Text

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)
	v • d • e

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 ~ea e no.

Introduction o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

1.0 Definitions SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 1.1/2.1 Fuel Cladding Integrity 1.2/2.2 Reactor Coolant System Integrity . 27 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 3.1/4.1 Reactor Protection System 31 3.2/4.2 Protective Instrumentation . 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 . 52 F. Surveillance Instrumentation G. Control Room Isolation . 52 H. Flood Protection . 53 I. Meteorological Monitoring Instrumentation 53 J ~ Seismic Monitoring Instrumentation . 54 K. Radioactive Gaseous Effluent Monitoring Instrumentation .. 54 3.3/4.3 Reactivity Control 120 A. Reactivity Limitations 120 B. Control Rods . 121 C. Scram Insertion Times 124 0241p

Section D. Reactivity Anomalies . 125 E. Reactivity Control 126 F. Scram Discharge Volume '126 3.4/4.4 Standby Liquid Control System 135 A. Normal System Availability . 135 B. Operation with Inoperable Components . 136 C. Sodium Pentaborate Solution 137 3.5/4.5 Core and Containment Cooling Systems 143 A. Core Spray System (CSS) 143 B. Residual Heat Removal System (RHRS)

(LPCI and Containment Cooling) 145 C. RHR Service Mater System and Emergency Equipment Cooling'Water System (EECWS) 151 D. Equipment Area Coolers 154 E. High Pressure Coolant Injection System (HPCIS ) ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 154 F. Reactor Core Isolation Cooling System (RC ICS ) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 156 G. Automatic Depressurization System

( ADS ) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 157 H. Maintenance of Filled Discharge Pipe . 158 I. Average Planar Linear Heat Generation Rate . 159 J. Linear Heat Generation Rate (LHGR) 159 K. Minimum Critical Power Ratio (MCPR) 160 L. APRM Setpoints 160A M. Reporting Requirements . 160A 3.6/4.6 Primary System Boundary 174 A. Thermal and Pressurization Limitations . 174 B. Coolant Chemistry 176 0241p

Section ~Pa e No.

C. Coolant Leakage 180 D. Relief Valves 181 E. Jet Pumps 181 F. Recirculation Pump Operation . 182 G. Structural Integrity . 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 tern H> Analyzer 249 3.8/4.8 Radioactive Materials 281 A. Liquid Effluents . 281 B. Airborne Effluents . 283 C. Radioactive Effluents Dose 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 t

292'95 B. Operation with Inoperable Equipment C. Operation in Cold Shutdown 298 3.10/4.10 Core Alterations 302 A. Refueling Interlocks . 302 0241p

Section 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 . 308 3.11/4.11 Fire Protection Systems 315 A. High Pressure Fire Protection System . 315 B. CO> Fire Protection System . 319 C. Fire Detectors 320 D. Roving Fire Watch 321 E. Fire Protection Systems inspection 322 F. Fire Protection Organization . 322 G. Air Masks and Cylinders 323 H. Continuous Fire Watch 323

i. Open 'Flames, Welding and Burning in the Cable Spreading Room 323 5.0 Major Design Features 330 5.1 Site Features 330 5.2 Reactor 330 5.3 Reactor Vessel 330 5.4 Containment 330 5.5 Fuel Storage . 330 5.6 Seismic Design . 331 6.0 Administrative Controls 332 6.1 Organization . 332 1v 0241p

Section ~Pa e No.

0 6.2 Review and Audit 6.3 Procedures 6.4 Actions to be Taken in the Event of a 333 338 Reportable Occurrence in Plant Operation . 346 6.5 Actions to be taken in the Event a Safety Limit is Exceeded 346 6.6 Station Operating Records 346 6.7 Reporting Requirements 349 6.8 Minimum Plant Staffing 358 024lp

LIST OF TABLES Title ~Pa e No.

Surveillance Frequency Notation 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 Meteorological Monitoring Instrumentation 83 3.2eJ Seismic Monitoring Instrumentation . 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 Title ~Pa e No.

4.2.F

~ ~ 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 4.2eK 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, 172a Primary Containment Isolation Valves t

3.7.A 250 3.7.B Testable Penetrations with Double 0-Ring Seals . 256 3.7.C Testable Penetrations with Testable Bellows 257 3.7.D Air Tested Isolation Valves 258 3.7.E Primary Containment. Isolation Valves which Terminate below the Suppression Pool Water Level 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 Fire Protection System Hydraulic Requirements 324 6.8.A Minimum Shift Crew Requirements 360 v11 0241p

LIST OF ILLUSTRATIONS e ~Fi ure 2.1.1 APRM Flow Reference Settings a ~ ~ a ~ a a a Title Scram and APRM Rod Block

. . a a a a a . a a ~

~Pa 13 e No.

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 Operation of Nuclear Power Plant 361 6.1-2 Functional Organization 362 6.2-1 Review and Audit Function 363 6.3-1 In-Plant Fire Program Organization . 364 v111 0241p

UNIT 2 TABLE OF CONTENTS 0241p

TABLE OF CONTENTS Section ~Pa e No.

Introduction .

1.0 Definitions SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 1.1/2.1 Fuel Cladding Integrity 1.2/2.2 Reactor Coolant System Integrity . 27 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 3.1/4.1 Reactor Protection System 31 3.2/4.2 Protective Instrumentation . 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 . 52 F. Surveillance Instrumentation .

G. Control Room Isolation . 52 H. Flood Protection . 53 I. Meteorological Monitoring Instrumentation 53 J. Seismic Monitoring Instrumentation . 54 K. Radioactive Gaseous Effluent Monitoring Instrumentation 54 3.3/4.3 Reactivity Control 120 A. Reactivity Limitations 120 B. Control Rods 121 C. Scram Insertion Times 124 0241p

Section ~Fa e No.

D. Reactivity Anomalies 125 E. Reactivity Control 126 F. Scram Discharge Volume 126 3.4/4.4 Standby Liquid Control System 135 A. Normal System Availability . 135 B. Operation with Inoperable Components 136 C. Sodium Pentaborate Solution 137 3.5/4 .5 Core and Containment Cooling Systems 143 A. Core Spray System (CSS) 143 B. Residual Heat Removal System (RHRS)

(LPCI and Containment Cooling) 145 C. RHR Service Water System and Emergency Equipment Cooling"Water System (EECWS) 151 D. Equipment Area Coolers 154 E. High Pressure Coolant Injection System (HPCIS) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 154 F. Reactor Core Isolation Cooling System (RCICS) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 156 G. Automatic Depressurization System

( ADS ) ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ e ~ ~ ~ ~ 157 H. Maintenance oE Filled Discharge Pipe 158 I. Average Planar Linear Heat Generation R ate . 759 J. Linear Heat Generation Rate (LHGR) 159 K. Minimum Critical Power Ratio (MCPR) 160 L. APRM Setpoints 160A M.. Reporting Requirements . 160A 3.6/4.6 Primary System Boundary 174 A. Thermal and Pressurization Limitations . 174 B. Coolant Chemistry 176 0241p

Section ~Pa e No.

C. Coolant Leakage 180 D. Relief Valves 181 E. Jet Pumps 181 F. Recirculation Pump Operation . 182 G. Structural Integrity . 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) Syst em H> Analyzer 249

3. 8/4. 8 Radioactive Materials 281 A. Liquid Effluents . 281 B. Airborne Effluents ~ ~ ~ 283 C. Radioactive Effluents Dose ~ ~ ~ 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 292 B. Operation with Inoperable Equipment 295 C. Operation in Cold Shutdown . 298 3.10/4.10 Core Alterations 302 A. Refueling Interlocks . 302 0241p

Section B. Core Monitoring 305 C. Spent Fuel Pool Water 305 D. Reactor Building Crane 307 E. Spent Fuel Cask 307 F. Spent Fuel Cask Handling-Refueling Floor 308 3.11/4.11 Fire Protection Systems 315 A. High Pressure Fire Protection System . 315 B. CO> Fire Protection System . 319 C. Fire Detectors . ~ ~ ~ ~ 320 D. Roving Fire Watch 321 E. Fire Protection Systems Inspection . 322 F. Fire Protection Organization . 322 G. Air Masks and Cylinders 323 H. Continuous Fire Watch 323 I. Open Flames, Welding and Burning in the Cable Spreading Room . 323 5.0 Major Design Features 330 5.1 Site Features 330 5.2 Reactor 330 5.3 Reactor Vessel 330 5.4 Containment 330 5.5 Fuel Storage . 330 5.6 Seismic Design . 331 6.0 Administrative Controls 332 6.1 Organization . 332 6.2 Review and Audit 333 1v 0241p

Section ~Fa e No.

6.3 Procedures 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 Event a Safety Limit is Exceeded 346 6.6 Station Operating Records 346 6.7 Reporting Requirements 349 6.8 Hinimum Plant Staffing 358 024lp

LIST OF TABLES Table Title ~pa e No.

1.1 Surveillance Frequency Notation 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 Meteorological Monitoring Instrumentation 83 3.2.J Seismic Monitoring Instrumentation . 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

LIST OF TABLES (:ont'di Table 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 Primary Containment Isolation Valves 250 3.7.B Testable Penetrations with Double 0-Ring Seals 256

3. 7.C Testable Penetrations with Testable Bellows 257 3.7.D Air Tested Isolation Valves 258 3.7.E Primary Containment Isolation Valves which Terminate below the Suppression Pool Water Level ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 262 3.7.F Primary Containment Isolation Valves Located in Water Sealed Seismic Class 1 Lines . 263 3.7.H Testable Electrical Penetrations 265 1

4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start 298a 3.11.A Fire Protect on System Hydraulic Requirements 324 6.8.A Minimum Shift Crew Requirements 360 vii 024lp

LIST OF ILLUSTRATIONS e ~Fi 2.1.1 ure APRM S

Flow .Reference t

ettlngS a

a a ~ ~ ~ ~ ~ ~

Title Scram and APRM Rod Block a a ~ ~ e a a a ~ ~

~Pa 13 e No.

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 KI Factor 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 Operation of Nuclear Power Plant 361 6.1-2 Functional Organization 362 6.2-1 Review and Audit Function 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.

7A 0242p

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.

7B 0242p

Table 1.1 SURVEILLANCE FRE UENCY NOTATION NOTATION F~RE UENCY S (Shift) At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D (Daily) At least once per normal calendar 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months day (midnight to midnight).

W (Weekly) At least once per 7 days.

M (Monthly) At least once per 31 days.

Q (Quarterly) At least once per 3 months or 92 days.

SA (Semi-Annually At least once per 6 months or 184 days.

Y (Yearly) At least once per year or 366 days.

R (Refueling) At least once per operating cycle.

S/U (Start-Up) Prior to each reactor startup.

N.A. Not applicable.

P (Prior) Completed prior to each release.

7C 0242p

LIMITING CONDITIONS FOR OPERAT10N SURVEILLANCE RE UIREMENTS

~

3.Q.B Core and Containment Coolin 4.2.B Core and Containment Coolin S stems Initiation 6 Control 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 Instrumentation shall be

,.operation for the instrumentation functionally tested, that initiates control rod block calibrated, and checked as are given in Table 3.2.C. 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 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation Monitorin Instrumentation

1. The radioactive liquid 1. Each of the radioactive effluent monitoring liquid effluent monitoring instrumentation listed in instruments shall be Table 3.2.D shall be demonstrated operable by operable with the performance of test in applicability as shown in accordance with Table 4.2.D.

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.

2. The action required when the of operable channels 'umber 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

~ ~

4.2.D Radioactive Li uid Effluent (Con') (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 Instrumentation shall be operation for the instrumentation calibrated and checked as that monitors drywell leak indicated in Table 4.2.E.

detection are given in Table 3.2.E.

F. Surveillance Instrumentation F. Surveillance Instrumentation The limiting conditions for the Instrumentation shall be instrumentation that provides calibrated and checked as surveillance information readouts indicated in Table 4.2.F.

are given in Table 3.2.F.

G. Control Room Isolation G. Control Room Isolation The limiting conditions for Instrumentation shall be instrumentation that isolates calibrated and checked as the control room and initiates indicated in Table 4.2.G.

the control room emergency pressurization systems are given in Table 3.2.G.

52 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UXREMENTS 3.2.J

~ ~ Seismic Monitorin Instrumentation 4.2.J Seismic Monitorin Instrumentation l.~ The seismic monitoring 1. Each of the seismic instruments listed in monitoring instruments Table 3.2.J shall be shall be demonstrated operable at all times. operable by performance of tests at the frequencies

2. With the number of seismic listed in Table 4.2.J.

monitoring instruments less than the number listed in 2. Data shall be retrieved Table 3.2.J, restore the from all seismic inoperable instrument(s) to instruments actuated during operable status within a seismic event and 30 days. analyzed to determine the magnitude of the vibratory

3. With one or more of the ground motion. A Special instruments listed in Table Report shall be submitted 3.2.J inoperable for more to the Commission pursuant than 30 days, submit a to specification 6.7.3.D Special Report to the within 10 days describing Commission pursuant to the magnitude, frequency specification 6.7.3.C within spectrum, and resultant the next 10 days describing effect upon plant features the cause of the malfunction important to safety.

and plans for restoring the instruments to operable status.

3.2.K Radioactive Gaseous Effluent 4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation Monitorin Instrumentation The radioactive gaseous l. Each of the radioactive effluent monitoring gaseous effluent monitoring instruments listed in instruments shall be Table 3.2.K shall be demonstrated operable by operable with the performance of tests in applicability as shown in accordance with Table 4.2.K.

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.

54 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.K Radioactive Gaseous Effluent 4.2.K Radioactive Gaseous 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.

54A 0233p

TABLE 3.2.D Radioactive Li uid Effluent Monitorin Instrumentation Minimum Channels Instrument ' 0 erable I It Action

1. LIQUID RADHASTE EFFLUENT A, B 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) 76 0240p

NOTES FOR TABLE 3.2.D 0 "~At all

~'~'~During times releases via this pathway

"~'-:<During operation of an RHR loop and associated ACTION A RHR service water system 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 samples taken every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and an analysis of at least an LLD' pCi/ml (gross) or < applicable MPC ratio (y isotopic ) shall be used to

'f installed monitoring system is not available, a temporary monitor or grab 1E-7 an 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab samples are collected and analyzed for radioactivity with an LLD' jCi/ml (gross) or < applicable MPC ratio (y isotopic).

'f 1E-7 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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.

76A 0242p

E 3.2.K Radioactive Gaseous Effluent Monitorin Instrumentation Minimum Channels/

Instrument Devices 0 erable A licabilit Action STACK (RM-90-147A 5 8)

a. Noble Gas Monitor (1) A/C

b. Iodine Cartridge (1) B/C

c. Particulate Filter (1) B/C

d. Sampler Flow Abnormal (1) D

e. Stack Flow (FT, FM, (1) D F I-90-271)

REACTOR/TURBINE BLDG VENTILATION (RM-90-250)

a. Noble Gas Monitor (1) A/C

b. Iodine Sampler (1) B/C

c. Particulate Sampler (1) B/C

d. Sampler Flowmeter (1) D

3. TURBINE BLDG EXHAUST (RM-90-249, 251)

a. Noble Gas Monitor (1) A/C

b. Iodine Sampler (1) B/C

c. Particulate Sampler (1) B/C

d. Sampler Flowmeter (1) D RADHASTE BLDG VENT (RM-90-252)

a. Noble Gas Monitor (1) A/C

b. Iodine Sampler (1) B/C

c. Particulate Sampler (1) B/C

d. Sampler Flowmeter (1) D

5. OFF GAS HYDROGEN ANALYZER (H~A, HgB)

6. OFF GAS POST TREATMENT

a. Noble Gas Activity Monitor (RM-90-265, 266)

b. Sample Flow Abnormal (PA-90-262) 84A 0240p

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.

ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 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 Channel Functional Instrument Instrument Check Source Check Calibration Test

1. LIQUID RADHASTE EFFLUENT D(4) R(5) Q(1)

MONITOR (RM-90-130)

2. RHR SERVICE HATER MONITOR D(4) R(5) Q(2)

(RM-90-133, -134)

3. RAH COOLING HATER MONITOR D(4) R(5) Q(2)

(RM-90-132)

4. LIQUID RADHASTE EFFLUENT D(4) NA Q(3)

FLOH RATE (77-60 loop) 103 0240p

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 the following conditions exist:

if any of

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0 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 Channel Functional Instrument Instrument Check Source Check Calibration Test STACK

a. Noble Gas Monitor ' M R( ) Q(Z)

b. Iodine Cartridge NA NA NA

c. Particulate Filter NA NA NA

d. Sampler Flow Abnormal NA R Q

e. Stack Flowmeter NA R Q 2 ~ REACTOR/TURBINE BLDG VENT

a. Noble Gas Monitor '"'. M R(1) Q(2)

Iodine Sampler NA NA NA

c. Particulate Sampler NA NA NA

d. Sampler Flowmeter NA R Q

3. TURBINE BLDG EXHAUST

a. Noble Gas Monitor " '.

M R( 1) Q(/)

Iodine Sampler NA NA NA

c. Particulate Sampler NA NA NA

d. Sampler Flowmeter NA R Q

4. RADHASTE BLDG VENT

a. Noble Gas Monitor . M R( 1 ) Q(Z)

Iodine Sampler NA NA NA

c. Particulate Sampler NA NA NA

d. Sampler Flowmeter NA R

5. OFF GAS HYDROGEN ANALYZER (HpA, HpB) Q(a)

R'"'(

6. OFF GAS POST TREATMENT I)

Noble Gas Activity Monitor Q(4)

b. Sample Flow Abnormal R Q(l) 108A 0240p

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.

little reduction shorter interval The best in The curve does have a definite knee and very system unavailability is achieved by testing at a than computed by the equation for a single channels 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 4.6 Primar S stem Boundar 6.

~ Whenever the react or is 6. Additional coolant samples critical, the limits on shall be taken whenever the activity concentrations in the reactor activity exceeds one reactor coolant shall not percent of the equilibrium exceed the equilibrium value concentration specified in of 3.2 pc/gm of does 3.6.B.6 and one of the equivalent I-131. following conditions are met:

This limit may be exceeded a. During startup following power transients for b. Following a signi'ficant a maximum of 48.hours. During power change~'~~

this activity transient the c. Following an increase in iodine concentrations shall the equilibrium off-gas not exceed 26 pCi/gm whenever level exceeding 10,000 the reactor is critical. The pCi/sec (at the steam reactor shall not be operated jet air ejector) within more than 5 percent of its a 48 hour period.

yearly power operation under d. Whenever the equilibrium this exception for the iodine limit specified equilibrium activity limits. in 3.6.B.6 is exceeded.

If the iodine concentration in the coolant exceeds 26 pCi/gm, The additional coolant the reactor shall be shut down, liquid samples shall be and the steam line isolation taken at 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months intervals valves shall be closed for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or until a immediately. 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 hour.

179 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials Applies to the release of Applies to the periodic test and radioactive liquids and gases record requirements and sampling from the facility. and monitoring methods used for facility effluents.

O~b ective

~Ob ective To define the limits and conditions for the release of To ensure that radioactive radioactive effluents to the liquid and gaseous releases from environs to assure that any the facility are maintained

.radioactive releases are as within the limits specified by low as reasonably achievable Specifications 3.8.A and 3.8.B.

and within the limits of 10 CFR Part 20. The specifications S ecification except for 3.8.A.l and 3.8.B.1 are exempt from the requirements of A. Li uid Effluents definition 1.0.C (Limiting Condition for Operation). 1. Facility records shall be maintained of radioactive concentrations and A. Li uid Effluents volume before dilution of each batch of liquid

1. The concentration of effluent released, and radioactive material of the average dilution released at any time from flow and length of time the site to unrestricted over which each areas (see Figure 4.8-lb) discharge occurred.

shall be limited to the concentrations specified 2. Radioactive liquid waste in 10 CFR Part 20, sampling and activity Appendix B, Table II, analysis of each liquid Column 2 for radionuclides waste batch to be other than dissolved or discharged shall be entrained noble gases. performed prior to For dissolved or entrained release in accordance noble gases, the with the sampling and concentration shall be analysis program limited to 2E-4 pCi/ml specified in the REM.

total activity.

3.. The operation of the

2. If the limits of 3.8.A.1 automatic isolation are exceeded, appropriate valves and discharge action shall be initiated tank selection valves without delay to bring shall be checked the release within annually.

281 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials limits. Provide prompt 4. The results of the notification to the NRC analysis of samples pursuant to section 6.7.2. collected from release points shall be used

3. The doses or dose with the calculational commitment to a member of methodology in the ODCM the public from radioactive to assure that the materials in liquid concentrations at the effluents released from point of release are each unit to unrestricted maintained within the areas (See Figure 4.8-1b) limits of specification shall be limited: 3.8.A.l.

a. During any calendar 5. Cummulative quarterly quarter to <1.5 mrem to and yearly dose the total body and <5 contributions from mrem to any organ and, liquid effluents shall be determined as

b. During any calendar specified in the ODCM at year to <3 mrem to the least once every 31 days.

total body and <10 mrem to any organ The quantity of radioactive material 4 ~ If the limits specified in contained in any outside liquid radwaste storage 3.8.A.3 a 6 b above are exceeded, prepare and tanks shall be submit 'Special Report determined to be within pursuant to Section 6.7.2. the above limit by analyzing a

5. The maximum activity to be 'representative sample of contained in one liquid the tank's contents at radwaste tank or temporary ~

least once per 7 days storage tank that can be when radioactive discharged directly to the materials are being environs shall not exceed added to the tank.

10 curies excluding tritium and dissolved/entrained noble gas.

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , 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 UIREMENTS Radioactive Materials 4.8 Radioactive Materials B. Airborne Effluents B. Airborne Effluents

1. The dose rate at any time 1. The gross 6/y and to areas at and beyond the particulate activity of site boundary (see Figure gaseous wastes released 4.8-lb) due to to the environment shall radioactivity released in be monitored and gaseous effluents from the recorded.

site shall be limited to the following values: a. For effluent streams having continuous

a. The dose rate limit monitoring for noble gases shall capability, the be <500 mrem/yr to the activity shall be total body and <3000 monitored and flow mrem/yr to the skin, rate evaluated and and recorded to enable release rates of

b. The dose rate limit gross radioactivity for I-131, I-133, H-3, to be determined at and particulates with least once per shift greater than eight day using instruments half-lives shall be specified in table

<1500 mrem/yr to any 3.2.K.

organ.

b. For effluent streams

2. If the 'limits of 3.8.B.1 without continuous are exceeded, appropriate monitoring corrective action shall be capability, the immediately initiated to activity shall be bring the release within monitored and limits. Provide prompt recorded and the notification to the NRC release through pursuant to section 6.7.2. 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 3. Cumulative quarterly and and beyond the site yearly dose boundary (see Figure contributions from 4.8-1b) due to noble gases gaseous releases shall released in gaseous be determined using effluents per unit shall methods contained in the be limited to the ODCM at least once every following: 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 any organ during any calendar year to

<15 mrem; 284 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS

6. If the calculated doses 4. During operation above exceed the limits oF 25/o power, the position 3.8.B.5 above, prepare of the charcoal bed and submit a special bypass valve will be report pursuant to verified daily.

section 6.7.2.

7. During operation above 5. The concentration of 25K power the discharge hydrogen downstream of of the SJAE must be the recombiners shall be routed through the determined to be within charcoal adsorbers. the limits of 3.8.B.9 by continuously monitoring

8. With gaseous waste being the offgass whenever the discharged for more than SJAE is in service using 7 days without treatment instruments described in through the charcoal Table 3.2.K. Instrument adsorbers, prepare and surveillance submit a special report requirements are pursuant to section specified in Table 4.2.K.

6.7.2.

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 hours.

285 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8.C Radioactive Effluents Dose 4.8.C Radioactive Effluents Dose

1. The dose or dose \ 1. Cumulative dose commitment to a real contributions from individual from all liquid and gaseous uranium fuel cycle sources effluents shall be is limited to <25 mrem to determined in accordance the total body or any with specifications organ (except the thyroid, 3.8.A.3, 3.8.B.3, and which is limited to <75 3.8.B.5 and the methods mrem) over a period of one in the ODCM.

calendar year.

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 At least once during each shall be capable of being operating cycle verify automatic automatically isolated and securing and isolation of the secured on a signal or mechanical vacuum pump.

high radioactivity in the steam lines whenever the main steam isolation valves are open.

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 E. Miscellaneous Radioactive Materials Sources Materials Sources

1. Source Leaka e Test 1. Surveillance Re uirement Each sealed source Tests for leakage and/or containing radioactive contamination shall be material either in excess performed by the of 100 microcuries of beta licensee or by other and/or gamma emitting persons specifically material or 5 microcuries authorized by the of alpha emitting material Commission or an shall be free of > 0.005 agreement State, as microcurie of removable follows:

contamination. Each sealed souce with removable a. Sources in Use contamination in excess of the above limit shall be Each sealed source, immediately withdrawn from excluding startup use and (a) either sources and flux decontaminated and detectors previously repaired, or (b) disposed subjected to core of in accordance with flux, containing Commission regulations. 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 1. The Process Control shall be operated in Program shall include accordance with a process surveillance checks control program, for the necessary to demonstrate solidification and compliance with 3.8.F.1.

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.

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)

Turbine Building Office Building Service Bldg.

ad-4aste Bldg.

Reactor Building Reactor Building Ventilation (40m)

Stack (180m)

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< AlllC 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 by 291 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.

A

1. Review changes to the radwaste treatment systems. 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 Written administrative procedures for committee operation shall be 0 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.......................... Deleted 2 .2 Chemical............ Deleted 2.2.1 Makeup Water Treatment Plan t Spent Demineralizer Regerants.. Deleted 2 .2.2 Chlorine. Deleted 3.0 DESIGN FEATURES AND OPERATING PRACTICES................ Deleted 3.1 Chemical Usage. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Deleted 0 3.1.1 3.1.2 Oils Other and Hazardous Materials Chemicals............................

.............. Deleted Deleted 3.2 Land Management............. Deleted 3.2.1 Power Plant Site........................... 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........................... Deleted 4 .1.1 Abiotlc Deleted 4 .1.2 ea Blotice ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Deleted 4.1.3 Special Studies.................... ~ .... ~ .- Deleted 4.2 Radiological Environmental Monitoring Program..... Deleted 0242p

0 5.0 ADMINISTRATIVE CONTROLS...... Deleted 5.1 Responsibility.......... Deleted 5.2 Organiratxon.............. Deleted 5.3 Review and Audit.......... Deleted 5.4 Action to be Taken if an Environment LCO is Ezceeded.............. ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Deleted 5.5 Procedure......................... ~ ~ ~ ~ ~ ~ ~ ~ Deleted 5.6 Reporting Requxrements............................ Deleted 5.7 Environmental Records... ~ ......................... Deleted Tables........................ Deleted Figures. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Deleted 0242p

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 Fuel Cladding Integrity.

1.2/2.2 Reactor Coolant System Integrity . 26 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 3.1/4.1 Reactor Protection System. 31 3.2/4.2 Protective Instrumentation ... 49 A. Primary Containment and Reactor Building Isolation Functions. 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 . 53 F. Surveillance Instrumentation . 53 G. Control Room Isolation .

H. Flood Protection . 54 I. Meteorological Monitoring Instrumentation. 54 J. Seismic Monitoring Instrumentation . 56 K. Radioactive Gaseous Effluent Monitoring Instrumentation. ~ ~ ~ ~ ~ ~ 56A 3.3/4.3 Reactivity Control 118 A. Reactivity Limitations 118 B. Control Rods 122 0

0243p

Section ~Pa e No.

C. Scram Insertion Times. 128 D. Reactivity Anomalies. 129 E. Reactivity Control 129 F. Scram Discharge Volume . 129 3.4/4.4 Standby Liquid Control System. 137 A. Normal System Availability . 137 B. Operation with Inoperable Components 139 C. Sodium Pentaborate Solution. 139 3.5/4.5 Core and Containment Cooling Systems . 146 A. Core Spray System. 146 B. Residual Heat Removal System (RHRS)

(LPCI and Containment Cooling) 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 167A M. Reporting Requirements . 167A 3.6/4.6

~

Primary System Boundary. 184 A.~ Thermal and Pressurization Limitations 184 0243p

Section ~Pa e No.

B. Coolant Chemistry. 187 C. Coolant Leakage. 191 D. Relief Valves. 192 E. Jet Pumps. 193 F. Recirculation Pump Operation . 195 G. Structural Integrity . 196 H. Seismic Restraints, Supports, and Snubbers 198 3.7/4.7 Containment Systems. 231 A. Primary Containment. 231 B. Standby Gas Treatment System . 247 C. Secondary Containment. 251 D. Primary Containment Isolation Valves . 254 E. Control Room Emergency Ventilation . 256 F. Primary Containment Purge System 258 G. Containment Atmosphere Dilution System (CAD) 260 H. Containment Atmosphere Monitoring (CAM)

System H~ Analyzer 261

3. 8/4' 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 Sources. 305 F. Solid Radwaste . 307 3.9/4.9 Auxiliary Electrical System. 316 A. Auxiliary Electrical Equipment 316 B. Operation with Inoperable Equipment. 321 0243p

t Section 3.10/4.10 Core A.

B.

Operation in Cold Shutdown.

Alterations .

Refueling Interlocks.

Core Monitoring .

'a

~Fa e No.

326 331 331 336 C. Spent Fuel Pool Water . 337 D. Reactor Building Crane. 338 E. Spent Fuel Cask . 339 F. Spent Fuel Cask Handling-Refueling F loor ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 339 3.11/4.11 Fire Protection Systems. 347 A. High Pressure Fire Protection System. 347 B. CO> Fire Protection System. 351 C. Fire Detectors. 352 D. Roving Fire Watch . 353 E. Fire Protection Systems Inspections 354 F. Fire Protection Organization. 354 G. Air Masks and Cylinders 355 H. Continuous Fire Watch . 355 I. Open Flames, Welding, and Burning

~

in the Cable Spreading Room. 355 5.0 Major Design Features. 360 5.1 Site Features . 360 5.2 Reactor . ~ ~ ~ 360 5.3 Reactor Vessel. 360 5.4 Containment 360 5.5 Fuel Storage. 360 5.6 Seismic Design. 361 Administrative Controls. 362 6.1 Organization. 362 1v 0243p

LIST OF TABLES Section Title ~Pa e No.

1.1 Surveillance Frequency Notation.

3.1.A 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 for Reactor Protection Instrument Channels 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 a

3.2.D Radioactive Liquid Effluent Monitoring Instrumentation. 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 Minimum RHRSW and EECW Pump Alignment. . . . . . 156a 3.5.I 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 Level. 279 3.7.F Primary Containment Isolation Valve Located in Water Sealed Seismic Class I Lines. 280 3.7.G Deleted 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 v11 0243p

t ~Fi ure 2.1.1 2.1-2 APRM S et t lngs APRM a

~ ~ ~ ~ ~

LIST Flow Reference Scram and

~ ~

OF ILLUSTRATIONS Title

~ ~ ~ ~

APRM Rod

~

Flow Bias Scram Vs. Reactor Core-Flow .

~ ~ ~

Block

~ ~ ~ ~ ~

~Pa e No.

14 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 Requirements . 142 3.5.K-1 MCPR Limits. 182c 3.5.2 KI Factor vs. Percent Core Flow. 183 3.6-1 Temperature-Pressure Limitations 207 Change in Charpy V Transition Temperature Vs.~ Neutron Exposure 208 4.8.1.a

~ ~ ~ Gaseous Release Points and Elevations. 308 4.8.1.b Site Boundary. 309 6.1-1 TVA Office of Power Organization for Operati on of Nuclear Power Plants. 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

a protective trip function. A trip system may require one or more

' instrument channel trip signals related to one or more plant 0 7.

.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.

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). 4 j>> '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 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.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. 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. 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.

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'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 ~E<EUENCY S (Shift) At least once per 12 hours.

D (Daily) At least once per normal calendar 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months day (midnight to midnight).

W (Weekly) At least once per 7 days.

M (Monthly) At least once per 31 days.

Q (Quarterly) At least once per 3 months or 92 days.

SA (Semi-Annually) At least once per 6 months or 184 days.

Y (Yearly) At least once per year or 366 days.

R (Refueling) At least once per operating cycle.

S/U (Start-Up) Prior 'to each reactor startup.

N.A. Not applicable.

P (Prior) 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 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation Monitorin Instrumentation The radioactive liquid l. Each of the radioactive effluent instrumentation liquid effluent listed in Table 3.2.D shall monitoring instruments be operable with the shall be demonstrated applicability as shown in operable by performance Table 3.2.D/4.2.D. Alarm/ of test in accordance trip setpoints will be set with Table 4.2.D.

in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.A.1 are not exceeded.

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 4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation Monitorin Instrumentation The radioactive gaseous l. Each of the radioactive effluent monitoring instruments gaseous effluent monitoring listed in Table 3.2.K shall be instruments shall be operable with the applicability demonstrated operable by as shown in Tables 3.2.K/4.2.K. performance of tests in

- Alarm/trip setpoints will be accordance with Table 4.2.K..-

set in accordance with guidance given in the ODCM to ensure that the limits of specification 3.8.B.l are not exceeded.

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

TABLE 3.2.D Radioactive Li uid Effluent Monitorin Instrumentation Minimum Channels Instrument ' 0 erable b lit Action

1. LIQUID RADHASTE EFFLUENT A, B 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) f ~

79 0240p

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 samples taken every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and an analysis of at least an LLD' monitor

'for (gross) or ( applicable MPC ratio (y isotopic) shall be used to grab 1E-7'Ci/ml 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , grab samples are collected and analyzed for radioactivity with an LLD' pCi/ml (gross) or ( applicable MPC ratio (y isotopic).

'f 1E-7 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 Minimum Channels/

Instrument Devices 0 erable A 1 i cab i 1 it Action STACK (RM-90-147A 5 B)

a. Noble Gas Monitor (1) A/C

b. Iodine Cartridge (1) 8/C .

c. Particulate Filter (1) B/C

d. Sampler Flow Abnormal (1) D

e. Stack Flow (FT, FM, (1) D FI-90-271)

2. REACTOR/TURBINE BLDG VENTILATION (RM-90-250)

a. Noble Gas Monitor (1) A/C

b. Iodine Sampler (1) B/C

c. Particulate Sampler (1) B/C d ~ Sampler Flowmeter (1) D

3. TURBINE BLDG EXHAUST (RM-90-249, 251)

a. Noble Gas Monitor (1) A/C

b. Iodine Sampler (1) B/C

c. Particulate Sampler (1) B/C

d. Sampler Flowmeter (1) D

4. RADHASTE BLDG VENT (RM-90-252)

a. Noble Gas Monitor (1) A/C

b. Iodine Sampler ~

(1) 8/C

c. Particulate Sampler (1) B/C

d. Sampler Flowmeter (1) D

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) 87A 0240p

l ~'~At all times NOTES FOR TABLE

>'~'<During releases via this pathway

~'~'~~During main condenser offgas treatment ACTION A 3.2.K system operation 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.

ACTION C monitoring system may be out of service for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for functional testing, t

A calibration, or repair without providing or initiating grab sampling.

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 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 Channel Functional Instrument Instrument Check Source Check Calibration Test 1 ~ LIQUID RADHASTE EFFLUENT D(4) R(5) Q(1)

MONITOR (RM-90-130)

2. RHR SERVICE HATER MONITOR D(4) R(5) Q(2)

(RM-90-133, -134)

3. RAW COOLING HATER MONITOR D(4) R(5) Q(2)

(RM-90-132)

4. LIQUID RADHASTE EFFLUENT D(4) R Q(3).

FLOH RATE (77-60 loop) 100 0240p

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 Channel Functional Instrument Instrument Check Source Check Calibration Test STACK

a. Noble Gas Monitor ' D M'A R(1) Q(2)

b. Iodine Cartridge W NA NA

c. Particulate Filter W NA NA NA

d. Sampler Flow Abnormal D NA R Q

e. Stack Flowmeter D NA R Q 2.

a. Noble Gas Monitor "

REACTOR/TURBINE BLDG VENT D M R"'A Q(2)

Iodine Sampler NA NA

c. Particulate Sampler NA NA NA

d. Stack Flowmeter D NA R Q

3. TURBINE BLDG EXHAUST

a. Noble Gas Monitor " '.

M R( 1) Q(2)

Iodine Sampler NA NA NA

c. Particulate Sampler NA NA NA

d. Stack Flowmeter NA R Q 4 RADWASTE BLDG VENT

a. Noble Gas Monitor " '.

R( 1) Q(2)

Iodine Sampler NA NA NA

c. Particulate Sampler NA NA NA

d. Stack Flowmeter NA R Q

5. OFF GAS HYDROGEN ANALYZER (H2A, H2B) R( ) Q(4)

6. OFF GAS POST TREATMENT .

Noble Gas Activity Monitor D R( 1) Q(4 )

b. Sample Flow Abnormal D R Q(2) 105A 0240p

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 f

Equivalent).

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

105B 0244p

t Cg I II 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 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 t

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 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

t 3.6 LIMITING CONDITIONS Primar 5.

S FOR OPERATION stem Boundar Whenever the critical, the reactor is limits activity concentrations in the reactor coolant shall not exceed the equilibrium on 4.6 SURVEILLANCE RE UIREMENTS Primar S'stem Boundar 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

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.

190 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 . Radioactive Materials 4.8 Radioactive Materials Applies to the release of Applies to the periodic test and radioactive liquids and gases record requirements and sampling from the facility. and monitoring methods used for facility effluents.

~Ob ective O~b ective To define the limits and conditions for the release of To ensure that radioactive radioactive effluents to the liquid and gaseous releases from environs to assure that any the facility are maintained

.radioactive releases are as within the limits specified by low as reasonably achievable Specifications 3.8.A and 3.8.B.

and within the limits of 10 CFR Part 20. The specifications S ecification except for 3.8.A.1 and 3.8.B.1 are exempt from the requirements of A. Li uid Effluents definition 1.0.C (Limiting Condition for Operation). 1. Facility records shall be maintained of radioactive concentrations and A. Li uid Effluents volume before dilution of each batch of liquid

1. The concentration of effluent released, and radioactive material of the average dilution released at any time from flow and length of time the site to unrestricted over which each areas (see Figure 4.8-1b) discharge occurred.

shall be limited to the concentrations specified 2. Radioactive liquid waste in 10 CFR Part 20, sampling and activity Appendix B, Table II, analysis of each liquid Column 2 for radionuclides waste batch to be other than dissolved or discharged shall be entrained noble gases. performed prior to For dissolved or entrained release in accordance noble gases, the with the sampling and concentration shall be analysis program limited to 2E-4 pCi/ml specified in the REM.

total activity.

3. The operation of the

2. If the limits of 3.8.A.l automatic isolation are exceeded, appropriate valves and discharge action shall be initiated tank selection valves without delay to bring shall be checked the release within annually.

299 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8i Radioactive Materials 4.8 Radioactive Materials limits. Provide prompt 4. The results of the notification to the NRC analysis of samples pursuant to section 6.7.2. collected from release points shall be used

3. The doses or dose with the calculational commitment to a member of methodology in the ODCM the public from radioactive to assure that the materials in liquid concentrations at the effluents released from point of release are each unit to unrestricted maintained within the areas (See Figure 4.8-1b) limits of specification shall be limited: 3.8.A.1.

a. During any calendar 5. Cummulative quarterly quarter to <1.5 mrem to and yearly dose the total body and <5 contributions from mrem to any organ and, liquid effluents shall be determined as

b. During any calendar specified in the ODCM at year to <3 mrem to the least once every 31 days.

total body and <10 mrem to any organ 6. The quantity of radioactive material

4. If the limits specified in contained in any outside 3.8.A.3 a 6 b above are liquid radwaste storage exceeded, prepare and tanks shall be submit Special Report determined to be within pursuant to Section 6.7.2. the above limit by analyzing a

5. The maximum activity to be representative sample of contained in one liquid the tank's contents at radwaste tank or temporary least once per 7 days storage tank that can be when radioactive discharged directly to the materials are being environs shall not exceed added to the tank.

10 curies excluding tritium and dissolved/entrained noble gas.

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , 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 4.8 Radioactive Materials B. Airborne Effluents B. Airborne Effluents

1. The dose rate at any time 1. The gross 0/y and to areas at and beyond the particulate activity of site boundary (see Figure gaseous wastes released 4.8-1b) due to to the environment shall radioactivity released in be monitored and gaseous effluents from the recorded.

site shall be limited to the following values: a. For effluent streams having continuous The dose rate limit monitoring for noble gases shall capability, the be <500 mrem/yr to the activity shall be total body and <3000 monitored and flow mrem/yr to the skin, rate evaluated and and recorded to enable release rates of

b. The dose rate limit gross radioactivity for I-131, I-133, H-3, to be determined at and particulates with least once per shift greater than eight day using instruments half-lives shall be specified in table

<1500 mrem/yr to any 3.2.K.

organ.

b. For effluent streams

2. If the'limits of 3.8.B.l without continuous are exceeded, appropriate monitoring corrective action shall be capability, the immediately initiated to activity shall be bring the release within monitored and limits. Provide prompt recorded and the notification to the NRC release through pursuant to section 6.7.2. 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 3. Cumulative quarterly and and beyond the site yearly dose boundary (see Figure contributions from 4.8-1b) due to noble gases gaseous releases shall released in gaseous be determined using effluents per unit shall methods contained in the be limited to the ODCM at least once every following: 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 4. During operation above 25'X power, the position exceed the limits of 3.8.B.5 above, prepare of the charcoal bed and submit a special bypass valve will be

'report pursuant to verified daily.

section 6.7.2.

7. During operation above 5. The concentration of 25K power the discharge hydrogen downstream of of the SJAE must be the recombiners shall be routed through the determined to be within charcoal adsorbers. the limits of 3.8.B.9 by continuously monitoring

8. With gaseous waste being the offgass whenever the discharged for more than SJAE is in service using 7 days without treatment instruments described in through the charcoal Table 3.2.K. Instrument adsorbers, prepare and surveillance submit a special report requirements are pursuant to section specified in Table 4.2.K.

6.7.2.

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

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 1. Cumulative dose commitment to a real contributions from individual from all liquid and gaseous uranium fuel cycle sources effluents shall be is limited to <25 mrem to determined in accordance the total body or any with specifications organ (except the thyroid, 3.8.A.3, 3.8.B.3, and which is limited to <75 3.8.B.5 and the methods mrem) over a period of one in the ODCM.

calendar year.

2. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits

't 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 least once during each shall be capable of being operating cycle verify automatic automatically isolated and securing and isolation of the secured on a signal or mechanical vacuum pump.

high radioactivity in the steam lines whenever the main steam isolation valves are open.

2. If the limits of 3.8.D.1 are not met, the vacuum pump shall be isolated.

304 0233p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials E. Miscellaneous Radioactive E. Miscellaneous Radioactive Materials Sources Sources .'aterials

1. Source Leaka e Test 1. Surveillance Re uirement Each sealed source Tests for leakage and/or containing radioactive contamination shall be material either in excess performed by the of 100 microcuries of beta licensee or by other and/or gamma emitting persons specifically material or.5 microcuries authorized by the of alpha emitting material Commission or an shall be free of > 0.005 agreement State, as microcurie of removable follows:

contamination. Each sealed source with removable. a. Sources in Use contamination in excess of the above limit shall be Each sealed source, immediately withdrawn from excluding startup use and (a) either sources and flux decontaminated and detectors previously repaired, or (b) disposed subjected to core of in accordance with flux, containing Commission regulations. 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 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 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 1. The Process Control shall be operated in Program shall include accordance with a process surveillance checks control program, for the necessary to demonstrate solidification and with 3.8.F.l. 'ompliance 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.

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 Turbine Building Exhaust Pan (32m)

Turbine Building Office Building Service Bldg.

Rad- "

Maste Bldg.

Reactor Building Reactor Building Ventilation (40m)

Stack (180m)

Pigure 4.8-la GASEOUS RELEASE POINTS AND ELEVATIONS 308

Ltqutd Dteeherge

/

A>tffueer Ptpee) eeeefr: ffeer Q~.

~ 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 criteria materials released as low as reasonably achievable in=accordance with 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 radioactive material Section IV.A of Appendix I to assure that the releases of 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.

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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.

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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 line is to limit the 3

The purpose of isolating the mechanical vacuum pump 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. 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.

,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:

a0 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 ~ 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. ~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.

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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.

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6. 0 ADMINISTRATIVE CONTROL 0 6.9 Process Control Pro ram (PCP)

1. 'he PCP shall implementation.

be approved by the Commission'prior to

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)

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.

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.......................... Deleted 2 .2 Chemical.......................................... Deleted 2.2.1 Makeup Water Treatment Plant Spent

.Demineralizer Regerants.................. Deleted 2 .2.2 ~ulorxne................................... 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.. Deleted 3 .2 Land Management................................... Deleted 3.2.1 Power Plant Site............ 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........................... Deleted 4~1 ~1 kl AU1OIL Xc ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Deleted 4 ~ 1 ~ 2 DloLlc ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Deleted 4.1.3 Special Studies............................ 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 Valley Authority P'ennessee 0232p

RADIOLOGICAL EFFLUENT MANUAL TABLE OF CONTENTS 0 A.

SECTION INTRODUCTION PAGE NO.

A-1 REV. NO.

B. RESPONSIBILITIES B-1 C. 1. LIQUID EFFLUENTS SAMPLING C-1 AND ANALYSIS PROGRAM

2. LIQUID WASTE TREATMENT C-5 D. 1. GASEOUS EFFLUENTS SAMPLING D-1 AND ANALYSIS PROGRAM

2. GASEOUS WASTE TREATMENT D-5 E. RADIOLOGICAL ENVIRONMENTAL MONITORING

1. SAMPLING AND ANALYSIS E-1

2. LAND USE CENSUS E-3

3. INTERLABORATORY E-5 COMPARISON PROGRAM F. REPORT CONTENT

1. ANNUAL RADIOLOGICAL F-1 ENVIRONMENTAL OPERATING REPORT

2. SEMIANNUAL RADIOACTIVE F-2 EFFLUENT RELEASE REPORT

3. SPECIAL REPORTS (RADIOLOGICAL F-3 ENVIRONMENTAL MONITORING) 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 DESIGN CAPABILITY LIQUID RELEASE MINIMUM ANALYSIS TYPE OF ACTIVITY LOWER LIMIT OF DETECTION-TYPE FRE UENCY FRE UENCY ANALYSIS (LLD) ( Ci/ml)

ReleasesAMPLING Batch Waste Each Batch Each Batch Prior EmittersYSTEM Principal Gamma to Release One Batch Monthly Dissolved and E 5<>>

per Month Entrained Gases' Monthly 'onthly Tritium 1 E-5 Composite "

Proportional Gross a 1 E-7 Quarterly Sr-89, Sr-90 5 E-8 Composite

uarterly Proportional Fe-55 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 shall be used to reduce the radioactive materials in liquid wastes prior to their discharge from the site when the projected monthly dose would exceed 0.06 mrem to the total body or 0.21 mrem to any organ per unit (see Figure 4.8-1b, Technical Specification).

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 SYSTEM DESIGN CAPABILITY GASEOUS RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTIVITY LOHER LIMIT OF DETECTION TYPE FRE UENCY FRE UENCY ANALYSIS ( Ci/ml)

A. Containment Prior to Each Prior to Each Purge Principal Gamma Purge Purge Grab Sample Emitters' 1E-4E-6 H-3 B. 1. Stack Grab Sample Monthly" 'rincipal" Emitters Gamma Building Ventilation Grab Sample Monthly'"'-3 '.

1E-6

a. Reactor/

Turbine

b. Turbine Exhaust

c. Radwaste C. All Release Continuous Charcoal Sample lE-12

Points Listed Sampler in B. Above Continuous Heekly'"'-131 Heekly'"'articulate Sample Principal Gamma E-11 Sampler fmitters' and I-131 1E-12ontinuous Composite Particulate Gross Alpha 1E-11 Sampler Sample Monthly Continuous Composite Particulate Sr-89, Sr-90 1E-11 Sampler Sample Quarterly D-2 0232p

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):

4.66 sb LLD =

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 monitoring samples shall be collected pursuant to Table E-1 from the locations given in the table and figure in the ODOM and shall be analyzed pursuant to the requirement of Table E-1 and the detection capabilities 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 owner consents.

if the 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

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:

0 a. Within a 2 mile radius from the plant or within the isodose line, whichever is larger, equivalent counting technique.

enumeration by a 15 mrem per year.

door-to-door or

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 Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sam le ~51 N Collection Fre uenc of Anal sis

3. WATERBORNE

a. Surface 2 locations Composite'ample collected Gamma isotopic analysis over a period of < 31 days. of each composite sample.

. Tritium analysis of com-posite sample at least once per 92 days.

b. Drinking Minimum of downstream 1 Composite'ample Gross beta and gamma location, or all water collected'ver a period < 31 days. isotopic analysis of supplies within 10 miles each composite sample.

downstream which are Tritium analysis of taken from the Tennessee composite sample at least River. once per 92 days.

c. Sediment of 1 location At least once per 184 days. Gamma isotopic analysis Ground'inimum of each sample.

d.

'Sample locations are shown in the ODCM.

'Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours.

'Composite samples shall be collected over a period of < 14 days for I 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.

E-7 0232p

TABLE E-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sam le Sam le Locations' Collection Fre uenc of Anal sis

4. INGESTION

a. Milk locations At least once per 15 days I-131 analysis of each when animals are on pasture; sample. Gamma isotopic at least once per 31 days analysis at least once at other times. per 31 days.

b. Fish 2 samples One sample in season, or at Gamma isotopic analysis least once per 184 days if on edible portions.

not seasonal. One sample of commercial and game species.

c. Food Products' locations At least once per year Gamma isotopic analysis at time of harvest. 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 Fish Mi 1 k Food Products Sediment (pCi/1) (pCi/m') (pCi/kg, wet) (pCi/1) (pCi/kg, wet) (pCi/kg, dry) gross beta 1 x10 N.A. N.A. N.A. N.A.

H-3 2000 N.A. N.A. N.A.

Mn-54 15 N.A. 130 N.A. N.A. N.A.

Fe-59 30 N.A. 260 N.A. N.A.

Co-58, 60 15 N.A. 130 N.A. N.A. N.A.

Zn-65 30 N.A. 260 N.A. N.A.

Zr-95 30 N.A. N.A. N.A. N.A.

Nb-95 15 N.A. N.A. N.A. N.A.

I-131 7x10' N.A. 60 N.A.

Cs-134 15 x 10

' 130 15 60 150 Cs-137 18 x 10 150 18 80 180 N.A.

'.A.

Ba-140 60 60 N.A.

La-140 15 N.A. N.A. 15 N.A. N.A.

E-9 0232p

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):

4.66 si, LLD =

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 Hater

~(Ci/1> ~G( Particulate C I '> (

Fish Ci/K wet) ~(Ci 1 k

/1)

Food Products

( Ci/K wet)

H-3 2 x 10"" N.A. N.A. N.AD N.A.

Mn-54 1 x10' N.A. 3 x 10' N.A. N.A.

Fe-59 x 10'irborneN.A.

10' x 10' Co-58 x 10' x 10' N.A. N.A.

Co-60 x 10' N.A. x 10' N.A. N.A.

x10' 10'i Zn-65 N.A. x N.A. N.A.

10'.A.

Zr-Nb-95 N.A. N.A.

x10'0 I-131 0.9 N.A. 1 x 10' Cs-134 10 1 x10' 60 x10" Cs-137 50 20 x 70 2 x 10'.A.

Ba-La-140 2 x N.A. 3x10

'For drinking water samples. This is 40 CFR Part 141 value.

E-12 0232p

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 Office of Inspection and Enforcement within 60 days after 'egional 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. remained the same while 4.8.A.2 was 1

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 is covered in Table 3.2.D. The Surveillance Requirement currently numbered it 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 All of these changes have resulted in page 310 of the unit 3 'oundary.

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.

and m:

These requirements were added as items j ., k., l.

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 286 11 287 ill 288 lv 289 V 290 Vl 290A Vl1 291 V111 291A 7 291B 7A 291C 7B 291D 7C 334A 51 337 52 338 54 340 54A 355 76 359 76A 84A 84B 103 103A 108A 108B 115A 118 179 281 282 283 284 285 Revise Appendix B as follows:

Table of Contents 2 pp.

0

0 TABLE OF CONTENTS Section ~pa e Wo.

Introduction .

1.0 Defxnitxons SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 1.1/2.1 Fuel Cladding Integrity 1.2/2.2 Reactor Coolant System Integrity . 27 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS 3.1/4.1 Reactor Protection System 31 3.2/4.2 Protective Instrumentation . 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 . 52 F. Surveillance Instrumentation . 52 G. Control Room Isolation . 52 H. Flood'rotection . 53" Meteorological Monitoring Instrumentation 53 J. Seismic Monitoring Instrumentation . 54 K. Radioactive Gaseous Effluent Monitoring Instrumentation 54 3.3/4.3 Reactivity Control 120 A. Reactivity Limitations . 120 B. Control Rods . 121 C. Scram Insertion Times 124 Amendment No. 132 0241p

0 Section P~ae No.

D. Reactivity Anomalies 125 E. Reactivity Control 126 F. Scram Discharge Volume 126 3.4/4.4 Standby Liquid Control System 135 A. Normal System Availability . 135 B. Operation with Inoperable Components . 136 C. Sodium Pentaborate Solution 137 3.5/4.5 Core and Containment Cooling Systems 143 A. Core Spray System (CSS) 143 B. Residual Heat Removal System (RHRS)

(LPCI and Containment Cooling) 145 C. RHR Service Mater System and Emergency Equipment Cooling'Water System (EELS) 151 D. Equipment Area Coolers 154 E. High Pressure Coolant Injection System (HPCIS) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 154 F. Reactor Core Isolation Cooling System (RC ICS ) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ 156 G. Automatic Depressurization System

( ADS ) ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 157 H. Maintenance of Filled Discharge Pipe . 158 I. Average Planar Linear Heat Generation Rate . 159 J. Linear Heat Generation Rate (LHGR) 159 K. Minimum Critical Power Ratio (MCPR) 160 L. APRM Setpoints 160A M. Reporting Requirements . 160A 3.6/4.6 Primary System Boundary ~ ~ . 174 A. Thermal and Pressurization Limitations . 174 B. Coolant Chemistry 176 0 Amendment No. 132 0241p

Ct ~

~ %

0

Section ~Pa e No.

C. Coolant Leakage 180 D. Relief Valves 181 E. Jet Pumps 181 F. Recirculation Pump Operation . 182 G. Structural Integrity . 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 tern H~ Analyzer 249 3.8/4.8 Radioactive Materials 281 A. Liquid Effluents . 281 B. Airborne Effluents . 283 C. Radioactive Effluents Dose . 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 292 B. Operation with Inoperable Equipment 295 t 3.10/4.10 .

C.

Core A.

Amendment No. 132 0241p Operation in Cold Shutdown Alterations .

Refueling Interlocks .

. 298 302 302

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 . 308 3.11/4.11 Fire Protection Systems 315 A. High Pressure Fire Protection System . 315 B. CO> Fire Protection System . 319 C. Fire Detectors 320 D. Roving Fire Watch 321 E. Fire Protection Systems Inspection 322 F. Fire Protection Organization . 322 G. Air Masks and Cylinders 323 H. Continuous Fire Watch 323 I. Open 'Flames, Welding and Burning in the Cable Spreading Room 323 5.0 Major Design Features ~ a ~ ~ 330 5.1 Site Features 330 5.2 Reactor 330 I v~

5.3 Reactor Vessel ~ ~ ~ ~ ~ ~ ~ ~

a

~ ~ ~

a

~ 330 5.4 Containment 330 5.5 Fuel Storage . 330 5.6 Seismic Design . 331 6.0 Administrative Controls 332 6.1 Organization . 332 1v Amendment No. 132 024lp

0 Section ~Pa e No.

6.2 Review and Audit . 333 6.3 Procedures 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 Event a Safety Limit is Exceeded 346 6.6 Station Operating Records 346 6.7 Reporting Requirements 349 6.8 Minimum Plant Staffing 358 Amendment No. 132 024lp

P LIST OF TABLES Table Title ~Fa e No.

1.1 Surveillance Frequency Notation 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 Circui ts 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 t

3.2.D Radioactive Liquid Effluent Monitoring Instrumentation 76 3.2.E 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 Meteorological Monitoring Instrumentation 83 3.2eJ Seismic Monitoring Instrumentation . 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 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 v1 Amendment No. 132 0241p

~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 Minimum RHRSW and EECW Pump Assignment 152a 3.5.I MAPLHGR Versus Average Planar Exposure . 171, 172, 172a 3.7.A Primary Containment Isolation Valves 250 t

3.7.B Testable Penetrations with Double 0-Ring Seals . 256 3.7.C Testable Penetrations with Testable Bellows 257 3.7.D Air Tested Isolation Valves 258 3.7.E Primary Containment'. Isolation Valves which Terminate below the Suppression. Pool Mater Level 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 Fire Protection System Hydraulic Requirements 324 6.8.A Minimum Shift Crew Requirements 360 V11 Amendment No. i32 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 K< Factor 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 Operation of Nuclear Power Plant . 361 6.1-2 Functional Organizationi a ~

~ ~ ~

3

~ ~

N

~ 362

'I y a il 6.2-1 Review and Audit Function 363 6.3-1 In-Plant Fire Program Organization . 364 v111 Amendment No. 132 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

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\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.

7A 0242p Amendment No. 132

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.

7B O242p Amendment No. 1 32

Table 1.1 SURVEILLANCE FRE UENCY NOTATION NOTATION FRE UENCY S (Shift) At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D (Daily) At least once per normal calendar 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months day (midnight to midnight) ~

W (Weekly) At least once per 7 days.

M (Monthly) At least once per 31 days.

Q (Quarterly) At least once per 3 months or 92 days.

SA (Semi-Annual ly At least once per 6 months or 184 days.

Y (Yearly) At least once per year or 366 days.

(Refueling) At least once per operating cycle.

S/U (Start-Up) Prior to each reactor startup.

N.A. Not applicable.

P (Prior) Completed prior to each release.

7C 0242p Amendmeng No. 132

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.Q.B Core and Containment Coolin 4.2.B Core and Containment Coolin S stems . Initiation S Control 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 Instrumentation shall be

.operation for the instrumentation functionally tested, that initiates control rod block calibrated, and checked as are given in Table 3.2.C. 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 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation Monitorin Instrumentation

1. The radioactive liquid 1. Each of the radioactive effluent monitoring liquid effluent monitoring instrumentation listed in instruments shall be Table 3.2.D shall be demonstrated operable by operable with the performance of test in applicability as shown in accordance with Table 4.2.D.

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.

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

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.2.D Radioactive Li uid Effluent 4.2.D Radioactive Li uid Effluent (Con't) (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 Instrumentation shall be operation for the instrumentation calibrated and checked as that monitors drywell leak indicated in Table 4.2.E.

detection are given in Table 3.2.E.

F. Surveillance Instrumentation F. Surveillance Instrumentation The limiting conditions for the Instrumentation shall be instrumentation that provides calibrated and checked as surveillance information readouts indicated in Table 4.2.F.

are given in Table 3.2.F.

G. Control Room Isolation G. Control Room Isolation The limiting conditions'ori- ~ Instrumentation"shall be instrumentation that isolates calibrated and checked as the control room and initiates indicated in Table 4.2.G.

the control room emergency pressurization systems are given in Table 3.2.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 The seismic monitoring 1. Each of the seismic instruments listed in monitoring instruments Table 3.2.J shall be shall be demonstrated operable at all times. operable by performance of tests at the frequencies 2~ With the 'number of seismic listed in Table 4.2.J.

monitoring instruments less than the number listed in 2. Data shall be retrieved Table 3.2.J, restore the from all seismic inoperable instrument(s) to instruments actuated during operable status within a seismic event and 30 days. analyzed to determine the magnitude of the vibratory

3. With one or more of the ground motion. A Special instruments listed in Table Report shall be submitted 3.2.J inoperable for more to the Commission pursuant than 30 days, submit a to specification 6.7.3.D Special Report to the within 10 days describing Commission pursuant to the magnitude, frequency specification 6.7.3.C within spectrum, and resultant the next 10 days describing effect upon plant features the cause of the malfunction important to safety.

and plans for restoring the instruments to operable status.

3.2.K Radioactive Gaseous Effluent 4.2.K Radioactive Gaseous Effluent Monitorin Instrumentation Monitorin Instrumentation The radioactive gaseous 1. Each of the radioactive effluent monitoring gaseous effluent monitoring instruments listed in instruments shall be Table 3.2.K shall be demonstrated operable by operable with the performance of tests in applicability as shown in accordance with Table 4:.2.K.

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.

54 Amendment No. 132 0233p

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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.

54A Amendment No. 132 0233p

TABLE 3.2.D Radioactive Li uid Effluent Moni torin Instrumentation Instrument " Minimum Channels 0 erable A licabilit Act>on LIQUID RADHASTE EFFLUENT A, B 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 E FLOH RATE (77-60 loop excluding fixed in line rotometer)

Amendment No. 132 76 0240p

~

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 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 if spec 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 f f ef 1 uent rom that uni t ' service water shall be continuously monitored . If installed moni toring system is not available, a temporary monitor samples taken every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and an analysis of at least an LLD' pCi /ml (gross ) or < applicable MPC ratio (y isotopic ) shall be

'f used or grab 1 E-'7 to an monitor the ef f1 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , samples are pCi/ml (gross) collected or <

and analyzed applicable MPC for ratio radioactivity (y isotopic) with an LLD ' 'fgrab 1 E-7 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases .

Pump curves may be used to estimate f1 ow .

ACTION F Alarm/trip setpoints will be calculated in accordance with the guidance given in the Offsi 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 Minimum Channels/

Devices 0 erable PULI'lib 1 'ction STACK (RM-90-147A & B)

a. Noble Gas Monitor (1) A/C

b. Iodine Cartridge (1) 8/C

c. Particulate Filter (1) B/C

d. Sampler Flow Abnormal (1) D

e. Stack Flow (FT, FM, (1) D FI-90-271)

2. REACTOR/TURBINE BLDG VENTILATION (RM-90-250)

a. Noble Gas Monitor (1) A/C

b. Iodine Sampler (1) B/C

c. Particulate Sampler (1) . B/C

d. Sampler Flowmeter (1) D TURBINE BLDG EXHAUST (RM-90-249, 251)

a. Noble Gas Monitor (1) A/C

b. Iodine Sampler (1) B/C

c. Particulate Sampler (1) B/C

d. Sampler Flowmeter (1) D

4. RADHASTE BLDG VENT (RM-90-252)

a. Noble Gas Monitor (1) A/C

b. Iodine Sampler (1) B/C

c. Particulate Sampler (1) 8/C

d. Sampler Flowmeter (1) D

5. OFF GAS HYDROGEN ANALYZER (HzA, HzB)

6. OFF GAS POST TREATMENT

a. Noble Gas Activity Monitor (RM-90-265, 266)

b. Sample Flow Abnormal (PA-90-262)

Amendment No. 132 84A 0240p

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.

ACTION C A monitoring system may be out of service for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for functional testing, t

calibration, or repair without providing or initiating grab sampling.

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Purging during SI performance is not considered a loss of monitoring capability.

84B Amendment No. 132 0242p

TABLE 4.2.D Radioactive Li uid Effluent Monitorin Instrumentation Surveillance Re uirements Channel Functional Instrument Instrument Check Source Check Calibration Test

1. LIQUID RADHASTE EFFLUENT D(4) R(5) Q(1)

MONITOR (RM-90-130)

2. RHR SERVICE HATER MONITOR D(4) R(5) Q(2)

(RM-90-133, -134)

3. RAN COOLING HATER MONITOR D(4) R(5) Q(2)

(RM-90-132)

4. LIQUID RADHASTE EFFLUENT D(4) Q(3)

FLOH RATE (77-60 loop) 103 Amendment No. 132 0240p

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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).

103A Amendment No. 132 0242p

TABLE 4.2.K Radioactive Gaseous Effluent Instrumentation Surveillance Channel Functional Instrument Instrument Check Source Check Calibration Test

l. STACK

a. Noble Gas Monitor ' M R() ) Q(Z)

b. Iodine Cartridge NA NA NA

c. Particulate Filter NA NA NA d.. Sampler Flow Abnormal NA R Q

e. Stack Flowmeter NA R Q

2. REACTOR/TURBINE BLDG VENT

a. Noble Gas Monitor '"'.

M Rl ) Q(2)

Iodine Sampler NA- NA NA

c. Particulate Sampler NA NA NA

d. Sampler Flowmeter NA R Q

3. TURBINE BLDG EXHAUST

a. Noble Gas Monitor " '.

M Rt 1) Q(C)

Iodine Sampler NA NA NA

c. Particulate Sampler NA ~

NA NA

d. Sampler Flowmeter NA. R Q

4. RADWASTE BLDG VENT

a. Noble Gas Monitor " M R< 1) Q(2)

Iodine Sampler NA. NA NA

c. Particulate Sampler NA, NA NA

d. Sampler Flowmeter NA R 0

5. OFF GAS HYDROGEN ANALYZER (HrA, HzB) NA Rl J) Q(4)

6. OFF GAS POST TREATMENT .

Noble Gas Activity Monitor M R(1) Q(4)

b. Sample Flow Abnormal NA R Q(C) 108A p24pp Amendment No. 132

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).

108B Amendment No. 132 0242p

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.

115A Amendment No. 132 0242p

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.

118 Amendment No. 132 0242p

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6 Primar S stem Boundar 4.6 Primar S'stem Boundar

6. Whenever the reactor is 6 ~ Additional coolant samples critical, the limits on shall, be taken whenever the activity concentrations in the reactor activity exceeds one reactor coolant shall not percent of the equilibrium exceed the equilibrium value concentration specified in of 3.2 pc/gm of does 3.6.B.6 and one of the equivalent I-131. following conditions are met:

This limit may be exceeded a. During startup following power transients for b. Following a significant a maximum of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . During power change ~<

this activity transient the c. Following an increase in iodine concentrations shall the equilibrium off-gas not exceed 26 pCi/gm whenever level exceeding 10,000 the reactor is critical. The pCi/sec (at the steam reactor shall not be operated jet air ejector) within more than 5 percent of its a 48 hour period.

yearly power operation under d. Whenever the equilibrium this exception for the iodine limit specified equilibrium activity limits. in 3.6.B.6 is exceeded.

lf the iodine concentration in the coolant exceeds 26 pCi/gm, The additional coolant the reactor shall be shut down, liquid samples shall be and the steam line isolation taken at 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months intervals valves shall be closed for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or until a immediately. 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

179 Amendment Ho. 132 0233p

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials Applies to the release of Applies to the periodic test and radioactive liquids and gases record requirements and sampling from the facility. and monitoring methods used for facility effluents.

~Ob ective O~b'ective To define the limits and conditions for the release of To ensure that radioactive radioactive effluents to the liquid and gaseous releases from environs to assure that any the facility are maintained

.radioactive releases are as within the limits specified by low as reasonably achievable Specifications 3.8.A and 3.8.B.

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 A. Li uid Effluents definition 1.0.C (Limiting Condition for Operation). 1. Facility records shall be maintained of radioactive concentrations and A. Li uid Effluents volume before dilution of each batch of liquid

1. The concentration, of effluent released, and radioactive material of the average dilution released at any time from flow and length of time the site to unrestricted over which each areas (see Figure 4.8-1b) discharge occurred.

shall be limited to the concentrations specified 2. Radioactive liquid waste in 10 CFR Part 20, sampling and activity Appendix B, Table II,; analysis of each liquid Column 2 for radionuclides waste batch to be other than dissolved or discharged shall be entrained noble gases. performed prior to For dissolved or entrained release in accordance noble gases, the with the sampling and concentration shall be analysis program limited to 2E-4 pCi/ml specified in the REM.

total activity.

3. The operation of the

2. If the limits of 3.8.A.l automatic isolation are exceeded, appropriate valves and discharge action shall be initiated tank selection valves without delay to bring shall be checked the release within annually.

281 mendment go. 132 0233p

'ln LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.8 Radioactive Materials 4.8 Radioactive Materials limits. Provide prompt 4. The results of the notification to the NRC analysis of samples pursuant to section 6.7.2. collected from release points shall be used

3. The doses or dose with the calculational commitment to a member of methodology in the ODCM the public from radioactive to assure that the materials in liquid concentrations at the effluents released from point of release are each unit to unrestricted maintained within the areas (See Figure 4.8-1b) limits of specification shall be limited: 3.8.A.1.

a. During any calendar 5. Cummulative quarterly quarter to <1.5 mrem to and yearly dose the total body and <5 contributions from mrem to any organ and, liquid effluents shall be determined as

b. During any calendar specified in the ODCM at year to <3 mrem to the least once every 31 days.

total body and <10 mrem to any organ 6. The quantity of radioactive material 4 ~ If the limits specified in contained in any outside 3.8.A.3 a & b above are liquid radwaste storage exceeded, prepare and tanks shall be submit 'Special Report determined to be within pursuant to Section 6.7.2. the above limit by analyzing a

5. The maximum activity to be representative sample of contained in one liquid the tank's contents at radwaste tank or temporary least once per 7 days storage tank that can be when radioactive discharged directly to the materials are being environs shall not exceed added to the. tank.

10 curies excluding tritium and dissolved/entrained noble gas.

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , 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 Amendment No. 132 0233p

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 1. The gross 0/y and to areas at and beyond the particulate activity of site boundary (see Figure gaseous wastes released 4.8-1b) due to to the environment shall radioactivity released in be monitored and gaseous effluents from the recorded.

site shall be limited to the following values: a. For effluent streams having continuous

a. The dose rate limit monitoring for noble gases shall capability, the be <500 mrem/yr to the activity shall be total body and <3000 monitored and flow mrem/yr to the skin, rate evaluated and and recorded to enable release rates of

b. The dose rate limit gross radioactivity for I-131, I-133, H-3, to,be determined at and particulates with least once per shift greater than eight day using instruments half-lives shall be specified in table

<1500 mrem/yr to any 3.2.K.

organ.

b. For effluent streams

2. If the 'limits of 3.8.B.1 without continuous are exceeded, appropriate monitoring corrective action shall be capability, the immediately initiated to activity shall be bring the release within monitored and limits. Provide prompt recorded and the if not i cat ion to the NRC release through pursuant to section 6.7.2. 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 Amendment No. 132 0233p

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS

3. The air dose to areas at . " Cumul i at velar ter ly and and beyond the site yearly dose boundary (see Figure contributions from 4.8-1b) due to noble gases gaseous releases shall released in gaseous be determined using effluents per unit shall methods contained in the be limited to the ODCM at least once every following: 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 284 Amendment No. 132 0233p

0 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS

6. If the calculated doses 4. During operation above exceed the limits of 25K power, the position 3.8.B.5 above, prepare of the charcoal bed and submit a special bypass valve will be report pursuant to verified daily.

section 6.7.2.

7. During operation above 5. The concentration of 25K power the discharge hydrogen downstream of of the SJAE must be the recombiners shall be routed through the determined to be within charcoal adsorbers. the limits of 3.8.B.9 by continuously monitoring

8. With gaseous waste being the offgass whenever the discharged for more than SJAE is in service using 7 days without treatment instruments described in through the charcoal Table 3.2.K. Instrument adsorbers, prepare and surveillance submit a special report requirements are pursuant to section specified in Table 4.2.K.

6.7.2.

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 hours.

Amendment No. 132 285 0233p

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS 3.8.C Radioactive Effluents Dose 4.8.C Radioactive Effluents Dose The dose or dose 1. Cumulative dose commitment to a real contributions from individual from all liquid and gaseous uranium fuel cycle sources effluents shall be is limited to (25 mrem to determined in accordance the total body or any with specifications organ (except the thyroid, 3.8.A.3, 3.8.B.3, and which is limited to (75 3.8.B.5 and the methods mrem) over a period of one in the ODCM.

calendar year.

24 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 At least once during each shall be capable of being operating cycle verify automatic automatically isolated and securing and isolation of the secured on a signal or mechanical vacuum pump.

high radioactivity in the steam lines whenever the main steam isolation'alves are open.

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 E. Miscellaneous Radioactive .

Materials Sources Materials Sources

1. Source Leaka e Test 1. Surveillance Re uirement Each sealed source Tests for leakage and/or containing radioactive contamination shall be material either in excess performed by the of 100 microcuries of beta licensee or by other and/or gamma emitting persons specifically material or 5 microcuries authorized by the of alpha emitting material Commi ss ion or an shall be free of ) 0.005 agreement State, as microcurie of removable follows:

contamination. Each sealed souce with removable a. Sources in Use contamination in excess of the above limit shall be Each sealed source, immediately withdrawn from excluding startup use and (a) either sources and flux decontaminated and detectors previously repaired, or (b) disposed subjected to core of in accordance with flux, containing Commission regulations. 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 Amendment No. 132 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.

288 Amendment No. 132 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 1. The Process Control shall be operated in Program shall include accordance with a process surveillance checks control program, for the necessary to demonstrate solidification and compliance with 3.8.F.l.

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.

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.

289 Amendment No. 132 0233p

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Switchyard Turbine Building Exhaust Fan (32m)-

Turbine Building Office Building Service Bldg.

Iladt.

Bldg.

Reactor Building Reactor Building Ventilation (40m)

Stack (180m)

Figure 4.8-1a GASEOUS REI.EASE POINTS AND ELEVATIONS 290-Amendment No. 132

Figure 4.8-1b LAND SITE BOUNDARY

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l nile 2 illlee 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 291 Amendment No. 132 0242p

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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 29 1A 02g2p Amendment No. 132

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.

291B Amendment No. 132 0242p

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AIRBORNE EFFLUENTS Specification 3.8.B.7 requires that the offgas charcoal adsorber beds be used e 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 291C 0242p Amendment No. 132

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4.8.A and 4.8.B BASES (cont'd) gaseous effluents. These surveillance requrr e'~men s pihvide the data ~r licensee and the Commission to evaluate the station's performance relative to the

~

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 Amendment No. 132 0242p

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