by using this operational flexibility and exerting every effort to keep levels or radioactive materials released as low as reasonably achievable in=accordance with criteria established in 10 CFR 50 Appendix I, the annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR Part 20.Specification 3.8.A.1 is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas.will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1)the Section 11.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2)the limits of 10 CFR Part 20.106(e)to the population.

The concentration limit for noble gases is based upon the assumption that Ze-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)Publication 2.Specification 3.8.A.3 is provided to implement the dose requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50.The Limiting Condition for Operation implements the guides set forth the Section 11.A of Appendix I.Specification 3.8.A.4 action statements provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept"as low as is reasonably achievable".

Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by 311 0244p

~(*calculational procedures based on models and data such that t'e actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials.in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April'977.NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.3.8.B AIRBORNE EFFLUENTS Specification 3.8.B.1 is provided to ensure that the dose rate at anytime at the exclusion boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas.The annual dose limits are the doses associated with the concentrations of 10 CFR part 20, Appendix B, Table II, Column 1.These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a member of the public in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR part 20 (10 CFR Part 20.106(b)).

For members of the public who may at times be within the exclusion area boundary, the occupancy of the members of the public will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary.312 0244p

3.8.B AIRBORNE EFFLUENTS (cont'd)The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to<500 mrem/year to the total body or to<3000 mrem/year to the skin.These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to<1500 mrem/year for the nearest cow to the plant.Specification 3.8.B.2 requires that appropriate correction action(s)be taken to reduce gaseous effluent releases if the limits of 3.8.B.1 are exceeded.Specification 3.8.B.5 dose limits is provided to implement the requirements of Section II.C, III.A, and IV of Appendix I, 10 CFR Part 50.The limiting conditions for operation are the guides set forth in Section II.C of Appendix X.Specification 3.8.B.6 action statement provides the required operating flexibility and at the same time implement the guides set forth in Section lV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be.shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

~The ODCM calculational methods used for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109,"Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977, NUREG/CR-1004,"A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides", October 1979, and Regulatory Guide 1.111,"Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.The pathways which are examined in the development of these calculations are: 1)individual inhalation of airborne radionuclides, 2)deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3)deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4)deposition on the ground with subsequent exposure of man.Specification 3.8.B.6 action statement requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.5.313 0244p 4.8.A and 4.8.B BASES (cont'd)gaseous effluents.

These surveillance requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive wastes released to the environment.

Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 6-of these technical specifications.

On , the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such actions as the Commission deems appropriate.

3.8.C and 4.8.C BASES This specification is provided to meet the dose limitations of 40 CFR 190.The specification requires the preparation and submittal of a Special Report whenever the calculated doses form plant radioactive effluents exceed twice the design objective doses of Appendix I.For sites containing up to four reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting.

requirement level.The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for the calendar year to be within 40 CFR 190 limits.For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of five miles must be considered.

3.8.D and 4.8.D MECHANICAL VACUUM PUMP 3 The purpose of isolating the mechanical vacuum pump line is to limit the release of activity from the main condenser.

During an accident, fission products would be transported from the reactor through the main steam lines to the condenser.

The fission product radioactivity would be sensed by the main steam line radioactivity monitors which initiate isolation.

3.8.E and 4.8.E BASES The limitations on removable contamination for sources requiring leak testing, including alpha emitters, based on 10 CFR 70.39(c)limits for plutonium.

This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group.Those sources which are frequently handled are required to be tested more often than those which are not.Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices)are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

315 0244p vk

6.0 ADMINISTRATIVE

CONTROLS k.The radiological environmental monitoring program and the results thereof at least once per 12 months.The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev.1, 1974 and Regulatory Guide 4.1, 1975 at least once per 12 months.m.n.The performance of activities required by the Safeguards Contingency Plan to meet the criteria of 10 CFR 73.40(d)at least once per 12 months.The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.,0~The Process Control Program and implementing procedures for solidification of wet radioactive wastes at least once per 24 months.p>>The Radiological Effluent Manual and implementing procedures, at least once per 12 months.9.AUTHORITY The NSRB shall report to and advise the Manager of Power on those areas of responsibility specified in Sections 6.2.A.7 and 6.2.A.8.10.RECORDS Records of NSRB activities shall be prepared, approved and distributed as indicated below: a 0 Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Manager of Power within 14 days following each meeting.b.Reports of reviews encompassed by Section 6.2.A.7 above, shall be prepared, approved and forwarded to the Manager of Power within 14 days following completion of the review.c~Audit reports encompassed by Section 6.2.A.8 above, shall be forwarded to the Manger of Power and to the management positions responsible for the areas audited within 30 days after completion of the audit.364A 0244p

6.0 ADMINISTRATIVE

CONTROLS 3~.k.Review proposed changes to the Radiological Effluent Manual.Review adequacy of the Process Control Program and Offsite Dose Calculation Manual at least once every 24 months.1.Review changes to the radwaste treatment systems.m.Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendation, and deposition of the corrective action to prevent recurrence to the Director, Nuclear Power and to the Nuclear Safety Review Board.5.~Authorit The PORC shall be advisory to the plant superintendent.

6.Records Minutes shall be kept for all PORC meetings with copies sent to Director;Nuclear Power;Assistant Director of Nuclear Power (Operations);

Chairman, NSRB: 7.Procedures Written administrative procedures for committee operation shall be prepared and maintained describing the method for submission and content of presentations to the committee, review and.approval by members of committee actions, dissemination of minutes, agenda and scheduling of meetings.367 0244p 6.0'ADMINISTRATIVE CONTROL 6.3 Procedures

.E.';ualit Assurance Procedures

-Effluent and Environmental M~ionitorin Quality Assurance procedures shall be established, implemented, and maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, rev.1, June 1974 and Regulatory Guide 4.1, rev.1, April 1975 or Regulatory Guide 4.15, Dec.1977.370 0244p

0 6.0 ADMINISTRATIVE CONTROL 6.9 Process Control Pro ram (PCP)1.'he PCP shall be approved by the Commission'prior to implementation.

2.Changes to the PCP shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change(s)was made.This submittal shall contain: a.Sufficiently.

detailed information to totally support the change.b.A determination that the change did not change the overall conformance of the solidified product to existing criteria.3.Changes to the PCP shall become effective upon review and acceptance by PORC.6.10 OFFSITE DOSE CALCULATIONAL MANUAL (ODCM)1.The ODCM shall be approved by the Commission prior to implementation.

2.Changes to the ODCM shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change(s)was made.This submittal shall contain: a.Sufficiently detailed information to totally support the change.3.Changes to the ODCM shall become effective upon review and acceptance by PORC.6.11 RADIOLOGICAL EFFLUENT MANUAL (REM)2.3.The REM shall be approved by the Commission prior to implementation.

Changes to the REM shall be reviewed by PORC prior to implementation.

Changes to the REM shall be approved by the Commission prior to implementation.

389 0244p

ENVIRONMENTAL TECHNICAL SPECIFICAITONS FOR BROWNS FERRY NUCLEAR PLANT TABLE OF CONTENTS~pa e No.1.0 DEFINITIONS............................................

Deleted 2.0'IMITING CONDITIONS FOR OPERATION......................

Deleted 2.1 Thermal Discharge Limits..........................

2.2 Chemical..........................................

Deleted Deleted 2.2.1 Makeup Water Treatment Plant Spent.Demineralizer Regerants..................

2.2.2~ulorxne...................................

Deleted Deleted 3.0 DESIGN FEATURES AND OPERATING PRACTICES................

Deleted 3.1 I.nemxcal Usage.Deleted 3.1.1 Oils and Hazardous Materials...............

Deleted 3.1.2 Other Chemicals..

3.2 Land Management...................................

3.2.1 Power

Plant Site............

Deleted Deleted Deleted 3.2.2 Transmission Line Right-of-Way Maintenance.

3.3 Onsite

Meteorological Monitoring..................

Deleted 4.0 ENVIRONMENTAL SURVEILLANCE.............................

Deleted 4.1 Ecological Surveillance...........................

4 kl L~1~1 AU1OI Xc~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~4~1~2 DloLlc~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~4.1.3 Special Studies............................

Deleted Deleted Deleted Deleted 4.2 Radiological Environmental Monitoring Program......

Deleted 0 0244p 0

3.2.2 Transmission

Line Ri ht-of-Wa Maintenance

~Ob ective The sole purpose of this section is to provide reporting requirements (to USNRC)on herbicide usage, if any, for purposes of right-of-way maintenance regarding only those transmission lines under USNRC's jurisdiction for the Browns Ferry Nuclear Plant.A statement as to whether or not herbicides have been used in maintaining rights-of-way for those transmission lines associated with the Browns Ferry Nuclear Plant shall be provided.If herbicides have been used, a description of the types, volumes, concentrations, manners and frequencies of application, and miles or rights-of-way that have been treated shall be included.Re ortin Re uirements Information as specified above shall be provided in the Annual Operating Report (Appendix A, Section 6.7.1(b)).

Bases Vegetation growth on a transmission line right-of-way must be controlled in such a manner that it will neither interfere with safe and reliable operation of the line or impede restoration of service when outages occur.Vegetation growth is controlled by mechanical cutting and the-limited use of herbicides.

Selected chemicals approved by EPA for use as herbicides are assigned (by EPA)label instructions which provide guidance on and procedures for their use.0244p ENCLOSURE 2 RADIOLOGICAL EFFLUENT MANUAL (REM)

RADlOLOGICAL EFFLUENT MANUAL (REM)For the Browns Ferry Nuclear Plant Limestone County, Alabama P'ennessee Valley Authority 0232p RADIOLOGICAL EFFLUENT MANUAL 0 SECTION TABLE OF CONTENTS PAGE NO.REV.NO.A.B.C.D.E.F.INTRODUCTION RESPONSIBILITIES 1.LIQUID EFFLUENTS SAMPLING AND ANALYSIS PROGRAM 2.LIQUID WASTE TREATMENT 1.GASEOUS EFFLUENTS SAMPLING AND ANALYSIS PROGRAM 2.GASEOUS WASTE TREATMENT RADIOLOGICAL ENVIRONMENTAL MONITORING 1.SAMPLING AND ANALYSIS 2.LAND USE CENSUS 3.INTERLABORATORY COMPARISON PROGRAM REPORT CONTENT 1.ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2.SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 3.SPECIAL REPORTS (RADIOLOGICAL ENVIRONMENTAL MONITORING)

A-1 B-1 C-1 C-5 D-1 D-5 E-1 E-3 E-5 F-1 F-2 F-3 0232p A.INTRODUCTION The purpose oF this manual is to provide the sampling and analysis programs which provide input to the ODCM for calculating liquid and gaseous effluent concentrations and offsite doses.Guidelines are provided for operating radioactive waste treatment systems in order that offsite doses are kept as-low-as-reasonable-achievable (ALARA).The Radiological Environmental Monitoring Program outlined within this manual provides confirmation that the measurable concentrations of radioactive material released as a result of operations at the Browns Ferry Plant are not higher than expected.In addition, this manual outlines the information required to be submitted to the NRC.in both the Annual Radiological Environmental Operating Report and the Semiannual Radioactive Effluent Release Report.A-1 0232p B.RESPONSIBILITIES All changes to this manual shall be reviewed by the Plant Operations Review Committee prior to implementation.

All changes to this manual shall be approved by the NRC prior to implementation.

It shall be the responsibility of the Plant Manager to ensure that this manual is used in performance of the surveillance requirements and administrative controls of the Technical Specifications.

B-1 0232p

1 C.LI UID EFFLUENT SAMPLING AND ANALYSIS PROGRAM C.l Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with Table C-l.The results of the analysis, of samples collected from release points shall be used with the calculational methodology in the ODCM to assure that the concentrations at the point of release are maintained within the limits of the Technical Specifications.

C-l 0232p TABLE C-1 RADIOACTIVE LI UID HASTE SAMPLING AND ANALYSIS PROGRAM LIQUID RELEASE TYPE Batch Waste ReleasesAMPLING FRE UENCY Each Batch MINIMUM ANALYSIS FRE UENCY Each Batch Prior to Release TYPE OF ACTIVITY ANALYSIS Principal Gamma EmittersYSTEM DESIGN CAPABILITY LOWER LIMIT OF DETECTION-(LLD)(Ci/ml)One Batch per Month Monthly Dissolved and Entrained Gases'E 5<>>Monthly Proportional Composite"'onthly Tritium Gross a 1 E-5 1 E-7 Quarterly Proportional Compositeuarterly Sr-89, Sr-90 Fe-55 5 E-8 1 E-6 C-2 0232p TABLE NOTATION-TABLE C-1 (1)A batch release is the discharge of liquid wastes of a discrete volume.The discharge shall be thoroughly mixed prior to sampling.(2)A proportional composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant and is representative of the liquid discharged.

(3)The LLD is defined, for the purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a new count (above system background) that will be detected with 95K probability with only 5X probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which may include radiochemical separation):

4.66 sb LLD=E f V f 2.22 x 10 Y exp (-Xdt)Where: LLD is the"a priori" lower limit of detection as defined above (as microcuries per unit mass or volume),"si, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegrat'ion), V is the sample size (in units of mass or volume), 2.22 x 10's the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), X is the radioactive decay constant for the particular radionuclide, and ht for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.Typical values of E, V, Y, and ht should be used in the calculation.

It should be recognized that the LLD is defined as a priori (before the fact)limit representing the capability of a measurement system and not as an a posteriori (after the facti limit for a particular measurement.

C-3 0232p

TABLE NOTATION-TABLE C-1 (Continued)

(4)The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:

Zn65, Co60, Cs137, Mn54, Co58, Cs134, Ce141, Ce144, Mo99, and Fe59 for liquid releases.This list does not mean that only these nuclides are to be detected and reported.Other nuclides detected within a-95K confidence level, together with the above nuclides, shall also be identified and reported as being present.Nuclides which are below the LLD for the analysis may not be reported as being present at the LLD Level for that nuclide.I-131 shall have a LLD of<1 E-6.(5)Gamma Emitters Only.C-4 0232p C.2 LI UID RADIOACTIVE WASTE TREATMENT This section requires that the appropriate portions of the liquid radwaste treatment system be used when specified.

This provides assurance that the releases of radioactive materials in liquid effluents will be kept"as low as is reasonably achievable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

This section also requires submittal of a special report if the limiting values are exceeded and unexpected failures of non-redundant radwaste processing equipment halt waste treatment.

The liquid radwaste system materials in liquid wastes the projected monthly dose 0.21 mrem to any organ per Specification).

shall be used to reduce the radioactive prior to their discharge from the site when would exceed 0.06 mrem to the total body or unit (see Figure 4.8-1b, Technical Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days, in accordance with the ODCM.With radioactive liquid waste being discharged for more than 31 days without treatment and when the projected dose is in excess of limits specified above prepare and submit the Special Report pursuant to Section 6.7.2 of the Technical Specifications.

C-5 0232p D.GASEOUS EFFLUENTS SAMPLING AND ANALYSIS PROGRAM D.l Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with Table D-1.Dose rates shall be determined to be within limits of the Technical Specifications using methods contained in the ODCM.Samples of offgas system effluents shall be analyzed at least weekly to determine the identity and quantity of the principal radionuclides being released.D-1 0232p

E D-1 RADIOACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM GASEOUS RELEASE TYPE SAMPLING FRE UENCY MINIMUM ANALYSIS FRE UENCY TYPE OF ACTIVITY ANALYSIS SYSTEM DESIGN CAPABILITY LOHER LIMIT OF DETECTION (Ci/ml)A.Containment Purge Prior to Each Prior to Each Purge Principal Gamma Purge Grab Sample Emitters'H-3 1E-4E-6 B.1.Stack Grab Sample Monthly"'rincipal Gamma Emitters"'.Building Grab Sample Ventilation a.Reactor/Turbine b.Turbine Exhaust c.Radwaste Monthly'"'-3 1E-6 C.All Release Points Listed in B.Above Continuous Sampler Continuous Sampler Charcoal Sample Heekly'"'articulate Sample Heekly'"'-131 Principal Gamma fmitters'and I-131 lE-12E-11 1E-12ontinuous Sampler Continuous Sampler Composite Particulate Gross Alpha Sample Monthly Composite Particulate Sr-89, Sr-90 Sample Quarterly 1E-11 1E-11 0232p D-2

TABLE NOTATION-TABLE D-1 (1)The LLD is defined, for the purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a new count (above system background) that will be detected with 95K probability with only 5'lo probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which may include radiochemical separation):

LLD=4.66 sb E<V<2.22 x 10 b'<Y>'<exp (-Xht)Where: LLD is the"a priori" lower limit of detection as defined above (as microcuries per unit mass or volume), si, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22 x 10's the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),'A is the radioactive decay constant for the particular radionuclide, and Dt for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.Typical values of E, V, Y, and At should be used in the calculation.

it should be recognized that the LLD is defined as an a priori ibe<ore the fact)limit representing the capability of a measurement system and not as an a posteriori iafter the fact)limit<or a particular measurement.

(2)When samples are taken more often than that shown, the minimum detectable concentrations can be correspondingly higher.D-3 0232p TABLE NOTATION-TABLE D-1 (Continued)

(3)The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported.Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.(4)Analysis shall also be performed if the radiation monitor alarm exceeds the setpoint value.D-4 0232p D.2 GASEOUS RAD10ACTIVE WASTE TREATHENT Doses due to gaseous releases to areas at and beyond the site boundary shall be projected in accordance with the ODCM at least once per 31 days.D-5 0232p

E.RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLING AND ANALYSIS The radiological monitoring program required by this section provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation.

This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measureable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.The radiological environmental monitoring program shall be conducted as specified in Table E-l.The radiological environmental pursuant to Table E-1 from the the ODOM and shall be analyzed and the detection capabilities monitoring samples shall be collected locations given in the table and figure in pursuant to the requirement of Table E-1 required by Table E-2.With the radiological environmental monitoring program not being conducted as specified in Table E-l, in lieu of a LER, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability or malfunction of automatic sampling equipment.

If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.All deviations form the sampling schedule shall be reported in the Annual Radiological Environmental Operating Report.With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table E-3 when averaged over any calendar quarter, in lieu of a LER, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a report which identifies the cause(s)for exceeding the limit(s)and defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of the Technical Specifications.

When more than one oF the radionuclides in Table E-3 are detected in the sampling medium, this report shall be submitted if: Conc(1)+Conc(2)+...)1.0 Limit(1)Limit(2)When radionuclides other than those in Table E-3 are detected and are result of plant effluents, this report shall be submitted if the potential annual dose to a member of the public is equal to or greater than the calendar year limits of the Technical Specification.

E-1 0232p Such reports are not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual'adiological Environmental Operating Report.With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by-Table E-1 identify locations for obtaining replacement samples, if available, and add them to the radiological environmental monitoring program within 30 days.The specific locations from which samples were unavailable may then be deleted from the monitoring program.In lieu of a LER, identify the cause of the unavailability of samples and identify the new location(s), if available, for obtaining replacement samples in the next Annual Radiological Environmental Operating Report and also include a revised figure(s)and table(s)for the ODCM reflecting the new locations.

The provisions of Technical Specification 1.0.C are not applicable.

The detection, capabilities required by Table E-2 are state-of-the-art for routine environmental measurements in industrial laboratories.

It should be recognized that the LLD is defined as an a priori (before the Pact)limit representing the capability of the measurement system and not as an a posteriori (after the fact)limit fol particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions, Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.E-2 0232p E.2 LAND USE CENSUS A land use census shall be conducted and shall identify'he location of the nearest milk animal, the nearest residence and the nearest garden~'<of.greater than 500 square feet producing fresh leafy vegetables in each oF the 16 meterological sectors within a distance of five miles.(For elevated releases.as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles).With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the maximum value currently being calculated in section D.2 of this manual, in lieu of a LER, identify the new locations in the next Annual Radiological Environmental Operating Report.With a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway)20 percent greater than at a location from which samples are currently being obtained in accordance with section E.l, add the new location(s) to the radiological environmental monitoring programs within 30 days if the owner consents.The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s)(via the same exposure pathway)may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

In lieu of a LER, identify the new location(s) in the next Annual Radiological Environmental Operating Report and provide a revised figure(s)and table for the ODCM reflecting the new location(s).

Broad leaf vegetation sampling may be performed at the site boundary in the direction section with the highest D/Q in lieu of the garden census.E-3 0232p 0 The land use census shall be conducted at least once per calendar year between the dates of April 1 and October 1 using the following techniques:

a.Within a 2 mile radius from the plant or within the 15 mrem per year.isodose line, whichever is larger, enumeration by a door-to-door or equivalent counting technique.

b.Within a 5 mile radius from the plan, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities or other reliable sources.This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring program are made if required by the results of this census.The best survey information from the door-to-door, mail, telephone, aerial or consulting with local agricultural authorities shall be used.This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year)of leafy vegetation assumed in Regulatory Guide 1.109 for consumption by a child.To determine this minimum garden size, the following assumptions were used: 1)that 20%of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2)a vegetation yield of 2 kg/square meter.E-4 0232p E.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with the ODCM (or participants in the EPA cross check program shall provide the EPA program code designation for the unit)shall be included in the Annual Radiological Environmental Operating Report.With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.E-5 0232p 0 TABLE E-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sam le 3.WATERBORNE a.Surface Number of Samples and~51 N 2 locations Sampling and Collection Fre uenc Composite'ample collected over a period of<31 days.Type and Frequency of Anal sis Gamma isotopic analysis of each composite sample..Tritium analysis of com-posite sample at least once per 92 days.b.Drinking Minimum of 1 downstream location, or all water supplies within 10 miles downstream which are taken from the Tennessee River.Composite'ample collected'ver a period<31 days.Gross beta and gamma isotopic analysis of each composite sample.Tritium analysis of composite sample at least once per 92 days.c.Sediment d.Ground'inimum of 1 location At least once per 184 days.Gamma isotopic analysis of each sample.'Sample locations are shown in the ODCM.'Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.'Composite samples shall be collected over a period of<14 days forI if drinking water is obtained within 3 miles downstream of the plant.'Ground water movement in the area has been determined to be from the plant site toward, the Tennessee River.Since no drinking water wells exist between the plant and the river, ground water will not be monitored.

0232p E-7 TABLE E-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sam le 4.INGESTION a.Milk b.Fish Number of Samples and Sam le Locations' locations 2 samples Sampling and Collection Fre uenc At least once per 15 days when animals are on pasture;at least once per 31 days at other times.One sample in season, or at least once per 184 days if not seasonal.One sample of commercial and game species.Type and Frequency of Anal sis I-131 analysis of each sample.Gamma isotopic analysis at least once per 31 days.Gamma isotopic analysis on edible portions.c.Food Products'locations At least once per year at time of harvest.Gamma isotopic analysis on edible portion.'Sample locations are shown in the ODCM.'Since water from the Tennessee River in the immediate area downstream is not used for irrigation purposes, the sampling of food products (primarily broad leaf vegetation) is not required unless milk sampling is not performed.

0232p

TABLE E-2 MAXIMUM VALUES FOR THE LONER LIMITS OF DETECTION (LLD)"'nalysis Airborne Particulate Nater or Gas (pCi/1)(pCi/m')Fish Mi 1 k (pCi/kg, wet)(pCi/1)Food Products (pCi/kg, wet)Sediment (pCi/kg, dry)gross beta H-3 Mn-54 Fe-59 Co-58, 60 Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2000 15 30 15 30 30 15 15 18 60 15 1 x10 N.A.N.A.N.A.N.A.N.A.N.A.N.A.7x10'x 10'x 10'.A.N.A.N.A.130 260 130 260 N.A.130 150 N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.15 18 60 15 N.A.N.A.N.A.N.A.N.A.N.A.N.A.60 60 80 N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.150 180 N.A.N.A.0232p E-9

TABLE E-2 (Continued)

TABLE NOTATION The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95K probability with 5X probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which may include radiochemical separation):

LLD=4.66 si, E V-2.22"f Y f exp (-"Aht)Where: LLD is the"a priori" lower limit of detection as defined above (as picocurie per unit mass or volume), si, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable), X is the radioactive decay constant for the particular radionuclide, and ht is the elapsed time between sample collection (or end of the sample collection period)and time of counting (for environmental samples, not plant effluent samples).It should be recognized that the LLD is defined as a priori ibefore the fact)limit representing the capability of a measurement system and not as an a osteriori (after the fact)limit for a particular measurement.

E-10 0232p TABLE E-2 (Continued)

TABLE NOTATION b.The LLD for anal sis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L.If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/L for I-131.c.Other peaks which are measurable and identifiable, together with the radionuclides in Table E-3, shall be identified and reported.E-ll 0232p TABLE E-3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels A~nal sis H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 I-131 Cs-134 Cs-137 Ba-La-140 Hater~(Ci/1>2 x 10"" 1 x10'x 10'x 10'x 10'x10'x10'0 50 2 x 10'irborne Particulate

~G(C I'>N.A.N.A.N.A.N.A.N.A.N.A.0.9 10 20 N.A.Fish (Ci/K wet)N.A.3 x 10'x 10'x 10'x 10'x 10'.A.N.A.1 x10'x 10'i 1 k~(Ci/1)N.AD N.A.N.A.N.A.N.A.N.A.60 70 3x10 Food Products (Ci/K wet)N.A.N.A.N.A.N.A.N.A.1 x 10'x10" 2 x 10'.A.'For drinking water samples.This is 40 CFR Part 141 value.0232p E-12

F.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT A report on the radioactive discharges released from the site during the previous 6 months of operation shall be submitted to the Director of the'egional Office of Inspection and Enforcement within 60 days after January 1 and July 1 of each year.The report shall include summary of the quantities of radioactive liquid and gaseous effluents released and solid waste shipped from the plant as delineated in Regulatory Guide 1.21, Revision 1,"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.The report shall include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly basis following the format of Appendix B thereof.Calculated offsite dose to members of the public resulting from the release of liquid and gaseous effluents and their subsequent dispersion in the river and atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision 1.The Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the report period (a)container volume, (b)total curie quantity, (specify whether determined by measurelnent or estimate), (c)principal radionuclides (specify whether determined by measurement or estimate), (d)sources of waste and processing employed (e.g.dewatered spent resins, compacted dry waste, etc.), (e)type of container (e.g., LSA, Type A, Type B, large quantity), and (f)solidification agent or absorbant (e.g.concrete, urea formaldehyde, etc.).F-2 0232p F.3 SPECIAL REPORTS (Radiolo ical Environmental Monitorin)If measured levels of radioactivity in an environmental sampling medium are determined to exceed the reporting level values of Table E-3 when averaged over any calendar quarter sampling period, a report shall be submitted to the Commission pursuant to Section E.l of this Manual.F-3 0232p

ENCLOSURE 3 DESCRIPTION AND JUSTIFICATION BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 Descri tion of Chan e The changes described below effect Appendix A of the Technical Specifications.

The changes are referenced by section number and refer to all three units unless stated otherwise.

Under section 1.V several new definitions were added.Additional definitions were added to section 1.0 as subparts 1.AA to 1.KK.The Definition of Surveillance Interval was renumbered 1.LL and expanded to require meeting requirements only on OPERABLE equipment and to define compliance by performance of Surveillance Requirements.

Table 1.1 was added to define Surveillance Frequency Notations.

Current Section 3/4.2.D was expanded to include additional Gaseous Effluent Monitoring Instrumentation and was renumbered as Sections 3/4.2.K.The current Specifications required Calibration, Functional testing and Operability requirements for the Offgas Post Treatment Monitor.The new Section requires demonstration of Channel Operability and testing of the Stack Honitors, the Reactor/Turbine Bldg.Ventilation Monitors, the Turbine Bldg.Vent Monitors, the Radwaste Bldg.Vent Monitors, the Offgas Hydrogen Analyzers, and the Offgas Post Treatment Monitors.These requirements are outlined in Tables 3.2.K and 4.2.K.A new set of requirements for Liquid Effluent Monitoring Instrumentation was added as 3/4.2.D.This Section requires the demonstration of Channel Operability and Test Requirements for the Liquid Radwaste Effluent Honitor, the Liquid Radwaste Effluent Flow Rate Monitor, the RHR Service Water Monitors, and the Raw Cooling Water Monitors.These requirements are outlined in TABLES 3.2.D and 4.2.D which replaces the current tables with these numbers.Additional Bases for Sections 3.2 and 4.2 were added to pages 115A and 118 of the Unit 1 and 2 Technical Specifications and to pages 113 and 116 of the Unit 3 Technical Specifications to account for the RETS changes.The definition of Dose Equivalent Iodine was removed from page 179 of the unit 1 and 2 Specifications and page 190 of the unit 3 Specifications since it is now defined in the definitions (1.II).Specification 3.8.A.l was changed to set the limit for dissolved and entrained noble gases at 2E-4 uCi/ml in lieu of the 10 CFR 20 Appendix B limits;The yearly limit for tritium and noble gases given in the current 3.8.A.2 was therefore deleted and replaced by an action statement should a release exceed the 3.8.A.1 limits.Section 4.8.A.1 remained the same while 4.8.A.2 was changed to incorporate the current 4,8.A.2 and 4.8.A.3 requirements.

The table referenced in the current 4.8.A.3 was moved to the Radiological Effluent Hanual (REM)in an expanded form.

The current Surveillance Requirement 4.8.A.5 was renumbered as 4.8.A.3 with only minor word changes.Current Specification 3.8.A.3 which requires continuous monitoring of flow and activity for liquid releases has been removed from Section 3.8 since it is covered in Table 3.2.D.The Surveillance Requirement currently numbered 4.8.A.4 which requires the radwaste monitor be calibrated quarterly, have a channel check monthly and a daily sensor check has been deleted from Section 4.8 since these requirements are now covered in Section 4.2.D and it'associated tables.Current Specification 3.8.A.4 which requires that liquid radwaste be processed if a quarterly limit of 1.25 curies could be reached has been included in the REM.The curie limit was replaced by a dose limit projection.

Current Specification 3.8.A.5 which limits the activity in a liquid radwaste tank to 10 curies has been modified to include temporary storage tanks but now excludes tritium and dissolved/entrained noble gases.Proposed Specification 3.8.A.6 was added and outlines operational practices based on tank activities.

A new surveillance requirement, 4.8.A.6, has been added to assure these tank limits are not exceeded.A new specification which provides limits for quarterly and yearly dose commitments to the public has been added as 3.8.A.3.Reporting requirements for 3.8.A.3 are given in 3.8.A.4.Proposed surveillance requirements for meeting LCO's 3.8.A.1 and 3.8.A.3 are included as 4.8.A.4 and 4.8.A.5 respectively.

Current Specification 3.8.8.1 which sets the release rate for gross activity, except for I-133 and particulates with half-lives greater than eight days at ((}1/0.13)+((}2/1.46)<=l has been changed to proposed Specification 3.8.8.1.a.

The new limits are based on dose rates.New Specification 3.8.B.2 provides reporting requirements for exceeding these limits.Current Specification 3.8.8.2 which sets the release rate for I-133 and particulates with half-lives greater than eight days to an instantaneous value of ((}3/0.33)+((}4/44)<=1 has been changed to proposed Specification 3.8.B.l.b.

The new limit is based on dose rates.Specification 3.8.B.4 which limits this type of release to 0.8 uCi/sec averaged over a quarter and 0.4 uCi/sec for a one week period have been replaced by Specification 3.8.B.5.The new limits which are based on dose rates at and beyond the site boundary, envelop the current requirements by adopting the NUREG 0473 requirements as given in 10 CFR 50 Appendix I.New Specification 3.8.B.2 and 3.8.B.6 provides reporting requirements if these limits are exceeded.Current Specification 3.8.B.3 which limits gross activity in gaseous releases to 0.10 Ci/sec averaged over a quarter and 0.05 Ci/sec in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> has been replaced with 3.8.8.1.The new limits will be based on dose rates.Specification 3.8.8.5 which required that appropriate corrective action be taken if current Specification 3.8.B limits are exceeded has been replaced by 3.8.B.2.

Current Specification 3.8.8.6 which required monitoring and recording of gaseous releases has been deleted and the requirements incorporated in the Tables of 3/4.2 and the requirements in the REH.Current Specifications 3.8.8.7 and 3.8.8.8 which require that a minimal number of monitors and isolation devices be operable for the Stack, Reactor and Turbine building vents and radwaste building vents or grab samples or temporary monitors have been incorporated in the tables of Section 3/4.2 and are therefore deleted from this section.Current Surveillance Requirement 4.8.8.l.a remains the same except that the frequency has been changed from hourly to once per shift and the required instruments are referenced.

These changes are consistent with NUREG 0473 requirements and the frequencies as specified in the REH.The intent of 4.8.8.1.b remains the same but there are word changes to account for the new LCO's'.Current Surveillance Requirement 4.8.8.2 is the same except that Table 4.8.8 is now in the REH.The new 4.8.8.2 also states that the dose rates are to be determined according to the methodology in the OOCH.Current Surveillance requirement 4.8.B.3 has been deleted and moved unchanged to the REM.Current Requirement 4.8.8.4 which required quarterly calibration of gaseous monitors, monthly channel checks and daily sensor checks has been deleted from this section since these requirements are now contained in Sections 3/4.2.D and 3/4.2.K.I Specifications 3.8.8.3 and 3.8.8.4 are new requirements which incorporate 10 CFR 50 Appendix I limits and associated reporting requirements.

Specifications 3.8.8.7, 3.8.8.8, 3.8.8.9 and 3.8.8.10 are new requirements.

Surveillance requirements 4.8.8.3, 4.8.8.4 and 4.8.8.5 are new.These requirements outline calculational methods, Charcoal Absorber Operational Requirements and limiting values for hydrogen concentrations in the offgas as well as monitoring requirements.

A total dose commitment to a real individual has been added as section 3/4.8.C and the current 3/4.8.C entitled"Mechanical Vacuum Pump" has been renumbered without change as section 3/4.8.0.The current Miscellaneous Radioactive Haterials Sources Section has been renumbered from 3/4.8.D to 3/4.8.E and contains changes which adopt Standard Technical Specification requirements as described in the following discussion.

The current LCO entitled"Source Leakage Test" (3.8.0.1)has been renumbered as 3.8.E.l and replaces".......those quantities of byproduct materials listed in 10 CFR 30.71 Schedule 8 and all other sources, including alphas emitters, in excess of O.l microcuries,..." with a specific value of 100 microcuries of beta and/or gamma emitters or 5 microcuries of alpha emitters.Current Surveillance Requirement 4.8.0.l.a is renumbered unchanged as 4.8.E.l.a.

The current Surveillance requirement 4.8.0.l.b exempts stored sealed sources from testing except prior to use or transfer or the absence of a test certificate on transferred source.This requirement as been renumbered as 4.8.E.l.b and changes the classification exempt from testing to sealed sources not previously subjected to core flux.The current 4.8.0.l.c requirement is renumbered as 4.8.E.l.c with only minor word rearrangements and no content changes.A new reporting requi rement has been added as 4.8.E.2.A new Section on the processing of solid Radwaste has been added as 3.4.8.F.This requires compliance with the Process Control Program.

Two new Figures 4.8-la and 4.8-1b have been added to show the locations of typical gaseous release points and their elevations and the Land Site'oundary.All of these changes have resulted in page 310 of the unit 3 Technical Specifications being left blank.Additionally, the Bases for Sections 3/4.8 have been rewritten to reflect the numberous changes to these sections.Section 6.2.A.8.1 has been revised to allow the use of Regulatory Guides 1.21 Rev 1 and 4.1.Audits of the ODCH, PCP, and REM have been added to Section 6.2.A.8 as items n., o.and p.Section 6.2.8.4 has been revised to include reviews by PORC of changes to the REH, PCP, ODCM, and Radwaste Treatment systems.PORC is also to review unplanned onsite releases.These requirements were added as items j., k., l.and m: The Procedures Section, 6.3.A, was revised to include REH implementing procedures, the ODCH and the PCP.These requirements were added as items 12, 13, and 14.Also, 6.3.E was added to require Quality Assurance procedures for Radiological Effluent Monitoring.

Section 6.7.3.A entitled"Radioactive Effluent Release Report" was moved to the REH.Section 6.9 was added to describe the Process Control Program, while new sections 6.10 describes the Offsite Dose Calculation Manual and 6.11 describes the Radiological Effluent Manual.All of the Requirements of Appendix B, with the exception of"Transmission Line Right-of-Hay" have been incorporated into the REH.Reason for Chan e These proposed changes are in response to NUREG-0473.

Justification of Pro osed Chan e The proposed technical specification and REH requirements for radiological effluent monitoring are based on NUREG-0473, and meetings between TVA and NRC staff held in Hay 1986, at Browns Ferry Nuclear Plant, and in July 1986, in Bethesda, MD.The NUREG-0473 changes are submitted in both the technical specifications and the Radiological Effluent Manual, as suggested by NRC staff.The creation of the REH and the division of the NUREG requirements conforms to the intent of the Technical Specification Improvement Program, and is patterned after such approved documents for the Haddem Neck Plant.Since this change imposes additional TS restrictions as required by NUREG-0473, TVA has concluded that none of these proposed TS changes will reduce the margin of nuclear safety.0147y ENCLOSURE a DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 Descri tion of Re uest The proposed amendment would change the Technical Specifications (TS)of BFN units 1, 2, and 3 to bring them into compliance with Appendix I of 10 CFR Part 50.It provides new radiological Effluent Technical Specifications sections defining limiting conditions for operation and surveillance requirements for radioactive liquid and gaseous effluent monitoring:

Concentration, dose and treatment.

of liquid, gaseous and solid wastes;total dose;radiological environmental monitoring that consists of a monitoring program, land use census, and interlaboratory comparison program.This change would also incorporate into the Technical Specifications the bases that support the operation and surveillance requirements.

In addition, some changes would be made in administrative controls, specifically dealing with the process control program, the offsite dose calculation manual, and a new document entitled"Radiological Effluent Manual (REM)~" The proposed amendment would supersede the current Radiological Effluent Technical Specifications in the Appendix"B" Technical Specifications.

Basis for Pro osed No Si nificant Hazards Consideration Determination The Commission has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50,92(c).A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with proposed amendment would'not:

(1)involve a significant increase in the.probability or consequences of an accident previously evaluated; or (2)create the possibility of a new or different kind of accident from any accident previously evaluated; or (3)involve a significant reduction in a margin of safety.1.This amendment will not increase the probability or consequences of an accident previously evaluated since additional TS requirements are being proposed.The Commission, in a revision to"Appendix I, 10 CFR Part 50 required a licensees to improve and modify their radiological effluent systems in a manner that would keep releases of radioactive material to unrestricted areas during normal operation as low as is reasonably achievable.

In complying with this requirement, it becomes necessary to add additional restrictions and controls to the Technical Specifications to assure compliance.

This caused the addition of Technical Specification described above.2.This amendment will not eliminate or modify any protective functions, nor permit any new operational conditions and therefore does not create the possibility of a new or different kind of accident.

3.This amendment will not result in a significant reduction in a margin of safety for the reasons given above and because the changes reflect the requirements of Appendix I of 10 CFR 50.Since the application for amendment involves proposed changes that are encompassed by the criteria for which no significant hazards consideration exist, and the specifications meet the Commission mandated release of"as low as reasonably achievable", TVA proposes to determine that the proposed amendments do not involve a safety hazards consideration.

ATTACHMENT TO LICENSE AMENDMENT NO.132 FACILITY OPERATING LICENSE NO.DPR-33 DOCKET NO.50-259 Replace, the following pages of the Appendix A Technical Specifications with the enclosed pages.The revised areas are indicated by marginal lines.~Pe ee 11 ill lv V Vl Vl1 V111 7 7A 7B 7C 51 52 54 54A 76 76A 84A 84B 103 103A 108A 108B 115A 118 179 281 282 283 284 285 286 287 288 289 290 290A 291 291A 291B 291C 291D 334A 337 338 340 355 359 Revise Appendix B as follows: Table of Contents 2 pp.0 0

Section Introduction

.TABLE OF CONTENTS~pa e Wo.1.0 1.1/2.1 1.2/2.2 Defxnitxons SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS Fuel Cladding Integrity Reactor Coolant System Integrity.LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 27 3.1/4.1 3.2/4.2 Reactor Protection System Protective Instrumentation

.31 50 A.Primary Containment and Reactor Building Isolation Functions B.Core and Containment Cooling Systems-Initiation and Control 50 50 C.Control Rod Block Actuation 51 D.Radioactive Liquid Effluent Monitoring Instrumentation 51 E.Drywell Leak Detection.F.Surveillance Instrumentation

.52 52 G.Control Room Isolation.52 H.Flood'rotection

.53"'.Meteorological Monitoring Instrumentation 53 J.Seismic Monitoring Instrumentation

.54 K.Radioactive Gaseous Effluent Instrumentation Monitoring 54 3.3/4.3 Reactivity Control A.Reactivity Limitations

.B.Control Rods.120 120 121 C.Scram Insertion Times 124 Amendment No.132 0241p 0

Section 3.4/4.4 3.5/4.5 D.Reactivity Anomalies E.Reactivity Control F.Scram Discharge Volume Standby Liquid Control System A.Normal System Availability

.B.Operation with Inoperable Components

.C.Sodium Pentaborate Solution Core and Containment Cooling Systems A.Core Spray System (CSS)B.Residual Heat Removal System (RHRS)(LPCI and Containment Cooling)C.RHR Service Mater System and Emergency Equipment Cooling'Water System (EELS)D.Equipment Area Coolers E.High Pressure Coolant Injection System (HPCIS)~~~~~~~~~~~~~~~~~P~ae No.125 126 126 135 135 136 137 143 143 145 151 154 154 F.Reactor Core Isolation Cooling System (RC I CS)~~~~~~~~~~~~e~~~~156 G.Automatic Depressurization System (ADS)~~~~~~e~~~~~~~~~~~157 H.Maintenance of Filled Discharge Pipe.I.Average Planar Linear Heat Generation Rate.J.Linear Heat Generation Rate (LHGR)158 159 159 K.Minimum Critical Power Ratio (MCPR)160 3.6/4.6 L.APRM Setpoints M.Reporting Requirements

.Primary System Boundary~~.160A 160A 174 0 A.Thermal and Pressurization Limitations

.B.Coolant Chemistry Amendment No.132 174 176 0241p Ct~~%0 Section~Pa e No.C.Coolant Leakage D.Relief Valves 180 181 E.Jet Pumps 181 F.Recirculation Pump Operation.G.Structural Integrity.182 183 H.Seismic Restraints, Supports and Snubbers....185 3.7/4.7 Containment Systems 227 A.Primary Containment 227 B.Standby Gas Treatment System...........236 C.Secondary Containment 240 D.Primary Containment Isolation Valves.......242 E.Control Room Emergency Ventilation

........244 F.Primary Containment Purge System.........246 G.Containment Atmosphere Dilution System (CAD)...248 H.Containment Atmosphere Monitoring (CAM)Sys H~Analyzer tern 249 3.8/4.8 Radioactive Materials A.Liquid Effluents.B.Airborne Effluents.C.Radioactive Effluents-Dose.281 281 283 286 D.Mechanical Vacuum Pump.286 E.Miscellaneous Radioactive Materials Sources...287 F.Solid Radwaste.289 3.9/4.9 Auxiliary Electrical System 292 A.Auxiliary Electrical Equipment B.Operation with Inoperable Equipment C.Operation in Cold Shutdown.292 295 298 t 3.10/4.10.Core Alterations

.A.Refueling Interlocks

.302 302 Amendment No.132 0241p W w II Section~Pa e No.B.Core Monitoring 305 C.Spent Fuel Pool Water 306 D.Reactor Building Crane 307 E.Spent Fuel Cask 307~~F.Spent Fuel Cask Handling-Refueling Floor.3.11/4.11 Fire Protection Systems A.High Pressure Fire Protection System.B.CO>Fire Protection System.C.Fire Detectors D.Roving Fire Watch E.Fire Protection Systems Inspection F.Fire Protection Organization

.G.Air Masks and Cylinders H.Continuous Fire Watch and Burning in the I.Open'Flames, Welding Cable Spreading Room Major Design Features 5.0~a~~5.1 Site Features 5.2 Reactor 5.3 Reactor Vessel 5.4 Containment v~a~~~I~~~~~~5.5 Fuel Storage.5.6 Seismic Design.Administrative Controls 6.0 6.1 Organization

.1v Amendment No.132 024lp a~~~308 315 315 319 320 321 322 322 323 323 323 330 330 330 330 330 330 331 332 332 0

Section 6.2 Review and Audit.~Pa e No.333 6.3 Procedures

6.4 Actions

to be Taken in the Event of a Reportable Occurrence in Plant Operation.338 346 6.5 Actions to be taken in the Limit is Exceeded Event a Safety 346 6.6 Station Operating Records 6.7 Reporting Requirements

6.8 Minimum

Plant Staffing 346 349 358 Amendment No.132 024lp P

LIST OF TABLES Table1.1 3.1.A 4.1.A Title Surveillance Frequency Notation Reactor Protection System (SCRAM)Instrumentation Requirements Reactor Protection System (SCRAM)Instrumentation Functional Tests Minimum Functional Test Frequencies for Safety Instrumentation and Control Circui ts~Fa e No.7c 33 37 4.1.B Reactor Protection System (SCRAM)Instrument Calibration Minimum Calibration Frequencies for Reactor Protection Instrument Channels 40 3.2.A Primary Containment and Reactor Building Isolation Instrumentatxon 55 3.2.B Instrumentation that Initiates or Controls the Core and Containment Cooling Systems 62 3.2".C Instrumentation that Initiates Rod Blocks 73 3.2.D Radioactive Liquid Effluent Monitoring Instrumentation 76 t 3.2.E 3.2.F Instrumentation that Monitors Leakage Into Drywell Surveillance Instrumentation

.77 78 3.2.G Control Room Isolation Instrumentation

.81 3.2eH Flood Protection Instrumentation

.82 3.2.I 3.2eJ 3.2eK Meteorological Monitoring Instrumentation Seismic Monitoring Instrumentation

.Radioactive Gaseous Effluent Monitoring Instrumentation 83 84 84A 4.2.A Surveillance Requirements for Primary Containment and Reactor Building Isolation Instrumentation

.85 4.2.B Surveillance Requirements for Instrumentation tha Initiate or Control the CSCS.96 4.2.C Surveillance Requirements for Instrumentation tha Initiate Rod Blocks 102 4.2.D Radioactive Liquid Effluent Monitoring Instrumentation Surve'illance Requirements.

103 Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation

.104 0241p Amendment No.132 v1

~4 i LIST OF TABLES (Cont'd)Table Title~Pa e No.Minimum Test and Calibration Frequency for Surveillance Instrumentation

.105 4.2.G Surveillance Requirements for Control Room Isolation Instrumentation 106 4.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation

.107 4.2eJ Seismic Monitoring Instrument Surveillance 108 4.2aK Radioactive Gaseous Effluent Instrumentation Surve1llance

.108A 3.5-1 3.5.I Minimum RHRSW and EECW Pump Assignment MAPLHGR Versus Average Planar Exposure.152a 171, 172, 172a 3.7.A 3.7.B t 3.7.C 3.7.D 3.7.E Primary Containment Isolation Valves Testable Penetrations with Double 0-Ring Seals.Testable Penetrations with Testable Bellows Air Tested Isolation Valves Primary Containment'.

Isolation Valves which Terminate below the Suppression.

Pool Mater evel L 250 256 257 258 262 3.7.F Primary Containment Isolation Valves Located in Water Sealed Seismic Class 1 Lines.263 3.7.H Testable Electrical Penetrations

.265 4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start 298a 3.11.A 6.8.A Fire Protection System Hydraulic Requirements Minimum Shift Crew Requirements 324 360 Amendment No.i32 V11 0241p I k

'IST OF ILLUSTRATIONS

~Fi ure Title~Fa e No.APRM Flow Reference Scram and APRM Rod Block Settings~~~~~~~~~~~~~e~~~~~13 2.1-2 APRM Flow Bias Scram Vs.Reactor Core Flow.26 4.1-1 Graphic Aid in the Selection of an Adequate Interval Between Tests 49 4.2-1 System Unavailability 119 3.4-1 Sodium Pentaborate Solution Volume Concentration Requirements 138 3.4-2 Sodium Pentaborate Solution Temperature Requirements

..139 3.5.K-1 MCPR Limits 172b 3.5.2<Factor K 173 3.6-1 Minimum Temperature

'F Above Change in Transient Temperature 194 3.6-2 Change in Charpy V Transition Temperature Vs.Neutron Exposure.195 Gaseous Release Points and Elevations 290 4.8.1b Land Site Boundary.290A 6.1-1 TVA Office of Power Organization for of Nuclear Power Plant.Operation 361 6.1-2 6.2-1 Functional Organization

'I i a~y Review and Audit Function~~~a 3~~~N il 362 363 6.3-1 In-Plant Fire Program Organization

.364 Amendment No.132 v111 0241p

1.0 DEFINITIONS

(Cont'd)10.~Lo ic-A logic is an arrangement of relays, contacts, and other components that produces a decision output.(ai~Initiatin

-A logic that receive signals from channels and produce decision outputs to the actuation logic.(b)Actuation-A logic that receives signals (either from initiation logic or channels)and produces decision outputs to accomplish a protective action.ll.Channel Calibration

-Shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel monitors.The channel calibration shall encompass the entire channel including alarm and/or trip functions and shall include the channel functional test.The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

Non-calibratable,components shall be excluded from this requirement, but will be included in channel functional test and source check.12.Channel Functional Test-Shall be: r a.Analog Channels-the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b.Bistable channels-the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

13.Source Check-Shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources.Amendment No.132 0242p I'kl*\Lv$1 0't D

1.0 DEFINITIONS

(Cont'd)Functional Tests-A functional Eeesis the'adual operation or initiation of a system, subsystem, or components to verify that it functions within design tolerances (e.g., the manual start of a core spray pump to verify that it runs and that it pumps the required volume of water).X.Shutdown-The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.

Y.En ineered Safe uard-An engineered safeguard is a safety system the actions of which are essential to a safety action required in response to accidents.

Z.Reportable Event-A reportable event shall be any of those conditions specified in section 50.73 to 10 CFR Part 50.4 Solidification

-Shall be the conversion of radioactive wastes into a form that meets shipping and burial ground requirements..

BB.Offsite Dose Calculation Manual (ODCM)-Shall be a manual describing the environmental monitoring program and the methodology and parameters used in the calculation of release rate limits and offsite doses due to radioactive gaseous and and liquid effluents.

The ODCM will also provide the plant with guidance for establishing alarm/trip setpoints to ensure technical specifications sections 3.8.A.1 and 3.8.B.1 are not exceeded.CC.Pur e or ur in-The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is required to purify the containment.

DD.Process Control Pro ram-Shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.EE.Radiolo ical Effluent Manual (REM)-Shall be a manual containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposure to individuals from station operation.

It shall also specify operating guidelines for radioactive waste treatment systems and report content.FF.V~entin-The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required.Vent, used in system names, does not imply a venting process.0242p Amendment No.132 7A t 4~0 1~0 DEFINITIONS (Cont'd)GG~owned, leased, or otherwise controlled by TVA.HH~Unrestricted Area-Any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for industrial, commercial, institutional, or recreational purposes.Dose E uivalent I-131-The DOSE EQUIUALENT I-131 shall be the concentration of I-131 (in pCi/gm)which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.The thyroid dose conversion factor used for this calculation shall be those listed in Table III of TID-14844"Calculation of Distance Factors for Power and Test Reactor Sites".Gaseous Waste Treatment S stem-The charcoal adsorber vessels installed on the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release.Members of the Public-Shall include all individuals who by virtue of their occupational status have no formal association with the plant.This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.

This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter restricted areas.LL.Surveillance

-Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements.

Each surveillance Requirement shall be performed within the specified time interval with, (1)A maximum allowable extention not to exceed 25K of the surveillance interval, but (2)The combined time entered for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications.

Surveillance requirements do not have to be performed on inoperable eouipment.

O242p Amendment No.1 32 7B

Table 1.1NOTATION S (Shift)D (Daily)SURVEILLANCE FRE UENCY NOTATION FRE UENCY At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.At least once per normal calendar 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day (midnight to midnight)~W (Weekly)M (Monthly)Q (Quarterly)

SA (Semi-Annual ly Y (Yearly)(Refueling)

S/U (Start-Up)

N.A.P (Prior)At least once per 7 days.At least once per 31 days.At least once per 3 months or 92 days.At least once per 6 months or 184 days.At least once per year or 366 days.At least once per operating cycle.Prior to each reactor startup.Not applicable.

Completed prior to each release.0242p Amendmeng No.132 7C I'.I'P LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.Q.B Core and Containment Coolin S stems-.Initiation S Control 4.2.B Core and Containment Coolin S stems-Initiation 6 Control are required to be operable shall be considered operable if they are within the required surveillance testing frequency and there is no reason to suspect that they are inoperable.

C.Control Rod Block Actuation C.Control Rod Block Actuation The limiting conditions of.operation for the instrumentation that initiates control rod block are given in Table 3.2.C.Instrumentation shall be functionally tested, calibrated, and checked as indicated in Table 4.2.C.System logic shall be functionally tested as indicated in Table 4.2.C.3.2.D Radioactive Li uid Effluent Monitorin Instrumentation 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation 1.The radioactive liquid effluent monitoring instrumentation listed in Table 3.2.D shall be operable with the applicability as shown in Tables 3.2.D/4.2.D.

Alarm/trip setpoints will be set in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.A.1 are not exceeded.1.Each of the radioactive liquid effluent monitoring instruments shall be demonstrated operable by performance of test in accordance with Table 4.2.D.2.The action required when the number of operable channels is less than the minimum channels operable requirement is specified in the notes for Table 3.2.D.Exert best efforts to return the instrument(s) to OPERABLE status within 30 days and if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.51 Amendment No.132 0233p 0 l" t LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.D Radioactive Li uid Effluent (Con't)4.2.D Radioactive Li uid Effluent (Con't)3~With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these specifications.

The provisions of specification 1.0.C and 6.7.2 are not applicable.

E.Dr ell Leak Detection E.Dr ell Leak Detection The limiting conditions of operation for the instrumentation that monitors drywell leak detection are given in Table 3.2.E.Instrumentation shall be calibrated and checked as indicated in Table 4.2.E.F.Surveillance Instrumentation F.Surveillance Instrumentation The limiting conditions for the instrumentation that provides surveillance information readouts are given in Table 3.2.F.Instrumentation shall be calibrated and checked as indicated in Table 4.2.F.G.Control Room Isolation The limiting conditions'ori-

~instrumentation that isolates the control room and initiates the control room emergency pressurization systems are given in Table 3.2.G.G.Control Room Isolation Instrumentation"shall be calibrated and checked as indicated in Table 4.2.G.52 Amendment No.132 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.J Seismic Monitorin Instrumentation 4.2.J Seismic Monitorin Instrumentation 2~3.The seismic monitoring instruments listed in Table 3.2.J shall be operable at all times.With the'number of seismic monitoring instruments less than the number listed in Table 3.2.J, restore the inoperable instrument(s) to operable status within 30 days.With one or more of the instruments listed in Table 3.2.J inoperable for more than 30 days, submit a Special Report to the Commission pursuant to specification 6.7.3.C within the next 10 days describing the cause of the malfunction and plans for restoring the instruments to operable status.1.Each of the seismic monitoring instruments shall be demonstrated operable by performance of tests at the frequencies listed in Table 4.2.J.2.Data shall be retrieved from all seismic instruments actuated during a seismic event and analyzed to determine the magnitude of the vibratory ground motion.A Special Report shall be submitted to the Commission pursuant to specification 6.7.3.D within 10 days describing the magnitude, frequency spectrum, and resultant effect upon plant features important to safety.3.2.K Radioactive Gaseous Effluent Monitorin Instrumentation 4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation The radioactive gaseous effluent monitoring instruments listed in Table 3.2.K shall be operable with the applicability as shown in Tables 3.2.K/4.2.K.

Alarm/trip setpoints will be set in accordance with guidance"given in the ODCM to ensure that the limits of specification 3.8.B.1 are not exceeded.1.Each of the radioactive gaseous effluent monitoring instruments shall be demonstrated operable by performance of tests in accordance with Table 4:.2.K.Amendment No.132 54 0233p Jr I 0 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.K Radioactive Gaseous Effluent W.2~Rad'ioactive GaseoQs Effluent Monitorin Instrumentation Monitorin Instrumentation (Con't)(Con't)2~The action required when the number of operable channels is less than the Minimum Channels Operable requirement is specified in the notes for Table 3.2.K.Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful,'explain in the next Semiannual Radioactive Release Report why the inoperability was not corrected in a timely manner.3.With a radioactive gaseous effluent monitoring channel alarm/trip setpoint less conservative than required by these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these specifications.

4, Both off-gas treatment monitors may be taken out of service for less than one hour for purging of monitors during SI performance.

5~The provisions of specifications 1.0.C and 6.7.2 are not applicable.

Amendment No.132 54A 0233p

TABLE 3.2.D Radioactive Li uid Effluent Moni torin Instrumentation Instrument

"'.LIQUID RADHASTE EFFLUENT MONITOR (RM-90-130) 2.RHR SERVICE HATER MONITOR (RM-90-133,-134)3.RAN COOLING HATER MONITOR (RM-90-132) 4.LIQUID RADHASTE EFFLUENT FLOH RATE (77-60 loop excluding fixed in line rotometer)

Minimum Channels 0 erable A licabilit Act>on A, B E 0240p Amendment No.132 76

~$

NOTES FOR TABLE 3.2.D<At al 1 times>'~During releases via this pathway<~~During operation of an RHR loop and associated RHR service water system ACTION A During release of radioactive wastes from the radwaste processing system, the following shall be met (1)liquid waste activity and f lowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits spec if ied in 3.8.A.1, (2)if this cannot be met, two independent samples of the tank being discharged shall be analyzed in accordance with the sampling and analysis program specified in the REM and two qualified station personnel, shall independently verify the release rate calculations and check va 1 ving before the discharge.Otherwise, suspend release via this pathway.ACTION B With a radioactive liquid effluent monitoring channel/alarm trip setpoint less conservative than requi red by these specifications, suspend release via this pathway without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism referred by these specifications

.ACTION C During operation of an RHR loop and assoc i ated RHR service wat er system, the ef f 1 uent f rom that uni t'service water shall be continuously monitored.If an installed moni toring system is not available, a temporary monitor or grab samples taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and an analysis of at least an LLDf 1 E-'7 pCi/ml (gross)or<applicable MPC ratio (y isotopic)shall be used to monitor the ef f 1 uent.ACTION D With the number of channels OPERABLE less than requi red by the Minimum Channels Oper abl e requi rement, effluent releases via this pathway may continued provided that a temporary monitor is installed or, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for radioactivity with an LLDf 1 E-7 pCi/ml (gross)or<applicable MPC ratio (y isotopic).ACTION E With the number of channels OPERABLE less than requ i red by the Minimum Channels Operable requi rement, effluent releases via this pathway may continued provided the flow rate 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.Pump curves may be used to estimate f 1 ow.ACTION F Alarm/trip setpoints will be calculated in accordance with the guidance given in the Off si te Dose Calculation Manual (ODCM).(1)See REM, TABLE NOTATIONS-TABLE C-l, for the definition of LLD.7 6A Q242p Amendment No.1 32 l'

Radioactive Gaseous Effluent Monitorin Instrumentation Instrument STACK (RM-90-147A

&B)a.Noble Gas Monitor b.Iodine Cartridge c.Particulate Filter d.Sampler Flow Abnormal e.Stack Flow (FT, FM, FI-90-271)

Minimum Channels/Devices 0 erable (1)(1)(1)(1)(1)PULI'lib 1'ction A/C 8/C B/C D D 2.4.5.6.REACTOR/TURBINE BLDG VENTILATION (RM-90-250) a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter TURBINE BLDG EXHAUST (RM-90-249, 251)a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter RADHASTE BLDG VENT (RM-90-252) a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter OFF GAS HYDROGEN ANALYZER (HzA, HzB)OFF GAS POST TREATMENT a.Noble Gas Activity Monitor (RM-90-265, 266)b.Sample Flow Abnormal (PA-90-262)

(1)(1)(1).(1)(1)(1)(1)(1)(1)(1)(1)(1)A/C B/C B/C D A/C B/C B/C D A/C B/C 8/C D 0240p Amendment No.132 84A 4

NOTES FOR TABLE 3.2.K i'~At all times~'<During releases via this pathway~'-':During main condenser offgas treatment system operation ACTION A With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via the affected pathway may continue provided a temporary monitoring system is installed or grab samples are taken and analyzed at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.ACTION B With a number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continued provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7)days and analyzed in accordance with the sampling and analysis program specified in the REM 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.ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for functional testing, calibration, or repair without providing or initiating grab sampling.ACTION D t With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided the flow rate 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 />.ACTION E Eh With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, operation of main condenser offgas treatment system may continue provided that a temporary monitor is installed or grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.ACTION F 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 at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 />.Purging during SI performance is not considered a loss of monitoring capability.

0242p Amendment No.132 84B

TABLE 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation Surveillance Re uirements Instrument 1.LIQUID RADHASTE EFFLUENT MONITOR (RM-90-130) 2.RHR SERVICE HATER MONITOR (RM-90-133,-134)3.RAN COOLING HATER MONITOR (RM-90-132) 4.LIQUID RADHASTE EFFLUENT FLOH RATE (77-60 loop)Instrument Check D(4)D(4)D(4)D(4)Source Check Channel Calibration R(5)R(5)R(5)Functional Test Q(1)Q(2)Q(2)Q(3)Amendment No.132 0240p 103 r 4 V NOTES FOR TABLE 4.2.D (1)The channel functional test shall also demonstrate that'utomatic isolation of this pathway and control room annunciation occurs iF any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint b.Instrument indicates an inoperative/downscale failure c.Instrument controls not set in operate mode (2)The channel functional test shall also demonstrate that control room annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint b.Instrument indicates an inoperative/downscale failure c.Instrument controls not set in operate mode (3)This functional test shall consist oF measuring rate of tank decrease over a period of time.and comparing this value with flow rate instrument reading.(4)INSTRUMENT CHECK shall consist of verifying indication during periods of release.INSTRUMENT CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days which continuous, periodic, or batch releases are made.P (5)The CHANNEL CALIBRATION shall include the use of a known (traceable to National Bureau of Standards Radiation Measurement System)radioactive source(s)positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards (NBS).0242p Amendment No.132 103A

TABLE 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance Instrument l.STACK a.Noble Gas Monitor'b.Iodine Cartridge c.Particulate Filter d..Sampler Flow Abnormal e.Stack Flowmeter 2.REACTOR/TURBINE BLDG VENT a.Noble Gas Monitor'"'.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter 3.TURBINE BLDG EXHAUST a.Noble Gas Monitor"'.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter 4.RADWASTE BLDG VENT a.Noble Gas Monitor"'.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter 5.OFF GAS HYDROGEN ANALYZER (HrA, HzB)6.OFF GAS POST TREATMENT.Noble Gas Activity Monitor b.Sample Flow Abnormal Instrument Check Source Check M NA NA NA NA M NA-NA NA M NA-'-NA~NA.M NA.NA, NA NA M NA Channel Calibration R())NA NA R R Rl)NA NA R Rt 1)NA NA R R<1)NA NA R Rl J)R(1)R Functional Test Q(Z)NA NA Q Q Q(2)NA NA Q Q(C)NA NA Q Q(2)NA NA 0 Q(4)Q(4)Q(C)p24pp Amendment No.132 108A NOTES FOR TABLE 4.2.K (1)The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of Standards Radiation Measurement System)radioactive source(s)positioned in a reproducible geometry with respect to the sensor or using standards that have obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards.

(2)The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint.b.Instrument indicates an inoperative/downscale failure.c.Instrument controls not set in operate mode (stack only).(3)The channel calibration shall include the use of standard gas samples containing a nominal: a.Zero volume percent hydrogen (compressed air)and, b.One volume percent hydrogen, balance nitrogen.(4)The channel functional test shall demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exists: a.Instrument indicates measured level above the alarm/trip setpoint.b.Instrument indicates an inoperative/downscale failure.c.Instrument controls not set in operate mode.The two channels are arranged in a coincidence logic such that 2 upscale, or 1 downscale and 1 upscale or 2 downscale will isolate the offgas line.(5)The noble gas monitor shall have a LLD of lE-5 (Xe 133 Equivalent).

(6)The noble gas monitor shall have a LLD of lE-6 (Xe 133 Equivalent).

0242p Amendment No.132 108B MP~a" LMm t 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 effiuents.

The alarm/trip setpoints for these instruments will be calculated in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.This instrumentation also includes provisions for monitoring the concentration of potentially explosive gas mixtures in the offgas holdup system.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.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 in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior.to exceeding the limits of 10 CFR Part 20 Appendix B, Table II, Column 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 50.0242p Amendment No.132 115A

'

4.2 BASES

there is no true minimum.The curve does have a definite knee and very little reduction in system unavailability is achieved by testing at a shorter interval than computed by the equation for a single channel.The best test procedure of all those examined is to perfectly stagger the tests.That is, if the test interval is four months, test one or the other channel every two months.This is shown in Curve No.5.The difference between Cases 4 and 5 is negligible.

There may be other arguments, however, that more strongly support the perfectly staggered tests, including reductions in human error.The conclusions to be drawn are these: l.A 1 out of n system may be treated the same as a single channel in terms of choosing a test interval;and 2.more than one channel should not be bypassed for testing at any one time.The radiation monitors in the refueling area ventilation duct which initiate building isolation and standby gas treatment operation ar'e arranged in two 1 out of 2 logic systems.The bases given for the rod blocks apply here also and were used to arrive at the functional testing frequency.

The off-gas post treatment monitors are connected in a 2 out of 2 logic arrangement.

Based on experience with instruments of similar design, a testing interval of once every three months has been found adequate.The automatic pressure relief instrumentation can be considered to be a 1 out oF 2 logic system and the discussion above applies also.The criteria for ensuring the reliability and accuracy of the radioactive gaseous effluent instrumentation is listed in Table 4.2.K.The criteria for ensuring the reliability and accuracy of the radioactive liquid effluent instrumentation is listed in Table 4.2.D.0242p Amendment No.132 118

3.6 LIMITING

CONDITIONS FOR OPERATION Primar S stem Boundar 4.6 SURVEILLANCE REQUIREMENTS Primar S'stem Boundar 6.Whenever the reactor is critical, the limits on activity concentrations in the reactor coolant shall not exceed the equilibrium value of 3.2 pc/gm of does equivalent I-131.6~Additional coolant samples shall, be taken whenever the reactor activity exceeds one percent of the equilibrium concentration specified in 3.6.B.6 and one of the following conditions are met: This limit may be exceeded following power transients for a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.During this activity transient the iodine concentrations shall not exceed 26 pCi/gm whenever the reactor is critical.The reactor shall not be operated more than 5 percent of its yearly power operation under this exception for the equilibrium activity limits.lf the iodine concentration in the coolant exceeds 26 pCi/gm, the reactor shall be shut down, and the steam line isolation valves shall be closed immediately.

a.During startup b.Following a significant power change~<c.Following an increase in the equilibrium off-gas level exceeding 10,000 pCi/sec (at the steam jet air ejector)within a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.d.Whenever the equilibrium iodine limit specified in 3.6.B.6 is exceeded.The additional coolant liquid samples shall be taken at 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or until a stable iodine concentration below the limiting value (3.2 pCi/gm)is established.

However, at least 3 consecutive samples shall be taken in all cases.An isotopic analysis shall be performed for each-sample, and quantitative measurements made to determine the dose equivalent I-131 concentration.

If the total iodine activity of the sample is below 0.32 pCi/gm, an isotopic analysis to determine equivalent I-131 is not required.i'~'iFor the purpose of this section on sampling frequency, a significant power exchange is defined as a change exceeding 15K of rated power in less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.Amendment Ho.132 179 0233p E)(I LIMITING CONDITIONS FOR OPERATION 3.8 Radioactive Materials SURVEILLANCE RE UIREMENTS Radioactive Materials 4.8 Applies to the release of radioactive liquids and gases from the facility.~Ob ective To define the limits and conditions for the release of radioactive effluents to the environs to assure that any.radioactive releases are as low as reasonably achievable and within the limits of 10 CFR Part 20.The specifications except for 3.8.A.1 and 3.8.B.1 are exempt from the requirements of definition 1.0.C (Limiting Condition for Operation).

A.Li uid Effluents 1.The concentration, of radioactive material released at any time from the site to unrestricted areas (see Figure 4.8-1b)shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II,;Column 2 for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity.2.If the limits of 3.8.A.l are exceeded, appropriate action shall be initiated without delay to bring the release within Applies to the periodic test and record requirements and sampling and monitoring methods used for facility effluents.

O~b'ective To ensure that radioactive liquid and gaseous releases from the facility are maintained within the limits specified by Specifications 3.8.A and 3.8.B.A.Li uid Effluents 1.Facility records shall be maintained of radioactive concentrations and volume before dilution of each batch of liquid effluent released, and of the average dilution flow and length of time over which each discharge occurred.2.Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with the sampling and analysis program specified in the REM.3.The operation of the automatic isolation valves and discharge tank selection valves shall be checked annually.281 0233p mendment go.132

'ln LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

3.8 Radioactive

Materials 4.8 Radioactive Materials 3.limits.Provide prompt notification to the NRC pursuant to section 6.7.2.The doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas (See Figure 4.8-1b)shall be limited: 4.The results of the analysis of samples collected from release points shall be used with the calculational methodology in the ODCM to assure that the concentrations at the point of release are maintained within the limits of specification 3.8.A.1.4~5.a.During any calendar quarter to<1.5 mrem to the total body and<5 mrem to any organ and, b.During any calendar year to<3 mrem to the total body and<10 mrem to any organ If the limits specified in 3.8.A.3 a&b above are exceeded, prepare and submit'Special Report pursuant to Section 6.7.2.The maximum activity to be contained in one liquid radwaste tank or temporary storage tank that can be discharged directly to the environs shall not exceed 10 curies excluding tritium and dissolved/entrained noble gas.5.Cummulative quarterly and yearly dose contributions from liquid effluents shall be determined as specified in the ODCM at least once every 31 days.6.The quantity of radioactive material contained in any outside liquid radwaste storage tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the.tank.6.With radioactive liquid waste exceeding 3.8.A.5 limits, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit.Events leading to this condition must be reported in the next Semiannual Radioactive Effluent Release Report (section F.2 of the REM)0233p Amendment No.132 282 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS3.8 Radioactive Materials B.Airborne Effluents 1.The dose rate at any time to areas at and beyond the site boundary (see Figure 4.8-1b)due to radioactivity released in gaseous effluents from the site shall be limited to the following values: a.The dose rate limit for noble gases shall be<500 mrem/yr to the total body and<3000 mrem/yr to the skin, and b.The dose rate limit for I-131, I-133, H-3, and particulates with greater than eight day half-lives shall be<1500 mrem/yr to any organ.2.If the'limits of 3.8.B.1 are exceeded, appropriate corrective action shall be immediately initiated to bring the release within limits.Provide prompt not if i cat ion to the NRC pursuant to section 6.7.2.4.8 Radioactive Materials B.Airborne Effluents 1.The gross 0/y and particulate activity of gaseous wastes released to the environment shall be monitored and recorded.a.For effluent streams having continuous monitoring capability, the activity shall be monitored and flow rate evaluated and recorded to enable release rates of gross radioactivity to,be determined at least once per shift using instruments specified in table 3.2.K.b.For effluent streams without continuous monitoring capability, the activity shall be monitored and recorded and the release through these streams controlled to within the limits specified in 3.8.B.2.Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with the sampling and analysis program specified in the REM.Dose rates shall be determined to be within limits of 3.8.B using methods contained in the ODCM.Amendment No.132 283 0233p 0 I1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.The air dose to areas at and beyond the site boundary (see Figure 4.8-1b)due to noble gases released in gaseous effluents per unit shall be limited to the following:

a.During any calendar quarter, to<5 mrad for gamma radiation and<10 mrad for beta radiation;

." Cumul at i velar ter ly and yearly dose contributions from gaseous releases shall be determined using methods contained in the ODCM at least once every 31 days.b.During any calendar year, to<10 mrad for gamma radiation and<20 mrad for beta radiation.

4.If the calculated air dose exceeds the limits specified in 3.8.B.3 above, prepare and submit a special report pursuant to section 6.7.2.5.The dose to a member of the public from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than 8 days in gaseous effluent released per unit to areas at and beyond the site boundary (see Figure 4.8-1b)shall be limited to the following:

~, a.To any organ during any calendar quarter to<7.5 mrem;b.To any organ during any calendar year to<15 mrem Amendment No.132 284 0233p 0

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 6.If the calculated doses exceed the limits of 3.8.B.5 above, prepare and submit a special report pursuant to section 6.7.2.7.During operation above 25K power the discharge of the SJAE must be routed through the charcoal adsorbers.

8.With gaseous waste being discharged for more than 7 days without treatment through the charcoal adsorbers, prepare and submit a special report pursuant to section 6.7.2.4.During operation above 25K power, the position of the charcoal bed bypass valve will be verified daily.5.The concentration of hydrogen downstream of the recombiners shall be determined to be within the limits of 3.8.B.9 by continuously monitoring the offgass whenever the SJAE is in service using instruments described in Table 3.2.K.Instrument surveillance requirements are specified in Table 4.2.K.9.Whenever the SJAE is in service, the concentration of hydrogen in the offgas downstream of the recombiners shall be limited to (4X by volume.10.With the concentration of hydrogen exceeding the limit of 3.8.B.9 above, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.Amendment No.132 285 0233p V 0' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8.C Radioactive Effluents-Dose 4.8.C Radioactive Effluents-Dose The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to (25 mrem to the total body or any organ (except the thyroid, which is limited to (75 mrem)over a period of one calendar year.1.Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with specifications 3.8.A.3, 3.8.B.3, and 3.8.B.5 and the methods in the ODCM.2 4 With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of specification 3.8.A.3, 3.8.B.3, or 3.8.B.5, prepare and submit a Special Report to the Commission pursuant to specification 6.7.2 and limit the subsequent releases such that the limits of 3.8.C.l are not exceeded.3.8.D Mechanical Vacuum Pum 4.8.D Mechanical Vacuum Pum Each mechanical vacuum pump shall be capable of being automatically isolated and secured on a signal or high radioactivity in the steam lines whenever the main steam isolation'alves are open.At least once during each operating cycle verify automatic securing and isolation of the mechanical vacuum pump.2.If the limits of 3.8.D are not met, the vacuum pump shall be isolated.endment Ho.132 286 0233p 0

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTG 3.8 Radioactive Materials 4.8.C Radioactive Materials E.Miscellaneous Radioactive Materials Sources E.Miscellaneous Radioactive

.Materials Sources 1.Source Leaka e Test 1.Surveillance Re uirement Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of)0.005 microcurie of removable contamination.

Each sealed souce with removable contamination in excess of the above limit shall be immediately withdrawn from use and (a)either decontaminated and repaired, or (b)disposed of in accordance with Commission regulations.

Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commi ss ion or an agreement State, as follows: a.Sources in Use Each sealed source, excluding startup sources and flux detectors previously subjected to core flux, containing radioactive material, other than Hydrogen 3, with a half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at least once per six months.The leakage test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample.Amendment No.132 287 0233p J

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 4.8.E Miscellaneous Radioactive Materials Sources 1.Surveillance Re uirements b.Stored Sources Not In Use Each sealed source and fission detector not previously subjected to core flux shall be tested prior to use or transfer to another licensee unless tested within the previous six months.Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to use.c.Startu Sources and Fission Detectors Each sealed startup source and fission detector shall be tested prior to being subjected to core flux and following repair or maintenance to the source.2.~Re orts A report shall be prepared and submitted to the Commission on an annual basis if sealed sources or fission detector leakage tests reveal the presence of greater than or equal to 0.005 mxcrocurxes of removable contamination.

Amendment No.132 288 0233p LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials F.Solid Radwaste F.Solid Radwaste 1.The solid radwaste system shall be operated in accordance with a process control program, for the solidification and packaging of wet radioactive wastes to ensure meeting the requirements of 10 CFR 20 and 10 CFR 71 and burial ground requirements prior to shipment of radioactive wastes from the site.1.The Process Control Program shall include surveillance checks necessary to demonstrate compliance with 3.8.F.l.2.With the packaging'equirements of 10 CFR 20 or burial ground requirements and/or 10 CFR 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site.0233p Amendment No.132 289

~'7 Switchyard Turbine Building Exhaust Fan (32m)-Office Building Service Bldg.Turbine Building Iladt.Bldg.Reactor Building Stack (180m)Reactor Building Ventilation (40m)Figure 4.8-1a GASEOUS REI.EASE POINTS AND ELEVATIONS 290-Amendment No.132

Figure 4.8-1b LAND SITE BOUNDARY~"Y'I.~i'\j;l.lquW nleeherae (I)l(lueer I'lpee)(e eeelre f I i"tT , lypt1kfl+II Jl IWp4 IV~eu~l nile 2 ill lee 290A Amendment No.132 Ey

3.8 BASES

Radioactive waste release levels to unrestricted areas should be kept"as low as reasonably achievable" and are not to exceed the concentration limits specified in 10 CFR Part 20.At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the concentration limits specified in 10 CFR Part 20.It is expected that by using this operational flexibility and exerting every effort to keep levels or radioactive materials released as low as reasonably achievable in accordance with criteria established in 10 CFR 50 Appendix I, the annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR Part 20.Specification 3.8.A.1 is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1)the Section 11.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2)the limits of 10 CFR Part 20.106(e)to the population.

The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)Publication 2.Specification 3.8.A.3 is provided to implement the dose requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50.The Limiting Condition for Operation implements the guides set forth, the Section 11.A of Appendix I.Specification 3.8.A.4 action statements provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept"as low as is reasonably achievable".

Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by Amendment No.132 0242p 291 0'll, tl 1 l calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977'UREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1 F 11'.8.B AIRBORNE EFFLUENTS Specification 3.8.B.1 is provided to ensure that the dose rate at anytime at the exclusion boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas The annual dose limits are the doses associated with the concentrations of 10 CFR part 20, Appendix B, Table II, Column 1~These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a member of the public in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20~106 (b))~For members of the public who may at times be within the exclusion area 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 exclusion area boundary 02g2p Amendment No.132 29 1A ll 3.8.B AIRBORNE EFFLUENTS (cont'd)The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to<500 mrem/year to the total body or to<3000 mrem/year to the skin.These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to<1500 mrem/year for the nearest cow to the plant.Specification 3.8.B.2 requires that appropriate correction action(s)be taken to reduce gaseous effluent releases if the limits of 3.8.B.1 are exceeded.Specification 3.8.B.5 dose limits is provided to implement the requirements of Section II.C, III.A, and IV of Appendix I, 10 CFR Part 50.The limiting conditions for operation are the guides set forth in Section II.C of Appendix I.Specification 3.8.B.6 action statement provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate

'pathways is unlikely to be substantially underestimated.

The ODCM calculational methods used for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109,"Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977, NUREG/CR-1004,"A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides", October 1979, and Regulatory Guide l.ill,"Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.The pathways which are examined in the development of these calculations are: 1)individual inhalation of airborne radionuclides,.

2)deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3)deposition onto grassy areas where milk animal and meat producing animals graze with consumption of the milk and meat by man, and 4)deposition on the ground with subsequent exposure of man.Specification 3.8.B.6 action statement requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.5.Amendment No.132 0242p 291B

'4 P f AIRBORNE EFFLUENTS e Specification 3.8.B.7 requires that the offgas charcoal adsorber beds be used when specified to treat gaseous effluents prior to their release to the environment.

This provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A'o 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

Specification 3.8.B.8 requires that a special report be prepared and submitted to explain reasons for any failure to comply with Specification 3.8.B.7.Specification 3.8.B.3 is provided to implement the requirements of Section II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50.The Limiting Condition for Operation implements the guide set forth in Section II.C of Appendix I.Specification 3.8.B.4 action statement provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated.

The dose calculations established in the ODCM for calculating'the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109,"Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1 October 1977, NUREG/CR-1004,"A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides", October 1979 and Regulatory Guide 1.111,"Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977., The ODCM.equations provided for determining the'air doses at the exclusion area boundary will be based upon the historical average atmospheric conditions.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111..Specifications 3.8.B.4 requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.3.4.8.A and 4.8.B BASES The surveillance requirements given under Specification 4.8.A and 4.8'provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release of'adioactive materials in the liquid and 0242p Amendment No.132 291C Qt~y+

4.8.A and 4.8.B BASES (cont'd)gaseous effluents.

These surveillance requrr e'~men s pihvide the data~r the licensee and the Commission to evaluate the station's performance relative to~radioactive wastes released to the environment.

Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 6 of these technical specifications.

On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such actions as the Commission deems appropriate.

3.8.C and 4.8.C BASES This specification is provided to meet the dose limitations of 40 CFR 190.The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.For sites containing up to four reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level.The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for the calendar year to be within 40 CFR 190 limits.For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of five miles must be considered.

3.8.D and 4.8.D MECHANICAL VACUUM PUMP The purpose of isolating the mechanical vacuum pump line is to limit the release of activity from the main condenser.

During an accident, fission products would be transported from the reactor through the main steam lines to the condenser.

The fission product radioactivity would be sensed by the main steam line radioactivity monitors which initiate isolation.

3.8.E and 4.8.E BASES The limitations on removable contamination for sources requiring leak testing, including alpha emitters, based on 10 CFR 70.39(c)limits for plutonium.

This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group.Those sources which are frequently handled are required to be tested more often than those which are not.Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices)are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

Amendment No.132 0242p 291D 1'J 1Q

6.0 ADMINISTRATIVE

CONTROLS k.The radiological environmental monitoring program and the , results thereof at least once per 12 months.1.The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev.1, 1974 and Regulatory Guide 4.1, 1975 at least once per 12 months.m.The performance of activities required by the Safeguards Contingency Plan to meet the criteria of 10 CFR 73.40(d)at least once per 12 months.n.The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.o.The Process Control Program and implementing procedures for solidification of wet radioactive wastes at least once per 24 months.p.The Radiological Effluent Manual and implementing procedures at least once per 12 months.9.AUTHORITY The NSRB shall report to and advise the Manager of Power on those areas of responsibility specified in Sections 6.2.A.7 and 6.2.A.8.10.RECORDS Records of NSRB activities shall be prepared, approved and distributed as indicated below: a.Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Manager of Power within 14 days following each meeting.b.Reports of reviews encompassed by Section 6.2.A.7 above, shall be prepared, approved and forwarded to the Manager of Power within 14 days following completion of the review.c.Audit reports encompassed by Section 6.2.A.8 above, shall be forwarded to the Manager of Power and to the management positions responsible for the areas audited within 30 days after completion of the audit.Amendment No.132 0242p 334A

6.0 ADMINISTRATIVE

CONTROLS j.Review proposed changes to the Radiological Effluent Manual.k.Review adequacy of the Process Control Program and Offsite Dose Calculation Manual at least once every 24 months.1.Review changes to the radwaste treatment systems.m.Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendation, and deposition of the corrective action to prevent recurrence to the Director, Nuclear Power and to the Nuclear Safety Review Board.5.Author i t The PORC shall be advisory to the plant superintendent.

6.Records Minutes shall be kept for all PORC meetings with copies sent to Director, Nuclear Power;Assistant Director of Nuclear Power (Operations);

Chairman, NSRB.7.Procedures Written administrative procedures for committee operation shall be prepared and maintained describing the method for submission and content of presentations to the committee, review and approval by members of'committee actions, dissemination of minutes, agenda and scheduling of meetings.Amendment No.132 0242p 337

6.0 ADMINISTRATIVE

CONTROLS 6.3 Procedures A.Detailed written procedures, including applicable checkoff lists covering items listed below shall be prepared, approved and adhered to.1.Normal startup, operation and shutdown oF the reactor and of all systems and components involving nuclear safety of the facility.2.Refueling operations.

3.Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks and abnormal reactivity changes.4.Emergency conditions involving potential or actual release of radioactivity.

5.Preventive or corrective maintenance operations which could have an effect on the safety of the reactor.6.Surveillance and testing requirements.

7.Radiation control procedures.

8.Radiological Emergency Plan implementing procedures.

9.Plant security program implementing procedures.

10.Fire protection and prevention procedures.

11.Limitations on the amount of overtime worked by individuals performing saFety-related functions in accordance with the NRC policy statement on working hours (Generic Letter No.82-12).12.Radiological Effluent Manual implementing procedures.

13.Process Control Program (PCP).14.OfFsite Dose Calculation Manual.B.Written procedures pertaining to those items listed above shall be reviewed by PORC and approved by the plant superintendent prior to implementation.

Temporary changes to a procedures which do not change the intent of the approved procedure may be made by a member of the plant staff knowledgeable in the area affected by the procedure except that temporary changes to those items listed above except item 5 require the additional approval of a member of the plant staff who holds a Senior Reactor Operator license on the unit affected.Such changes shall be documented and subsequently reviewed by PORC and approved by the plant superintendent.

Amendment No.132 0242p 338

6.0 ADMINISTRATIVE

CONTROLS 6.3 Procedures E.ualit Assurance Procedures

-Effluent and Environmental Monitorin Quality Assurance procedures shall be established, implemented, and maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, rev.1, June 1974 and Regulatory Guide 4.1, rev.1, April 1975 or Regulatory Guide 4.15, Dec.1977.0242p Amendment No.132 340

6.0 Administrative

Controls 3.Uni ue Re ortin Re uirements A.Radioactive Effluent Release Re ort Deleted.(See REH section F.2)02429 Amendment No.132 355 r ll

6.0 ADMINISTRATIVE

CONTROLS 6.9 Process Control Pro ram (PCP)1.The PCP shall be approved by the Commission prior to implementation.

2.Changes to the PCP shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change(s)was made.This submittal shall contain: a.Sufficiently detailed information to totally support the change.b.A determination that the"hange did not change the overall conformance of the solidified product to existing criteria.3.Changes to the PCP shall become effective upon review and acceptance by PORC.6.10 Offsite Dose Calculational Manual (ODCM)1.The ODCM shall be approved by the Commission prior to implementation.

2.Changes to the ODCM shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change(s)was made.This submittal shall contain: a.Sufficiently detailed information to totally support the change.3.Changes to the ODCM shall become effective upon review and acceptance by PORC.6.11 RADIOLOGICAL EFFLUENT MANUAL (REM)1.The REM shall be approved by the Commission prior to implementation.

2.Changes to the REM shall be reviewed by PORC prior to implementation.

3.Changes to the REM shall be approved by the Commission prior to implementation.

0242p Amendment No.132 359 0

APPENDIX B TECHNICAL SPECIFICATIONS BROWNS FERRY UNITS 1 AND 2 0 0242p Amendment No.l32

ENVIRONMENTAL TECHNICAL SPECIFICAITONS FOR BROWNS FERRY NUCLEAR PLANT TABLE OF CONTENTS~Pa e No.1.0 DEFINITIONS........

~~~~~~~.~~~~~~~~~~~~~~~~~~~~~~~~~~~.Deleted 2.0 LIMITING CONDITIONS FOR OPERATION.

~~~~~~~~~~~~~~~~~~~~.Deleted 2.1 Thermal Discharge Limits.~~~~~~~~~~~~~~~~~~~~~~~~.2.2 Chemical............

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~.Deleted Deleted 2.2.1 Makeup Water Treatment Plant Spent Demineralizer Regerants.

~~~~~~~~~~~~~~~~.2.2.2 Chlorine.Deleted Deleted 3.0 DESIGN FEATURES AND OPERATING PRACTICES~~~~~~~~~~~~~~~.Deleted 3.1 Chemical Usage.~~Deleted 3.1.1 Oils and Hazardous Materials.

~~~~~~~~~~~~~.Deleted 3'~2 Other Chemicals.

~~~~~3.2 Land Management.

~~~~~~.~~~~~~~~~.~~~~~~~~~~~~~~~~.3.2.1'ower Plant Site.~~~~~~~~Deleted Deleted Deleted 3.2.2 Transmission Line Right-of-Way Maintenance.

3.3 Onsite

Meteorological Monitoring.

~~~~.~~~~~~.~~~~.~a'eleted 4.0 ENVIRONMENTAL SURVEILLANCE

~~~~~~~~~~~~~~~~~~~~.~~~~~~~~Deleted 4.1 Ecological Surveillance.

~~~~~.~~~~~~~~~~~~~~~~~~~-4 L alai AvlOtlc~~~~~~~~~~~~~~~~~~~~~~~~~~~~~e~~~e~4 n~1~2 Blotlc~~~~~~~~~~~~~~~e~~~~~~~~~~~~~~~~~~~~4.1.3 Special Studies~~~~~~~~~~~~~~~~~~~~~~~~~~~~Deleted Deleted Deleted Deleted 4.2 Radiological Environmental Monitoring Program.~~~~Deleted 0242p Amendment No.132 1

5.1 R'I esponsxbxlity.....................................

5.2 0 I rganizatxon..

.5.3 Review'and Audit.........

5.0 ADMINISTRATIVE

CONTROLS................................

Deleted Deleted Deleted Deleted 5.4 Action to be Taken if an Exceeded..............

Environment LCO is 5.5 Procedure..............

5.7 Environmental

Records.............................

Tables...............

Fxgurest~~~~~~~~0~~~5.6 Reporting Requirements............................

Deleted Deleted Deleted Deleted Deleted Deleted p242p Amendment No.132 r la<'E

3.2.2 Transmission

Line Ri ht-of-Wa Maintenance

~Ob ective The sole purpose of this section is to provide reporting requirements (to USNRC)on herbicide usage, if any, for purposes of right-of-way maintenance regarding only those transmission lines under USNRC's jurisdiction for the Browns Ferry Nuclear Plant~S ecification A statement as to whether or not herbicides have been used in maintaining rights-of-way for those transmission lines associated with the Browns Ferry Nuclear Plant shall be provided'f herbicides have been used, a description of the types, volumes, concentrations, manners and frequencies of application, and miles or rights-of-way that have been treated shall be included.Re ortin Re uirements Information as specified above shall be provided in the Annual Operating Report (Appendix A, Section 6.7.1(b)).

Bases Vegetation growth on a transmission line right-of-way must be controlled in such a manner that it will neither interfere with safe and reliable operation of the line or impede restoration of service when outages occur.Vegetatiori growth is controlled by mechanical cutting and the limited use of herbicides.

Selected chemicals approved by EPA for use as herbicides are assigned (by EPA)label instructions which provide guidance on and procedures for their use.0242p Amendment No.132

~pg RE0y Vp 0 Cy A 0 Pg qO++*++UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.20555 TENNESSEE VALLEY AUTHORITY DOCKET"NO.

50-260 BROMNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.128 License No.DPR-52 1.The Nuclear Regulatory Commission (the Commission) has found that: A.The applications for amendment by Tennessee Valley Authority (the licensee)dated September 30, 1986, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;B.The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.There is reasonable assurance (i)that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii)that such activities will be conducted in compliance with the Commission's regulations; D.The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public;and E.The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2)of Facility Operating License No.DPR-52 is hereby amended to read as follows:

q1 rt C (2)Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.128, are hereby incorporated in the license.The licensee shall operate the facility in accordance with the Technical Specifications.

3.This license amendment is effective as of the date of issuance and shall be implemented within 90 days from the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Daniel R.Muller, Director BWR Project Directorate 82 Division of BWR Licensing

ATTACHMENT TO LICENSE AMENDMENT NO.l28 FACILITY OPERATING LICENSE NO.DPR-52 DOCKET NO.50-260 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.The revised areas are indicated by marginal lines.~Pa ea 1 li 111 lv V Vl Vll V111 7 7A 7B 7C 51 52 54 54A 76 76A 84A 84B 103 103A 108A 108B 115A 118 179 281 282 283 284 285 286 287 288 289 290 290A 291 291A 2918 291C 291D 334A 337 338 340 355 359 Revise Appendix B as follows: Table of Contents 2 pp.

TABLE OF CONTENTS Section~Pa e No.Introduction e~~~~~~~~~~~~~~~1.0 Defxnxtxons SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 1.1/2.1 1.2/2.2 Fuel Cladding Integrity Reactor Coolant System Integrity.LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 27 3.1/4.1 3.2/4.2 Reactor Protection System Protective Instrumentation

.A.Primary Containment and Reactor Building Isolation Functions B.Core and Containment Cooling Systems-Initiation and Control 31 50 50 50 C.Control Rod Block Actuation 51 D.Radioactive Liquid Effluent Monitoring Instrumentation 51 E.Drywell Leak Detection.F.Surveillance Instrumentation

.52 52 G.Control Room Isolation.H.Flood Protection

.52 53 I.Meteorological Monitoring Instrumentation 53 J.Seismic Monitoring Instrumentation

.3.3/4.3 K.Radioactive Gaseous Effluent Instrumentation Reactivity Control A.Reactivity Limitations B.Control Rods.C.Scram Insertion Times Monitoring 54 120 120 121 124 024lp Amendment No.128

Section 3,4/4'3.5/4.5 D.'eactivity Anomalies.E.Reactivity Control F.Scram Discharge Volume.Standby Liquid Control System A.Normal System Availability

.B.Operation with Inoperable Components

.C.Sodium Pentaborate Solution Core and Containment Cooling Systems A.Core Spray System (CSS)B.Residual Heat Removal System (RHRS)(LPCI and Containment Cooling)C.RHR Service Water System and Emergency Equipment Cooling'Water System (EECWS)D.Equipment Area Coolers E.High Pressure Coolant Injection System (HPCIS)e~~~~~~~~~~~~~~~~~Fa e No.125 126 126 135 135 136 137 143 143 145 151 154 154 F.Reactor Core Isolation Cooling System (RCICS)~~~~~~~~~~'a~e~~156 G.Automatic Depressurization System (ADS)~~~e~~~~~~~~~~~~157 H.Maintenance oE Filled Discharge Pipe.I.Average Planar Linear Heat Generation R ate.~~158 159 J.Linear Heat Generation Rate (LHGR)K.Minimum Critical Power Ratio (MCPR)159 160 3.6/4.6 L.APRM Setpoints.M.Reporting Requirements Primary System Boundary A.Thermal and Pressurization Limitations

.~~160A 160A 174 174 B.Coolant Chemistry 176 0241p Amendment No.128

Section 3.7/4.7 3.8/4.8 C.Coolant Leakage D.Relief Valves E.Jet Pumps F.Recirculation Pump Operation.G.Structural Integrity.H.Seismic Restraints, Supports and Snubbers Containment Systems A.Primary Containment B.Standby Gas Treatment System.C.Secondary Containment D.Primary Containment Isolation Valves E.Control Room Emergency Ventilation

.F.Primary Containment Purge System.G.Containment Atmosphere Dilution System (CAD)H.Containment Atmosphere Monitoring (CAM)Syst H>Analyzer Radioactive Materials A.Liquid Effluents.B.Airborne Effluents.~~180 181 181 182 183 185 227 227 236 240 242 244 246 248 249 281 281 283 C.Radioactive Effluents-Dose.286 D.Mechanical Vacuum Pump.E.Miscellaneous Radioactive Materials Sources 286 287 3.9/4.9 F.Solid Radwaste.Auxiliary Electrical System A.Auxiliary Electrical Equipment B.Operation with Inoperable Equipment C.Operation in Cold Shutdown.Core Alterations

.A.Refueling Interlocks

.289 292 292 295 298 302 302 0241p Amendment No.128 Section~Pa e No.B.Core Mon~torxng C.Spent Fuel Pool Water D.Reactor Building Crane E.Spent Fuel Cask 305 305 307 307 F.Spent Fuel'ask Handling-Refueling Floor.....308 3.11/4.11 Fire Protection Systems A.High Pressure Fire Protection System.B.CO>Fire Protection System.C.Fire Detectors.315 315 319 320 D.Roving Fire Watch E.Fire Protection Systems Inspection

.F.Fire Protection Organization

.G.Air Masks and Cylinders H.Continuous Fire Watch 321 322 322 323 323 5.0 I.Open Flames, Welding Spreading Room.Major Design Features 5.1 Site Features and Burning in the Cable 323-330 330 5.2 Reactor 330 5.3 Reactor Vessel 5.4 Containment 330 330 6.0 5.5 Fuel Storage.5.6 Seismic Design.Administrative Controls 6.1 Organization

.6.2 Review and Audit 330 331 332 332 333 1v 024lp Amendment Ho.128 Section 6.3 Procedures

~~~~Pa e No.338 6.4 Actions to be Taken in the Event of a Reportable Occurrence in Plant Operation.6.5 Actions to be taken in the Event a Safety Limit is Exceeded 346 346 6.6 Station Operating Records 6.7 Reporting Requirements

6.8 Minimum

Plant Staffing 346 349 358 endment No.128 024lp W7 r LIST OF TABLES Table 0 3.1.A 4.1.A Title Surveillance Frequency Notation Reactor Protection System (SCRAM)Instrumentation Requirements

.Reactor Protection System (SCRAM)Instrumentation Functional Tests Minimum Functional Test Frequencies for Safety Instrumentation and Control Circuits~Pa e No.7c 33 37 Reactor Protection System (SCRAM)Instrument Calibration Minimum Calibration Frequencies for Reactor Protection Instrument Channels.40 3.2.A Primary Containment and Reactor Building Isolation Instrumentation 55 3.2.B Instrumentation that Initiates or Controls the Core and Containment Cooling Systems 62 3.2.C Instrumentation that Initiates Rod Blocks 73 3.2.D t 3.2.E 3.2.F 3.2.G 3.2eH 3.2.I 3.2eJ Radioactive Liquid Effluent Monitoring Instrumentation Instrumentation that Monitors Leakage Into Drywell Surveillance Instrumentation

.Control Room Isolation Instrumentation

.Flood Protection Instrumentation

.Meteorological Monitoring Instrumentation Seismic Monitoring Instrumentation

.76 77 78 81 82 83 84 3.2eK Radioactive Gaseous Effluent Monitoring Instrumentation 84A 4.2.A Surveillance Requirements for Primary Containment and Reactor Building Isolation Instrumentation

.;85 4.2.B Surveillance Requirements for Instrumentation that Initiate or Control the CSCS.89 4.2.C Surveillance Requirements for Instrumentation that Initiate Rod Blocks 102 4.2.D Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.

103 Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation

.104 024 1 Amendment Ho.1 28 024lp vl

LIST OF TABLES (;:m.1t d j;able Title 4o2e F Minimum Test and Calibration Frequency for Surveillance Instrumentation

.105 Surveillance Requirements for Control Room Isolation Instrumentation 106>>'.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation

.107 2 J Seismic Monitoring Instrument Surveillance 108 4+2.ÃRadioactive Gaseous Effluent Instrumentation Surve1llance 108A 3.5-'1 3~3~Hinimum RHRSW and EECW Pump Assignment 6'fAPLHGR Uersus Average Planar Exposure 152a 171, 172, 3.7.A Primary Containment Isolation Valves.250 3.7.B Testable Penetrations with Double 0-Ring Seals 256 3.7.C 3.7.D Testable Penetrations with Testable Bellows Air Tested Isolation Valves~~257 258 3.7.E Primary Containment Isolation Valves which Terminate below the Suppression Pool Water L evel 262 3.7.F Primary Containment Isolation Valves Located Water Sealed Seismic Class 1 Lines in 263 3.7.H Testable Electrical Penetrations

.265 4.9.A.4.C Uoltage Relay Setpoints/Diesel Generator Start 298a 3.11.A 6.8.A Fire Protection System Hydraulic Requirements Hinimum Shift Crew Requirements 324 360 Amendment No.128 V11 024:p

LIST OF ILLUSTRATIONS

~Fi ere Title~pa e No.2.1.1~~APRM Flow Reference Scram and APRM Rod Block S t et t lngs~~~~~~~~~~~~~~~~~~~13 2.1-2 APRM Flow Bias Scram,Vs.Reactor Core Flow.26 4.1-1 Graphic Aid in the Selection of an Adequate Interval Between Tests 49 4.2-1 System Unavailability 119 3.4-1 Sodium Pentaborate Solution Volume Concentration Requirements

.138 3.4-2 Sodium Pentaborate Solution Temperature Requirements 139 3.5.K-1.MCPR Limits 172a 3.5.2<Factor K 173 3.6-1 Minimum Temperature

'F Above Change in Transient Temperature 194 3.6-2 Change in Charpy V Transition Temperature Vs.Neutron Exposure.195 Gaseous Release Points and Elevations 290 4.8.1b Land Site Boundary.290A 6.1-1 TVA Office of Power Organization for of Nuclear Power Plant Operation 361 6.1-2 6.2-1 Functional Organization Review and Audit Function 362 363 6.3-1 In-Plant Fire Program Organization

.364 Amendment No.128 v111 02419

~'r~4

1.0 DEFINITIONS

(Cont'd)10.~Lo'c-A logic is an arrangement od relays, contacts, and other components that produces a decision output.ia)~initiatin

-A logic that receive signals from channeis and produce decision outputs to the actuation logic.(b)Actuation-A logic that receives signals (either from initiation logic or channels)and produces decision outputs to accomplish a protective action.11.Channel Calibration

-Shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel monitors.The channel calibration shall encompass the entire channel including alarm and/or trip functions and shall include the channel functional test.The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

Non-calibratable components shall be excluded from this requirement, but will be included in channel functional test and source check.12.Channel Functional Test-Shall be: a.Analog Channels-the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b.Bistable channels-the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

13.Source Check-Shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources.Amendment No.128 0242p 0 c'L ,I

1.0 DEFINITIONS

(Cont'd)Functional Tests-A functional test is the manual operation or initiation of a system, subsystem, or components to verify that it functions within design tolerances (e.g., the manual start of a core spray pump to verify that it runs and that it pumps the required volume of water).X.Shutdown-The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.

Y.En ineered Safe uard-An engineered safeguard is a safety system the actions of which are essential to a safety action required in response to accidents.

Z.Reportable Event-A r portable event shall be any of those conditions specified in section 50.73 to 10 CFR Part 50.BB.Solidification

-Shall be the conversion of radioactive wastes into a form that meets shipping and burial ground requirements..

Offsite Dose Calculation Manual (ODCM)-Shall be a manual describing the environmental monitoring program and the methodology and parameters used in the calculation of release rate limits and offsite doses due to radioactive gaseous and and liquid effluents.

The ODCM will also provide the plant'with guidance for establishing alarm/trip setpoints to ensure technical specifications sections 3.8.A.1 and 3.8.B.1 are not exceeded.CC.Pur e or our in-The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is required to purify the containment.

DD.Process Control Pro ram-Shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.EE.Radiolo ical Effluent Manual (REM)-Shall be a manual containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposure to individuals from station operation.

It shall also specify operating guidelines for radioactive waste treatment systems and report content.FF.p~entin-The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required.Vent, used in system names, does not imply a venting process.0242&Amendment No.128 7A

• ~0

1.0 DEFINITIONS

(Cont'd)GG.owned, leased, or otherwise controlled by TVA.HH.Unrestricted Area-Any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for industrial, commercial, institutional, or recreational purposes.Dose E uivalent I-131-The DOSE EQUIVALENT I-131 shall be the concentration of I-131 (in pCi/gm)which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.The thyroid dose conversion factor used for this calculation shall be those listed in Table III of TID-14844"Calculation of Distance Factors for Power and Test Reactor Sites".Gaseous Waste Treatment S stem-The charcoal adsorber vessels installed on the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release.Members of the Public-Shall'nclude all individuals who by virtue of their occupational status have no formal association with the plant.This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.

This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter restricted areas.LL.Surveillance

-Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements.

Each surveillance Requirement shall be performed within the specified time interval with, (1)A maximum allowable extention not to exceed 25K of the surveillance interval, but (2)The combined time entered for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications.

Surveillance requirements do not have to be performed on inoperable equipment.

0242p Amendment Ho.128 7B 4

Table 1.1 SURVEILLANCE FRE UENCY NOTATION NOTATION FRE UENCY S (Shift)D (Daily)I W (Weekly)M (Monthly)Q (Quarterly)

SA (Semi-Annually Y (Yearly)R (Refueling)

S/U (Start-Up)

N.A.P (Prior)At least once per 12, hours.At least once per normal calendar 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day (midnight to midnight).

At least once per 7 days.At least once per 31 days.At least once per 3 months or 92 days.At least once per 6 months or 184 days.At least once per year or 366 days.At least once per operating cycle.Prior to each reactor startup.Not applicable.

Completed prior to each release.Amendment No.128 7C 0242p Ir a LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.Q.B Core and Containment Coolin S stems-Initiation 6 Control 4.2.B Core and Containment Coolin S stems-Initiation 6 Control I C.Control Rod Block Actuation are required to be operable shall be considered operable if they are within the required surveillance testing frequency and there is no reason to suspect that they are inoperable.

C.Control Rod Block Actuation The limiting conditions of.operation for the instrumentation that initiates control rod block are given in Table 3.2.C.Instrumentation shall be functionally tested, calibrated, and checked as indicated in Table 4.2.C.System logic shall be functionally tested as indicated in Table 4.2.C.3.2.D Radioactive Li uid Effluent Monitorin Instrumentation 1.The radioactive liquid effluent monitoring instrumentation listed in Table 3.2.D shall be operable with the applicability as shown in Tables 3.2.D/4.2.D.

Alarm/trip setpoints will be set in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.A.l are not exceeded.4.2.D Radioactive Li uid Effluent Monitorin Instrumentation v l.Each of the radioactive liquid effluent monitoring instruments shall be demonstrated operable by performance of test in accordance with Table 4.2.D.2.The action required when the number of operable channels is less than the minimum channels operable requirement is specified in the notes for Table 3.2.D.Exert best efforts to return the instrument(s) to OPERABLE status within 30 days and if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.51 Amendment No.128 0233p eA,~0 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.D Radioactive Li uid Effluent (Con't)4.2.D Radioactive Li uid Effluent (Con't)With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these specifications.

4.The provisions of specification 1.0.C and 6.7.2 are not applicable.

E.Dr ell Leak Detection E.Dr ell Leak Detection The limiting conditions of operation for the instrumentation that monitors drywell leak detection are given in Table 3.2.E.Instrumentation shall be calibrated and checked as indicated in Table 4.2.E.F.Surveillance Instrumentation F.Surveillance Instrumentation The limiting conditions for the instrumentation that provides surveillance information readouts are given in Table 3.2.F.Instrumentation shall be calibrated and checked as indicated in Table 4.2.F.G.Control Room Isolation G.Control Room Isolation The limiting conditions for instrumentation that isolates the control room and initiates the control room emergency pressurization systems are given in Table 3.2.G.Instrumentation shall be calibrated and checked as indicated in Table 4.2.G.Amendment No.128 52 0233p

/4I't' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.J Seismic Monitorin Instrumentation 4.2.J Seismic Monitorin Instrumentation 2.3.The seismic monitoring instruments listed in Table 3.2.J shall be operable at all times.With the number of seismic monitoring instruments less than the number listed in Table 3.2.J, restore the inoperable instrument(s) to operable status within 30 days.With one or more of the instruments listed in Table 3.2.J inoperable for more than 30 days, submi,t a Special Report to the Commission pursuant to specification 6.7.3.C within the next 10 days describing the cause of the malfunction and plans for restoring the instruments to operable status.1.Each of the seismic monitoring instruments shall be demonstrated operable by performance of tests at the frequencies listed in Table 4.2.J.2.Data shall be retrieved from all seismic instruments actuated during a seismic event and analyzed to determine the magnitude of the vibratory ground motion.A Special Report shall be submitted to the Commission pursuant to specification 6.7.3.D within 10 days describing the magnitude, frequency spectrum, and resultant effect upon plant features important to safety.3.2.K Radioactive Gaseous Effluent Monitorin Instrumentation 4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation The radioactive gaseous effluent monitoring instruments listed in Table 3.2.K shall be operable with the applicability as shown in Tables 3.2.K/4.2.K.

Alarm/-trip setpoints will be set in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.B.l are not exceeded.'.

Each of the radioactive gaseous effluent monitoring instruments shall be demonstrated operable by performance of tests in accordance with Table 4.2.K.Amendment No.128 54 0233p l4 4 I' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.K Radioactive Gaseous Effluent Monitorin Instrumentation (Con't)4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation (Con't)2.The action required when the number of operable channels is less than the Minimum Channels Operable requirement is specified in the notes for Table 3.2.K.Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Release Report why the inoperability was not corrected in a timely manner.3.With a radioactive gaseous effluent monitoring channel alarm/trip setpoint less conservative than required by these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these specifications.

4.Both off-gas treatment monitors may be taken out of service for less than one hour for purging of monitors during SI performance.

5.The provisions of specifications 1.0.C and 6.7.2 are not applicable.

54A 0233p

TABLE 3.2.D Radioactive Li uid Effluent Monitorin Instrumentation Instrument

'1.LIQUID RADHASTE EFFLUENT MONITOR (RM-90-130) 2.RHR SERVICE HATER MONITOR (RM-90-133,-134)3.RAH COOLING HATER MONITOR (RM-90-132) 4.LIQUID RADHASTE EFFLUENT FLOH RATE (77-60 loop excluding fixed in line rotometer)

Minimum Channels 0 erable A 1 i cab i 1 i t Action A, B Amendment No.128 0240p 76 l

NOTES FOR TABLE 3.2.D~'<At all times'~~During releases via this pathway i'~'-::During operation of an RHR loop and associated RHR service water system ACTION A During release of radioactive wastes from the radwaste processing system, the following shall be met (1)liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in 3.8.A.1, (2)if this cannot be met, two independent samples of the tank being discharged shall be analyzed in accordance with the sampling and analysis program specified in the REM and two qualified station personnel shall independently verify the release rate calculations and check valving before the discharge.

Otherwise, suspend release via this pathway.ACTION B With a radioactive liquid effluent monitoring channel/alarm trip setpoint less conservative than required by these specifications, suspend release via this pathway without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism referred by these specifications.

ACTION C During operation of an RHR loop and associated RHR service water system, the effluent from that unit's service water shall be continuously monitored.

If an installed monitoring system is not available, a temporary monitor or grab samples taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and an analysis of at least an LLDf lE-7 pCi/ml (gross)or<applicable MPC ratio (y isotopic)shall be used to monitor the effluent.ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continued provided that a temporary monitor is installed or, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for radioactivity with an LLDf 1E-7 pCi/ml (gross)or<applicable MPC ratio (y isotopic).

ACTION E'-'ith the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continued provided the flow rate 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.Pump curves may be used to estimate flow.ACTION F Alarm/trip setpoints will be calculated in accordance with the guidance given in the Offsite Dose Calculation Manual (ODCM).(1)See REM, TABLE NOTATIONS-TABLE C-l, for the definition of LLD.Amendment No.128 0242p 76A I

LE 3.2.K Radioactive Gaseous Effluent Monitorin Instrumentation Instrument 1I.STACK (RM-90-147A 5 B)a.Noble Gas Monitor b.Iodine Cartridge c.Particulate Filter d.Sampler Flow Abnormal e.Stack Flow (FT, FM, FI-90-271) 2.REACTOR/TURBINE BLDG VENTILATION (RM-90-250) a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter 3.TURBINE BLDG EXHAUST (RM-90-249, 251)a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter 4.RADWASTE BLDG VENT (RM-90-252) a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter 5.OFF GAS HYDROGEN ANALYZER (HgA, HgB)6.OFF GAS POST TREATMENT a.Noble Gas Activity Monitor (RM-90-265, 266)b.Sample Flow Abnormal (PA-90-262)

Minimum Channels/Devices 0 erable (1)(1)(1)(1)(1)(1)(1)(1)(1)(1)(1)(1)(1)(1)(1)(1)(1)A 1 i cabi 1 i t*Action A/C B/C B/C D D A/C B/C B/C D A/C B/C B/C D A/C B/C B/C D 0240p Amendment No.128 84A gt'g ,/

NOTES FOR TABLE 3.2.K'iAt all times"~'During releases via this pathway"~~':During main condenser offgas treatment system operation ACTION A With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via the affected pathway may continue provided a temporary monitoring system is installed or grab samples are taken and analyzed at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.ACTION B With a number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continued provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7)days and analyzed in accordance with the sampling and analysis program specified in the REM 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.ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for functional testing, calibration, or repair without providing or initiating grab sampling.ACTION D t With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided the flow rate 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 />.ACTION E With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, operation of main condenser offgas treatment system may continue provided that a temporary monitor is installed or grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.ACTION F 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 at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 />.Purging during SI performance is not considered a loss of monitoring capability.

Amendment No.128 0242p 84B 0

TABLE 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation Surveillance Re uirements iInstrument 1.LIQUID RADWASTE EFFLUENT MONITOR<RM-90-130) 2.RHR SERVICE HATER MONITOR (RM-90-133,-134)3.RAH COOLING WATER MONITOR (RM-90-132) 4.LIQUID RADWASTE EFFLUENT FLOW RATE (77-60 loop)Instrument Check D(4)D,(4)D(4)D(4)Source Check Channel Calibration R(5)R(5)R(5)Functional Test Q(1)Q(2)Q(2)Q(3)Amendment No.128 0240p 103

~A P t t~(~-

NOTES FOR TABLE 4.2.D (1)The channel functional test shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint b.Instrument indicates an inoperative/downscale failure c.Instrument controls not set in operate mode (2)The channel functional test shall also demonstrate that control room annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint b.Instrument indicates an inoperative/downscale failure c.Instrument controls not set in operate mode (3)This functional test shall consist of measuring rate of tank decrease over a period of time and comparing this value with flow rate instrument reading.(4)INSTRUMENT CHECK shall consist of verifying indication during periods of release.INSTRUMENT CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days which continuous, periodic, or batch releases are made.(5)The CHANNEL CALIBRATION shall include the use of a known (traceable to National Bureau of Standards Radiation Measurement System)radioactive source(s)positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards (NBS).Amendment No.128 0242p 103A 1 s1 0 TABLE 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance Instrument STACK a.Noble Gas Monitor'b.Iodine Cartridge c.Particulate Filter d.Sampler Flow Abnormal e.Stack Flowmeter Instrument Check Source Check M NA NA NA NA Channel Calibration R()NA NA R R Functional Test Q(2)NA NA Q Q 2.3.4.5.6.REACTOR/TURBINE BLDG VENT a.Noble Gas Monitor"'.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter TURBINE BLDG EXHAUST a.Noble Gas Monitor'b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter RADWASTE BLDG VENT a.Noble Gas Monitor"'.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter OFF GAS HYDROGEN ANALYZER (HpA, HpB)OFF GAS POST TREATMENT.Noble Gas Activity Monitor b.Sample Flow Abnormal M NA NA NA.M NA NA-NA M NA NA~NA R(I)NA NA R R"'A NA R R(I)NA NA R R(3)R(1)R Q(Z)NA NA Q QtÃ)NA NA Q Q(Z)NA NA Q Q(4)Q(4)Q(t)0240p Amendment No.128 108A 1i NOTES FOR TABLE 4.2.K (1)The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of Standards Radiation Measurement System)radioactive source(s)positioned in a reproducible geometry with respect to the sensor or using standards that have obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards.

(2)The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint.b.Instrument indicates an inoperative/downscale failure.c.Instrument controls not set in operate mode (stack only).(3)The channel calibration shall include the use of standard gas samples containing a nominal: a.Zero volume percent hydrogen (compressed air)and, b.One volume percent hydrogen, balance nitrogen.(4)The channel functional test shall demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exists: a.Instrument indicates measured level above the alarm/trip setpoint.b.Instrument indicates an inoperative/downscale failure.c.Instrument controls not set in operate mode.The two channels are arranged in a coincidence logic such that 2 upscale, or 1 downscale and 1 upscale or 2 downscale will isolate the offgas line.(5)The noble gas monitor shall have a LLD of lE-5 (Xe 133 Equivalent).

(6)The noble gas monitor shall have a LLD of 1E-6 (Xe 133 Equivalent).

Amendment No.128 108B 0242p Vgi 0 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 osseous-effluents.

Zhe alarm/trip setpoints for these instruments will be calculated in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.This instrumentation also includes provisions for monitoring the concentration of potentially explosive gas mixtures in the offgas holdup system.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.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 in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior.to exceeding the limits of 10 CFR Part 20 Appendix B, Table II, Column 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 50.115A 0242p

4.2 BASES

e there is no true minimum.The curve does have a definite knee and very little reduction in system unavailability is achieved by testing at a shorter.interval than computed by the equation for a single channel.The best test procedure of all those examined is to perfectly stagger the tests.That is, if the test interval is four months, test one or the other channel every two months.This is shown in Curve No.5.The difference between Cases 4 and 5 is negligible.

There may be other arguments, however, that more strongly support the perfectly staggered tests, including reductions in human error.The conclusions to be drawn are these: l.A 1 out of n system may be treated the same as a single channel in terms of choosing a test interval;and 2.more than one channel should not be bypassed for testing at any one time.The radiation monitors in the refueling area ventilation duct which initiate building isolation and standby gas treatment operation are arranged in two 1 out of 2 logic systems.The bases given for the rod blocks apply here also and were used to arrive at the functional testing frequency.

The off-gas post treatment monitors are connected in a 2 out of 2 logic arrangement.

Based on experience with instruments of similar design, a testing interval of once every three months has been found adequate.The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also.The criteria for ensuring the reliability and accuracy of the radioactive gaseous effluent instrumentation is listed in Table 4.2.K.The criteria for ensuring the reliability and accuracy of the radioactive liquid effluent instrumentation is listed in Table 4.2.D.Amendment No.128 118 02429

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

3.6 Primar

S stem Boundar 4.6 Primar S stem Boundar 6.Whenever the reactor is critical, the limits on activity concentrations in the reactor coolant shall not exceed the equilibrium value of 3.2 pc/gm of does equivalent I-131.6.Additional coolant samples.shall be taken whenever the reactor activity exceeds one percent of the equilibrium concentration specified in 3.6.B.6 and one of the following conditions are met: This limit may be exceeded following power transients for a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.During this activity transient the iodine concentrations shall not exceed 26 pCi/gm whenever the reactor is critical.The reactor shall not be operated more than 5 percent of its yearly power operation under this exception for the equilibrium activity limits.If the iodine concentration in the coolant exceeds 26 pCi/gm, the reactor shall be shut down, and the steam line isolation valves shall be closed immediately.

a.During startup b.Following a significant power change<'<c.Following an increase in the equilibrium off-gas level exceeding 10,000 pCi/sec (at the steam jet air ejector)within a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.d.Whenever the equilibrium iodine limit specified in 3.6.B.6 is exceeded.The additional coolant liquid samples shall be taken at 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or until a stable iodine concentration below the limiting value (3.2 pCi/gm)is established.

However, at least 3 consecutive samples shall be taken in all cases.An isotopic analysis shall be performed for each.-sample, and quantitative measurements made to determine the dose equivalent I-131 concentration.

If the total iodine activity of the sample is below 0.32 pCi/gm, an isotopic analysis to determine equivalent I-131 is not required."r'rFor the purpose of thi s sec t ion on sampling frequency, a significant power exchange is defined as a change exceeding 15K of rated power in less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.179 0233 ent No.1 28 0233p 0

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMER1S 3.8 Radioactive Materials 4.8 Radioactive Materials A licabilit Applies to the release of radioactive liquids and gases from the facility.O~b'ective To define the limits and conditions for the release of radioactive effluents to the environs to assure that any.radioactive releases are as low as reasonably achievable and within the limits of 10 CFR Part 20.The specifications except for 3.8.A.1 and 3.8.B.1 are exempt from the requirements of definition 1.0.C (Limiting Condition for Operation).

S ecification A.Li uid Effluents 1.The concentration of radioactive material released at any time from the site to unrestricted areas (see Figure 4.8-lb)shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II,;Column 2 for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity.2.If the limits of 3.8.A.1 are exceeded, appropriate action shall be initiated without delay to bring the release within Applies to the periodic test and record requirements and sampling and monitoring methods used for facility effluents.

~Ob ective To ensure that radioactive liquid and gaseous releases from the facility are maintained within the limits specified by Specifications 3.8.A and 3.8.B.A.Li uid Effluents 1.Facility records shall be maintained of radioactive concentrations and volume before dilution of each batch of liquid effluent released, and of the average dilution flow and length of time over which each discharge occurred.2.Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with the sampling and analysis program specified in the REM.3.The operation of the automatic isolation valves and discharge tank selection valves shall be, checked annually.Amendment No.128 281 0233p gl E'l~I Ci LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

3.8 Radioactive

Materials 4.8 Radioactive Materials 3.limits.Provide prompt notification to the NRC pursuant to section 6.7;2.The doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas (See Figure 4.8-1b)shall be limited: 4.The results of the analysis of samples collected from release points shall be used with the calculational methodology in the ODCM to assure that the concentrations at the point of release are maintained within the limits of specification 3.8.A.1.4~5.a.During any calendar quarter to<1.5 mrem to the total body and<5 mrem to any organ and, b.During any calendar year to<3 mrem to the total body and<10 mrem to any organ If the limits specified in 3.8.A.3 a 6 b above are exceeded, prepare and submit Special Report pursuant to Section 6.7.2.The maximum activity to be contained in one liquid radwaste tank or temporary storage tank that can be discharged directly to the environs shall not exceed 10 curies excluding tritium and dissolved/entrained noble gas.5.Cummulative quarterly and yearly dose contributions from liquid effluents shall be determined as specified in the ODCM at least once every 31 days.6.The quantity of radioactive material contained in any outside liquid radwaste storage tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.6.With radioactive liquid waste exceeding 3.8.A.5 limits, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit.Events leading to this condition must be reported in the next Semiannual Radioactive Effluent Release Report (section F.2 of the REM)Amendment No.128 0233p 282

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials B.Airborne Effluents 4.8 Radioactive Materials B.Airborne Effluents 1.The dose rate at any time to areas at and beyond the site boundary (see Figure 4.8-1b)due to radioactivity released in gaseous effluents from the site shall be limited to the following values: a.The dose rate limit for noble gases shall be<500 mrem/yr to the total body and<3000 mrem/yr to the skin, and b.The dose rate limit for I-131, I-133, H-3, and particulates with greater than eight day half-lives shall be<1500 mrem/yr to any organ.2.If the'limits of 3.8.B.1 are exceeded, appropriate corrective action shall be immediately initiated to bring the release within limits.Provide prompt notification to the NRC pursuant to section 6.7.2.1.The gross 0/y and particulate activity of gaseous wastes released to the environment shall be monitored and recorded.a.For effluent streams having continuous monitoring capability, the activity shall be monitored and flow rate evaluated and recorded to enable release rates of gross radioactivity to be determined at least once per shift using'nstruments specified in table 3.2.K.b.For effluent streams without continuous monxtorxng capability, the activity shall be monitored and recorded and the release through these streams controlled to within the limits specified in 3.8.B.2.Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with the sampling and analysis program specified in the REM.Dose rates shall be determined to be within limits of 3.8.B using methods contained in the ODCM.283 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.The air dose to areas at and beyond the site boundary (see Figure 4.8-lb)due to noble gases released in gaseous effluents per unit shall be limited to the following:

3.Cumulative quarterly aud yearly dose contributions from gaseous releases shall be determined using methods contained in the ODCM at least once every 31 days.a.During any calendar quarter, to<5 mrad for gamma radiation and<10 mrad for beta radiation; b.During any calendar year, to<10 mrad for gamma radiation and<20 mrad for beta radiation.

4.If the calculated air dose exceeds the limits specified in 3.8.B.3 above, prepare and submit a special report pursuant to section 6.7.2.5.The dose to a member of the public from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than 8 days in gaseous effluent released per unit to areas at and beyond the site boundary (see Figure 4.8-1b)shall be limited to the following:

a.To any organ during any calendar quarter to<7.5 mrem;b.To any organ during any calendar year to<15 mrem;Amendment No.128 284 0233p LIMITING CONDITIONS FOR OPERATION 6.If the calculated doses exceed the limits of 3.8.B.5 above, prepare ,and submit a special report pursuant to section 6.7.2.SURVEILLANCE RE UIREMENTS 4.During operation above 25K power, the position of the charcoal bed bypass valve will be verified daily.7.During operation above 25K po~er the discharge of the SJAE must be routed through the charcoal adsorbers.

8.With gaseous waste being discharged for more than 7 days without treatment through the charcoal adsorbers, prepare and submit a special report pursuant to section 6.7.2.5.The concentration of hydrogen downstream of the recombiners shall be determined to be within the limits of 3.8.B.9 by continuously monitoring the offgass whenever the SJAE is in service using instruments described in Table 3.2.K.Instrument surveillance requirements are specified in Table 4.2.K.9.Whenever the SJAE is in service, the concentration of hydrogen in the offgas downstream of the recombiners shall be limited to (4X by volume.10.With the concentration of hydrogen exceeding the limit of 3.8.B.9 above, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.285 0233p LIMITING CONDITIONS FOR OPERATION 3.8.C Radioactive Effluents-Dose SURVEILLANCE RE UIREMENTS 4.8.C Radioactive Effluents-Dose 1.The dose or dosecommitment to a real individual from all uranium fuel cycle sources is limited to<25 mrem to the total body or any organ (except the thyroid, which is limited to<75 mrem)over a period of one calendar year.1.Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with specifications 3.8.A.3, 3.8.B.3, and 3.8.B.5 and the methods in the ODCM.2.With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of specification 3.8.A.3, 3.8.B.3, or 3.8.B.5, prepare and submit a Special Report to the Commission pursuant to specification 6.7.2 and limit the subsequent releases such that the limits of 3.8.C.1 are not exceeded.3.8.D Mechanical Vacuum Pum Each mechanical vacuum pump shall be capable of being automatically isolated and secured on a signal or high radioactivity in the steam lines whenever, the main steam isolation valves are open.4.8.D Mechanical Vacuum Pum At least once during each operating cycle verify automatic securing and isolation of the mechanical vacuum pump.2.If the limits of 3.8.D are not met, the vacuum pump shall be isolated.Amendment No.128 286 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials 4.8.C Radioactive Materials E.Miscellaneous Radioactive Materials Sources E.Miscellaneous Radioactive Materials Sources 1.Source Leaka e Test 1.Surveillance Re uirement'ach sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of>0.005 microcurie of removable contamination.

Each sealed souce with removable contamination in excess of the above limit shall be immediately withdrawn from use and (a)either decontaminated and repaired, or (b)disposed of in accordance with Commission regulations.

Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an agreement State, as follows: a.Sources in Use Each sealed source, excluding startup sources and flux detectors previously subjected to core flux, containing radioactive material, other than Hydrogen 3, with a half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at least once per six months.The leakage test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample.287 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 0 4.8.E Miscellaneous Radioactive Materials Sources 1.Surveillance Re uirements b.Stored Sources Not In Use Each sealed source and fission detector not previously subjected to core flux shall be tested prior to use or transfer to another licensee unless tested within the previous six months.Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to use.c.Startu Sources and Fission Detectors Each sealed startup source and fission detector shall be tested prior to being subjected to core flux and following repair or maintenance to the.source.2.Rior ts A report shall be prepared and submitted to the Commission on an annual basis if sealed sources or fission detector leakage tests reveal the presence of greater than or equal to 0.005 mxcrocurxes of removable contamination.

Amendment No.128 288 0233p N

3.8 LIMITING

CONDITIONS FOR OPERATION Radioactive Materials 4.8 SURVEILLANCE RE UIREMENTS Radioactive Materials F.Solid Radwaste F.Solid Radwaste 1.The solid radwaste system shall be operated in accordance'ith a process control program, for the solidification and packaging of wet radioactive wastes to ensure meeting the requirements of 10 CFR 20 and 10 CFR 71 and burial ground requirements prior to shipment of radioactive wastes from the site.1.The Process Control Program shall include surveillance checks necessary to demonstrate compliance with 3.8.F.1.2.With the packaging requirements of 10 CFR 20 or burial ground , requirements and/or 10 CFR 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site.t Amendment No.128 289 0233p C

Switchyard Turbine Building Exhaust Fan (32m)~Office Building Service Bldg.Turbine Building ad-4aste Bldg.Reactor Building Stack (180m)Reactor Building Ventilation (40m)Figure 4.8-la GASEOUS REI.EASE POlNTS AND ELEVATIONS 290 Amendment No.128 0

Figure 4.8-lb LAND SITE BOUNDARY'~~.*Up~~eu weal:, lz i"'.'.lqufd Dlseherrc (l)lf fueer Pl pew)~llh a w IQel~ecwrr.ltrer

~.,<>rw awe>l elle 2 ulled 290A Amendment No.128 4

3.8 BASES

Radioactive waste release levels to unrestricted areas shouTd be kept"as low as reasonably achievable" and are not to exceed the concentration limits specified in 10 CFR Part 20.At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual oper'ating conditions which may temporarily result in releases higher than design objectives but still within the concentration limits specified in 10 CFR Part 20.It is expected that by using this operational flexibility and exerting every effort to keep levels or radioactive materials released as low as reasonably achievable in accordance with criteria established in 10 CFR 50 Appendix I, the annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR Part 20.Specification 3.8.A.1 is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1)the Section 11.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2)the limits of 10 CFR Part 20.106(e)to the population.

The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)Publication 2.Specification 3.8.A.3 is provided to implement the dose requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50.The Limiting Condition for Operation implements the guides set forth the Section 11.A of Appendix I.Specification 3.8.A.4 action statements provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept"as low as is reasonably achievable".

Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by Amendment No.128 291 0242p C~,p P

.*~(*calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.3.8.B AIRBORNE EFFLUENTS Specification 3.8.B.1 is provided to ensure that the dose rate at anytime at the exclusion boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas.The annual dose limits are the doses associated with the concentrations of 10 CFR part 20, Appendix B, Table II, Column 1.These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a member of the public in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).

Fo'r members of the public who may at times be within the exclusion area 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 exclusion area boundary.0 Amendment No.128 291A 0242p IQ 1 ll 4 3.8.B AIRBORNE EFFLUENTS (cont'd)The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to<500 mrem/year to the total body or to<3000 mrem/year to the skin.These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to<1500 mrem/year for the nearest cow to the plant.Specification 3.8.B.2 requires that appropriate correction action(s)be taken to reduce gaseous effluent releases if the limits of 3.8.B.1 are exceeded.Specification 3.8.B.5 dose limits is provided to implement the requirements of Section II.C, III.A, and IV of Appendix I, 10 CFR Part 50.The limiting conditions for operation are the guides set forth in Section II.C of Appendix I.Specification 3.8.B.6 action statement provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational proc'edures based, on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methods used for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109,"Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977, NUREG/CR-1004,"A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides", October 1979, and Regulatory Guide 1.111,"Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for radioiodines,.radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.The pathways which are examined in the development of these calculations are: 1)individual inhalation of airborne radionuclides, 2)deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3)deposition onto grassy areas where milk animal and meat producing animals graze with consumption of the milk and meat by man, and 4)deposition on the ground with subsequent exposure of man.Specification 3.8.B.6 action statement requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.5.Amendment No.128 291B 0242p Ql ,t~t 4-I, C V

AIRBORNE EFFLUENTS Specification 3.8.B.7 requires that the offgas charcoal adsoiber beds be used when specified to treat gaseous effluents prior to their release to the environment.

This provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

Specification 3.8.B.8 requires that a special report be prepared and submitted to explain reasons for any failure to comply with Specification 3.8.B.7.Specification 3.8.B.3 is provided to implement the requirements of Section II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50.The Limiting Condition for Operation implements the guide set forth in Section II.C of Appendix I.Specification 3.8.B.4 action statement provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated.

The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109,"Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the.Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1 October 1977, NUREGICR-1004,"A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides", October 1979 and Regulatory Guide 1.111,"Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.The ODCM, equations provided for determining the air doses at the exclusion area boundary will be based upon the historical average atmospheric conditions.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.Specifications 3.8.B.4 requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.3.4.8.A and 4.8.B BASES The surveillance requirements given under Specification 4.8.A and 4 8.B provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release of radioactive materials in the liquid and Amendment No.128 0242p 291C

4.8.A and 4.8.B BASES (cont'd)gaseous effluents.

These surveillance requirements provide the data~or the licensee and the Commission to evaluate the station's performance relative to~radioactive wastes released to the environment.

Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 6 of these technical specifications.

On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such actions as the Commission deems appropriate.

3.8.C and 4.8.C BASES This specification is provided to meet the dose limitations of 40 CFR 190.The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I.For sites containing up to four reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level.The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for the calendar year to be within 40 CFR 190 limits.For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose-contributions from other nuclear fuel cycle facilities at the same site or within a radius of five miles must be considered.

3.8.D and 4.8.D MECHANICAL VACUUM PUMP The purpose of isolating the mechanical vacuum pump line is to limit the release of activity from the main condenser.

During an accident, fission products would be transported from the reactor through the main steam lines to the condenser.

The fission product radioactivity would be sensed by the main steam line radioactivity monitors which initiate isolation.

3.8.E and 4.SEE BASES The limitations on removable contamination for sources requiring leak testing, including alpha emitters, based on 10 CFR 70.39(c)limits for plutonium.

This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group.Those sources which are frequently handled are required to be tested more often than those which are not.Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices)are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

Amendment No.128 0242p 291D 1.C>n'i

6.0 ADMINISTRATIVE

CONTROLS k.The radiological environmental monitoring program and the results thereof at least once per 12 months.l.The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev.1, 1974 and Regulatory Guide 4.1, 1975 at least once per 12 months.m.The performance of activities required by the Safeguards Contingency Plan to meet the criteria of 10 CFR 73.40(d)at least once per 12 months.n.The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.o.The Process Control Program and implementing procedures for solidification of wet radioactive wastes at least once per 24 months.p.The Radiological Effluent Manual and implementing procedures at least once per 12 months.9.AUTHORITY The NSRB shall report to and advise the Manager of Power on those areas of responsibility specified in Sections 6.2.A.7 and 6.2.A.8.10.RECORDS Records of NSRB activities shall be prepared, approved and distributed as indicated below: a.Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Manager of Power within 14 days following each meeting.b.Reports of reviews encompassed by Section 6.2.A.7 above, shall be prepared, approved and forwarded to the Manager of Power within 14 days following completion of the review.c.Audit reports encompassed by Section 6.2.A.8 above, shall be forwarded to the Manager of Power and to the management positions responsible for the areas audited within 30 days after completion of the audit.Amendment No.128 334A 0242p

6.0 ADMINISTRATIVE

CONTROLS j.Review proposed changes to the Radiological Effluent Manual.k.Review adequacy of the Process Control Program and Offsite Dose Calculation Manual at least once every 24 months.1.Review changes to the radwaste treatment systems.m.Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendation, and deposition of the corrective action to prevent recurrence to the Director, Nuclear Power and to the Nuclear Safety Review Board.5.A~uthorit 6.The PORC shall be advisory to the plant superintendent.

Records Minutes shall be kept for all PORC meetings with copies sent,to Director, Nuclear Power;Assistant Director of Nuclear Power (Operations);

Chairman, NSRB.7.Procedures Written administrative procedures for committee operation shall be prepared and maintained describing the method for submission and content of presentations to the committee, review and approval by members of'committee actions, dissemination of minutes, agenda and scheduling of meetings.Amendment No.128 0242p 337

'I~C

6.0 ADMINISTRATIVE

CONTROLS 6.3 Procedures A.Detailed written procedures, including applicable checkoff lists covering items listed below shall be prepared, approved and adhered to.1.Normal startup, operation and shutdown of the reactor and of all systems and components involving nuclear safety of the facility.E 2.Refueling operations.

3.Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks and abnormal reactivity changes.4." Emergency conditions involving potential or actual release of radioactivity.

5.Preventive or corrective maintenance operations which could have an effect on the safety of the reactor.6.Surveillance and testing requirements.

7.Radiation control procedures.

8.Radiological Emergency Plan implementing procedures.

9.Plant security program implementing procedures.

10.Fire protection and prevention procedures.

ll.Limitations on the amount of overtime worked by individuals performing safety-related functions in accordance with the NRC policy statement on working hours (Generic Letter No.82-12).12.Radiological Effluent Manual implementing procedures.

13.Process Control Program (PCP).14.Offsite Dose Calculation Manual.B.Written procedures pertaining to those items listed above shall be reviewed by PORC and approved by the plant superintendent prior to implementation.

Temporary changes to a procedures which do not change the intent of the approved procedure may be made by a member of the plant staff knowledgeable in the area affected by the procedure except that temporary changes to those items listed above except item 5 require the additional approval of a member of the plant staff who holds a Senior Reactor Operator license on the unit affected.Such changes shall be documented and subsequently reviewed by PORC and approved by the plant superintendent.

Amendment No.128 0242p 338 0 k'

6.0 ADMINISTRATIVE

CONTROLS 6.3 Procedures E.ualit Assurance Procedures

-Effluent and Environmental Monitorin Quality Assurance procedures shall be established, implemented, and maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, rev.1, June 1974 and Regulatory Guide 4.1, rev.1, April 1975 or Regulatory Guide 4.15, Dec.1977.Amendment No.128 340 0242p

k 6.0 Administrative Controls 3.Uni ue Re ortin Re uirements A.Radioactive Effluent Release Re ort Deleted.(See REM section F.2)Amendment No.128 355 0242p

6.0 ADMINISTRATIVE

CONTROLS 6.9 Process Control Pro ram (PCP)1.The PCP shall be approved by the Commission prior to implementation.

2.Changes to the PCP shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change(s)was made.This submittal shall contain: a.Sufficiently detailed information to totally support the change.b.A determination that the"hange did not change the overall conformance of the solidified product to existing criteria.3.Changes to the PCP shall become effective upon review and acceptance by PORC.6.10 Offsite Dose Calculational Manual (ODCM)1.The ODOM shall be approved by the Commission prior to implementation.

2.Changes to the ODCM shall, be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change(s)was made.This submittal shall contain: a.Sufficiently detailed information to totally support the change.3.Changes to the ODCM shall become effective upon review and acceptance by PORC.6.11 RADIOLOGICAL EFFLUENT MANUAL (REM)1.The REM shall be approved by the Commission prior to implementation.

2.Changes to the REM shall be reviewed by PORC prior to implementation.

3.Changes to the REM shall be approved by the Commission prior to implementation.

Amendment No.128 359 0242p

~" e ENVIRONMENTAL TECHNICAL SPECIFICAITONS FOR BROWNS FERRY NUCLEAR PLANT TABLE OF CONTENTS 1.0 DEFINITIONS............

~~~~~~~~~~~~~~~~~~pa e ND.Deleted 2.0 LIMITING CONDITIONS FOR OPERATION......................

Deleted 2.1 Thermal Discharge Limits..........................

.2 Chemical..........................................

2 Deleted Deleted 2.2.1 Makeup Water Treatment Plant Spent Demlnerallzer Regerants.

2.2.2 Chlorine...................................

3.0 DESIGN

FEATURES AND OPERATING PRACTICES.

3.1 Chemical

Usage....................................

Deleted Deleted Deleted Deleted 3.1.1 Oils and Hazardous Materials..............

Deleted 3.1.2 Other Chemicals............................

3.2 Land Management...................................

3.2.1 Power

Plant Site..............

~-~~~~~~~~--~Deleted Deleted Deleted 3.2.2 Transmission Line Right-of-Way Maintenance.

3.3 Onsite

Meteorological Monitoring.................-

Deleted I 4.0 ENVIRONMENTAL SURVEILLANCE.............................

Deleted 4.1 Ecological Surveillance..........-....

4 L el F 1 aulor.lc.~~~~~~~~.~~~~~~~~~~~~~~~~~~~~~~~~~~4 II L.1.2 olor.lc...,~...~~~.......~.~~..I...~~~I~~~~~4.1.3 Special Studies..........

~-~~~~~~-~~~~~~~~~4.2 Radiological Environmental Monitoring Program.....

Deleted Deleted Deleted Deleted Deleted 0242p

5.0 ADMINISTRATIVE

CONTROLS...............................

Deleted F 1 5.2'esponsxbxlxty.....................................

0 rga'nxzatxon..

5.3 Review

and Audit~~~~~~~~~4~~~~~~~~~~~~~~~~~Deleted Deleted Deleted 5.4 Action to be Taken if an Exceeded...............

Environment LCO is~~~~~~~~~~~~~~~~~~~~4~~~~5.5 Procedure..............

5.6 Reporting

Requirements............................

5.7 Environmental

Records.Figures..ables...............

00~~~~~~~~~~~~~~~~~~~~~~0 T Deleted Deleted Deleted Deleted Deleted Deleted Amendment No.128 0242p I!

3.2.2 Transmission

Line Ri ht-of-Wa Maintenance O~b ective The sole purpose of this section is to provide reporting requirements (to USNRC)on herbicide usage, if any, for purposes of right-of-way maintenance regarding only those transmission lines under USNRC's jurisdiction for the Browns Ferry Nuclear Plant.A statement as to whether or not herbicides have been used in maintaining rights-of-way for those transmission lines associated with the Browns Ferry Nuclear Plant shall be provided.If herbicides have been used, a description of the types, volumes, concentrations, manners and frequencies of application, and miles or rights-of-way that have been treated shall be included.Re ortin Re uirements Information as specified above shall be provided in the Annual Operating Report (Appendix A, Section 6.7.l(b)).

Bases Vegetation growth on a transmission line right-of-way must be controlled in such a manner that it will neither interfere with safe and reliable operation of the line or impede restoration of service when outages occur.Vegetation growth is controlled by mechanical cutting and the limited use of herbicides.

Selected chemicals approved by EPA for use as herbicides are assigned (by EPA)label instructions which provide guidance on and procedures for their use.Amendment No.128 0242p i',i CI4

~p,g REGS~Vp 0 Cy A I 0 O~O+>>*++UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.20555 TENNESSEE VALLEY AUTHORITY DOCKET NO.50-296 BROMNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.103 License No.DPR-68 1.The Nuclear Regulatory Commission (the Commission) has found that: A.The applications for amendment by Tennessee Valley Authority (the licensee)dated September 30, 1986, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;B.The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.There is reasonable assurance (i)that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii)that such activities will be conducted in compliance with the Commission's regulations; D.The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public;and E.The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2)of Facility Operating License No.DPR-68 is hereby amended to read as follows:

I f 4 r' (2)Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.103 , are hereby incorporated in the license.The licensee shall operate the facility in accordance with the Technical Specifications.

3.This license amendment is effective as of the date of issuance and shall be implemented within 90 days from the date of issuance.FOR THE NUCLEAR REGULATORY COMMIS I N

Attachment:

Changes to the Technical Specifications Daniel R.Muller, Director BWR Project Directorate 82 Di vi s i on of BWR Li censing Date of Issuance: February 5, l987

ATTACHMENT TO LICENSE AMENDMENT N0.103 FACILITY OPERATING LICENSE NO.DPR-68 DOCKET NO.50-296 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.The revised areas are indicated by marginal lines.~Pe ee 1 11 ill lv V Vl Vl 1 V111 7 7A 7B 8 51 52 56A 79 79A 87A 87B 100 100A 105A 105B 113 ,"'16 190 299 300 301 302 303 304 305 306 307 308 309 310 311 312 313 314 315 364A 367 368 370 385 389 Revise Appendix B as follows: Table of Contents 2 pp.

Section TABLE OF CONTENTS~Pa e No.Introduction

.1.0 Derlnx t1ons.SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 1.1/2.1 1.2/2.2 Fuel Cladding Integrity.

Reactor Coolant System Integrity.LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 26 3.1/4.1 3.2/4.2 Reactor Protection System.Protective Instrumentation

.A.Primary Containment and Reactor Building Isolation Functions.

31 49 49 B.Core and Containment Cooling Systems-Initiation and Control 50 C.Control Rod Block Actuation.

D.Radioactive Liquid Effluent Monitoring Instruments.

50 51 E.Drywell Leak Detection.F.Surveillance Instrumentation

.53 53 G.Control Room Isolation.H.Flood Protection

.53 54 I.Meteorological Monitoring Instrumentation.

J.Seismic Monitoring Instrumentation

.56 K.Radioactive Gaseous Effluent Instrumentation.

Monitoring

~~~~~~56A 3.3/4.3 Reactivity Control A.Reactivity Limitations

.B.Control Rods.'118 118 122 Amendment No.103 0243p

Section P~ae No.C.Scram Insertion Times.128 D.Reactivity Anomalies.

E.Reactivity Control 129 129 F.Scram Discharge Volume.129 3.4/4.4 3.5/4.5 Standby Liquid Control System.A.Normal System Availability

.B.Operation with Inoperable Components C.Sodium Pentaborate Solution.Core and Containment Cooling Systems 137 137 139 139 146 A.Core Spray System.B.Residual Heat Removal System (RHRS)(LPCI and Containment Cooling)146 149 C.RHR Service Water System and Emergency Equipment Cooling Water System (EECWS)155 D.Equipment Area Coolers.158 E.High Pressure Coolant Injection System (HPCIS)~~~~~~~~~e~~~~~~~159 F.Reactor Core Isolation Cooling System (RCICS)~~~~~~~~~~~~~~~~160 G.Automatic Depressurization System (ADS)~~~~~<~~~,'e e~e~~e~~161 H.Maintenance oE Filled Discharge Pipe.163 I.Average Planar Linear Heat Generation R ate.165 J.'inear Heat Generation Rate.166 K.Minimum Critical Power Ratio (MCPR).167 3.6/4.6 L.APRM Setpoints.M.Reporting Requirements Primary System Boundary.167A 167A 184 A.Thermal and Pressurization Limitations

.184 Amendment No.103 0243p Section B.Coolant Chemistry.

C.Coolant Leakage.~Pa e No.187 191 D.Relief Valves.192 E e Je't Pumps~~~~~~~~~~~~~~~~193 F.Recirculation Pump Operation.195 G.Structural Integrity.196 H.Seismic Restraints, Supports, and Snubbers 198 3.7/4.7 Containment Systems.A.Primary Containment.

231 231 B.Standby Gas Treatment System.247 C.Secondary Containment.

a D.Primary Containment Isolation Valves 251 254 E.Control Room Emergency Ventilation

.256 F.Primary Containment Purge System 258 G.Containment Atmosphere Dilution System (CAD)260 CAM)H.Containment Atmosphere Monitoring (System H>Analyzer.261 3.8/4.8 Radioactive Materials.

299 A.Liquid Effluents.299 B.Airborne Effluents.301 C.Radioactive Effluents-Dose.304 D.Mechanical Vacuum Pumps.304 E.Miscellaneous Radioactive Materials Sourcese~~~~~~~~~~~~~~~305 F.Solid Radwaste.307 3.9/4.9 Auxiliary Electrical System.A.Auxiliary Electrical Equipment 316 316 B.Operation with Inoperable Equipment.

321 Amendment Ho.103 0243p

(

Section C.Operation in Cold Shutdown.~~~~~~~3.10/4.10 Core Alterations A.Refueling Interlocks.

326 331 331 B.Core Monitoring 336 C.Spent Fuel Pool Water D.Reactor Building Crane.337 338 E.Spent Fuel Cask.339 F.Spent Fuel Cask Handling-Refueling Floor~~~~~~~~,~~~~~~~~~339 3.11/4.11 Fire Protection Systems.A.High Pressure Fire Protection System.347 347 B.CO>Fire Protection System.P C.Fire Detectors.

351 352 D.Roving Fire Watch.353 E.Fire Protection Systems Inspections 354 F.Fire Protection Organization.

354 G.Air Masks and Cylinders.H.Continuous Fire Watch.~~355 355 I.Open Flames, Welding,., Cable Spreading Room.and Burning in the~~355 5.0 Major Design Features.5.1 Site Features.360 360 5.2 Reactor.360 5.3 Reactor Vessel.360 5.4 Containment 360 5.5 Fuel Storage.5.6 Seismic Design.360 361 Administrative Controls.362 6.1 Organization.

362 Amendment No.]p3 lv 0243p

Section 6.2 Review and Audit.~Pa e No.6.3 Procedures.

368 6.4 Actions to be Taken in the Event of A Reportable Occurrence in Plant Operation.

376 6e5 Action to be Taken in the Limit is Exceeded.Event a Safety 376 6.6 Station Operating Records 6.7 Reporting Requirements.

6.8 Minimum

Plant Staffing.376 379 388 Amendment No.103 0243p 1 0 Section LIST OF TABLES Title~pa e No.3.1.A Surveillance Frequency Notation.Reactor Protection System (SCRAM)Instrumentation Requirements 32 4.1.A Reactor Protection System (SCRAM)Instrumentation Functional Tests Minimum Functional Test Frequencies for Safety Instr.and Control Circuits.'36 4.1.B Reactor Protection System (SCRAM)Instrument Calibration Minimum Calibration Frequencies Reactor Protection Instrument Channels for 39 3.2.A Primary Containment and Reactor Building Isolation Instrumentation.

57 3.2.B Instrumentation that Initiates or Controls the Core and Containment Cooling Systems 64 3.2.C Instrumentation that Initiates Rod Blocks.76 3.2.D Radioactive Liquid Effluent Monitoring Instrumentation.

79 Instrumentation that Monitors Leakage Into Drywell 80 3.2.F 3.2.G Surveillance Instrumentation

.Control Room Isolation Instrumentation

.81 84 3.2.H Flood Protection Instrumentation

.3.2.I 3.2.J 3.2.K Meteorological Monitoring Instrumentation.

Seismic Monitoring Instrumentation

.Radioactive Gaseous Effluent Monitoring.

Instrumentation.

86 87 II 87A 4.2.A Surveillance Requirements for Primary Containment and Reactor Building Isolation Instrumentation.

88 4.2.B Surveillance Requirements for Instrumentat that Initiate or Control the CSCS.ion 92 4.2.C Surveillance Requirements for Instrumentat that Initiate Rod Blocks.ion 99 4.2.D~~Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirement 100 Amendment No.103 v1 0243p ok 4J 4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation

.101 Minimum Test and Calibration Frequency for Surveillance Instrumentation

.102 4.2.G Surveillance Requirements for Control Room Isolation Instrumentation.

103 4.2.M Minimum Test and Calibration Frequency for Flood Protection Instrumentation

.104 4.2.J Seismic Monitoring Instrument Surveillance Requirements 105 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance

.105A 3.5.-1 Minimum RHRSW and EECW Pump Alignment.

156a 3.5.I 3.7.A MAPLHGR vs.Average Planar Exposure.....181, 182, 182a, 182b Primary Containment Isolation Valve.262 3.7.B Testable Penetrations with Double 0-Rang Seals.268 3.7.C Testable Penetrations with Testable B ellows~o~~~~~~~~~~~~~~~o 269 3.7.D~~Air Tested Isolation Valves.270 3.7.E Primary Containment Isolation Valve which Terminate Below the Suppression'Pool Water L evel 4~~~~~~~~~~~~~~~~~~~279 3.7.F 3.7.G Primary Containment Isolation Valve Located in Water Sealed Seismic Class I Lines.I Deleted 280 3.7.H Testable Electrical Penetrations

.283 4.9.A.4.c Voltage Relay Setpoints/Diesel Generator Start.327 3.11.A Fire Protection System Hydraulic Requirements 355a 6.8.A Minimum Shift Crew Requirements.

390 Amendment No.103 v11 0243p 0

LIST OF ILLUSTRATIONS F~iure Title~Fa e No.APRM Flow Reference Scram and APRM Rod Block Set tlngs~~~~~~~~~~~~~~~~~~~~2.1-2 APRM Flow Bias Scram Vs.Reactor Core-Flow.25 4.1-1 Graphic Aid in the Selection of an Adequate Interval Between Tests 48 4.2-1 System Unavailability.

117 3.4-1 Sodium Pentaborate Solution Volume Concentration Requirements

.141 3.4-2 Sodium Pentaborate Solution Temperature Requ1rements

.142 3.5.K-1 MCPR Limits.182c 3.5.2 K~Factor vs.Percent Core Flow.183 3.6-1 Temperature-Pressure Limitations 207 3.6-2 Change in Charpy V Transition Temperature Vs.Neutron Exposure 208 4.8.1.a Gaseous Release Points and Elevations.

4.8.l.b Site Boundary.308 309 6.1-1 TVA Office of Power Organization for Operat of Nuclear Power Plants.ion 391 6.1-2 Functional Organization.

392 6.2-1 Review and Audit Function.393 6.3-1 In-Plant Fire Program Organization

.394 V111 0243p

~l V~>

7.a protective trip function.A trip system may require one or more instrument channel trip signals-related-to one-.or more plant parameters in order to initiate trip system action.Initiation of protective action may require the tripping of a single trip system.or the coincident tripping of two trip systems.Protective Action-A action initiated by the protective system when a limit is reached.A protective action can be at a channel or system level.8.Protective Function-A system protective action which results from the protective action of the channels monitoring a particular plant condition.

9.Simulated Automatic Acutation-Simulated automatic acutation means applying a simulated signal to the sensor to actuate the circuit in question.10.~Lo ic-A logic is an arrangement of relays, contacts, and other components that produces a decision output.(a)Initiatin-A logic that receives signals from channels and produces decision outputs to the actuation logic.(b)Actuation-A logic that receives signals (either from initiation logic or channels)and produces decision outputs to accomplish a protective action.Channel Calibration

-Shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel monitors.The channel calibration shall encompass the entire channel including alarm and/or trip functions and shall include the channel function test.The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

Non-calibratable components shall be excluded from this requirement, but will be included in channel functional test and source check.12.Channel Functional Test-Shall be: a.Analog Channels-the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b.Bistable channels-the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.

13.Source Check-Shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources.0244p'mendment No.103 0 I, Y, 4 0 Functional Tests-A functional test is the manual operation or initiation of a system, subsystem, or component to verify that it functions within design tolerances (e.g., the manual start of a core spray pump to verify that it runs and that it pumps the required volume of water).Shutdown-The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.

Y.En ineered Safe uard-An engineered safeguard is a safety system the actions of which are essential to a safety action required in response to accidents.

Z.Re ortable Event-A reportable event shall be any of those conditions specified in section 50.73 to 10 CFR Part 50.Solidification

-Shall be the conversion of radioactive wastes into a form that meets shipping and burial ground requirements.

BB.Offsite Dose Calculation Manual (ODCM)-Shall be a manual describing the environmental monitoring program and the methodology and parameters used in the calculation of release rate limits and offsite doses due to radioactive gaseous and liquid effluents.

The ODCM will also provide the plant with guidance for establishing alarm/trip setpoints to ensure technical specifications section 3.8.A.1 and 3.8.B.1 are not exceeded.CC.Pur e or ur in-The controlled process of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is required to purify the containment.

DD.EE.Process Control Pro ram-Shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.Radiolo ical Effluent Manual (REM)-Shall be a manual containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposure to individuals from station operation.

It shall also specify operating guidelines for radioactive waste treatment systems and report content.FF.V~entin-The controlled process oE discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required.Vent, used in system names, does not imply a venting process.Amendment No.103 0244p 7A P

1.0 DEFINITIONS

(Cont'd)GG.owned, leased, or otherwise controlled by TVA-HH., Unrestricted Area-Any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for industrial, commercial, institutional, or recreational purposes.Dose E uivalent I-131-The DOSE EQUIVALENT I-131 shall be the concentration of I-131 (in pCi/gm)which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.The thyroid dose conversion factor used for this calculation shall be those listed in Table III of TID-14844"Calculation of Distance Factors for Power and Test Reactor Sites".Gaseous Waste Treatment S stem-The charcoal adsorber vessels installed on the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release.Members of the Public-Shall include all individuals who by virtue of their occupational status have no formal association with the plant.This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions.

This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter restricted areas.LL.'urveillance

-Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements.

Each Surveillance Requirement shall be performed within the specified time interval with, (1)A maximum allowable extention not to exceed 25K of the surveillance interval, but (2)The combined time entered for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications.

Surveillance requirements do not have to be performed on inoperable equipment.

02449 Amendment No.103 7B

Table 1.1 SURVEILLANCE PRE UENCY NOTATION NOTATION S (Shift)D (Daily)W (Weekly)M (Monthly)Q (Quarterly)

SA (Semi-Annually)

Y (Yearly)R (Refueling)

S/U (Start-Up)

N.A.P (Prior)~EIEUENCY At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.At least once per normal calendar 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day (midnight to midnight).

At least once per 7 days.At least once per 31 days.At least once per 3 months or 92 days.At least once per 6 months or 184 days.At least once per year or 366 days.At least once per operating cycle.Prior 6o each reactor startup.Not applicable.

Completed prior to each release.Amendment No.103 0244p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2 Protective Instrumentation

4.2 Protective

Instrumentation 3.2.D Radioactive Li uid Effluent Monitorin Instrumentation 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation The radioactive liquid effluent instrumentation listed in Table 3.2.D shall be operable with the applicability as shown in Table 3.2.D/4.2.D.

Alarm/trip setpoints will be set in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.A.1 are not exceeded.1.Each of the radioactive liquid effluent monitoring instruments shall be demonstrated operable by performance of test in accordance with Table 4.2.D.2~The action required when the number of operable channels is less than the minimum channels operable requirement is specified in the notes for Table 3.2.D.Exert best efforts to return the instrument(s) to OPERABLE status within 30 days and if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.3~With a radioactive liquid effluent monitoring channel alarm/trip setpoint less conservative than required by these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these specifications.

4, The provisions of specifications 1.0.C and 6.7.2 are not applicable.

Amendment No.103 51 0233p

-LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.K Radioactive Gaseous Effluent 4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation Monitorin Instrumentation The radioactive gaseous effluent monitoring instruments listed in Table 3.2.K shall be operable with the applicability as shown in Tables 3.2.K/4.2.K.

Alarm/trip setpoints will be set in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.B.1 are not exceeded.l.Each of the radioactive gaseous effluent monitoring instruments shall be demonstrated operable by performance of tests in accordance with Table 4.2.K.2.The action required when the number of operable channels is less than the minimum channels operable requirement is specified in the notes for Table 3.2.K.Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Release Report why the inoperability was not corrected in a timely manner.3.With a radioactive gaseous effluent monitoring channel alarm/trip setpoint less conservative than required by these specifications, suspend the release without delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism required by these specifications.

4, Both off-gas posttreatment monitors may be taken out-of-service for less than one hour for purging of monitors during SI performance.

5.The provisions of specifications 1.0.C and 6.7.2 are not applicable.

Amendment No.103 56A 0233p 7

TABLE 3.2.D Radioactive Li uid Effluent Monitorin Instrumentation Instrument

"'.LIQUID RADHASTE EFFLUENT MONITOR (RM-90-130) 2.RHR SERVICE WATER MONITOR (RM-90-133,-134)3.RAW COOLING HATER MONITOR (RM-90-132) 4.LIQUID RADHASTE EFFLUENT FLOW RATE (77-60 loop excluding fixed in line rotometer)

Minimum Channels 0 erable A 1 icabi 1 i t Action A, B Amendment No.103 0240p 79

('t n h NOTES FOR TABLE 3.2.D"At all times>'<'During releases via this pathway~'-:~~During operation of an RHR loop and associated RHR service water system ACTION A During release of radioactive wastes from the radwaste processing system, the following shall be met (1)liquid waste activity and flowrate shall be continuously monitored and recorded during release and shall be set to alarm and automatically close the waste discharge valve before exceeding the limits specified in 3.8.A.1, (2)if this cannot be met, two independent samples of the tank being discharged shall be analyzed in accordance with the sampling and analysis program specified in the REM and two qualified station personnel shall independently verify the release rate calculations and check valving before the discharge.

Otherwise, suspend release via this pathway.ACTION B, With a radioactive liquid eff1uent monitoring channel/alarm trip setpoint less conservative than required by these specifications, suspend release via this pathway without'delay, declare the channel inoperable, or adjust the alarm/trip setpoint to establish the conservatism referred by these specifications.

r ACTION C During operation of an RHR loop and associated RHR service water system, the effluent from that unit's service water shall be continuously monitored.

If an installed monitoring system is not available, a temporary monitor or grab samples taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and an analysis of at least an LLDf 1E-7 pCi/ml (gross)or<applicable MPC ratio (y isotopic)shall be used to monitor the effluent.ACTION D With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided that a temporary monitor is installed or, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab samples are collected and analyzed for radioactivity with an LLDf lE-7 pCi/ml (gross)or (applicable MPC ratio (y isotopic).

ACTION E l With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent releases via this pathway may continue provided the flow rate 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.Pump curves may be used to estimate flow.ACTION F Alarm/trip setpoints will be calculated in accordance with the guidance given in the Offsite Dose Calculation Manual (ODCM).(1)See REM, TABLE NOTATIONS-TABLE C-l, for the definition of LLD.Amendment No.103 0244p 79A

ABLE 3.2.K Radioactive Gaseous Effluent Monitorin Instrumentation Instrument STACK (RM-90-147A 5 B)a.Noble Gas Monitor b.Iodine Cartridge c.Particulate Filter d.Sampler Flow Abnormal e.Stack Flow (FT, FM, F I-90-271)Minimum Channels/Devices 0 erable (1)(1)(1)(1)(1)A licabilit Action A/C B/C B/C D D 2.4.6~REACTOR/TURBINE BLDG VENTILATION (RM-90-250) a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter TURBINE BLDG EXHAUST (RM-90-249, 251)a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter RADNASTE BLDG VENT (RM-90-252) a.Noble Gas Monitor b.Iodine Sampler c.Particulate Sampler d.Sampler Flowmeter OFF GAS HYDROGEN ANALYZER (HzA, HcB)OFF GAS POST TREATMENT a.Noble Gas Activity Monitor (RM-90-265, 266)b.Sample Flow Abnormal (PA-90-262)

(1)(1)(1)(1)(1)(1)(1)(1)(1)(1)(1)(1)A/C B/C B/C D A/C 8/C B/C D A/C B/C B/C D Amendment No.103 0240p 87A 0 r NOTES FOR TABLE 3.2.K"<At all times e o'<During releases via this pathway~'~'~<During main condenser offgas treatment system operation ACTION A With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, effluent-releases via the affected pathway may continue provided a temporary monitoring system is installed or grab samples are taken and analyzed at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.ACTION B With a 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 sampling equipment for periods on the order of seven (7)days and analyzed in accordance with the sampling and analysis program specified in the REM 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.ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for functional testing, calibration, or repair without providing or initiating grab sampling.ACTION D 1 With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement; effluent releases via this pathway may continue provided the flow rate 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 />.ACTION E With the number of channels OPERABLE less than required by the Minimum Channels Operable requirement, operation of main condenser offgas treatment system may continue provided that a temporary monitor is installed or grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.ACTION F 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 at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 />.Purging during SI performance is not considered a loss of monitoring capability.

87B 0244p

TABLE 4.2.0 Radioactive Li uid Effluent Monitorin Instrumentation Surveillance Re uirements Instrument 1.LIQUID RADHASTE EFFLUENT MONITOR (RM-90-130) 2.RHR SERVICE HATER MONITOR (RM-90-133,-134)3.RAN COOLING HATER MONITOR (RM-90-132) 4.LIQUID RADHASTE EFFLUENT FLOH RATE (77-60 loop)Instrument Check D(4)D(4)D(4)D(4)Source Check Channel Calibration R(5)R(5)R(5)Functional Test Q(1)Q(2)Q(2)Q(3)Amendment No.103 0240p 100 tI leaf't It NOTES FOR TABLE 4.2.D (1)The channel functional test shall also demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint b.Instrument indicates an inoperative/downscale failure c.Instrument controls not set in operate mode (2)The channel functional test shall also demonstrate that control room annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm setpoint b.Instrument indicates an inoperative/downscale failure c.Instrument controls not set in operate mode (3)This functional test shall consist of measuring rate of tank decrease over a period of time and comparing this value with flow rate instrument reading.(4)INSTRUMENT CHECK shall consist of verifying indication during periods of release.INSTRUMENT CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days'hich continuous, periodic, or batch releases are made.(5)The CHANNEL CALIBRATION shall include the use of a known (traceable to National Bureau of Standards Radiation Measurement System)radioactive source(s)positioned in a reproducible geometry with respect to the sensor or using standards that have been obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards (NBS).100A 02449 4

TABLE 4.2.K Radioactive Gaseous-Effluent Instrumentation Surveillance Instrument STACK a.Noble Gas Monitor'b.Iodine Cartridge c.Particulate Filter d.Sampler Flow Abnormal e.Stack Flowmeter Instrument Check D N H D D Source Check M NA NA NA HA Channel Calibration R(I)HA NA R R Functional Test Q(2)NA NA Q Q 2.4.5.6.REACTOR/TURBINE BLDG VENT a.Noble Gas Monitor"'.Iodine Sampler c.Particulate Sampler d.Stack Flowmeter TURBINE BLDG EXHAUST a.Nob1 e Gas Moni tor"'.Iodine Sampler c.Particulate Sampler d.Stack Flowmeter RADNASTE BLDG VENT a.Noble Gas Monitor"'.Iodine Sampler c.Particulate Sampler d.Stack Flowmeter OFF GAS HYDROGEN ANALYZER (HzA, H2B)OFF GAS POST TREATMENT.Noble Gas Activity Monitor b.Sample Flow Abnormal M NA NA HA M.NA NA HA'-.NA.HA NA R(1)HA NA R R(I)NA NA R R(1)NA NA R R(3)R())R Q(2)NA NA Q Q(2)NA NA Q Q(2)NA NA Q Q(4)Q(4)Q(2)Amendment No.103 0240p 105A 0

NOTES FOR TABLE 4.2.K(1)The CHANNEL CALIBRATION shall include the use of a known (traceable to the National Bureau of Standards Radiation Measurement System)radioactive source(s)positioned in a reproducible geometry with respect to the sensor or using standards that have obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards.

(2)The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: a.Instrument indicates measured levels above the alarm/trip setpoint.b.Instrument indicates an inoperable/downscale failure.c.Instrument controls not set in operate mode (stack only).(3)The channel calibration shall include the,use of standard gas samples containing a nominal: I a.Zero volume percent hydrogen (compressed air)and, b.One volume percent hydrogen, balance nitrogen.(4)The channel functional test shall demonstrate that automatic isolation of this pathway and control room annunciation occurs if any of the following conditions exists: a.Instrument indicates measured levels above the alarm/trip setpoint.b.Instrument indicates an inoperative/downscale failure.c.Instrument controls not set in operate mode.The two channels are arranged in a coincidence logic such that 2 upscale, or 1 downscale and 1 upscale or 2 downscale will isolate the offgas line.(5)The noble gas monitor shall have a LLD of lE-5 (Xe 133 Equivalent).

(6)The noble gas monitor shall have a LLD of 1E-6 (Xe 133 Equivalent).

105B 0244p

, Q~r e The operability of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.This capability is required to permit comparison of the measured response to that used in the design basis for Browns Ferry Nuclear Plant.The instrumentation provided is consistent with specific portions of the recommendations of Regulatory Guide 1.12"instrumentation for Earthquakes".

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 will be calculated in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.This instrumentation also includes provisions for monitoring the concentration of potentially explosive gas mixtures in the offgas holding system.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.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 in accordance with guidance provided in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20 Appendix B, Table II, Column 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.Amendment No.103 0244p 113 gl y 95 Wtu 1~0 The most likely cause would be to stipulate that one, channel be bypassed, tested, and restored, and then immediately following, the second channel be bypassed, tested, and restored.This is shown by Curve No.4.Note that there is no true minimum.The curve does have a definite knee and very little reduction in system unavailability is achieved by testing at a shorter interval than computed by the equation for a single channel.The best test procedure of all those examined is to perfectly stagger the tests.That is, if the test interval is four months, test one or the other channel every two months.This is shown in Curve No.5.The difference between Cases 4 and 5 is negligible.

There may be other arguments, however, that more strongly support the perfectly staggered tests, including reductions in human error.The conclusions to be drawn are these: l.A 1 out of n system may be treated the same as a single channel in terms of choosing a test interval;and 2.more than one channel should not be bypassed for testing at any one time.The radiation monitors in the refueling area ventilation duct which initiate building isolation and standby gas treatment operation are arranged in two 1 out of 2 logic systems.The bases given for the rod blocks apply here also and were used to arrive at the functional testing frequency.

The off-gas post treatment monitors are connected in a 2 out of 2 logic arrangement.

Based on experience with instruments of similar design, a testing interval of once every three months has been found adequate.t The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also.The criteria for ensuring the reliability and accuracy of the radioactive gaseous effluent instrumentation is listed in Table 4.2.K.The criteria for ensuring the reliability and accuracy of the radioactive liquid effluent instrumentation is listed in Table 4.2.D.Amendment No.103 116 0244p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.6 Primar S stem Boundar 4.6 Primar S'stem Boundar 5.Whenever the reactor is critical, the limits on activity concentrations in the reactor coolant shall not exceed the equilibrium value of 3.2 pc/gm of dose equivalent I-131.This limit may be exceeded following power transients for a maximum of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.During this activity transient the iodine concentrations shall not exceed the equilibrium values by a factor of more than 10 whenever the reactor is critical.The reactor shall not be operated more than 5 percent of its yearly power operation under this exception for the equilibrium activity limits.If the iodine concentration in the coolant exceeds the equilibrium limit by a factor of ten, the reactor shall shutdown, and the steam line isolation valves shall be closed immediately.

Amendment No.103 190 0233p 0 t'0 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials A licabilit Applies to the release of radioactive liquids and gases from the facility.~Ob'ective To define the limits and conditions for the release of radioactive effluents to the environs to assure that any.radioactive releases are as low as reasonably achievable and within the limits of 10 CFR Part 20.The specifications except for 3.8.A.1 and 3.8.B.1 are exempt from the requirements of definition 1.0.C (Limiting Condition for Operation).

S ecification A.Li uid Effluents 1.The concentration of radioactive material released at any time from the site to unrestricted areas (see Figure 4.8-1b)shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity.2.If the limits of 3.8.A.l are exceeded, appropriate action shall be initiated without delay to bring the release within Applies to the periodic test and record requirements and sampling and monitoring methods used for facility effluents.

O~b ective To ensure that radioactive liquid and gaseous releases from the facility are maintained within the limits specified by Specifications 3.8.A and 3.8.B.S ecification A.Li uid Effluents 1.Facility records shall be maintained of radioactive concentrations and volume before dilution of each batch of liquid effluent released, and of the average dilution flow and length of time over which each discharge occurred.2.Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be e discharged shall be performed prior to release in accordance with the sampling and analysis program specified in the REM.3.The operation of the automatic isolation valves and discharge tank selection valves shall be checked annually.299 0233p 0

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials 3.limits.Provide prompt notification to the NRC pursuant to section 6.7.2.The doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas (See Figure 4.8-lb)shall be limited: 4.The results of the analysis of samples collected from release points shall be used with the calculational methodology in the ODCM to assure that the concentrations at the point of release are maintained within the limits of specification 3.8.A.1.4~5.a.During any calendar quarter to<1.5 mrem to the total body and<5 mrem to any organ and, b.During any calendar year to<3 mrem to the total body and<10 mrem to any organ If the limits specified in 3.8.A.3 a 6 b above are exceeded, prepare and submit'Special Report pursuant to Section 6.7.2.The maximum activity to be contained in one liquid radwaste tank or temporary storage tank that can be discharged directly to the environs shall not exceed 10 curies excluding tritium and dissolved/entrained noble gas.6.The quantity of radioactive material contained in any outside liquid radwaste storage tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to=the tank.5.Cummulative quarterly and yearly dose contributions from liquid effluents shall be determined as specified in the ODCM at least once every 31 days.6.With radioactive liquid waste exceeding 3.8.A.5 limits, without delay suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit.Events leading to this condition must be reported in the next Semiannual Radioactive Effluent Release Report (section F.2 of the REM)Amendment No.103 0233p 300 4 k'\:7 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials B.Airborne Effluents B.Airborne Effluents 1.The dose rate at any time to areas at and beyond the site boundary (see Figure 4.8-1b)due to radioactivity released in gaseous effluents from the site shall be limited to the following values: a.The dose rate limit for noble gases shall be<500 mrem/yr to the total body and<3000 mrem/yr to the skin, and b.The dose rate limit for I-131, I-133, H-3, and particulates with greater than eight day half-lives shall be<1500 mrem/yr to any organ.2.If the'limits of 3.8.B.l are exceeded, appropriate corrective action shall be immediately initiated to bring the release within limits.Provide prompt notification to the NRC pursuant to section 6.7.2.1.The gross 6/y and particulate activity of gaseous wastes released to the environment shall be monitored and recorded.For effluent streams having continuous monitoring capability, the activity shall be monitored and flow rate evaluated and recorded to enable release rates of gross radioactivity to be determined at least once per shift using instruments specified in table 3.2.K.b.-For effluent streams without continuous monitoring capability, the activity shall be monitored and recorded and the release through these streams controlled to within the limits specified in 3.8.B.2.Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with the sampling and analysis program specified in the REM.Dose rates shall be determined to be within limits of 3.8.B using methods contained in the ODCM.Amendment No.103 301 0233p 0

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTh 3.The air dose to areas at and beyond the site boundary (see Figure 4.8-lb)due to noble gases released in gaseous effluents per unit shall be limited to the following:

a.During any calendar quarter, to<5 mrad for gamma radiation and<10 mrad for beta radiation; 3.Cumulative quarterly and yearly dose contributions from gaseous releases shall be determined using methods contained in the ODCM at least once every 31 days.b.During any calendar year, to<10 mrad for gamma radiation and<20 mrad for beta radiation.

4.If the calculated air dose exceeds the limits specified in 3.8.B.3 above, prepare and submit a special report pursuant to section 6.7.2.5.The dose to a member of the public from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than 8 days in gaseous effluent released per unit to areas at and beyond the site boundary (see Figure 4.8-1b)shall be limited to the following:

a.To any organ during any calendar quarter to<7.5 mrem;b.To any organ during any calendar year to<15 mrem;Amendment No.103 302 0233p

LIMITING CONDITIONS FOR OPERATION 6.If the calculated doses exceed the limits of 3.8.B.5 above, prepare and submit a special report pursuant to section 6.7.2.SURVEILLANCE RE UIREMENTS 4.During operation above 25K power, the position of the charcoal bed bypass valve will be verified daily.7.During operation above 25'ower the discharge of the SJAE must be routed through the charcoal adsorbers.

8.With gaseous waste being discharged for more than 7 days without treatment through the charcoal adsorbers, prepare and submit a special report pursuant to section 6.7.2.5.The concentration of hydrogen downstream of the recombiners shall be determined to be within the limits of 3.8.B.9 by continuously monitoring the offgass whenever the SJAE is in service using instruments described in Table 3.2.K.Instrument surveillance requirements are specified in Table 4.2.K.9.Whenever the SJAE is in service, the concentration of hydrogen in the offgas downstream of the recombiners shall be limited to (4X by volume.10.With the concentration of hydrogen exceeding the limit oF 3.8.B.9 above, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.Amendment No.103 303 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8.C Radioactive Effluents-Dose The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to<25 mrem to the total body or any organ (except the thyroid, which is limited to<75 mrem)over a period of one calendar year.4.8.C Radioactive Effluents-Dose 1.Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with specifications 3.8.A.3, 3.8.B.3, and 3.8.B.5 and the methods in the ODCM.2.With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding'wice the limits of specification 3.8.A.3, 3.8.B.3, or 3.8.B.5, prepare and submit a Special Report to the Commission pursuant to specification 6.7.2 and limit the subsequent releases such that the limits of 3.8.C.l are not exceeded.3.8.D Mechanical Vacuum Pum 4.8.D Mechanical Vacuum Pum Each mechanical vacuum pump shall be capable of being automatically isolated and secured on a signal or high radioactivity in the steam'lines whenever the main steam isolation valves are open.At least once during each operating cycle verify automatic securing and isolation of the mechanical vacuum pump.2.If the limits of 3.8.D.1 are not met, the vacuum pump shall be isolated.Amendment No.103 304 0233p 0 0 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

3.8 Radioactive

Materials E.Miscellaneous Radioactive Materials Sources 4.8 Radioactive Materials E.Miscellaneous Radioactive

~Materials Sources 1.Source Leaka e Test 1.Surveillance Re uirement Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or, 5 microcuries of alpha emitting material shall be free of)0.005 microcurie of removable contamination.

Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and (a)either decontaminated and repaired, or (b)disposed of in accordance with Commission regulations.

C~~I Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an agreement State, as follows: a.Sources in Use Each sealed source, excluding startup sources and flux detectors previously subjected to core flux, containing radioactive material, other than Hydrogen 3, with a half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at least once per six months.The leakage test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample.Amendment No.103 305 0233p I

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.8.E Miscellaneous Radioactive Materials Sources 1.Surveillance Re uirements b.Stored Sources Not In Use Each sealed source and fission detector not previously subjected to core flux shall be tested prior to use or transfer to another licensee unless tested within the previous six months.Sealed sources and fission detectors transferr'ed without a certificate indicating the last test date shall be tested prior to use.c.Startu Sources and Fission Detectors Each sealed startup source and fission detector shall be tested prior to being subjected to core flux and following repair or maintenance to the source.2.R~eorts A report shall be prepared and submitted to the Commission on an annual basis if sealed sources or fission detector leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.

306 0233p l I'f h LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials F.Solid Radwaste F.Solid Radwaste 1.The solid radwaste system shall be operated in accordance with a process control program, for the solidification and packaging of wet radioactive wastes to ensure meeting the requirements of 10 CFR 20 and 10 CFR 71 and burial ground requirements prior to shipment of radioactive wastes from the site.1.The Process Control Program shall include surveillance checks necessary to demonstrate compliance with 3.8.F.l.2.With the packaging requirements of 10 CFR 20 or burial ground requirements and/or 10 CFR 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site..~~~Amendment No.103 307 0233p

Switchyard Turbine Building Exhaust Pan (32m)Office Building Service Bldg.Turbine Building Reactor Building Stack (180m)Reactor Building Ventilation (40m)Figure 4.8-1a GASEOUS RELEASE POINTS AND ELEVATIONS Amendment No.l03 308

Figure 4.8-lb LAND SITE BOUNDARY~.liquid Dfacharee (l>l(fusee Ploce))-paqerri f f e"+.lhktteeacC

~a gp/All flaN1 A~Ihee~lie w%Q 1 elle~s 2 eues 309 Amendment No.l03

3.8 BASES

Radioactive waste release levels to unrestricted areas should be kept"as low as reasonably achievable" and are not to exceed the concentration limits specified in 10 CFR Part 20.At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than design objectives but still within the concentration limits specified in 10 CFR Part 20.It is expected that by using this operational flexibility and exertingevery effort to keep levels or radioactive materials released as low as reasonably achievable in accordance with criteria established in 10 CFR 50 Appendix I, the annual releases will not exceed a small fraction of the annual average concentration limits specified in 10 CFR Part 20.3.8.A.LIOUID EFFLUENTS Specification 3.8.A.1 is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1)the Section 11.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2)the limits of 10 CFR Part 20.106(e)to the population.

The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)Publication 2.Specification 3.8.A.3 is provided to implement the dose requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50.The Limiting Condition for Operation implements the guides'et forth the Section 11.A of Appendix I.Specification 3.8.A.4 action statements provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept"as low as is reasonably achievable".

Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141.The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by Amendment No.103 311 0244p I Jgy'I calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.3.8.B AIRBORNE EFFLUENTS Specification 3.8.B.1 is provided to ensure that the dose rate at anytime at the exclusion boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas.The annual dose limits axe the doses associated with the concentrations of 10 CFR part 20, Appendix B, Table II, Column 1.These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a member of the public in an unrestricted area, either within or outside the exclusion, area boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR part 20 (10 CFR Part 20.106(b)).

For members of the public who may at times be within the exclusion area boundary, the occupancy of the members of the public will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary.Amendment No.103 312 0244p z!<Cy 3.8.B AIRBORNE EFFLUENTS (cont'd)The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to<500 mrem/year to the total body or to<3000 mrem/year to the skin.These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to<1500 mrem/year for the nearest cow to the plant.Specification 3.8.B.2 requires that appropriate correction action(s)be taken to reduce gaseous effluent releases if the limits of 3.8.B.1 are exceeded.Specification 3.8.B.5 dose limits is provided to implement the requirements of Section II.C, III.A, and IV of Appendix I, 10 CFR Part 50.The limiting conditions for operation are the guides set forth in Section II.C of Appendix I.Specification 3.8.B.6 action statement provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methods used for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109,"Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977, NUREG/CR-1004,"A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides", October 1979, and Regulatory Guide 1.111,"Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.These equations also provide for determining the actual doses based upon the histori'cal average atmospheric conditions.

The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.The pathways which are examined in the development of these calculations are: 1)individual inhalation of airborne radionuclides, 2)deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3)deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4)deposition on the ground with subsequent exposure of man.Specification 3.8.B.6 action statement requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.5.0 Amendment No.103 313 0244p I

AIRBORNE EFFLUENTS Specification 3.8.B.7 requires that the offgas charcoal adsoiber beds be used when specified to treat gaseous effluents prior to their release to the environment.

This provides reasonable assurance that the release of radioactive materials in gaseous effluents will be kept"as low as is reasonably achievable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

Specification 3.8.B.8 requires that a special report be prepared and submitted to explain reasons for any failure to comply with Specification 3.8.B.7.Specification 3.8.B.3 is provided to implement the requirements of Section II.B, III.A, and IV.A of Appendix I,'0 CFR Part 50.The Limiting Condition for Operation implements the guide set forth in Section II.C of Appendix I.Specification 3.8.B.4 action statement provides the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept""as low as is reasonably achievable".

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated.

The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109,"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1 October 1977, NUREG/CR-1004,"A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and Internal Dose of Radionuclides", October 1979 and Regulatory Guide 1.111,"Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.The ODCM equations provided for determining the air doses at the exclusion area boundary will be based upon the historical average atmospheric conditions.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.Specificaitons 3.8.B.4 requires that a special report be prepared and submitted to explain violations of the limiting doses contained in Specification 3.8.B.3.4.8.A and 4.8.B BASES The surveillance requirements given under Specification 4.8.A and 4.8.B provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release or radioactive materials in the liquid and Amendment No.103 0244p 314 It ff>I 4.8.A and 4.8.B BASES (cont'd)gaseous effluents.

These surveillance requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive wastes released to the environment.

Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 6 of these technical specifications.

On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such actions as the Commission deems appropriate.

3.8.C and 4.8.C BASES This specification is provided to meet the dose limitations of 40 CFR 190.The specification requires the preparation and submittal of a Special Report whenever the calculated doses form plant radioactive effluents exceed twice the design objective doses of Appendix I.For sites containing up to four reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level.The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for the calendar year to be within 40 CFR 190 limits.For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose'contributions from other nuclear fuel cycle facilities at the same site or within a radius of five miles must be considered.

3.8.D and 4.8.D MECHANICAL VACUUM PUMP The purpose of isolating the mechanical vacuum pump line is to limit the release of activity from the main condenser.

During an accident, fission products would be transported from the reactor through the main steam lines to the condenser.

The fission product radioactivity would be sensed by the main steam line radioactivity monitors which initiate isolation.

3.8.E and 4.8.E BASES The limitations'n removable contamination for sources requiring leak testing, including alpha emitters, based on 10 CFR 70.39(c)limits for plutonium.

This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group.Those sources which are frequently handled are required to be tested more often than those which are not.Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices)are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

Amendment No, 103 0244p 315

6.0 ADMINISTRATIVE

CONTROLS k.The radiological environmental monitoring program and the results thereof at least once per 12 months.1.The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev.1, 1974 and Regulatory Guide 4.1, 1975 at least once per 12 months.m.The performance of activities required by the Safeguards Contingency Plan to meet the criteria of 10 CFR 73.40(d)at least once per 12 months.n.The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.o.The Process Control Program and implementing procedures for solidification of wet radioactive wastes at least once per 24 months.p.The Radiological Effluent Manual and implementing procedures at least onCe per 12 months.I 9.AUTHOR ITY The NSRB shall report to and advise the Manager of Power on those areas of responsibility specified in Sections 6.2.A.7 and 6.2.A.8.10.RECORDS Records of NSRB activities shall be prepared, approved and distributed as indicated below: a.Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Manager of Power within 14 days following each meeting.~~i~i~~i.~i~'4~b.Reports of reviews encompassed by Section 6.2.A.7 above, shall be prepared, approved and forwarded to the Manager of Power within 14 days following completion of the review.C~Audit reports encompassed by Section 6.2.A.S above, shall be forwarded to the Manger of Power and to the management positions responsible for the areas audited within 30 days after completion of the audit.Amendment No.-103 364A 0244p

6.0 ADMINISTRATIVE

CONTROLS j.Review proposed changes to the Radiological Effluent Manual.k.Review adequacy of the Process Control Program and Offsite Dose Calculation Manual at least once every 24 months.1.Review changes to the radwaste treatment systems.m.Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendation, and deposition of the corrective action to prevent recurrence to the Director, Nuclear Power and to the Nuclear Safety Review Board.5.A~UthOIit The PORC shall be advisory to the plant superintendent.

6.Records Minutes shall be kept for all PORC meetings with copies sent to Director, Nuclear Power;Assistant Director of Nuclear Power (Operations);

Chairman, NSRB.7.Procedures Written administrative procedures for committee operation shall be prepared and maintained describing the method for submission and content of presentations to the committee, review and approval by members of committee actions, dissemination of minutes, agenda and scheduling of meetings.367 0244p II 4

6.0 ADMINISTRATIVE

CONTROLS 6.3 Procedures A.Detailed written procedures, including applicable checkoff lists covering items listed below shall be prepared, approved and adhered to.1.Normal startup, operation and shutdown of the reactor and of all systems and components involving nuclear safety of the facility.2.Refueling operations.

3.Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks and abnormal reactivity changes.4.Emergency conditions involving potential or actual release of radioactivity.

5.Preventive or corrective maintenance ope ations which could have an effect on the safety of the reactor.6.Surveillance and testing requirements.

7.Radiation control procedures.

8.Radiological Emergency Plan implementing procedures.

9.Plant security program implementing procedures.

10.Fire protection and prevention procedures.

11.Limitations on the amount of overtime worked by individuals performing safety-related functions in accordance with the NRC policy statement on working hours (Generic Letter No.82-12).12.Radiological Effluent Manual implementing procedures.

13.Process Control Program (PCP).14.Offsite Dose Calculation Manual.B.Written procedures pertaining to those items listed above shall be reviewed by PORC and approved by the plant superintendent prior to implementation.

Temporary changes to a procedure which do not change the intent of the approved procedure may be made by a member of the plant staff knowledgeable in the area affected by the procedure except that temporary changes to those items listed above except item 5 require the additional approval of a member of the plant staff who holds a Senior Reactor Operator license on the unit affected.Such changes shall be documented and subsequently reviewed by PORC and approved by the plant superintendent.

Amendment No.103 368 0244p

6.0 ADMINISTRATIVE

CONTROL 6.3 Procedures E.ualit Assurance Procedures

-Effluent and Environmental M~onitonin Quality Assurance procedures shall be established, implemented, and maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, rev.1, June 1974 and Regulatory Guide 4.1, rev.1, April 1975 or Regulatory Guide 4.15, Dec.1977.Amendment No.103 370 0244p 0

6.0 ADMINISTRATIVE

CONTROLS 3.Uni ue Re ortin Re uirements A.Radioactive Effluent Release Re ort Deleted (See REM section F2).385 0244p

~l f'

6.0 ADMINISTRATIVE

CONTROL 6.9 Process Control Pro ram (PCP)1.The PCP shall be approved by the Commission prior to implementation.

2.Changes to the PCP shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change(s)was made.This submittal shall contain: a.Sufficiently detailed information to totally support the change.b.A determination that the change did not change the overall conformance of the solidified product to existir criteria.3.Changes to the PCP shall become effective upon review and acceptance by PORC.6.10 OFFSITE DOSE CALCULATIONAL MANUAL (ODCM)1.The ODCM shall be approved by the Commission prior to implementation.

2.Changes to the ODCM shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change(s)was made.This submittal shall contain: a.Sufficiently detailed information to totally support the change.3.Changes to the ODCM shall become effective upon review and acceptance by PORC.6.11 RADIOLOGICAL EFFLUENT MANUAL (REM)1.The REM shall be approved by the Commission prior to implementation.

2.Changes to the REM shall be reviewed by PORC prior to implementation.

3.Changes to the REM shall be approved by the Commission prior to implementation.

Amendment No.103 389 0244p

ENVIRONMENTAL TECHNICAL SPECIFICAITONS FOR BROWNS FERRY NUCLEAR PLANT TABLE OF CONTENTS~Pa e No.1.0 DEFINITIONS..................

Deleted 2.0 LIMITING CONDITIONS FOR OPERATION......................

Deleted 2.1 Thermal Discharge Limits..........................

2.2 Chemical..........................................

Deleted Deleted 2.2.1 Makeup Water Treatment Plant Spent Demineralizer Regerants..................

2.2.2~iilorxne.

~~~~~~~~~~e~e~~~~~~~~~Deleted Deleted 3.0 DESIGN FEATURES AND OPERATING PRACTICES................

Deleted 3.1 Chemical Usage....................................

Deleted 3.1.1 Oils and Hazardous Materials...............

Deleted 3.1.2 Other Chemicals............................

3.2 Land Management...................................

e 3.2.1 Power Plant Site...........................

Deleted Deleted Deleted 3.2.2 Transmission Line Right-of-Way Maintenance.

3.3 Onsite

Meteorological Monitoring..................

Deleted 4.0 ENVIRONMENTAL SURVEILLANCE.............................

Deleted 4.1 Ecological Surveillance.................

'.........

4 al L riel auloclc~~~~~~~~~~~e~e~~~~~~~~~~~e~~~~~~~~~~4 tl~1~2 Diotlc~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~4.1.3 Special Studies................

~~~~~~~~-~~~4.2 Radiological Environmental Monitoring Program.....

Deleted Deleted Deleted Deleted Deleted 0244p Amendment No.103 5.1 R L esponslbll1tpo

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~5.2 0 L rganxzation......................................

5.3 Review

and Audit............

5.0 ADMINISTRATIVE

CONTROLS................................

Deleted Deleted Deleted Deleted 5.4 Action to be Taken if Exceeded............

an Environment LCO is 5.5 rocedure.........................................

P 5.6 Reporting Requirements............................

T ablesia~~~~~~~~~~~~~~~~~~~~~~~~~~~~~t~~~F figures...........................................

5.7 Environmental

Records.............................

Deleted Deleted Deleted Deleted Deleted Deleted 02449 Amendment No.303 0~,

3.2.2 Transmission

Line Ri ht-of-Wa Maintenance

~Ob'ective The sole purpose of this section is to provide reporting requirements (to USNRC)on herbicide usage, if any, for purposes of right-of-way maintenance regarding only those transmission lines under USNRC's jurisdiction for the Browns Ferry Nuclear Plant.S ecification A statement as to whether or not herbicides have been used in maintaining rights-of-way for those transmission lines associated with the Browns Ferry Nuclear Plant shall be provided.If herbicides have been used, a description of the types, volumes, concentrations, manners and frequencies of application, and miles or rights-of-way that have been treated shall be included.Re ortin Re uirements Information as specified above shall be provided in the Annual Operating Report (Appendix A, Section 6.7.1(b)).

Bases Vegetation growth on a transmission line right-of-way must be controlled in such a manner that it will neither interfere with safe and reliable operation of the line or impede restoration of service when outages occur.Vegetation growth is controlled by mechanical cutting and the limited use of herbicides.

Selected chemicals approved by EPA for use as herbicides are assigned (by.EPA)label instructions which provide guidance on and procedures for their use.Amendment No.103 0244p O ,t t, II 1 I+