Text

Proposed Tech Specs Reflecting non-intent Editorial Changes Including Latest 10CFR20 Refs
	ML20084F260
Person / Time
Site:	Beaver Valley
Issue date:	05/23/1995
From:	; DUQUESNE LIGHT CO.
To:	;
Shared Package
ML20084F223	List: ML20084F220; ML20084F260;
References
	NUDOCS 9506020125
	Download: ML20084F260 (100)
	v • d • e

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ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A, Technical Specifications, '

with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove: Insert: Remove: Insert:

I thru XXVI I thru XXI 3/4 11-20 -

1-6 1-6 3/4 11-21 -

1-7 1-7 3/4 11-22 -

3/4 3-53 3/4 3-53 3/4 11-23 -

3/4 3-54 3/4 3-54 3/4 12-1 3/4 12-1 3/4 3-55 3/4 3-55 3/4 12-2 -

3/4 3-56 3/4 3-56 3/4 12-3 -

3/4 3-57 3/4 3-57 3/4 12-4 -

3/4 3-57a 3/4 3-58 3/4 12-5 -

3/4 3-58 -

3/4 12-6 -

3/4 3-58a -

3/4 12-7 -

3/4 3-59 -

3/4 12-8 -

3/4 3-60 -

3/4 12-9 -

3/4 3-61 -

3/4 12-10 -

3/4 3-62 -

3/4 12-11 -

3/4 3-63 -

3/4 12-12 -

3/4 3-64 -

B 3/4 3-4 B 3/4 3-4 3/4 3-65 -

B 3/4 11-1 B 3/4 11-1 3/4 3-66 -

B 3/4 11-2 -

3/4 3-67 -

B 3/4 11-3 -

3/4 3-63 -

B 3/4 11-4 -

3/4 11-1 3/4 11-1 B 3/4 11-5 -

3/4 11-2 3/4 11-2 B 3/4 11-6 -

3/4 11-3 3/4 11-3 B 3/4 12-1 -

3/4 11-4 3/4 11-4 6-13a 6-14 3/4 11-5 3/4 11-5 6-14 6-15 3/4 11-Sa 3/4 11-6 6-15 6-16 3/4 11-6 -

6-20 6-17 3/4 11-7 -

6-21 6-18 3/4 11-8 -

6-22 6-19 3/4 11-10 -

6-22a 6-20 3/4 11-11 -

6-23 6-21 3/4 11-12 -

6-24 6-22 3/4 11-13 -

6-25 6-23 3/4 11-14 -

6-27 6-24 3/4 11-15 -

6-28 6-25 3/4 11-16 -

6-29 -

3/4 11-18 -

6-30 -

2 6-31 -

9506020125 950523 PDR ADOCK 05000334 p PDR

I 1-1 s e e, .*oo DPR-66 INDEX 1

DEFINITIONS SECTION PAGE 1.0 DEFINITIONS Defined Terms . . . . . . . . . . . . . . . . . . . 1-1 Thermal Power . . . . . . . . . . . . . . . . . . . 1-1 Rated Thermal Power . . . . . . . . . . . . . . . . 1-1 Operational Mode . . . . . . . . . . . . . . . . . 1-1 Action . . . . . . . . . . . . . . . . . . . . . . 1-1 Operable - Operability . . . . . . . . . . . . . . 1-1 Reportable Event . . . . . . . . . . . . . . . . . 1-2 Containment Integrity . . . . . . . . . . . . . . . 1-2 Channel Calibration . . . . . . . . . . . . . . . . 1-2 Channel Check . . . . . . . . . . . . . . . . . . . 1-2 Channel Functional Test . . . . . . . . . . . . . . 1-3 Core Alteration . . . . . . . . . . . . . . . . . . 1-3 Shutdown Margin . . . . . . . . . . . . . . . . . . 1-3 Leakage . . . . . . . . . . . . . . . . . . . . . . 1-3 Quadrant Power Tilt Ratio . . . . . . . . . . . . . 1-4 Dose Equivalent I-131 . . . . . . . . . . . . . . . 1-4 Staggered Test Basis . . . . . . . . . . . . . . . 1-4 Frequency Notation . . . . . . . . . . . . . . . . 1-4 Reactor Trip System Response Time . . . . . . . . . 1-5 Engineered Safety Feature Response Time . . . . . . 1-5 Axial Flux Difference . . . . . . . . . . . . . . . 1-5 Physics Tests . . . . . . . . . . . . . . . . . . . 1-5 E-Average Disintegration Energy . . . . . . . . . . 1-5 BEAVER VALLEY - UNIT 1 I Amendment No.

DPR-66 INDEX i

DEFINITIONS SECTION PAGE -

Source Check. . . . . . . . . . . . . . . . . . . . 1-6 Process Control Program . . . . . . . . . . . . . . 1-6 Offsite Dose Calculation Manual (ODCM). . . . . . . 1-6 Gaseous Radwaste Treatment System . . . . . . . . . 1-6 Ventilation Exhaust Treatment System . . . . . . . 1-6 Purge - Purging . . . . . . . . . . . . . . . . . . 1-7 Venting . . . . . . . . . . . . . . . . . . . . . . 1-7 Major Changes . . . . . . . . . . . . . . . . . . . 1-7 Member (s) of the Public . . . . . . . . . . . . . . 1-8 1 Core Operating Limits Report. . . . . . . . . . . . 1-8 l Operational Modes (Table 1.1) . . . . . . . . . . . 1-9 Frequency Notation (Table 1.2). . . . . . . . . . . 1-10 l l

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS i i

SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 Reactor Core . . . . . . . . . . . . . . . . . . 2-1 2.1.2 Reactor Coolant System Pressure. . . . . . . . . 2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 Reactor Trip System Instrumentation Setpoints. . 2-5 l

BASES l l

SECTION PAGE l l

2.1 SAFETY LIMITS 2.1.1 Reactor Core . . . . . . . . . . . . . . . . . . B 2-1 2.1.2 Reactor Coolant System Pressure. . . . . . . . . B 2-2 BEAVER VALLEY - UNIT 1 II Amendment No.

DPR-66 INDEX BASES SECTION PAGE 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 Reactor Trip Setpoints . . . . . . . . . . . . . B 2-3 l

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS )

SECTION PAGE 3/4.0 APPLICABILITY. . . . . . . . . . . . . . . . . . 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL 3/4.1.1.1 Shutdown Margin - Tavg > 200*F. . . . 3/4 1-1 1 3/4.1.1.2 Shutdown Margin - T avg i 200*F. . . . 3/4 1-3 3/4.1.1.3 Boron Dilution. . . . . . . . . . . . . 3/4 1-4 3/4.1.1.4 Moderator Temperature Coefficient . . . 3/4 1-5 3/4.1.1.5 Minimum Temperature for Criticality . .

3/4 1-6 3/4.1.2 BORATION SYSTEMS 3/4.1.2.1 Flow Paths - Shutdown . . . . . . . . . 3/4 1-7 3/4.1.2.2 Flow Paths - Operating. . . . . . . . . 3/4 1-9 3/4.1.2.3 Charging Pump - Shutdown. . . . . . . . 3/4 1-11 3/4.1.2.4 Charging Pumps - Operating. . . . . . . 3/4 1-12 3/4.1.2.5 Boric .nid Transfer Pumps - Shutdown. . 3/4 1-13 3/4.1.2.6 Boric Acid Transfer Pumps - Operating . 3/4 1-14 3/4.1.2.7 Borated Water Sources - Shutdown. . . . 3/4 1-15 3/4.1.2.8 Borated Water Sources - Operating . . . 3/4 1-16 3/4.1.3 MOVABLE CONTROL ASSEMBLIES 3/4.1.3.1 Group Height. . . . . . . . . . . . . . 3/4 1-18 3/4.1.3.2 Position Indication Systems - Operating 3/4 1-20 BEAVER VALLEY - UNIT 1 III Amendment No.

. . s, . .**m ,

DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTIQH PAGE 3/4.1.3.3 Position Indication System - Shutdown . . 3/4 1-21 3/4.1.3.4 Rod Drop Time . . . . . . . . . . . . . . 3/4 1-22 3/4.1.3.5 Shutdown Rod Insertion Limit. . . . . . . 3/4 1-23 3/4.1.3.6 Control Rod Insertion Limits. . . . . . . 3/4 1-23a l 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE . . . . . . . . . . 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR. . . . . . . 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR . . . 3/4 2-8 3/4.2.4 QUADRANT POWER TILT RATIO . . . . . . . . 3/4 2-10 3/4.2.5 DNB PARAMETERS. . . . . . . . . . . . . . 3/4 2-12 3/4,3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION . . . 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION . . . . . . . . . . . . . 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring. . . . . . . . . . . 3/4 3-33 3/4.3.3.2 Movable Incore Detectors. . . . . . . . . 3/4 3-37 3/4.3.3.3 Seismic Instrumentation . . . . . . . . . 3/4 3-38 3/4.3.3.4 Meteorological Instrumentation. . . . . . 3/4 3-41 3/4.3.3.5 Remote Shutdown Instrumentation . . . . . 3/4 3-44 1

3/4.3.3.7 Chlorine Detection System . . . . . . . . 3/4 3-49 3/4.3.3.8 Accident Monitoring Instrumentation . . . 3/4 3-50 3/4.3.3.11 Explosive Gas Monitoring Instrumentation. 3/4 3-54 BEAVER VALLEY - UNIT 1 IV Amendment No.

DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS 3/4.4.1.1 Normal Operation. . . . . . . . . . . . . 3/4 4-1 3/4.4.1.2 Hot Standby . . . . . . . . . . . . . . . 3/4 4-2b 3/4.4.1.3 Shutdown. . . . . . . . . . . . . . . . . 3/4 4-2c 3/4.4.1.4 Isolated Loop . . . . . . . . . . . . . . 3/4 4-3 3/4.4.1.5 Isolated Loop Startup . . . . . . . . . . 3/4 4-4 3/4.4.1.6 Reactor Coolant Pump Startup. . . . . . . 3/4 4-4a 3/4.4.2 SAFETY VALVES - SHUTDOWN. . . . . . . . . 3/4 4-5 3/4.4.3 SAFETY VALVES - OPERATING . . . . . . . . 3/4 4-6 3/4.4.4 PRESSURIZER . . . . . . . . . . . . . . . 3/4 4-7 3/4.4.5 STEAM GENERATORS. . . . . . . . . . . . . 3/4 4-8 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 Leakage Detection Instrumentation . . . . 3/4 4-11 3/4.4.6.2 Operational Leakage . . . . . . . . . . . 3/4 4-13 3/4.4.6.3 Pressure Isolation Valves . . . . . . . . 3/4 4-14a 3/4.4.7 CHEMISTRY . . . . . . . . . . . . . . . . 3/4 4-15 3/4.4.8 SPECIFIC ACTIVITY . . . . . . . . . . . . 3/4 4-18 3/4.4.9 PRESSURE / TEMPERATURE LIMITS 3/4.4.9.1 Reactor Coolant System . . . . . . . . . 3/4 4-22 3/4.4.9.2 Pressurizer . . . . . . . . . . . . . . . 3/4 4-27 3/4.4.9.3 Overpressure Protection Systems . . . . . 3/4 4-27a 3/4.4.10 STRUCTURAL INTEGRITY - ASME Code Class 1, 2 and 3 Components . . . . . . . . . . 3/4 4-28 3/4.4.11 RELIEF VALVES . . . . . . . . . . . . . . 3/4 4-29 3/4.4.12 REACTOR COOLANT SYSTEM VENTS. . . . . . . 3/4 4-32 BEAVER VALLEY - UNIT 1 V Amendment No.

C e DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION EAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS. . . . . . . . . . . . . . . 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - Tavg 2 350*F. . . . . 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - Tavg < 350'F. . . . . 3/4 5-6 3/4.5.4 BORON INJECTION SYSTEM 3/4.5.4.1.1 Boron Injection Tank 2 350*F. . . . . . . 3/4 5-7 3/4.5.4.1.2 Boron Injection Tank < 350*F. . . . . . . 3/4 5-7a 3/4.5.5 SEAL INJECTION FLOW . . . . . . . . . . . 3/4 5-8 3/4.6 CONTAINMENT SYSTEME !

l 3/4.6.1 PRIMARY CONTAINMENT l 3/4.6.1.1 Containment Integrity . . . . . . . . . . 3/4 6-1 l

3/4.6.1.2 Containment Leakage . . . . . . . . . . . 3/4 6-2 l 3/4.6.1.3 Containment Air Locks . . . . . . . . . . 3/4 6-5 l l

3/4.6.1.4 Internal Pressure . . . . . . . . . . . . 3/4 6-6 3/4.6.1.5 Air Temperature . . . . . . . . . . . . . 3/4 6-8 l l

3/4.6.1.6 Containment Structural Integrity. . . . . 3/4 6-10 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS l 3/4.6.2.1 Containment Quench Spray System . . . . . 3/4 6-11 l 3/4.6.2.2 Cont lim' cit Recirculation Spray System. . 3/4 6-13 )

3/4.6.2.3 Chemicit j .v.% it ion System. . . . . . . . . 3/4 6-15 3/4.6.3 CONTAINMENT ISOLATION VALVES. . . . . . . 3/4 6-17 3/4.6.4 COMBUSTIBLE GAS CONTROL 3/4.6.4.1 Hydrogen Analyzers. . . . . . . . . . . . 3/4 6-20 3/4.6.4.2 Electric Hydrogen Recombiners . . . . . . 3/4 6-21 BEAVER VALLEY - UNIT 1 VI Amendment No.

i 1

.e<

DPR-66 l INDEX l i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 Safety Valves . . . . . . . . . . . . . . 3/4 7-1 3/4.7.1.2 Auxiliary Feedwater System. . . . . . . . 3/4 7-5 l 3/4.7.1.3 Primary Plant Demineralized Water (PPDW). 3/4 7-7 3/4.7.1.4 Activity. . . . . . . . . . . . . . . . . 3/4 7-8 1

l 3/4.7.1.5 Main Steam Line Isolation Valves. . . . . 3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION. . . . . . . . . . . . . . . . 3/4 7-11 3/4.7.3 COMPONENT COOLING WATER SYSTEM. . . . . . 3/4 7-12 3/4.7.4 REACTOR PLANT RIVER WATER SYSTEM. . . . . 3/4 7-13 3/4.7.5 ULTIMATE HEAT SINK - OHIO RIVER . . . . . 3/4 7-14 3/4.7.6 FLOOD PROTECTION. . . . . . . . . . . . . 3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS . . . . . . . . . . . . . . . . . 3/4 7-16 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM. . . . . . . . . . . . . . 3/4 7-19 1

3/4.7.9 SEALED SOURCE CONTAMINATION . . . . . . . 3/4 7-22 3/4.7.12 SNUBBERS. . . . . . . . . . . . . . . . . 3/4 7-26 l

3/4.7.13 AUXILIARY RIVER WATER SYSTEM. . . . . . . 3/4 7-34 l !

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 3/4.8.1.1 Operating . . . . . . . . . . . . . . . . 3/4 8-1 3/4.8.1.2 Shutdown. . . . . . . . . . . . . . . . . 3/4 8-5 BEAVER VALLEY - UNIT 1 VII Amendment No.

. o s, e

) l DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION EAGI 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS ,

3/4.8.2.1 A.C. Distribution - Operating . . . . . . 3/4 8-6 3/4.8.2.2 A.C. Distribution - Shutdown. . . . . . . 3/4 8-7 3/4.8.2.3 D.C. Distribution - Operating . . . . . . 3/4 8-8 3/4.8.2.4 D.C. Distribution - Shutdown. . . . . . . 3/4 8-10 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION . . . . . . . . . . . ,3 /4 9-1 3/4.9.2 INSTRUMENTATION . . . . . . . . . . . . . 3/4 9-2 3/4.9.3 DECAY TIME. . . . . . . . . . . . . . . . 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS . . . . 3/4 9-4 3/4.9.5 COMMUNICATIONS. . . . . . . . . . . . . . 3/4 9-5 ,

3/4.9.6 MANIPULATOR CRANE OPERABILITY . . . . . . 3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING. . . . . . . . . . . . . . . . . 3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION 3/4.9.8.1 High Water Level . . . . . . . . . . . . 3/4 9-8 3/4.9.8.2 Low Water Level . . . . . . . . . . . . . 3/4 9-8a i

3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM. . . . . . . . . . . . . . . . . . 3/4 9-9 3/4.9.10 WATER LEVEL-REACTOR VESSEL. . . . . . . . 3/4 9-10 1

3/4.9.11 STORAGE POOL WATER LEVEL. . . . . . . . . 3/4 9-11 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM - FUEL MOVEMENT. . . . . . . . . . . . . . . . . 3/4 9-12 3/4.9.13 FUEL BUILDING VENTILATION SYSTEM - FUEL STORAGE . . . . . . . . . . . . . . . . . 3/4 9-13 3/4.9.14 FUEL STORAGE - SPENT FUEL STORAGE POOL. .

3/4 9-14 BEAVER VALLEY - UNIT 1 VIII Amendment No.

DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS EECTION PAGE 3/4.9.15 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS . . . . . . . . . . . . . . . . . 3/4 9-16 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . . . . . . . . . . . . . 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS . . . . . . . . . . . 3/4 10-2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION -

REACTOR CRITICALITY . . . . . . . . . . . 3/4 10-4 3/4.10.4 PHYSICS TEST. . . . . . . . . . . . . . . 3/4 10-6 3/4.10.5 NO FLOW TESTS . . . . . . . . . . . . . . 3/4 10-7 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.4 Liquid Holdup Tanks . . . . . . . . . . . 3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.5 Gas Storage Tanks . . . . . . . . . . . . 3/4 11-4 3/4.11.2.6 Explosive Gas Mixture . . . . . . . . . . 3/4 11-5 BASES SECTION PAGE l l

3/4.0 APPLICABILITY. . . . . . . . . . . . . . . . . . B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL. . . . . . . . . . . . . B 3/4 1-1 3/4.1.2 BORATION SYSTEMS. . . . . . . . . . . . . B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES . . . . . . . B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE . . . . . . . . . . B 3/4 2-1 l BEAVER VALLEY - UNIT 1 IX Amendment No.

l . . . ..s.

I DPR-66 INDEX ,

1 BASES SECTION PAGE l

l 3/4.2.2 AND 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACTORS . . . . . B 3/4 2-4 l 3/4.2.4 QUADRANT POWER TILT RATIO . . . . . . . . B 3/4 2-5 l 3/4.2.5 DNB PARAMETERS . . . . . . . . . . . . . B 3/4 2-6 l 3/4.3 INSTRUMENTATION i l 3/4.3.1 AND 3/4.3.2 PROTECTIVE AND ENGINEERED l SAFETY FEATURES (ESP) INSTRUMENTATION . B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION . . . . . . . B 3/4 3-2 1

3/4.3.3.1 Radiation Monitoring Instrumentation . . B 3/4 3-2 1 l

3/4.3.3.2 Moveable Incore Detectors . . . . . . . . B 3/4 3-2 3/4.3.3.3 Seismic Instrumentation . . . . . . . . . B 3/4 3-2 3/4.3.3.4 Meteorological Instrumentation . . . . . B 3/4 3-2 3/4.3.3.5 Remote Shutdown Instrumentation . . . . . B 3/4 3-3 i l

3/4.3.3.7 Chlorine Detection Systems . . . . . . . B 3/4 3-3 3/4.3.3.8 Accident Monitoring Instrumentation . . . B 3/4 3-3 l 3/4.3.3.11 Explosive Gas Monitoring Instrumentation. B 3/4 3-4 l

l l

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOCPS . . . . . . . . . . B 3/4 4-1 1 3/4.4.2 AND 3/4.4.3 SAFETY VALVES. . . . . . . . . . . B 3/4 4-la 1 3/4.4.4 PRESSURIZER , . . . . . . . . . . . . . . B 3/4 4-2 l

3/4.4.5 STEAM GENERATORS . . . . . . . . . . . . B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE. . . . . . B 3/4 4-3 3/4.4.6.1 Leakage Detection Instrumentation . . . . B 3/4 4-3 3/4.4.6.2 Operational Leakage . . . . . . . . . . . B 3/4 4-3d 3/4.4.6.3 Pressure Isolation Valve Leakage. . . . . B 3/4 4-3j l 3/4.4.7 CHEMISTRY . . . . . . . . . . . . . . . . B 3/4 4-4 BEAVER VALLEY - UNIT 1 X Amendment No.

DPR-66 INDEX BASES SECTION PAGE 3/4.4.8 SPECIFIC ACTIVITY . . . . . . . . . . . . B 3/4 4-4 1

3/4.4.9 PRESSURE / TEMPERATURE LIMITS . . . . . . . B 3/4 4-5 3/4.4.10 STRUCTURAL INTEGRITY. . . . . . . . . . . B 3/4 4-11 3/4.4.11 RELIEF VALVES . . . . . . . . . . . . . . B 3/4 4-11 3/4.4.12 REACTOR COOLANT SYSTEM VENTS . . . . . . B 3/4 4-11 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5 3/4.5.1 ACCUMULATORS . . . . . . . . . . . . . . B 3/4 5-1

~"

3/4.5.2 AND 3/4.5.3 ECCS SUBSYSTEMS . . . . . . . . . B 3/4 5-1 3/4.5.4 BORON INJECTION SYSTEM . . . . . . . . . B 3/4 5-2 3/4.5.5 SEAL INJECTION FLOW . . . . . . . . . . . B 3/4 5-3 2]4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 Containment Integrity . . . . . . . . . . B 3/4 6-1 3/4.6.1.2 Containment Leakage . . . . . . . . . . . B 3/4 6-1 3/4.6.1.3 Containment Air Locks . . . . . . . . . . B 3/4 6-1 3/4.6.1.4 AND 3/4.6.1.5 Internal Pressure and Air Temperature . . . . . . . . . . . . . . B 3/4 6-2 3/4.6.1.6 Containment Structural Integrity . . . . B 3/4 6-2 ,

1 3/4.6.2

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DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 AND 3/4.6.2.2 Containment Quench and Recirculation Spray Systems . . . . . . B 3/4 6-2 3/4.6.2.3 Chemical Addition System . . . . . . . . B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES . . . . . . B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTROL . . . . . . . . . B 3/4 6-3 BEAVER VALLEY - UNIT 1 XI Amendment No.

DPR-66 INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves . l 3/4.7.1.1 . . . . . . . . . . . . . B 3/4 7-1 3/4.7.1.2 Auxiliary Feedwater Pumps . . . . . . . . B 3/4 7-2 l

3/4.7.1.3 Primary Plant Demineralized Water . . . . B 3/4 7-2 3/4.7.1.4 Activity . . . . . . . . . . . . . . . . B 3/4 7-3 i i

3/4.7.1.5 Main' Steam Line Isolation Valves . . . . B 3/4 7-3 '

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION . . . . . . . . . . . . . . . B 3/4 7-4

3/4.7.3 COMPONENT COOLING WATER SYSTEM . . . . . B 3/4 7-4 l 1

\

3/4.7.4 RIVER WATER SYSTEM . . . . . . . . . . . B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK . . . . . . . . . . . B 3/4 7-4 3/4.7.6 FLOOD PROTECTION . . . . . . . . . . . . B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEM . . . . . . . . . . . . . . . . . B 3/4 7-5 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM . . . . . . . . . . . . . B 3/4 7-5 3/4.7.9 SEALED SOURCE CONTAMINATION . . . . . . . B 3/4 7-5 3/4.7.12 SNUBBERS . . . . . . . . . . . . . . . . B 3/4 7-6 3/4.7.13 AUXILIARY RIVER WATER SYSTEM . . . . . . B 3/4 7-7 l

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 AND 3/4.8.2 A.C. SOURCES, D.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS . . . . B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION . . . . . . . . . . . B 3/4 9-1 3/4.9.2 INSTRUMENTATION . . . . . . . . . . . . . B 3/4 9-1 BEAVER VALLEY - UNIT 1 XII Amendment No. i l

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. . I DPR-66 I INDEX BASES SECTION PAGE 3/4.9.3 DECAY TIME . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS . . . . B 3/4 9-1 3/4.9.5 COMMUNICATIONS . . . . . . . . . . . . . B 3/4 9-2 3/4.9.6 MANIPULATOR CRANE OPERABILITY . . . . . . B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXRAUST ISOLATION SYSTEM . . . . . . . . . . . . . . . . . B 3/4 9-3 l 3/4.9.10 AND 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL . . . . . . . . . . . . . B 3/4 9-3 3/4.9.12 AND 3/4.9.13 FUEL BUILDING VENTILATION SYSTEM B 3/4 9-3 3/4.9.14 FUEL STORAGE - SPENT FUEL STORAGE POOL .

B 3/4 9-4 3/4.9.15 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS . . . . . . . . . . . . . . . . . B 3/4 9-5 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . . . . . . . . . . . . . B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS . . . . . . . . . . . B 3/4 10-1 ,

3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS-REACTOR CRITICALITY . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.4 PHYSICS TESTS . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.5 NO FLOW TESTS . . . . . . . . . . . . . . B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.4 Liquid Holdup Tanks . . . . . . . . . . . B 3/4 11-1 BEAVER VALLEY - UNIT 1 XIII Amendment No. 1 l

DPR-66 )

INDEX BASES SECTION PAGE 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.5 Gas Storage Tanks . . . . .. . . . . . . B 3/4 11-1 3/4.11.2.6 Explosive Gas Mixture . . . . . . . . . . B 3/4 11-1 )

DESIGN FEATURES SECTION PAGE 5.1 SITE l

l 5.1.1 Site Boundary for Gaseous Effluents . . . 5-1 l 5.1.2 Site Boundary for Liquid Effluents . . . 5-1 l

l 5.1.3 Exclusion Area. . . . . . . . . . . . . . 5-1 5.1.4 Low Population Zone . . . . . . . . . . . 5-1 l 5.1.5 Flood Control . . . . . . . . . . . . . . 5-1 1

1 5.2 CONTAINMENT 5.2.1 Configuration . . . . . . . . . . . . . . 5-1 5.2.2 Design Pressure and Temperature . . . . . 5-4 5.2.3 Penetrations. . . . . . . . . . . . . . . 5-4 5.3 REACTOR CORE 5.3.1 Fuel Assemblies . . . . . . . . . . . . . 5-4 5.3.2 Control Rod Assemblies. . . . . . . . . . 5-4 5.4 REACTOR COOLANT SYSTEM 5.4.1 Design Pressure and Temperature . . . . . 5-5 5.4.2 Volume. . . . . . . . . . . . . . . . . . 5-5 BEAVER VALLEY - UNIT 1 XIV Amendment No.

r i -

DPR-66 INDEX ,

DESIGN FEATURES SECTION PAGE 5.5 EMERGENCY CORE COOLING' SYSTEMS . . . . . . . . . . 5-5 5.6 FUEL STORAGE 5.6.1 Criticality . . . . . . . . . . . . . . . 5-5 5.6.2 Drainage. . . . . . . . . . . . . . . . . 5-5 5.6.3 Capacity. . . . . . . . . . . . . . . . . .5-6 5.7 SEISMIC CLASSIFICATION . . . . . . . . . . . . . . 5-6 5.8 METEOROLOGICAL TOWER LOCATION. . . . . . . . . . . 5-6 ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY . . . . . . . . . . . . . . . . . . 6-1 ORGANIZATION 6.2 6.2.1 Onsite and Offsite Organizations. . . . . 6-1 6.2.2 Unit Staff. . . . . . . . . . . . . . . . 6-2 6.3 FACILITY STAFF QUALIFICATIONS. . . . . . . . . . . 6-5 6.4 TRAINING . . . . . . . . . . . . . . . . . . . . . 6-5 6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC) 6.5.1.1 Function. . . . . . . . . . . . . . . . . 6-5 6.5.1.2 Composition . . . . . . . . . . . . . . . 6-5 l

l 6.5.1.3 Alternates. . . . . . . . . . . . . . . . 6-6 6.5.1.4 Meeting Frequency . . . . . . . . . . . . 6-6 l

BEAVER VALLEY - UNIT 1 XV Amendment No.

o. .

I DPR-66 l INDEX j ADMINISTRATIVE CONTROLS !

SECTION PAGE

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l 6.5.1.5 Quorum. . . . . . . . . . . . . . . . . . 6-6 l l

6.5.1.6 Responsibilities. . . . . . . . . . . . . 6-6 6.5.1.7 Authority . . . . . . . . . . . . . . . . 6-7 l 6.5.1.8 Records . . . . . . . . . . . . . . . . . 6-7 6.5.2 OFFSITE REVIEW COMMITTEE (ORC) 6.5.2.1 Function. . . . . . . . . . . . . . . . . 6-7 )

6.5.2.2 Composition . . . . . . . . . . . . . . . 6-8 6.5.2.3 Alternates. . . . . . . . . . . . . . . . 6-8 6.5.2.4 Consultants . . . . . . . . . . . . . . . 6-8 6.5.2.5 Meeting Frequency . . . . . . . . . . . . 6-9 6.5.2.6 Quorum. . . . . . . . . . . . . . . . . . 6-9 6.5.2.7 Review. . . . . . . . . . . . . . . . . . 6-9 6.5.2.8 Audits. . . . . . . . . . . . . . . . . . 6-10 6.5.2.9 Authority . . . . . . . . . . . . . . . . 6-11 6.5.2.10 Records . . . . . . . . . . . . . . . . . 6-11 l

6.6 REPORTABLE EVENT ACTION. . . . . . . . . . . . . . 6-11 l 6.7 SAFETY LIMIT VIOLATION . . . . . . . . . . . . . . 6-11 l l

l 6.8 PROCEDURES . . . . . . . . . . . . . . . . . . . . 6-12 1

6.9 REPORTING REQUIREMENTS . . . . . . . . . . . . . . 6-16 6.9.1 Routine Reports . . . . . . . . . . . . . 6-16 l 6.9.1.1,2,3 Startup Reports . . . .. . . . . . . . . . 6-16 6.9.1.4,5 Annual Reports. . . . . . . . . . . . . . 6-17 6.9,1.6 Monthly Operating Report. . . . . . . . . 6-18 BEAVER VALLEY - UNIT 1 XVI Amendment No.

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'DPR-66 INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.9.1.10 Annual Radiological Environmental Operating Report. . . . . . . . . . . . . . . . . . 6-18 6.9.1.11 Annual Radioactive Effluent Release Report. . . . . . . . . . . . . . . . . . 6-19 6.9.1.12 Core Operating Limits Report. . . . . . . 6-19 6.9.2 SPECIAL REPORTS . . . . . . . . . . . . . 6-20 6.10 RECORD RETENTION. . . . . . . . . . . . . . . . . 6-21 5 11 RADIATION PROTECTION PROGRAM. . . . . . . . . . . 6-22 6.12 HIGH RADIATION AREA . . . . . . . . . . . . . . . 6-23 6.13 PROCESS CONTROL PROGRAM (PCP) . . . . . . . . . . 6-24 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM). . . . . . 6-24 6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS . . . . . . . . . . . . . . . . 6-25 i

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BEAVER VALLEY - UNIT 1 XVII Amendment No.

'"7 DPR-66 TABLE INDEX TABLE TITLE PAGE !

l 2.2-1 Reactor Trip System Instrumentation Trip 2-6 Setpoints 3.1-1 Accident Analyses Requiring Reevaluation 3/4 1-19a l in the event of an Inoperable Full or Part Length Rod 3.2-1 DNB Parameters 3/4 2-13 3.3-1 Reactor Trip System Instrumentation 3/4 3-2 3.3-2 Reactor Trip System Instrumentation 3/4 3-9 Response Times 4.3-1 Reactor Trip System Instrumentation 3/4 3-11 Surveillance Requirements 3.3-3 Engineered Safety Features Actuation System 3/4 3-15 Instrumentation 3.3-4 Engineered Safety Features Actuation System 3/4 3-22 Instrumentation Trip Setpoints 3.3-5 Engineered Safety Feature Response Times 3/4 3-25 4.3-2 Engineered Safety Feature Actuation System 3/4 3-29 Instrumentation Surveillance Requirements 3.3-6 Radiation Monitoring Instrumentation 3/4 3-34 4.3-3 Radiation Monitoring Instrumentation 3/4 3-36 Surveillance Requirements 3.3-7 Seismic Monitoring Instrumentation 3/4 3-39 4.3-4 Seismic Monitoring Instrumentation 3/4 3-40 surveillance Requirements 3.3-8 Meteorological Monitoring Instrumentation 3/4 3-42 4.3-5 Meteorological Monitoring Instrumentation 3/4 3-43 Surveillance Requirements 3.3-9 Remote Shutdown Panel Monitoring 3/4 3-45 Instrumentation 4.3-6 Remote Shutdown Monitoring Instrumentation 3/4 3-46 Surveillance Requirements I

BEAVER VALLEY - UNIT 1 XVIII Amendment No.

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DPR-66 i Table Index (cont.) l TABLE TITLE PAGE ;

3,3-11 Accident Monitoring Instrumentation 3/4 3-51 4.3-7 Accident Monitoring Instrumentation 3/4 3-52 Surveillance Requirements 3.3-13 Explosive Gas Monitoring Instrumentation 3/4 3-55 4.3-13 Explosive Gas Monitoring Instrumentation 3/4 3-57 Surveillance Requirements 4.4-1 Minimum Number of Steam Generators to be 3/4 4-10e !

Inspected During Inservice Inspection !

4.4-2 Steam Generator Tube Inspection 3/4 4-10f ,

4.4-3 Reactor Coolant System Pressure Isolation 3/4 4-14b Valves 3.4-1 Reactor Coolant System Chemistry Limits 3/4 4-16 4.4-10 Reactor Coolant System Chemistry Limits 3/4 4-17 Surveillance Requirements 4.4-12 Primary Coolant Specific Activity Sample 3/4 4-20 and Analysis Program I

3.7-1 Maximum Allowable Power Range Neutron Flux 3/4 7-2 High Setpoint With Inoperable Steamline Safety Valves During 3 Loop Operation 3.7-2 Maximum Allowable Power Range Neutron Flux 3/4 7-3 '

High Setpoint with Inoperable Steam Line Safety Valves During 2 Loop Operation I

3.7-3 Steam Line Safety Valves Per Loop 3/4 7-4 I 4.7-1 Snubber Visual Inspection Interval 3/4 7-31 4.7-2 Secondary Coolant System Specific Activity 3/4 7-9 Sample and Analysis Program 3.8-1 Battery Surveillance Requirements 3/4 8-9a

, 3.9-1 Beaver Valley Fuel Assembly Minimum Burnup 3/4 9-15 ;

vs. Initial U235 Enrichment For Storage in Region 2 Spent Fuel Racks -

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BEAVER VALLEY - UNIT 1 XIX Amendment No.

E. ;

DPR-66 Table Index (cont.) ;

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TABLE TITLE PAGE B 3/4.4-1 Reactor Vessel Toughness Data (unirradiated) B 3/4 4-7 6.2-1 Minimum Shift Crew Composition 6-4 s

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l BEAVER VALLEY - UNIT 1 XX Amendment No.

1 DPR-66 Fiaure Index i

I FIGURE TITLE PAGE 1

2.1-1 Reactor Core Safety Limit - Three Loop 2-2 ;

operation l l

3.4-1 Dose Equivalent I-131 Primary Coolant 3/4 4-21 Specific Activity Limit Versus Percent of Rated Thermal Power with the Primary Coolant Specific Activity > 1.0 pCi/ gram Dose Equivalent I-131 3.4-2 Beaver Valley Unit 1 Reactor Coolant 3/4 4-24 System Heatup Limitations Applicable for the First 16.0 EFPY l 3.4-3 Beaver Valley Unit 1 Reactor Coolant 3/4 4-25 System Cooldown Limitations Applicable for the First 16.0 EFPY l 3.6-1 Maximum Allowable Primary Containment Air 3/4 6-7 Pressure Versus River Water Temperature B 3/4.2-1 Typical Indicated Axial Flux Difference B 3/4 2-3 Versus Thermal Power at BOL.

B 3/4.4-1 Fast Neutron Fluence (E>l Mev) as a B 3/4 4-6a Function of Full Power Service Life B 3/4.4-2 Effect of Fluence, Copper Content, and B 3/4 4-6b Phosphorus Content on ARTNDT f0f Reactor Vessel Steels Per Reg. Guide 1.99 B 3/4.4-3 Isolated Loop Pressure-Temperature Limit B 3/4 4-10a l Curve 5.1-1 Site Boundary for Gaseous and Liquid 5-lb Effluents for the Beaver Valley Power Station 5.1-3 Exclusion Area - Beaver Valley Power Station 5-1d 5.1-4 Low Population Zone - Beaver Valley Power 5-le Station 5.1-5 Gaseous Release Points - Beaver Valley Power 5-2 Station 5.1-6 Liquid Release Points - Beaver Valley Power 5-3 Station l

BEAVER VALLEY - UNIT 1 XXI Amendment No.

_. - ^ -- __

DPR-66 DEFINITIONS I SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

PROCESS CONTROL PROGRAM 1.28 The PROCESS CONTROL PROGRAM (PCP) shall contain the current 1 formulas, sampling, analyses, test, and determinations to be made to .

ensure that processing and packaging of solid radioactive wastes '

based on demonstrated processing of actual or simulated wat solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.

1.29 DELETED OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.30 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid affluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive '

Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.6 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.10 and 6.9.1.11.

GASEOUS RTDWASTE TREATMENT SYSTEM 1.31 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous affluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

VENTILATION EXHAUST TREATMENT SYSTEM 1.32 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radiocctive BEAVER VALLEY - UNIT 1 1-6 Amendment No.

DPR-66 DEFINITIONS material in particulato form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust stream prior to the release to the environment'(such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

PURGE-PURGING 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, i humidity, concentration or other operating conditions, in such a manner that replacement air or gas is required to purify the -

confinement. ,

VENTING 1.34 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

MAJOR CHANGES '

1.35 MAJOR CHANGES to radioactive waste systems (liquid, gaseous ,

and solid), as addressed in the PROCESS CONTROL PROGRAM shall l include the following:

1) Major changes in process equipment, components, structures ;

and effluent monitoring instrumentation from those described in the Final Safety Analysis Report (FSAR) or the i Hazards Summary Report and evaluated in the staff's safety Evaluation Report (SER) (e.g., deletion of evaporatorc and ,

installation of demineralizers; use of fluidized bed !

calciner/ incineration in place of cement solidification systems); ;

BEAVER VALLEY - UNIT 1 1-7 Amendment No.

.s t . * * ',.

DPR-66 i

Specification 3.3.3.9 has been moved to the OFFSITE DOSE CALCULATION MANUAL.

Specification 3.3.3.10 has been partially moved to the OFFSITE DOSE CALCULATION MANUAL and the remaining part renumbered as 3.3.3.11.

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BEAVER VALLEY - UNIT 1 3/4 3-53 Amendment No.

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l 9; . ' ' 'f DPR-66 l INSTRUMEEIATION l EXPLOSIVE GAS MONITORING INSTRUMENTATION l LIMITING CONDITION FOR OPERATION 3.3.3.11 The explosive gas monitoring instrumentation channels shown ;

in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints !

set to ensure that the limits of Specification 3.11.2.6 are not exceeded.

APPLICABILITY: As shown in Table 3.3-13.

ACTION

a. With an explosive gas monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-13.

b. With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.11 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

l BEAVER VALLEY - UNIT 1 3/4 3-54 Amendment No. l l

2.

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TABLE 3.3-13 DPR-66 b EXPLOSIVE GAS MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Waste Gas Decay Tanks Monitor

a. Oxygen Monitor (2) ** 31 (02 -AS-GW-110-1,2)

- During waste gas decay tank filling operation.

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BEAVER VALLEY - UNIT 1 3/4 3-55 Amendment No.

_ _ .. - - . _. __ . - ._. ._ _ . . _ - ~ _ . _ __ _

DPR-66 TABLE 3.3-13, (Continued)

ACTION STATEMENTS ACTION 27 - (This ACTION is not used) i l

i ACTION 28 - (This ACTION is not used)

ACTION 29 - (This ACTION is not used)

ACTION 30 - (This ACTION is not used) !

ACTION 31 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue provided gran samples are taken and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . With both channels inoperable, operation may continue provided grab samples are taken and analyzed at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing operations and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations.

ACTION 32 - (This ACTION is not used) l t

BEAVER VALLEY - UNIT 1 3/4 3-56 Amendment No. l

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l TABLE 4.3-13 '*

DPR-66 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CALIBRATION TEST

1. Waste Gas Decay Tanks Monitor

a. Oxygen Monitor D** Q(1) M (02 -AS-GW-110-1,2) l l

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- During waste gas decay tank filling operation.

BEAVER VALLEY - UNIT 1 3/4 3-57 Amendment No. l

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DPR-66 I TABLE 4.3-13 (Continued)

I TABLE NOTATION (1) The CHANNEL CALIBRATION .shall include the use of standard l >

gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and

2. Four volume percent oxygen, balance nitrogen l

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I BEAVER VALLEY - UNIT 1 3/4 3-58 Amendment No. l

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DPR-66 i

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Specifications 3.11.1.1 through 3.11.1.3 ,

have been moved.to the OFFSITE DOSE CALCULATION MANUAL.

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t BEAVER VALLEY - UNIT 1 3/4 11-1 Amendment No.

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DPR-66 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS LIOUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 l

]

curies, excluding tritium and dissolved or entrained noble gases.

a. BR-TK-6A (Primary Water Storage Tank) i

b. BR-TK-6B (Primary Water Storage Tank) i

c. LW-TK-7A (Steam Generator Drain Tank) j I

d. LW-TK-7B (Steam Generator Drain Tank)

e. Miscellaneous temporary outside radioactive liquid storage tanks.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the ,

above listed tanks exceeding the above limit, immediately j 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, and )

b. Submit a Special Report to the Commission within 30 days l pursuant to Specification 6.9.2 and include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

~

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4.1 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

BEAVER VALLEY - UNIT 1 3/4 11-2 Amendment No. l

DPR-66 l l

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l BEAVER VALLEY - UNIT 1 3/4 11-3 Amendment No. i i

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DPR-66 l RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS l GAS STORAGE TANKS l LIMITING CONDITION FOR OPERATION '

)

l 3.11.2.5 The quantity of radioactivity contained in each gas l storage tank shall be limited to less than or equal to 52,000 curies l noble gases (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately 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, and l b. Submit a Special Report to the Commission within 30 days I pursuant to Specification 6.9.2 and include a schedule and a i description of activities planned and/or taken to reduce the l contents to within the specified limits.

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c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank. Performance of this surveillance is required when the gross concentration of the primary coolant is greater than 100 l uCi/ml.

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BEAVER VALLEY - UNIT 1 3/4 11-4 Amendment No. l l

8 9 48'

DPR-66 RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION l 3.11.2.6 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal t6 2% by volume l whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal to l 4% by volume, immediately suspend all additions of waste gases to the gaseous waste decay tank and reduce the concentration of oxygen to less than or equal to 2% by l volume within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. With the concentration of oxygen in the waste gas holdup system greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the affected tank and reduce the concentration of oxygen to less than or equal to 4% by volume, then take ACTION a, above.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6.1 The concentrations of oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.11 or monitoring in conjunction with its l associated action statement.

l BEAVER VALLEY - UNIT 1 3/4 11-5 Amendment No. l

DPR-66 Specification 3.11.3.1 has been moved to the PROCESS CONTROL PROGRAM.

Specification 3.11.4.1 has been moved to the OFFSITE DOSE CALCULATION MANUAL.

BEAVER VALLEY - UNIT 1 3/4 11-6 Amendment No.

o ;,. ... ,..

DPR ,

I f

Specifications 3.12.1 through 3.12.3 have been moved to the OFFSITE DOSE CALCULATION MANUAL.

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BEAVER VALLEY - UNIT 1 3/4 12-1 Amendment No.

DPR-66 INSTRUMENTATION BASES 3/4.3.3.11 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas i mixtures in the waste gas 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.

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l BEAVER VALLEY - UNIT 1 B 3/4 3-4 Amendment No.

': l DPR v6 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS l

LIOUID HOLDUP TANKS I

3/4.11.1.4 Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area. ,

(

l 3/4.11.2 GASEOUS EFFLUENTS l

3/4.11.2.5 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas 1 storage tank provides assurance that in the event of an uncontrolled )

release of the tanks' contents, the resulting total body exposure to an individual located at the nearest exclusion area boundary for two hours immediately following the onset of the release will not exceed 0.5 rem. The specified limit restricting the quantity of radioactivity contained in each gas storage tank was specified to ensure that the total body exposure resulting from the postulated release remained a suitable fraction of the reference value set forth in 10 CFR 100.11 (a) (1) .

3/4.11.2.6__EhPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Isolation of the affected tank for purposes of purging and/or discharge permits the flammable gas concentrations of the tank to be reduced below the lower explosive limit in a hydrogen rich system. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

BEAVER VALLEY - UNIT 1 B 3/4 11-1 Amendment No.

-_ - _ - _ -------- _---- _ ----_ -------- _ ---- a

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, DPR-66 ADMINISTRATIVE CONTROLS 6.8.6 The following programs shall be established,' implemented,.

and maintained: !

a. Radioactive Effluent Controls Proaram

A' program' shall- be provided conforming with 10 CFR 50.36a I for the control of radioactive effluents and for ,

o maintaining the doses to MEMBERS- OF THE PUBLIC from ,

radioactive affluents as low as reasonably achievable. The :

program (1) shall be . contained in the ODCM, (2) shall be implemented by . operating procedures,.and (3) shall include j remedial actions to be taken whenever the' program limits >

are exceeded. The program shall . include the following elements: '

1) Limitations on the operability of radioactive liquid I and gaseous monitoring instrumentation including ,

surveillance tests and setpoint determination in l accordance with the methodology in the ODCM, ;

2) Limitations on the concentrations of' radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, r Table 2, Column 2, 1

3) Monitoring, sampling, and analysis of radioactive '

liquid and gaseous affluents in accordance with 10 CFR i 20.106 or.10 CFR 20.1302, as appropriate, and with the methodology and parameters in the ODCM, ,

i

4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive i materials in liquid effluents relearied from -each unit ~

to' UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, I l

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in I accordance with the methodology and parameters in the ODCM at least every 31 days,

6) Limitations on the operability and use of the liquid and gaseous affluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, BEAVER VALLEY - UNIT 1 6-14 Amendment No.

. . , . i . ,o DPR ADMINISTRATIVE CONTROLS

7) Limitations on the dose rate resulting from radio-active material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table 2, Column 1,

8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,

10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

b. Badioloaical Environmental Monitorina Procram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting or radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and I

l BEAVER VALLEY - UNIT 1 6-15 Amendment No.

l

. . . e e .' l DPR-66 )

ADMINISTRATIVE CONTROLS I i

3) Participation in an Interlaboratory Comparison Program 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.

6.9 REPORTING REOUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the U. S. Nuclear Regulatory Commission, Document Control Desk.

STARTUP REPORTS 6.9.1.1 A summary report of plant startup and power escalation testing will be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained- during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details requested in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation),

supplementary reports shall be submitted at least every three months until all three events have been completed.

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BEAVER VALLEY - UNIT 1 6-16 Amendment No. l l

,.,. ...c f DPR-66 ADMINISTRATIVE CONTROLS ANNUAL REPORTS (1) 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. l ,

6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associate exposure according to work and job functions 2) man-rem (,,g,,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling). The dose assignments to various duty functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

b. Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or pressurizer safety valves.

c. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1)

Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit war exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should l

1 (1) A single submittal may be made for a multiple unit site. The submittal should combine those sections that are common to all units at the site.

(2) This tabulation supplements the requirements of Section 20.2206 of 10 CFR Part 20.

BEAVER VALLEY - UNIT 1 6-17 Amendment No. l

-.~e

. .+.,

.?

DPR-66 ,

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) i include 'date and ~ time of sampling and the radioiodine ,

concentrations;, (3) Clean-up system flow history starting ;

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one .!

other radioiodine isotope concentration in microcuries per -

gram as a function of time for the duration of the specific activity above the steady-state. level; and (5) The time

duration 'when -the specific activity of the primary coolant.

exceeded the radioiodine limit. l H !

MONTHLY OPERATING REPORT ;

6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the ,

report. i 6.9.1.7 DELETED by Amendment No. 84 6.9.1.8 DELETED by Amendment No. 84 {

6.9.1.9 DELETED by Amendment No. 84 i

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (3) :

6.9.1.10 The Annual Radiological Environmental Operating . Report l covering- the. operation of the unit during the previous calendar year l shall be submitted before May 1 of each year. The report shall l include summaries, interpretations, and analysis of trends of the l results of the Radiological Environmental Monitoring Program.for the reporting period. The material provided shall be consistent with l the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

(3) A single submittal may be made for a multi-unit station.

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BEAVER VALLEY - UNIT 1 6-18 Amendment No. l l

l DPR-66 I ADMINISTRATIVE CONTROLS l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (4) 6.9.1.11 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation l shall be submitted before April 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

CORE OPERATING LIMITS REPORT 6.9.1.12 Core operating limits shall be established and documented l l in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle. The analytical methods used to )

determine the core operating limits shall be those previously reviewed and approved by the NRC in:

1. WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY", July 1985 (Westinghouse Proprietary). Methodology applied for the following Specifications: ;

3.1.3.5, Shutdown Rod Insertion Limits 3.1.3.6, Control Rod Insertion Limits 3.2.1, Axial Flux Difference-Constant Axial Offset Control !

3.2.2, Heat Flux Hot Channel Factor-FQ(Z) 3.2.3, Nuclear Enthalpy Rise Hot Channel Factor-FN delta H

2. WCAP-9220-P-A, Rev. 1, " WESTINGHOUSE ECCS EVALUATION MODEL-1981 l VERSION", February 1982 (Westinghouse Proprietary).

l Methodology applied for the following Specification: 3.2.2, l Heat Flux Hot Channel Factor-FQ(Z) l

3. WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES -

TOPICAL REPORT", September 1974 (Westinghouse Proprietary). Methodology applied for the following l Specification: 3.2.1, Axial Flux Difference-Constant Axial !

Offset Control l l

(4) A single submittal may be made for a multi-unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

l BEAVER VALLEY - UNIT 1 6-19 Amendment No. l

l

"',' I DPR-66 ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) j

4. T. M. Anderson to K. Kniel (Chief of Core Performance Branch, 1 NRC) January 31, 1980 --

Attachment:

Operation and Safety )

Analysis Aspects of an Improved Load Follow Package. '

Methodology applied for the following Specification: 3.2.1, Axial Flux Difference-Constant Axial Offset Control

5. NUREG-0800, Standard Review Plan, U. S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981. Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981. Methodology applied for the following Specification: 3.2.1, Axial Flux Difference-Constant Axial Offset Control The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided on issuance, for each reload cycle, to the NRC Document Control Desk.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U. S. Nuclear Regulatory Commission, Document Control Desk, within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

c. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

d. Seismic event analysis, Specification 4.3.3.3.2.

e. Sealed source leakage in excess of limits, Specification 4.7.9.1.3.

f. Miscellaneous reporting requirements specified in the Action Statements for Appendix C of the ODCM. l !

g. Containment Inspection Report, Specification 4.6.1.6.2. ;

l l

BEAVER VALLEY - UNIT 1 6-20 Amendment No. l l i

. .. ,e s .- (

DPR-66 ADMINISTRATIVE CONTROLS SPECIAL REPORTS (Continuedl

h. Steam Generator Tube Inservice Inspection Results Report, Specification 4.4.5.5.

i .. Liquid Hold Up Tanks, Specification 3.11.1.4.

j. Gas Storage Tanks, Specification 3.11.2.5.

k. Explosive Gas Monitoring Instrumentation, Specification 3.3.3.11.

6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five (5) years:

a. Records and logs of facility operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. All Reportable Events.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

e. Records of reactor tests and experiments.

f. Records of changes made to Operating Procedures.

g. Records of radioactive shipments.

h. Records of sealed source leak tests and results.

i. Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a. Records and drawing changes reflecting facility design modifications made *o systems and equipment described in the Final Safety Analysis Report.

BEAVER VALLEY - UNIT 1 6-21 Amendment No. l

h- f or f

~ DPR-66 ADMINISTRATIVE CONTROLS-RECORD RETENTION-(Continued) ;

b. Records of new irradiated fuel inventory, fuel transters and assembly burnup-histories.

l' c. Records of facility radiation and contamination surveys. I

~

d. - Records of radiation exposure for all individuals entering f radiation control areas. i L e. Records of gaseous and liquid radioactive material released to the environs. j

f. Records of transient or operational cyc.las for those facility components designed for a limited number of .'

transients or cycles.

g. Records of training. and qualification for current members ;

t of the plant staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required'by the QA Manual.

j. Records of reviews performed for changes made to procedures !

or equipment or reviews of tests and experiments pursuant !

to 10 CFR 50.59. I i

k. Records of meetings of the OSC and the ORC. !

1. Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service !

~

life commences and associated installation and maintenance records. l

m. Records of analyses required by the Radiological i Environmental Monitoring Program.

n. Records of reviews performed for changes made to the .

OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

i i

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared j consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

BEAVER VALLEY - UNIT 1 6-22 Amendment No. l i

n-.---wy-e r- -e--i - , - = - % ,rw+*-s- ---r- -m-w my - , a t------ "

r w'w wre-- -im r- ai' M

.. j ...*

DPR-66 ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.1601 of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation areaandentrancetheretoshallpg)controlledbyrequiring issuance of a Radiological Work Permit or Radiological Access l Control Permit. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by a facility health physics supervisor in the Radiological Work Permit or Radiological Access Control Permit.

6.12.2 The requirements of 6.12.1, above, also apply to each high '

radiation area in which the intensity of radiation is greater than 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor i on duty and/or a facility health physics supervisor.

(1) Health physics personnel, or personnel escorted by health l physics personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

I BEAVER VALLEY - UNIT 1 6-23 Amendment No. l 1

)

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. .' f DPR-66

' ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM-(PCP)

Changes to the PCP:

a. Shall be documented and records of reviews performed shall )

be retained as required by Specification 6.10.2.n. This. ;

documentation shall contain: l

1) Sufficient information to support the change together with the appropriate- analyses or evaluations.

justifying the change (s) and

2) A determination that- the change will maintain the l overall conformance of the solidified waste product to :

existing requirements of Federal, State, or other applicable regulations.

b. Shall become effective after review and acceptance by the OSC and the approval of the General Manager Nuclear Operations, predesignated alternate or a predesignated )

Manager to whom the General Manager Nuclear Operations has assigned in writing the. responsibility for review and approval of specific subjects.

6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the ODCM:

a. Shall be documented and records of reviews performed shall '

be retained as required by Specification 6.10.2.n. This documentation shall.contain: :

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2) A determination that the change will maintain the level of radioactive affluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the OSC and the approval of the- General Manager Nuclear Operations, predesignated alternate or a predesignated Manager to whom the General Manager Nuclear Operations has assigned in writing the responsibility for review and approval of specific subjects.

-BEAVER VALLEY - UNIT 1 6-24 Amendment No.

o . ,, . . . .

DPR-66 ADMINISTRATIVE CONTROLS OFFSITE DOSE CALCULATION MANUAL (ODCM) (Continued)

, c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

6.16 Moved to the PROCESS CONTROL PROGRAM.

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BEAVER VALLEY - UNIT 1 6-25 Amendment No. l

1 l

i ATTACIIMENT B-2 Unit No. 2 Technical Specifice.tioni Pages i

l 1

l

ATTACHMENT'TO LICENSE AMENDMENT NO.

FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 t

Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove: Insert: Remove: Insert:

I thru XVII I thru XVI 3/4 11-17 -

1-5 1-5 3/4 11-18 -

1-6 1-6 3/4 11-19 -

1-7 1-7 3/4 12-1 3/4 12-1 1-8 1-8 3/4 12-2 -

3/4 3-60 3/4 3-60 3/4 12-3 -

l 3/4 3-61 3/4 3-61 3/4 12-4' -

3/4 3-62 3/4 3-62 3/4 12-5 -

3/4 3-63 3/4 3-63 3/4 12-6 -

3/4 3-64 3/4 3-64 3/4 12-7 -

3/4 3-65 3/4 3-65 3/4 12-8 -

3/4 3-66 3/4 3-66 3/4 12-9 -

3/4 3-67 3/4 3-67 3/4 12-10 -

3/4 3-68 -

B 3/4 3-6 B 3/4 3-6 3/4 3-69 -

B 3/4 11-1 B 3/4 11-1 3/4 3-70 -

B 3/4 11-2 -

3/4 3-71 -

B 3/4 11-3 -

3/4 3-72 -

B 3/4 11-4 -

3/4 3-73 -

B 3/4 11-5 -

l 3/4 3-74 -

B 3/4 12-1 -

l 3/4 3-75 -

6-13 6-13 !

3/4 11-1 3/4 11-1 6-14 6-14 l 3/4 11-2 3/4 11-2 6-15 6-15

{j i 3/4 11-3 3/4 11-3 6-16 6-16 3/4 11-4 3/4 11-4 6-17 6-17 3/4 11-5 1/4 11-5 6-18 6-18 3/4 11-6 3/4 11-6 6-18a 6-19 l 3/4 11-7 -

6-19 6-20

, 3/4 11-8 -

6-20 6-21 3/4 11-9 -

6-21 6-22 )

3/4 11-10 -

6-22 6-23 3/4 11-11 -

6-23 6-24 3/4 11-12 -

6-24 6-25 l

3/4 11-13 -

3/4 11-14 -

3/4 11-15 -

l 3/4 11-16 -

1 l - - . - - - - - - - - - - - - - - - _ - - - ------- - - - - u

- . . . - - . . ~

, n.< f NPF-73 INDEX DEFINITIONS ,

SECTION PAGE ,

1.0 DEFINITIONS 1.1 DEFINED TERMS . . . . . . . . . . . . . . . . . . . . 1-l '

i 1.2 THERMAL POWER . . . . . . . . . . . . . . . . . . . . 1-1 1.3 RATED THERMAL POWER . . . . . . . . . . . . . . . . . 1-1 l'.4' OPERATIONAL MODE . . . . . . . . . . . . . . . . . . 1-1 1.5 ACTION . . . . .. . . . . . . . . . . . . . . . . . 1-1 1.6 OPERABLE - OPERABILITY . . . . . . . . . . . . . . . 1-1 1.7 REPORTABLE EVENT . . . . . . . . . . . . . . . . . . 1-1 1.8 CONTAINMENT INTEGRITY . . . . . . . . . . . . . . . . 1-1 1.9 CHANNEL CALIBRATION . . . . . . . . . . . . . . . . . 1-2 l 1.10 CHANNEL CHECK . . . . . . . . . . . . . . . . . . . 1-2 1.11 CHANNEL FUNCTIONAL TEST . . . . . . . . . . . . . . 1-2 1.12 CORE ALTERATION . . . . . . . . . . . . . . . . . . 1-2 1.13 SHUTDOWN MARGIN . . . . . . . . . . . . . . . . . . 1-2 1.14 LEAKAGE. . . . . . . . . . . . . . . . . . . . . . . 1-3 1.15 DELETED 1.16 DELETED 1 1.17 DELETED 1.18 QUADRANT POWER TILT RATIO . . . . . . . . . . . . . 1-3 1.10 DOSE EQUIVALENT I-131 . . . . . . . . . . . . . . . 1-4

.1.20 STAGGERED TEST BASIS . . . . . . . . . . . . . . . . 1-4 1.21 FREQUENCY NOTATION . . . . . . . . . . . . . . . . . 1-4 1.22 REACTOR TRIP SYSTEM RESPONSE TIME . . . . . . . . . 1-4 1.23 ENGINEERED SAFETY FEATURE RESPONSE TIME . . . . . . 1-4 BEAVER VALLEY - UNIT 2 I Amendment No.

m e ,4mf a m Sn.- % 4 6 Ja 2.SaJL.--- mas,-e s+ + -4 a } b__

t

,. s . .. .

a NPF-73 INDEX DEFINITIONS ;

SECTION PAGE

'1.24 AXIAL FLUX DIFFERENCE . - . . . . . . . . . . . . . . 1-4 1.25 PHYSICS TESTS . . . . . . . . . . . . - . . - . . . . . 1-5 1.26 E-AVERAGE DISINTEGRATION ENERGY . . . . . . . . . . 1-5 1.27 SOURCE CHECK . . . . . . . . . . . . . . . . . . . . 1-5 1.28 PROCESS CONTROL PROGRAM . . . . . . . . . . . . . . 1-5 1.29 DELETED 1.30 OFFSITE DOSE CALCULATION MANUAL (ODCM) . . . . . . . 1-5 1.31 GASEOUS RADWASTE TREATMENT SYSTEM . . . . . . . . . 1-6 1.32 VENTILATION EXHAUST TREATMENT SYSTEM . . . . . . . 1-6 1.33 PURGE - PURGING . . . . . . . . . . . . . . . . . . 1-6 1.34 VENTING . . . . . . . . . . . . . . . . . . . . . . 1-6 L 1.35 MAJOR CHANGES . . . . . . . . . . . . . . . . . . . 1-6 1.36 MEMBER (S) OF THE PUBLIC . . . . . . . . . . . . . . 1-7 1.37 CORE OPERATING LIMITS REPORT . . . . . . . . . . . . 1-7 j TABLE 1.1 OPERATIONAL MODES . . . . . . . . . . . . . . .. 1-8 j j

TABLE 1.2 FREQUENCY NOTATION . . . . . . . . . . . . . . 1-9 l 1

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE

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2.1 SAFETY LIMITS I 2.1.1 REACTOR CORE . . . . . . . . . . . . . . . 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE . . . . . . 2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS . . . . . . . . . . . . . . . . . 2-3 .

BEAVER VALLEY - UNIT 2 II Amendment No.

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NPF-73 INDEX BASES i i

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2.1 SAFETY LIMITS 2.1.1 REACTOR CORE. . . . . . . . . . . . . . . . B 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE . . . . . . B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP INSTRUMENTATION SETPOINTS. . . B 2-2 LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY . . . . . . . . . . . . . . . . . . 3/4 0-1 1

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL 3/4.1.1.1 Shutdown Margin - Tavg > 200*F . . . . . 3/4 1-1 3/4.1.1.2 Shutdown Margin - T avg 5 200*F . . . . . 3/4 1-3 3/4.1.1.3 Boron Dilution . . . . . . . . . . . . . . 3/4 1-4 3/4.1.1.4 Moderator Temperature Coefficient (MTC) . . 3/4 1-5 3/4.1.1.5 Minimum Temperature for Criticality . . . . 3/4 1-6 3/4.1.2 BORATION SYSTEMS 3/4.1.2.1 Flow Paths - Shutdown . . . . . . . . . . . 3/4 1-7 3/4.1.2.2 Flow Paths ~ Operating. . . . . . . . . . . 3/4 1-8 3/4.1.2.3 Charging Pump - Shutdown. . . . . . . . . . 3/4 1-10 3/4.1.2.4 Charging Pumps - Operating. . . . . . . . . 3/4 1-11 I 3/4.1.2.5 Boric Acid Transfer Pumps - Shutdown. . . . 3/4 1-12 3/4.1.2.6 Boric Acid Transfer Pumps - Operating . . . 3/4 1-13 3/4.1.2.7 Borated Water Sources - Shutdown. . . . . . 3/4 1-14 3/4.1.2.8 Borated Water Sources - Operating . . . . . 3/4 1-15 BEAVER VALLEY - UNIT 2 III Amendment No.

- : " :- i NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAG.E 3/4.1.2.9 Isolation of Unborated Water Sources -

Shutdown. . . . . . . . . . . . . . . . . . 3/4 1-17 3/4.1.3 MOVABLE CONTROL ASSEMBLIES 3/4.1.3.1 Group Height. . . . . . . . . . . . . . . . 3/4 1-18 3/4.1.3.2 Position Indication Systems - Operating . .

3/4 1-21 3/4.1.3.3 Position Indication System - Shutdown. . . 3/4 1-22 3/4.1.3.4 Rod Drop Time . . . . . . . . . . . . . . . 3/4 1-23 3/4.1.3.5 Shutdown Rod Insertion Limit. . . . . . . . 3/4 1-24 3/4.1.3.6 Control Rod Insertion Limits. . . . . . . . 3/4 1-25 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) . . . . . . . . 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR -gF (Z). . . 3/4 2-4 3/4.2.3 NgCLEARENTHALPYHOTCHANNELFACTOR-F H. . . . . . . . . . . . . . . . . . 3/4 2-7 3/4.2.4 QUADRANT POWER TILT RATIO . . . . . . . . . 3/4 2-9 3/4.2.5 DNB PARAMETERS. . . . . . . . . . . . . . . 3/4 2-11 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION . . . . 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION . . . . . . . . . . . . . . 3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring. . . . . . . . . . . . 3/4 3-39 ,

i 3/4.3.3.2 Movable Incore Detectors. . . . . . . . . . 3/4 3-45 3/4.3.3.3 Seismic Instrumentation . . . . . . . . . . 3/4 3-46 (

3/4.3.3.4 Meteorological Instrumentation. . . . . . . 3/4 3-49 1

I BEAVER VALLEY - UNIT 2 Amendment No.

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, NPF-73 INDEX

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i LIMITING-CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS

! SECTION PAGE l

3/4.3.3.5 Remote Shutdown Instrumentation . . . . . . 3/4 3-52 3/4.3.3.7 Chlorine Detection Systems. . . . . . . . . 3/4 3-56 3/4.3.3.8 Accident Monitoring Instrumentation . . . . 3/4 3-57 3/4.3.3.11 Explosive Gas Monitoring Instrumentation. . 3/4 3-61 3/4.3.4 TURBINE OVERSPEED PROTECTION. . . . . . . . 3/4 3-66 3/4.4 REACTOR COOLANT SYSTEM l l l 1

3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION j 1

3/4.4.1.1 Normal Operation. . . . . . . . . . . . . . 3/4 4-1 ]

3/4.4.1.2 Hot Standby . . . . . . . . . . . . . . . . 3/4 4-2 3/4.4.1.3 Shutdown. . . . . . . . . . . . . . . . . . 3/4 4-3 3/4.4.1.6 Reactor Coolant Pump-Startup. . . . . . . . 3/4 4-7 3/4.4.2 SAFETY VALVES - SHUTDOWN. . . . . . . . . . 3/4 4-8 3/4.4.3 SAFETY VALVES - OPERATING . . . . . . . . . 3/4 4-9 3/4.4.4 PRESSURIZER . . . . . . . . . . . . . . . . 3/4 4-10 l 3/4.4.5 STEAM GEN:7ATORS. . . . . . . . . . . . . . 3/4 4-11 l 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 Leakage Detection Instrumentation . . . . . 3/4 4-17 3/4.4.6.2 Operational Leakage . . . . . . . . . . . . 3/4 4-19 3/4.4.6.3 Pressure Isolation Valves . . . . . . . . . 3/4 4-21 3/4.4.7 CHEMISTRY . . . . . . . . . . . . . . . . . 3/4 4-24 3/4.4.8 SPECIFIC ACTIVITY . . . . . . . . . . . . . 3/4 4-27 3/4.4.9 PRESSURE / TEMPERATURE LIMITS 3/4.4.9.1 Reactor Coolant System. . . . . . . . . . . 3/4 4-30 3/4.4.9.2 Pressurizer . . . . . . . . . . . . . . . . 3/4 4-34 BEAVER VALLEY - UNIT 2 V Amendment No.

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NPF-73 INDEX ,

l LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS i l

SECTION PAGE )

3/4.4.9.3 Overpressure Protection Systems . . . . . . 3/4 4-35 3/4.4.10 STRUCTURAL INTEGRITY . . . . . . . . . . . 3/4 4-38 3/4.4.11 RELIEF VALVES . . . . . . . . . . . . . . . 3/4 4-39 3/4.4.12 REACTOR COOLANT SYSTEM HEAD VENTS . . . . . 3/4 4-40 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS. . . . . . . . . . . . . . . . 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T avg 2 350*F. , . . . .

3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - Tavg < 350*F. . . . . . 3/4 5-6 3/4.5.4 SEAL INJECTION FLOW . . . . . . . . . . . . 3/4 5-7 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 Containment Integrity . . . . . . . . . . . 3/4 6-1 3/4.6.1.2 Containment Leakage . . . . . . . . . . . . 3/4 6-2 3/4.6.1.3 Containment Air Locks . . . . . . . . . . . 3/4 6-4 3/4.6.1.4 Internal Pressure . . . . . . . . . . . . . 3/4 6-6 3/4.6.1.5 Air Temperature . . . . . . . . . . . . . . 3/4 6-8 3/4.6.1.6 Containment Structural Integrity. . . . . . 3/4 6-9 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS '

3/4.6.2.1 Containment Quench Spray System . . . . . . . 3/4 6-10 3/4.6.2.2 Containment Recirculation Spray System. . . 3/4 6-12 3/4.6.2.3 Chemical Addition System. . . . . . . . . . 3/4 6-14 3/4.6.3 CONTAINMENT ISOLATION VALVES. . . . . . . . 3/4 6-15 DEAVER VALLEY - UNIT 2 VI Amendment No.

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, ./f NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE .

3/4.6.4 COMBUSTIBLE GAS CONTROL 3/4.6.4.1 Hydrogen Analyzers. . . . . . . . . . . . . 3/4 6-31 3/4.6.4.2 Electric Hydrogen Recombiners . . . . . . . 3/4 6-32 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 Safety Valves . . . . . . . . . . . . . . . 3/4 7-1 3/4.7.1.2 Auxiliary Feedwater System. . . . . . . . . 3/4 7-4 3/4.7.1.3 Primary Plant Demineralized Water (PPDW). .

3/4 7-6 3/4.7.1.4 Activity . . . . . . . . . . . . . . . . . 3/4 7-7 3/4.7.1.5 Main Steam Line Isolation Valves . . . . . 3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION. . . . . . . . . . . . . . . . . 3/4 7-10 3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM. . . 3/4 7-11 1 3/4.7.4 SERVICE WATER SYSTEM (SWS). . . . . . . . . 3/4 7-12 ,

1 3/4.7.5 ULTIMATE HEAT SINK - OHIO RIVER . . . . . . 3/4 7-13 3/4.7.6 FLOOD PROTECTION. . . . . . . . . . . . . . 3/4 7-14 3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP AND PRESSURIZATION SYSTEM . . . . . . . . . . 3/4 7-15 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM (SLCRS). . . . . . . . . . . . . . . 3/4 7-18 3/4.7.9 SEALED SOURCE CONTAMINATION . . . . . . . . 3/4 7-20 3/4.7.12 SNUBBERS. . . . . . . . . . . . . . . . . . 3/4 7-24 3/4.7.13 STANDBY SERVICE WATER SYSTEM (SWE). . . . . 3/4 7-30 BEAVER VALLEY - UNIT 2 VII Amendment No.

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NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.8 ELECTRICAL POWER SYSTEMS l 3/4.8.1 A.C. SOURCES l

3/4.8.1.1 Operating . . . . . . . . . . . . . . . . . 3/4 8-1 3/4.8.1.2 Shutdown. . . . . . . . . . . . . . . . . . 3/4 8-6 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEM 3/4.8.2.1 A.C. Distribution - Operating . . . . . . . 3/4 8-7 3/4.8.2.2 A.C. Distribution - Shutdown. . . . . . . . 3/4 8-8 3/4.8.2.3 D.C. Distribution - Operating . . . . . . . 3/4 8-9 3/4.8.2.4 D.C. Distribution - Shutdown. . . . . . . . 3/4 8-12 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION . . . . . . . . . . . . 3/4 9-1 3/4.9.2 INSTRUMENTATION . . . . . . . . . . . . . . 3/4 9-2 3/4.9.3 DECAY TIME. . . . . . . . . . . . . . . . . 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS . . . . . 3/4 9-4 3/4.9.5 COMMUNICATIONS. . . . . . . . . . . . . . . 3/4 9-5 1

i 1

3/4.9.6 MANIPULATOR CRANE OPERABILITY . . . . . . . 3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING. . . . . . . . . . . . . . . . . . 3/4 9-7 l

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION 3/4.9.8.1 High Water Level . . . . . . . . . . . . . 3/4 9-8 3/4.9.8.2 Low Water Level . . . . . . . . . . . . . . 3/4 9-9 l 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION i SYSTEM. . . . . . . . . . . . . . . . . . . 3/4 9-10 3/4.9.10 WATER LEVEL-REACTOR VESSEL. . . . . . . . . 3/4 9-11 3/4.9.11 STORAGE POOL WATER LEVEL. . . . . . . . . . 3/4 9-12 BEAVER VALLEY - UNIT 2 VIII Amendment No.

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NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTIQH PAGE i

3/4.9.12 FUEL BUILDING VENTILATION SYSTEM -

FUEL MOVEMENT . . . . . . . . . . . . . . . 3/4 9-13 3/4 9.13 FUEL BUILDING VENTILATION SYSTEM -

FUEL STORAGE. . . . . . . . . . . . . . . . 3/4 9-14 3/4.9.14 FUEL STORAGE - SPENT FUEL STORAGE POOL. . . 3/4 9-15 l l

l 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . . . . . . . . . . . . . . 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS . . . . . . . . . . . . 3/4 10-2 3/4.10.3 PHYSICS TESTS . . . . . . . . . . . . . . . 3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS . . . . . . . . . . . 3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM-SHUTDOWN . . . . 3/4 10-5 1 3/4.11 RADIOACTIVE EFFLUENTS i l

3/4.11.1 LIQUID EFFLUENTS l 3/4.11.1.4 Liquid Holdup Tanks . . . . . . . . . . . . 3/4 11-2 l l

3/4.11.2 GASEOUS EFFLUENTS j 3/4.11.2.5 Gareous Waste Storage Tanks . . . . . . . . 3/4 11-4 3/4.11.2.6 Explosive Gas Mixture . . . . . . . . . . . 3/4 11-5 BASES SECTION PAGE 3/4.0 APPLICABILITY. . . . . . . . . . . . . . . . . . . B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL. . . . . . . . . . . . . . B 3/4 1-1 3/4.1.2 BORATION SYSTEMS. . . . . . . . . . . . . . B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES. . . . . . . . . B 3/4 1-4 BEAVER VALLEY - UNIT 2 IX Amendment No.

' l' NPF-73 INDEX BASES SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) . . . . . . . . B 3/4 2-1 3/4.2.2AND3/4.2.3HEATFLUXANDNUCLEARENTgALPY

, HOT CHANNEL FACTORS Pg(Z) AND F H. . . . . B 3/4 2-2 3/4.2.4 QUADRANT POWER TILT RATIO . . . . . . . . . B 3/4 2-5 l l

1 3/4.2.5 DNB PARAMETERS. . . . . . . . . . . . . . . B 3/4 2-5 l

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION . . . . B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION. . . . . . . . . . . B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring Instrumentation. . . . B 3/4 3-4 3/4.3.3.2 Movable Incore Detectors. . . . . . . . . . B 3/4 3-4 3/4.3.3.3 Seismic Instrumentation . . . . . . . . . . B 3/4 3-5 3/4.3.3.4 Meteorological Instrumentation. . . . . . . B 3/4 3-5 3/4.3.3.5 Remote Shutdown Instrumentation . . . . . . B 3/4 3-5 l 3/4.3.3.7 Chlorine Detection Systems. . . . . . . . . B 3/4 3-5 )

l I 3/4.3.3.8 Accident Monitoring Instrumentation . . . . B 3/4 3-6 l 3/4.3.3.11 Explosive Gas Monitoring Instrumentation. .

B 3/4 3-6 <

3/4.3.4 TURBINE OVERSPEED PROTECTION . . . . . . . B 3/4 3-6 1

REACTOR COOLANT SYSTEM 3/4.4 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION . . . . . . . . . . . . . . . . B 3/4 4-1 3/4.4.2 AND 3/4.4.3 SAFETY VALVES . . . . . . . . . . . . B 3/4 4-2 3/4.4.4 PRESSURIZER . . . . . . . . . . . . . . . . B 3/4 4-2 BEAVER VALLEY - UNIT 2 X Amendment No. i j

o'p .tf NPF-73 INDEX BASES SECTION PAGE 3/4.4.5 STEAM GENERATORS . . . . . . . . . . . . . B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE. . . . . . . B 3/4 4-4 3/4.4.7 CHEMISTRY . . . . . . . . . . . . . . . . . B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY . . . . . . . . . . . . . B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS . . . . . . . . B 3/4 4-6 3/4.4.10 STRUCTURAL INTEGRITY. . . . . . . . . . . . B 3/4 4-15 3/4.4.11 REACTOR COOLANT SYSTEM RELIEF VALVES. . . . B 3/4 4-16 3/4.4.12 REACTOR COOLANT SYSTEM HEAD VENTS . . . . . B 3/4 4-16 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS. . . . . . . . . . . . . . . . B 3/4 5-1 3/4.5.2 AND 3/4.5.3 ECCS SUBSYSTEMS . . . . . . . . . . . B 3/4 5-1 3/4.5.4 SEAL INJECTION FLOW . . . . . . . . . . . . B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT . . . . . . . . . . . . B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS. . . . B 3/4 6-2 3/4.6.3 CONTAINMENT ISOLATION VALVES. . . . . . . . B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTROL . . . . . . . . . . B 3/4 6-3 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE . . . . . . . . . . . . . . . B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION . . . . . . . . . . . . . . . . B 3/4 7-3 3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM. . . B 3/4 7-3 l

1 BEAVER VALLEY - UNIT 2 XI Amendment No. )

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s ' ,s <tf NPF-73 INDEX BASES SECTION PAGE 3/4.7.4 SERVICE WATER SYSTEM. . . . . . . . . . . . B 3/4 7-3 3/4.7.5. ULTIMATE HEAT SINK. . . . . . . . . . . .. B 3/4 7-3 3/4.7.6 FLOOD PROTECTION. . . . . . . . . . . . . . B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY AIR CLEANUP AND PRESSURIZATION SYSTEM . . . . . . . . . . . B 3/4 7-4 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM (SLCRS). . . . . . . . . . . . . . . B 3/4 7-4 3/4.7.9 SEALED SOURCE CONTAMINATION . . . . . . . . B 3/4 7-5 4

J 3/4.7.12 SNUBBERS. . . . . . . . . . . . . . . . . . B 3/4 7-5 3/4.7.13 STANDBY SERVICE WATER SYSTEM (SWE). . . . . B 3/4 7-6 j 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES. . . . . . . . . . . . . . . . B 3/4 8-1

3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS . . . . . B 3/4 8-1 3/4.9 REFUELING OPERATIONS )

l 3/4.9.1 BORON CONCENTRATION . . . . . . . . . . . . B 3/4 9-1 3/4.9.2 INSTRUMENTATION . . . . . . . . . . . . . . B 3/4 9-1 1

3/4.9.3 DECAY TIME. . . . . . . . . . . . . . . . . B 3/4 9-1 j i

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS . . . . . B 3/4 9-1 3/4.9.5 COMMUNICATIONS. . . . . . . . . . . . . . . B 3/4 9-2 1 3/4.9.6 MANIPULATOR CRANE OPERABILITY . . . . . . . B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING. B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE AND EXKAUST ISOLATION l SYSTEM. . . . . . . . . . . . . . . . . . . B 3/4 9-3 l l l

3/4.9.10 AND 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL . . . . . . . . . . . . . . . B 3/4 9-3 l l

I BEAVER VALLEY - UNIT 2 XII Amendment No.

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NPF-73 l unzx BASES SECTION PAGE 3/4.9.12 AND 3/4.9.13 FUEL BUILDING VENTILATION SYSTEM. . B 3/4 9-3 3/4.9.14 FUEL STORAGE - SPENT FUEL STORAGE POOL. . . B 3/4 9-4 l 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS. . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.3 PHYSICS TESTS . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.4 REACTOR COOLANT LOOPS . . . . . . . . . . . B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM-SHUTDOWN . . . . B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS. . . . . . . . . . . . . . B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS . . . . . . . . . . . . . B 3/4 11-1 DESIGN FEATURES i

SECTION PAGE ,

5.1 SITE 5.1.1 Site Boundary for Gaseous Effluents . . . . 5-1 5.1.2 Site Boundary for Liquid Effluents. . . . . 5-1

)

5.1.3 Exclusion Area. . . . . . . . . . . . . . . 5-1

, 5.1.4 Low Population Zone . . . . . . . . . . . 5-1 I

! 5.1.5 Flood Control . . . . . . . . . . . . . . . 5-1 i

6 5.2 CONTAINMENT 5.2.1 Configuration . . . . . . . . . . . . . . . 5-1

} 5.2.2 Design Pressure and Temperature . . . . . . 5-6 >

5.2.3 Penetrations. . . . . . . . . . . . . . . . 5-6 4

BEAVER VALLEY - UNIT 2 XIII Amendment No.

e

.r .-_ - , , . - - . _ . . . _ _ _ _ . _ m._,_- . , - . . - - ,

oy 1 ,,'

NPF-73 INDEX DESIGN FEATURES SECTION PAGE 5.3 REACTOR CORE 5.3.1 Fuel Assemblies . . . . . . . . . . . . . . 5-6 5.3.2 Control Rod Assemblies. . . . . . . . . . . 5-6 5.4 REACTOR COOLANT SYSTEM 5.4.1 Design Pressure and Temperature . . . . . . 5-6 q 5.4.2 Volume. . . . . . . . . . . . . . . . . . . 5-7 5.5 EMERGENCY CORE COOLING SYSTEMS . . . . . . . . . . . 5-7 5.6 FUEL STORAGE f l 5.6.1 Criticality . . . . . . . . . . . . . . . . 5-7 5.6.2 Drainage. . . . . . . . . . . . . . . . . . 5-7 5.6.3 Capacity. . . . . . . . . . . . . . . . . . 5-7 5.7 SEISMIC CLASSIFICATION . . . . . . . . . . . . . . . 5-7 5.8 METEOROLOGICAL TOWER LOCATIOE. . . . . . . . . . . . 5-7 ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY . . . . . . . . . . . . . . . . . . . 6-1 522 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS. . . . . . 6-1 6.2.2 UNIT STAFF. . . . . . . . . . . . . . . . . 6-1 1

I 6.2.3 INDEPENDENT SAFETY EVALUATION GROUP (ISEG). 6-2 1

6.3 FACILITY STAFF OUALIFICATIONS. . . . . . . . . . . . 6-6 BEAVER VALLEY - UNIT 2 XIV Amendment No.

1 L. -- . _ .

e ,% 'l l*

HPF-73 INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.4 TRAINItIQ . . . . . . . . . . . . . . . . . . . . . . 6-6 6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC) 6.5.1.1 Function. . . . . . . . . . . . . . . . . . 6-6 6.5.1.2 Composition . . . . . . . . . . . . . . . . 6-6 6.5.1.3 Alternates. . . . . . . . . . . . . . . . . 6-7 6.5.1.4 Meeting Frequency . . . . . . . . . . . . . 6-7 6.5.1.5 Quorum. . . . . . . . . . . . . . . . . . . 6-7 6.5.1.6 Responsibilities. . . . . . . . . . . . . . 6-7 6.5.1.7 Authority . . . . . . . . . . . . . . . . . 6-8 6.5.1.8 Records . . . . . . . . . . . . . . . . . . 6-8 6.5.2 OFFSITE REVIEW COMMITTEE (ORC) 6.5.2.1 Function. . . . . . . . . . . . . . . . . . 6-8 6.5.2.2 Composition . . . . . . . . . . . . . . . . 6-9 6.5.2.3 Alternates. . . . . . . . . . . . . . . . . 6-9 6.5.2.4 Consultants . . . . . . . . . . . . . . . . 6-9 6.5.2.5 Meeting Frequency . . . . . . . . . . . . . 6-9 6.5.2.6 Quorum. . . . . . . . . . . . . . . . . . . 6-9 6.5.2.7 Review. . . . . . . . . . . . . . . . . . . 6-9 6.5.2.8 Audits. . . . . . . . . . . . . . . . . . . 6-10 6.5.2.9 Authority . . . . . . . . . . . . . . . . . 6-11 6.5.2.10 Records . . . . . . . . . . . . . . . . . . 6-11 6.6 REPORTABLE EVENT ACTION . . . . . . . . . . . . . 6-11 BEAVER VALLEY - UNIT 2 XV Amendment No.

l

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INDEX !

ADMINISTRATIVE CONTROLS SECTION PAGE 6.7 SAFETY LIMIT VIOLATION . . . . . . . . . . . . . . . 6-12 6.8 PROCEDURES . . . . . . . . . . . . . . . . . . . . . 6-12 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS . . . . . . . . . . . . . . 6-16 6.9.1.1 Startup Reports . . . . . . . . . . . . . . 6-16 6.9.1.4 Annual Reports. . . . . . . . . . . . . . . 6-17 6.9.1.6 Monthly Operating Report. . . . . . . . . . 6-18 6.9.1.10 Annual Radiological Environmental Operating Report. . . . . . . . . . . . . . . . . . . 6-19 6.9.1.11 Annual Radioactive Effluent Release Report. 6-19 6.9.1.12 Core Operating Limits Report. . . . . . . . 6-19 6.9.2 SPECIAL REPORTS . . . . . . . . . . . . . . 6-20 6.10 RECORD RETENTION. . . . . . . . . . . . . . . . . . 6-21 6.11 RADIATION PROTECTION PROGRAM. . . . . . . . . . . . 6-23 6.12 HIGH RADIATION AREA . . . . . . . . . . . . . . . . 6-23 6.13 PROCESS CONTROL PROGRAM (PCP) . . . . . . . . . . . 6-24 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM). . . . . . . 6-25 6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Licuid, Gaseous and Solid) . . . . . . . . 6-25 I l

BEAVER VALLEY - UNIT 2 XVI Amendment No. '

1

1 y <t q' NPF-73 DEFINITIONS PHYSICS TESTS 1.25 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

E - AVERAGE DISINTEGRATION ENERGY 1.26 5 shall be the average sum (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

PROCESS CONTROL PROGRAM 1.28 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground i requirements, and other requirements governing the disposal of solid l radioactive waste.

1.29 DELETED OFFSITE DOSE CALCULATION MANUAL (QD_Cli),

1.30 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.6 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.10 and 6.9.1.11.

BEAVER VALLEY - UNIT 2 1-5 Amendment No.

r p ./ f' NPF-73 DEFINITIONS GASEOUS RADWASTE TREATMENT SYSTEM 1.31 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

VENTILATION EXHAUST TREATMENT SYSTEM f 1.32 VENTILATION EXHAUST TREATMENT SYSTEM is any system designed I and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent l exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing lodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

PURGE-PURGING 1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions, in such a manner that replacement air or gas is required to purify the confinement.

VENTING ;

{

1.34 VENTING is the controlled process of discharging air or gas i from a confinement to maintain temperature, pressure, humidity, l concentration or other operating conditions, in such a manner that )

replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

MAJOR CHANGES 1.35 MAJOR CHANGES to radioactive waste systems (liquid, qaseous and solid), as addressed in the PROCESS CONTROL PROGRAM, shall I include the following:

1) Major changes in process equipment, components, l structures, and effluent monitoring instrumentation from l those described in the Final Safety Analysis Report (FSAR) or the Hazards Summary Report and evaluated in the l

l l BEAVER VALLEY - UNIT 2 1-6 Amendment No.

i 1

l r p .tf NPF-73 DEFINITIONS MAJOR CHANGES (Continued) staff's Safety Evaluation Report (SER) (e.g., deletion of evaporators and installation of domineralizers; use of fluidized bed calciner/ incineration in place of cement solidification systems);

2) Major changes in the design of radwaste treatment systems (liquid, gaseous, and solid) that could significantly increase the quantities < activity of effluents released or volumes of solid waste stored or shipped offsite from those previously considered in the FSAR and SER (e.g., use of asphalt system in place of cement);

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

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

MEMBER (S) OF THE PUBLIC 1.36 MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or its vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries and persons who traverse portions of the site as the consequence of a public highway, railway, or waterway located within the confines of the site boundary. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

CORE OPERATING LIMITS REPORT 1.37 The CORE OPERATING LIMITS REPORT (COLR) is the unit-specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.12. Plant operation within these operating limits is addressed in individual specifications.

i BEAVER VALLEY - UNIT 2 1-7 Amendment No.

- j .I f

NPF-73 TABLE 1.1 OPERATIONAL MODES REACTIVITY % RATED AVERAGE CONDITION, COOLANT THERMAp1)

MODE K,gg POWER TEMPERATURE. l ;

1. POWER OPERATION 20.99 >5% 2350*F

2. STARTUP 20.99 $5% 2350*F

3. HOT STANDBY <0.99 0 2350'F

4. HOT SHUTDOWN <0.99 0 350'F >T avg I

>200*F

5. COLD SHUTDOWN <0.99 0 $200*F

6. REFUELING I2) $0.95 0 $140*F l l

l I

(1) Excluding decay heat. l (2) Reactor vessel head unbolted or removed and fuel in the vessel. I BEAVER VALLEY - UNIT 2 1-8 Amendment No.

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NPF-73 I

1 I

l

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i Specification 3.3.3.9 has been moved to the ,

OFFSITE DOSE CALCULATION. MANUAL.

Specification 3.3.3.10 has been partially i moved to the OFFSITE DOSE CALCULATION MANUAL l and the remaining part renumbered 3.3.3.11. '

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BEAVER VALLEY - UNIT 2 3/4 3-60 Amendment'No.

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NPF-73 INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION l LIMITING CONDITION FOR OPERATION 3.3.3.11 The explosive gas monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.6 are l not exceeded.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

a. With an explosive gas monitoring instrumentation channel I Alarm / Trip Setpoint less conservative than required by the ,

above specification declare the channel inoperable and take I the ACTION shown in Table 3.3-13.

b. With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why the inoperability was not corrected in a timely manner.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.s 11 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-13.

BEAVER VALLEY - UNIT 2 3/4 3-61 Amendment No. l

TABLE 3.3-13 NPF-7I; EXPLOSIVE GAS MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Gaseous Waste System Surge Tank Discharge

a. Oxygen Monitor 2

31 (2GWS-OA100A & B)

During vaste gas decay tank filling operation.

BEAVER VALLEY - UNIT 2 3/4 3-62 Amendment No.

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NPF-73 TABLE 3.3-13 (Continuedi ACTION STATEMENTS ACTION.27 - (This' ACTION is not used)

ACTION 28 -

(This ACTION is not used) !

I ACTION 29 - (This ACTION is not used)

ACTION 30 - (This ACTION is not used)

ACTION 31 - With the number of channels OPERABLE one less than l required by the MINIMUM Channels OPERABLE requirement, '

operation of this system may continue provided grab- ;

samples are taken and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . With both channels' inoperable, operation may continue provided grab samples are taken and analyzed l at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing operations and' at least .once per- 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during. other ,

operations.

ACTION 32 - (This ACTION is not used) ;

ACTION 35 - (This ACTION is not used) t i

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l BEAVER VALLEY - UNIT 2 3/4 3-63 Amendment No. l i

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TABLE 4.3-13 NPF-73 ,f Explosive Gas Monitorina Instrumentation Surveillance Recuirements-CHANNEL' CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CALIBRATION TEST

1. Gaseous Waste System Surge Tank Discharge

a. Oxygen Monitor D** Q(1) M (2GWS-OA100A & B) i I

i

- During waste gas decay tank filling operation.

i.

l BEAVER VALLEY - UNIT 2 3/4 3-64 Amendment No.

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_ _ _ _ _ - _ __ - _ _ __ _ _ ,,- - , - m ._ ,,.- , _ . . . . , , ,. . . . , - , . . . -

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'NPF-73 .

TABLE 4.3-13 (Continued)

TABLE NOTATION (1) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and

2. Four volume percent oxygen, balance nitrogen l BEAVER VALLEY - UNIT 2 3/4 3-65 Amendment No. l l l

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NPF-73 i INSTRUMENTATION l i

1 3/4.3.4 TURBINE OVERSPEED PROTECTION l LIMITING CONDITION FOR OPERATION 1

l 3.3.4 At least one Turbine Overspeed Protection System shall be l OPERABLE.

and 3 (1) ,

APPLICABILITY: MODES 1, 2 (1) ,

l ACTIQH:

a. With one throttle valve or one governor valve per high pressure turbine steam line inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam line inoperable, restore the inoperable valve (s) to OPERABLE status kLthin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or close at least one valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With the above required Turbine overspeed Protection System otherwise inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months isolate the turbine from the steam supply.

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.

4.3.4.2 The above required Turbine Overspeed Protection System shall be demonstrated OPERABLE:

a. By cycling each of the following valves through at least one complete cycle from the running position:

1) Four high pressure turbine throttle valves at least once per 31 days,

2) Four high pressure turbine governor valves at least once per 31 days,

3) Four low pressure turbine reheat stop valves at least once per 18 months,

4) Four low pressure turbine reheat intercept valves at least once per 18 months, (1) Specification not applicable with all main steam isolation l valves and associated bypass valves in the closed position and all other steam flow paths to the turbine isolated.

BEAVER VALLEY - UNIT 2 3/4 3-66 Amendment No. l

) <t NPF-73 INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued)

b. By direct observation of the movement of each of the i following valves through one complete cycle from the running position:

1) Four high pressure turbine throttle valves at least once per 31 days,

2) Four high pressure turbine governor valves at least once per 31 days,

3) Four low pressure turbine reheat stop valves at least once per 18 mcnths,

4) Four low pressure turbine reheat intercept valves at least once per 18 months,

c. At least once per 18 months by performing a CHANNEL ,

l CALIBRATION on the turbine overspeed protection systems, '

and

d. At least once per 40 months by disas'= ambling at least one of each of the above valves and per forming a visual and surface inspection of valve seats, disks, and stems and verifying no unacceptable flaws or excessive corrosion. If unacceptable flaws or excessive corrosion are found, all other valves of that type shall be inspected unless the nature of the problem can be directly attributed to a service condition specific to that valve. For reheat stop and intercept valves the inspection cycle may be' increased to a maximum of 60 months, provided there is no indication of operational distress.

i BEAVER VALLEY - UNIT 2 3/4 3-67 Amendment No. l l

)

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s Specifications 3.11.1.1 through 3.11.1.3 have been moved to the OFFSITE DOSE CALCULATION MANUAL.

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BEAVER VALLEY - UNIT 2 3/4 11-1 Amendment No.

> ,1 e ,. '

NPF-73 l 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS I LIOUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each miscellaneous temporary outside radioactive liquid storage tank shall be limited to less than or equal to 10 curies, excluding l tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above tanks exceeding the above limit, immediately 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, and

b. Submit a Special Report to the Commission within 30 days pursuant to Specification 6.9.2 and include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4.1 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank. ;

l l

BEAVER VALLEY - UNIT 2 3/4 11-2 Amendment No. I

I l

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. v;? l NPF-73 l l

6 l-l

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1 Specifications 3.11.2.1 through 3.11.2.4 l have been moved to the OFFSITE DOSE :

CALCULATION MANUAL. !

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BEAVER VALLEY - UNIT 2 3/4 11-3 Amendment-No. l j

J vf' l

NPF-73 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS l l GASEOUS WASTE STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.5 The quantity of radioactivity contained in any connected group of gaseous waste storage tanks shall be limited to less than or equal to 19,000 curies noble gases (considered as i Xe-133).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any connected group of gaseous waste storage tanks exceeding the above l limit, immediately suspend all additions of radioactive material to the tanks and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tanks' contents to within the limit, and

b. Submit a Special Report to the Commission within 30 days pursuant to Specification 6.9.2 and include a schedule and a description of activities planned and/or taken to reduce the contents to within the specified limits.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 The quantity of radioactive material contained in any connected group of gaseous waste storage tanks shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tanks.

J BEAVER VALLEY - UNIT 2 3/4 11-4 Amendment No. I

,1 Y*

f NPF-73 RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume l whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY: At all times ACTION:

a. With the concentration of oxygen in the waste gas holdup system greater than 2% by volume but less than or equal to I 4% by volume, immediately suspend all additions of waste gases to the gaseous waste decay tank and reduce the concentration of oxygen to less than or equal to 2% within l 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b. With the concentration of oxygen in the waste gas holdup system greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the affected tank and reduce the concentration of oxygen to less than or equal to 4% by volume, then take action a, above.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS l

l 4.11.2.6.1 The concentrations of oxygen in the waste gas holdup i system shall be determined to be within the above limits by I continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.11 or monitoring in conjunction with its I associated action statement.

l l

BEAVER VALLEY - UNIT 2 3/4 11-5 Amendment No. l

,e y y ,,

NPF-73 l

i specification 3.11.3.1 has been moved ,

to the PROCESS CONTROL PROGRAM.

Specification 3.11.4.1.has been moved i to the OFFSITE DOSE CALCULATION MANUAL.

e

}

BEAVER VALLEY - UNIT 2 3/4 11-6 Amendment No.

- - _ . ~ . - . . -

7._

'F-j ft NPF-73 i

Specifications 3.12.1 through 3.12.3 have been moved to the OFFSITE DOSE CALCULATION MANUAL.

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BEAVER VALLEY - UNIT 2 3/4 12-1 Amendment 1:o.

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NPF-73 INSTRUMENTATION BASES 3/4.3.3.8 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant l parameters to monitor and assess these variables during and following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

3/4.3.3.11 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the waste gas 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.

3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially 1 damaging missiles which could impact and damage safety related components, equipment or structures. ,

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l BEAVER VALLEY - UNIT 2 B 3/4 3-6 Amendment No.

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,* / 6' NPF-73 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIOUID EFFLUENTS l

3/4.11.1.4 LIOUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table 2, Column 2, at the nearest potable water supply ,

and the nearest surface water supply in an unrestricted area. l l

3/4.11.2 GASEOUS EFFLUENTS I

3/4.11.2.5 GASEOUS WASTE STORAGE TANKS Restricting the quantity of radioactivity contained in any connected group of gaseous waste storage tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting total body exposure to an individual located at the nearest exclusion area boundary for two hours immediately following the onset of the release will not exceed 0.5 rem. The specified limit restricting the quantity of radioactivity contained in any connected group of gaseous waste storage tanks was specified to ensure that the total body exposure resulting from the postulated release remained a suitable fraction of the reference value set forth in 10 CFR 100.11(a) (1) . The curie content limit is applied individually to each gaseous waste storage tank and collectively to the number of unisolated gaseous waste storage tanks.

3/4.11.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Isolation of the affected tank for purposes of purging and/or discharge permits the flammable gas concentrations of the tank to be reduced below the lower explosive limit in a hydrogen rich system. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

BEAVER VALLEY - UNIT 2 B 3/4 11-1 Amendment No.

- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ l

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NPF-73 ADMINISTRATIVE CONTROLS l

PROCEDURES (Continued) 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

b. The change is approved by two (2) members of the plant management staff, at least one (1) of whom holds a Senior Reactor Operator's License on the unit affected.

c. The change is documented, reviewed by the OSC and approved by the General Manager . Nuclear Operations,- predesignated alternate or a predesignated Manager to whom the General Manager Nuclear Operations has- assigned in writing the responsibility for review and approval of specific subjects, within 14 days of implementation.

6.8.4 A Post-Accident monitoring program shall be established, .

implemented, and maintained. The program will provide the capability to obtain and analyze reactor coolant, radioactive iodines- and particulates in plant gaseous effluents, and containment atmosphere samples following an accident. The program shall include the following:

(i) Training of personnel, (ii) Procedures for sampling and analysis, and (iii) Provisions for maintenance of sampling and analysis equipment.

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6.8.5 A program for monitoring of secondary water chemistry to I

inhibit steam generator tube degradation shall be implemented. This program shall be described in the station chemistry manual and shall include:

l l a. Identification of a sampling schedule for the critical I parameters and control points for these parameters;

b. Identification of the procedures used to measure the values of the critical parameters;

c. Identification for process sampling points;

d. Procedures for the recording and management of data;

e. Procedures defining corrective actions for off control point chemistry conditions; and I

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BEAVER VALLEY - UNIT 2 6-13 Amendment No. )

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l NPF-73 ADMINISTRATIVE CONTROL 3 PROCEDURES (Continued)

f. A procedure identifying:

1

1) the authority responsible for the interpretation of the l data, and l

2) the sequence and timing of administrative events ;

required to initiate corrective action. j i'

6.8.6 The following programs chall be established, implemented, and maintained ,

a.~ Radioactive Effluent Control Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the !

doses to MEMBERS OF THE PUBLIC from radioactive affluents as low as_ reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures,. and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program l shall include the following elements. ;

1) Limitations on the operability of radioactive liquid and ,

gaseous monitoring -instrumentation including surveillance tests and setpoint determination in .,

accordance with the methodology in the ODCM, j

2) Limitations on the concentrations of . radioactive material released in liquid affluents to UNRESTRICTED j AREAS conforming to 10 CFR Part 20, Appendix B,. Table 2, i Column 2, 1

3) Monitoring, sampling, and analysis of radioactive liquid !

and gaseous effluents in accordance with 10 CFR 20.106 !

or 10 CFR 20.1302, as appropriate, and with the i methodology and parameters in the ODCM, I

4) Limitations on the annual and quarterly doses or dose i commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid affluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, j l

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1 BEAVER VALLEY - UNIT 2 6-14 Amendment No.

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NPF-73 ADMINISTRATIVE CONTROLS PROCEDURES (Continuedl

5) Determination of cumulative and projected dose contributions from radioactive effluents for the current

! calendar quarter and current calendar year in accordance l with the methodology and parameters in the ODCM at least j l every 31 days, I l 6) Limitations on the operability and use of the liquid and l

gaseous effluent treatment systems to ensure that the

! appropriate portions of these systems are used to reduce I

releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,

7) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table 2, Column 1,

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8) Limitations on the annual and quarterly air doses l resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY f conforming to Appendix I to 10 CFR Part 50, I'

9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, ,

tritium, and all radionuclides in particulate form with '

half-lives greater than 8 days in gaseous effluents ;

released from each unit to areas beyond the SITE I BOUNDARY conforming to Appendix I to 10 CFR Part 50, j l

10) Limitations on the annual dose or dose commitment to any i MEMBER OF THE PUBLIC due to releases of radioactivity !

and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

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BEAVER VALLEY - UNIT 2 6-15 Amendment No.

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NPF-73.

ADMINISTRATIVE CONTROLS PROCEDURES (Continued)

b. Radioloalcal Environmental Monitorina Procram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall . provide (1) . -representative measurements of radioactivity in the highest potential. exposure pathways, and (2) verification of the accuracy of the affluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,

2) A Land Use Consus to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and

3) Participation in an Interlaboratory Comparison Program 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.

6.9 REM ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, code of Federal Regulations, the following reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk.

STARTUP REPORTS 6.9.1.1 A summary report of plant startup and power escalation testing will be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel'that has a different design or had been manufactured by a different fuel supplier,. and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

BEAVER VALLEY - UNIT 2 6-16 Amendment No. l

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NPF-73 ADMINISTRATIVE CONTROLS STARTUP REPORTS (Continued) 6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details requested in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operations, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS II) 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. l 6.9.1.5 Reports required on an annual basis shall include:

a. A tabulation of the number of station, utility, and other personnel (including contractors) receiving exposure greater than 100 mrem /yr and their associate exposure according to (e.g., reactor work and job functions 2) man-rem operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling). The dose assignments to various duty functions may be estimated based on pocket j i

(1) A single submittal may be made for a multiple unit site. The I submittal should combine those sections that are common to all units at the site.

(2) This tabulation supplements the requirements of Section ;

20.2206 of 10 CFR Part 20. j i

BEAVER VALLEY - UNIT 2 6-17 Amendment No. l l l

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NPF-73 ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

b. Documentation of all challenges to the pressurizer power operated relief valves (PORVS) or pressurizer safety valves.

c. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8.

The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other l radioiodine isotope concentration in microcuries per gram as l a function of time for the duration of the specific activity L above the steady-state level; and (5) The time duration when.

the specific activity of the primary coolant exceeded the radioiodine limit.

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

6.9.1.7 This item intentionally blank 6.9.1.8 This item intentionally blank 6.9.1.9 This item intentionally blank BEAVER VALLEY - UNIT 2 6-18 Amendment No. I w _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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NPF-73 ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (3) 6.9.1.10 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (4)

The Annual Radioactive Effluent Release Report covering

~

6.9.1.11 the operation of the unit during the previous 12 months of operation shall be submitted before April 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

CORE OPERATING LIMITS REPORT 6.9.1.12 Core operating limits shall be established and I documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

1. WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY", July 1985 (Westinghouse Proprietary).

Methodology applied for the following Specifications:

3.1.3.5, Shutdown Rod Insertion Limits 3.1.3.6, Control Rod Insertion Limits 3.2.1, Axial Flux Difference-Constant Axial Offset Control 3.2.2, Heat Flux Hot Channel Factor-Fg(Z) 3.2.3, Nuclear Enthalpy Rise Hot Channel Factor-FN delta H I

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(3) A single submittal may be made for a multi-unit station.

(4) A single submittal may be made for a multi-unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

6 BEAVER VALLEY - UNIT 2 6-19 Amendment No.

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'NPF-73 ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)

2. WCAP-9220-P-A, Rev. 1, " WESTINGHOUSE ECCS EVALUATION MODEL-1981 VERSION", February 1982 (Westinghouse Proprietary). Methodology applied for the following Specification: 3.2.2, Heat Flux Hot Channel Factor-Fg(Z).

3. WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES -

TOPICAL REPORT", September 1974 (Westinghouse Proprietary). Methodology applied for the following Spanification; 3.2.1, Axial Flux Difference-Constant Axial Off at Control.

4. T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC) January 31, 1980 --

Attachment:

Operation and Safety Analysis Aspects of an Improved Load Follow Package.

Methodology applied for the following Specification: 3.2.1, Axial Flux Difference-Constant Axial Offset Control.

5. NUREG-0800, Standard Review Plan, U.S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981. Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control-(CAOC), Rev. 2, July 1981. Methodology applied for the following Specification: 3.2.1, Axial Flux Difference-Constant Axial Offset Control.

The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

BEAVER VALLEY - UNIT 2 6-20 Amendment No. l

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NPF-73 .

ADMINISTRATIVE CONTROLS SPECIAL REPORTS (Continued)

c. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

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d. Seismic event analysis, Specification 4.3.3.3.2.

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e. Sealed source leakage in excess of limits, Specification 4.7.9.1.3. l

f. Miscellaneous reporting requirements specified in the ACTION {

Statements for Appendix C of the ODCM. l 4

g. Containment Inspection Report, Specification 4.6.1.6.2.

h. Steam generator tube inservice inspection, Specification f 4.4.5.5.

1. Inoperable accident monitoring, Specification 3.3.3.8.

j. Liquid Hold-Up Tanka, Specification 3.11.1.4. ,

k. Gas Storage Tanks, Specification 3.11.2.5. +

1. Explosive Gas Monitoring Instrumentation, Specification ,

3.3.3.11.

6.10 RECORD RETENTION 6.10.1 The following records shall be retained for.at least five (5) ;

years;

a. Records and logs of facility operation covering time interval at each power level.

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b. Records and logs of principal maintenance activities, i inspections, repair and replacement of principal items of equipment related to nuclear safety.

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c. All REPORTABLE EVENTS. 1 l

d. Records of surveillance activities, inspections and ;

calibrations required by these Technical Specifications. '

e. Records of reactor tests and experiments.

i BEAVER VALLEY - UNIT 2 6-21 Amendment No. l l

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NPF-73 ADMINISTRATIVE CONTROLS ;

RECORD RETENTION (Continued) !

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f. Records of changes made to Operating Procedures.

g. Records of radioactive shipments.

h. Records of sealed source leak tests and results. -

i. Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Facility Operating License:

I a. Records and drawing changes reflecting facility design !

modifications made to systems and equipment described in the Final Safety Analysis Report.

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b. Records of new irradiated fuel inventory, fuel transfers and assembly burnup. histories.

c. Records of facility radiation and contamination surveys.

d. Records of radiation exposure for all individuals entering radiation control areas.

e. _ Records of gaseous and liquid radioactive material released to the environs.

f. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.

g. Records of training and qualification for current members of the plant staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the QA Manual.

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the OSC and the ORC. .

1 BEAVER VALLEY - UNIT 2 6-22 Amendment No. l l

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> l- D' NPF-73 l ADMINISTRATIVE CONTROLS I RECORD RETENTION (Continued)

1. Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance I records.

m. Records of analyses required by the Radiological Environmental Monitoring Program.

n. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.1601 of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area andentrancetheretoshall(gpcontrolledbyrequiring issuance of a Radiological Work Permit i or Radiological Access I Control Permit. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

(1) Health physics personnel, or personnel escorted by health l physics personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

BEAVER VALLEY - UNIT 2 6-23 Amendment No. l

l. n' NPF-73 ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.

This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by a facility health physics supervisor in the Radiological Work Permit or Radiological Access Control Permit.

6.12.2 The requirements of 6.12.1, above, also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or a facility health physics supervisor.

6.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.n. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b. Shall become effective after review and acceptance by the OSC and the approval of the General Manager Nuclear Operations, predesignated alternate or a predesignated Manager to whom the General Manager Nuclear Operations has assigned in writing the responsibility for review and approval of specific subjects.

I BEAVER VALLEY - UNIT 2 6-24 Amendment No. l I J

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NPF-73 ADMINISTRATIVE CONTROLS 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.n. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the OSC and the approval of the General Manager Nuclear Operations, predesignated alternate or a predesignated Manager to whom the General Manager Nuclear Operations has assigned in writing the responsibility for review and approval of specific subjects.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was )

implemented.

l 6.16 Moved to the PROCESS CONTROL PROGRAM.

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l BEAVER VALLEY - UNIT 2 6-25 Amendment No. l l

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ML20084F260

Text

Attachment:

Attachment:

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