Text

Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301
	ML20086B301
Person / Time
Site:	Beaver Valley
Issue date:	06/12/1995
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co
Shared Package
ML20086B306	List: ML20086B309; NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301;
References
	RTR-NUREG-1301, GL-89-001, DPR-66-A-188, NPF-73-A-070 NUDOCS 9507050286
	Download: ML20086B301 (108)
	v • d • e

{{#Wiki_filter:I cP* "O, -4 UNITED STATES i S NUCLEAR REGULATORY COMMISSION f WASHINGTON, D.C. 2066Hm01 %,...../ DUOVESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.188 License No. DPR-66 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment by Duquesne Light Company, et al. (the licensee) dated June 17, 1993, as supplemented October 20, 1993,.and May 23, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (i) that the activities authorized l by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. l 1 9507050286 950612 PDR ADOCK 05000334 P PDR i

t i 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows: j (2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 188, are hereby incorporated in the license. 1 The licensee shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective as of the date. of its issuance, to be implemented within 60 days. FOR THE NUCLEAR REGULATORY COMMISSION GA R% ps John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l Date of Issuance: June 12, 1995 i 1 6 r 1 l

ATTACHMENT TO LICENSE AMENDMENT NO.188 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET N0. 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 I thru XXVI I thru XXI 1-6 1-6 1-7 1-7 3/4 3-53 3/4 3-53 3/4 3-54 3/4 3-54 3/4 3-55 3/4 3-55 3/4 3-56 3/4 3-56 3/4 3-57 3/4 3-57 3/4 3-57a 3/4 3-58 3/4 3-58 3/4 3-59 3/4 3-60 3/4 3-61 3/4 3-62 3/4 3-63 3/4 3-64 3/4 3-65 3/4 3-66 3/4 3-67 3/4 3-68 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 3/4 11-3 3/4 11-3 3/4 11-4 3/4 11-4 3/4 11-5 3/4 11-5 3/4 ll-Sa 3/4 11-6 3/4 11-6 3/4 11-7 3/4 11-8 3/4 11-10 3/4 11-11 3/4 11-12 3/4 11-13 3/4 11-14 3/4 11-15 3/4 11-16 3/4 11-18 l l ATTACHMENT TO LICENSE AMENDMENT NO.188 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A Technical Specifications, with the i enclosed pages as: indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. Remove Insert 3/4 11-20 3/4 11-21 3/4 11-22 3/4 11-23 3/4 12-1 3/4 12-1 3/4 12-2 3/4 12-3 3/4 12-4 3/4 12-5 3/4 12-6 3/4 12-7 3/4 12-8 3/4 12-9 3/4 12-10 3/4 12-11 3/4 12-12 B 3/4 3-4 B 3/4 3-4 8 3/4 11-1 B 3/4 11-1 B 3/4 11-2 B 3/4 11-3 B 3/4 11-4 B 3/4 11-5 B 3/4 11-6 B 3/4 12-1 6-13a 6-14 6-14 6-15 6-15 6-16 6-20 6-17 6-21 6-18 6-22 6-19 6-22a 6-20 6-23 6-21 6-24 6-22 6-25 6-23 6-27 6-24 6-28 6-25 6-29 6-30 6-31

4 / / DE bPR-66: INDEX DEFINITIONS 'k SECTION PAGE I I 1.0 DEFINITIONS t Defined. Terms. 1-1 Thermal Power. 1-1 l i Rated Thermal, Power.. 1 j f operational' Mode' 1-1 f f Action 1-1 i operable - operability 1-l' Reportable Event 1-2-- Containment Integrity. 1 1 1 Channel Calibration. 1-2 i Channel Check. 1-2 { i Channel Functional Test. 1-3 I ~ Core'Alterat1on'. 1-3 3 [ Shutdown Margin. 1-3 Leakage. 1-3 Quadrant Power Tilt Ratio. 1-4 ] f Dose Equivalent I-131'. 1-4 ( Staggered Test Basis 1-4 l t 'i Frequency Notation 1-4 -{ Reactor Trip System Response Time. 1-5 t i Engineered Safety Feature Response Time. 1-5 l i Axial' Flux Difference. 1-5 Physics Tests. 1-5 I i o -E-Average Disintegration Energy. 1-5 BEAVER VALLEY - UNIT 1 I Amendment No.188 i i

DPR-66 INDEX DEFINITIONS SECTION PAGE Source Check. 1-6 Process Control Program. 1-6 Offsite Dose Calculation Manual (ODCM). 1-6 Gaseous Radwa'ste 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 Core Operating Limits Report. 1-8 'l Operational Modes (Table 1.1) 1-9 Frequency Notation (Table 1.2). ,1-10 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 Reactor Core. 2-1 2.1.2 Reactor Coolant System Pressure. 2-1 1 l 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 Reactor Trip System Instrumentation Setpoints. 2-5 i BASES SECTION PAGE 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.188 i

DPR-66 INDEX BASES SECTION PAGE 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 Reactor Trip Setpoints. B 2-3 LIMITING CONDITIO,NS FOR OPERATION AND SURVEILLANCE REQUIREMENTS' ~ SECTION PAGE 3/4.0 APPLICABILITY. 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS I 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 - Tavg $ 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 i 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 Acid 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 t 3/4.1.3.2 Position Indication Systems - Operating 3/4 1-20 BEAVER VALLEY - UNIT 1 III Amendment No.188 c

DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTIOH 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.188

.] DPR-66 i INDEX j LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS r SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS i 3/4.4.1.1 Normal Operation. 3/4 4-1 i 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 i 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 Irstrumentation. 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 4-1Aa 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 Compenents. 3/4 4-28 3/4.4.11 RELIEF VALVES 3/4 4-29 i 3/4.4.12 REACTOR COOLANT SYSTEM VENTS, 3/4 4-32 BEAVER VALLEY - UNIT 1 V Amendment No.188

DPR-66 INDEX i . LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS. 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T 2 350*F. 3/4 5-3 avg 3/4.5.3 ECdS SUBSYSTEMS - Tavg < 350*F. 3/4 5-6 3/4.5.4 BORON INJECTION SYSTEM 3/4.5.4.1.1 Boron Injection Tank A 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 i 3/4.6 CONTAINMENT SYSTEMS i 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 6-5 P 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 6-10 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 Containment Quench Spray System. 3/4 6-11 3/4.6.2.2 Containment Recirculation Spray System. 3/4 6-13 3/4.6.2.3 Chemical Addition System. 3/4 6 15 I 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.138

k DPR INDEX LIMITING CONDITIONS'FOR OPERATION AND SURVEILLANCE REQUIREMENTS i SECTION PAGE l 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE' t 3/4.7.1.1 Safety Valves. 3/4 7-1 l 3/4.7.1.2 Au$111ary Feedwater System. 3/4 7-5 i 3/4.7.1.3 Primary Plant Demineralized Water (PPDW). 3/4 7-7 3/4.7.1.4 Activity. 3/4 7-8 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 [ -t 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS 3/4 7-16 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND 3/4 7-19 RELEASE SYSTEM............... 3/4.7.9 SEALED SOURCE CONTAMINATION. 3/4 7-22 3/4.7.12 SNUBBERS. 3/4 7-26 3/4.7.13 AUXILIARY RIVER WATER SYSTEM. 3/4 7-34 1 I 3/4.8 ELECTRICAL POWER SYSTEMS 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 8-5 c i BEAVER VALLEY - UNIT 1 VII Amendment No.188

4 DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 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.d. Distribution - Operating. 3/4 8-8 3/4.8.2.4 D.C. Distribution - Shutdown. 3/4 8-10 3/4.9 REFUELING OPERATIONS ,/4 9-1 3/4.9.1 BORON CONCENTRATION. 3 3/4.9.2 INSTRUMENTATION. 3/4 9-2 3/4.9.3 DECAY TIME. 3/4 9-3 3/4.9.4 CONTAINMENT DUILDING 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-Ba 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 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.188

r DPR-66 INDEX LIMITING CONDITIONS FOR OPERATION AND' SURVEILLANCE REQUIREMENTS SECTION 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 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 BEAVER VALLEY - UNIT 1 IX Amendment No.188

DPR-66 INDEX e i BASES SECTION PAGE 3/4.2.2-AND 3/4.2.3 HEAT FLUX AND NUCLEAR. ENTHALPY HOT CHANNEL FACTORS B:3/4 2-4 3/4.2.4 QUADRANT POWER TILT RATIO. B 3/4 2-5 3/4.2.5 DNB PARAMETERS B 3/4 2-6 f 3-3/4.3 INSTRUMENTATION 3/4.3.1 AND 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF) INSTRUMENTATION. B 3/4 3-1 j 3/4.3.3 MONITORING INSTRUMENTATION B 3/4L3-2 B 3/4 3-2 i 3/4.3.3.1 Radiation Monitoring Instrumentation 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 1 3/4.3.3.7 Chlorine Detection Systems B 3/4 3-3 j 3/4.3.3.8 Accident Monitoring Instrumentation. B 3/4 3-3 3/4.3.3.11 Explosive Gas Monitoring Instrumentation. B 3/4 3-4 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS. B 3/4 4-1 3/4.4.2 AND 3/4.4.3 SAFETY VALVES. B 3/4 4-la 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..... 1 3/4.4.6.1 Leakage Detection Instrumentation. E 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.188 a a

,---,---------s

J i DPR-66 i INDEX BASES SECTION PAGE 3/4.4.8 SPECIFIC ACTIVITY. B 3/4 4-4 [ 3/4.4.9 PRESSURE / TEMPERATURE LIMITS. B 3/4 4-5 1 -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 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) l 3/4.5.1 ACCUMULATORS B 3/4 5-1 1 3/4.5.2 AND 3/4.5.3 ECCS SUBSYSTEMS B 3/4 5-1 I 3/4.5.4 BORON INJECTION SYSTEM B 3/4'5-2 l 3/4.5.5 SEAL INJECTION FLOW. B 3/4 5-3 3/4.6 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 3/4.6.2 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.188 l

..e .~ .i ' DPR-66 INDEX

BASES SECTION PAGE i

3/4.7 PLANT SYSTEMS 3/4.7.1' TURBINE CYCLE 3/4.7.1.1 Safety Valves. .~. B 3/417-1 I 3/4.7.1.2 Auxiliary Feedwater' Pumps. B 3/4 7-2 3/4.7.1.3 Primary Plant. Demineralized Water. B 3/4 7-2 i 3/4.7.1.4 . Activity B 3/4 7-3 ) - 3 / 4. 7.1. 5. Main Steam Line Isolation Valves B 3/4 7 l 3/4.7.2 STEAM. GENERATOR PRESSURE / TEMPERATURE f LIMITATION B 3/4 7-4 l 3/4.7.3 COMPONENT COOLING WATER SYSTEM B 3/4 7-4 l ^' 3/4.7.4 RIVER-WATER SYSTEM 'B 3/4 7-4 i 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 .i 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND -RELEASE SYSTEM B 3/4 7-5 j 3/4.7.9 SEALED SOURCE CONTAMINATION.. B 3/4 7-5' i 3/4.7.12-SNUBBERS B 3/4-7-6 3/4.7.13 AUXILIARY RIVER WATER SYSTEM B 3/4 7-7 l l i 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 AND 3/4.8.2 A.C.

SOURCES, D.C.

SOURCES AND l ONSITE POWER DISTRIBUTION SYSTEMS B 3/4 8-1 l 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. '88

= p,.3&; ? -DPR-66' INDEX r . BASES.- SEC'1 ION RAgg 0 ' 3 /4. 9. 3.~ DECAY TIME ...._.:........ _...... B 3/4 9-1 s ."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_ g h-3/4.9.7 CRANE TRAVEL SPENT FUEL' STORAGE' L BUILDING B 3/4'9-2 p f 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.. B 3/4 9-2 L 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION B 3/4 9-3 l SYSTEM 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 VENTIIJTION 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 l. SYSTEMS B 3/4 9-5 1 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 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 l~ 3/4.10.5 NO FLOW TESTS B 3/4 10-1 _3_f_4.,_11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.4 Liquid Holdup Tanks. B 3/4 11-1 I BEAVER VALLEY - UNIT 1 XIII Amendment No. 188 L- _ _j

~lgYb. ?* : 'i 2 - E l 'DPR-66: INDEX 4 i G, BASES-1 SECTION PAGE i i l3 / 4.11. 2. GASEOUS EFFLUENTS. l 3/4.11.2.5. Gas Storage Tanks. B 3/4 11-1 l 3/4.11.2.6 Explosive Gas Mixture. B 3/4 11-1 !'i DESIGN FEATURES SECTION PAGE l 5.1 SITE l 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 l i 5.1.4 Low Population Zone. 5-1 i i i 5.1.5 Flood Control. 5 ; 5.2 CONTAINMENT i l 5.2.1 Configuration. 5-1 5.2.2 Design Pressure and Temperature. 5-4 j 5.2.3 Penetrations. 5-4 l t 5.3 REACTOR CORE I 5.3.1 Fuel Assemblies. 5-4 5.3.2 Control Rod Assemblies.. 5-4

5. 4 ' REACTOR COOLANT SYSTEM i

5.4.1 Design Pressure and Temperature. 5-5 5.4.2 Volume. 5-5 i i .i BEAVER VALLEY - UNIT 1 XIV Amendment No.188 f ~.,. +, ~. ...I

ja a DPR-66 INDEX

DESIGN FEATURES SECTION PAGE 5.5 EMERGENCY CORE COOLING SYSTEMS 5-5' l

t .5.6 FUEL STORAGE 5.6.1 Criticality. 5-5 1 t y 5.6.2 Drainage. 5-5 I 5.6.3 Capacity.. 5-6 5.7 SEISMIC CLASSIFICATION 5-6 i 5.8 METEOROLOGICAL TOWER LQCATION. 5-6 i I i ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY, 6-1 j 6.2 ORGANIZATION 6.2.1 Onsite and Offsite Organizations. 6-1 'l 6.2.2 Unit Staff. 6-2 i i 1c3 FACILITY STAFF OUALIFICATIONS. 6-5 6.4 TRAININfg 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 6.5.1.3 Alternates. 6-6 i 6.5.1.4 Meeting Frequency. 6-6 BEAVER VALLEY - UNIT 1 XV Amendment No. 100 f b a

DPR-66 INDEX ADMINISTRATIVE CONTROLS Il .Il l l I I-1 I I I I I SECTIQH PAGE 6.5.1.5 Quorum. 6-6 6.5.1.6 Responsibilities. 6-6 6.5.1.7 Authority. 6-7 6.5.1.8 Records. 6-7 6.5.2 OFFSITE REV1EW 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 1 56 REPORTABLE EVENT ACTION. 6-11 6.7 SAFETY LIMIT VIOLATION 6-11 l i i 6.8 PROCEDURES 6-12 6.9 REPORTING REOUIREMENTS 6-16 6.9.1 Routino Reports. 6-16 6.9.1.1,2,3 Startup Reports. 6-16 6.9.1.4,5 Annual Reports. 6-17 j i 6.9.1.6 Monthly Operating Report. 6-18 BEAVER VALLEY - UNIT 1 XVI Amendment No.188 l i

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 1 ) l l 6.10 RECORD RETENTION. 6-21 l l l l 6.11 RADIATION PROTECTION PROGRAM. 6-22 l l 6.12 HIGH RADIATION AREA 6-23 1 i l l 6.13 PROCESS CONTROL PROGRAM (PCP) 6-24 l 1 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM). 6-24 i 6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS 6-2a I J BEAVER VALLEY - UNIT 1 XVII Amendment No.188

g j?? i 13 y>u- ?DPR-66f' 1 ' ~ ~ P 'l TABLE INDEX -j s ^ TABLE TITLE PAfgg -c I T !2.2 l Reactor Trip System Instrumentation:Tripf 2-6 'l p 'Setpoints 3.1-l' ' Accident. Analyses Requiring. Reevaluation 3/4 1-19a l:~ in the. event of.an Inoperable Pull or. Part' Length Rod l P ! 3.2-1 DNB Parameters 3/4l2-13 i n ,3.3-1

Reactor l Trip' System Instrumentation 3/4'3 'i 0

3.3 Reactor' Trip System Instrumentation '3/4 3-9 Response Times 4.3-1 ReactorfTrip System. Instrumentation 3/4 3-11 Surveillance Requirements 3.3-3 Engineered Safety Features Actuation System 3/4'3-15 ') Instrumentation j P 3.3-4' . Engineered Safety Features Actuation System 3/4 3 l Instrumentation Trip Setpoints 3.3 Engineered Safety Feature Response Times 3/4l3-25 !] 4.3 Engineered Safety Feature Actuation' System 3/4:3-29 Instrumentation Surveillance, Requirements 3.3-6 Radiation Monitoring Instrumentation 3/4 3-34 i 4.3-3 Radiation Monitoring Instrumentation 3/4 3, Surveillance Requirements-i 3.3-7 Seismic Monitoring Instrumentation 3/4 3-39 'I l 4.3-4 Seismic Monitoring Instrumentation '3/4 3-40 g Surveillance Requirements j i 3.3-8 Meteorological Monitoring Instrumentation 3/4 3-42' L 4.3-5 Meteorological Monitoring Instrumentation 3/4.3-43 Surveillance Requirements j 1 3.3-9 Remote Shutdown Panel. Monitoring 3/4 3-45 i Instrumentation l 4.3-6 Remote Shutdown Monitoring Instrumentation 3/4.3-46 i surveillance Requirements j l 1 1 BEAVER VALLEY - UNIT 1 XVIII Amendment No.lSB l 1

w:s Tu " J.?.Q-1JDPR-66 Table Index:-(conti) TABLE II.TJJ PAGE !3.3 Accident' Monitoring Instrumentation 3/4 3-51'. 4.3 Accident. Monitoring Instrumentation 3/4'3-52 Surveillance Requirements b 3.3-13 Explosive Gas Fonitoring' Instrumentation

3/4 3-55

) 4.3-13 . Explosive Gas' Monitoring' Instrumentation. 3/4 3-57 Surveillance 'tequirements -l 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 j l 3.7-1 Maximum Allowable Power Range Neutron Flux 3/4 7-2 High Setpoint With Inoperable Steamline -l l Safety Valves During 3 Loop Operation 3.7-2 Maximum Allowable Power Rangc Neutron Flux 3/4-7-3 High Setpoint with Inoperable Steam Line-l- Safety Valves During 2 Loop operation 3.7-3 Steam Line' Safety Valves Per Loop '3/4 7-4 l l 4.7-1 Snubber Visual Inspection. Interval 3/4 7-31 j 4.7-2 Secondary Coolant System Specific Activity 3/4 7-9 l Sample and Analysis Program i ? 3.8-1 Battery Surveillance Requirements 3/4 8-9a -3.9-1 Beaver Valley Fuel Asserbly Minimum Burnup 3/4 9-15 l vs. Initial U235 Enrichtont For Storage in i Region 2 Spent Fuel Racks ) BEAVER VALLEY - UNIT 1 XIX Amendment No.188 i

y --t.. f ) - DPR-66'. Table'Index (cont.) i TABLE TITLE PAGE l l ~ B'3/4.4-1 Reactor Vessel Toughness Data:(unirradiated) B 3/4 4-7 6.2-1 Minimum Shift Crew Composition 6-4 I e f a i s L i r t T 6 i i i BEAVER VALLEY - UNIT 1 XX Amendment No.1@ i i t .. ~..

I DPR-66 Ficure'Index FIGURE TITLE PAGE 2.1-1 Reactor Core Safety uisit - Three-Loop 2-2 l Operation 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 Va21ey Unit 1 Reactor _ Coolant 3/4 4-24 l

System Heatup Limitations Applicable for the First 16.0 EFPY I 3.4-3 Beaver Valley Unit 1 Reactor Coolant 3/4 4-25 l 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 l 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.188

i DPR-66 DEFINITIONS SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative assessment of channel i response when the channel sensor is exposed to a radioactive source. PROCESS CONTROL PROGRAM i 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 requirements, and other requirements governing the disposal of solid radioactive waste.

1.29 DELETED OFFSITE DOSE CALCULATION MANUAL (ODCM1 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 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 i 1.32 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive i BEAVER VALLEY - UNIT 1 1-6 Amendment No.100

DPR-66 DEFINITIONS material in particulate form in effluents by passing ventilation.or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines 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.

I VENTING l 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 durir.g VENTING. l 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 Hazards Summary Report and evaluated in the staff's Safety Evaluation Report (SER) (e.g., deletion of evaporators and installation of demineralizers; use of fluidized bed calciner/ incineration in place of cement solidification systems); i i P BEAVER VALLEY - UNIT 1 1-7 Amendment No.188 4--- =

~ DPR-66 l 1 t I i Specification 3.3.3.9 has been moved to the OFFSITE' DOSE CALCULATION MANUAL. l Specification 3.3.3.10 has been partially moved to the OFFSITE DOSE CALCULATION MANUAL and the remaining part i renumbered as 3.3.3.11. l t i ii i r i [ 5 i t i I i 7 I t t i BEAVER ALLEY - UNIT 1 3/4 3-53 Amendment No.188 I

DPR-66 INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION 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 I BEAVER VALLEY - UNIT 1 3/4 3-54 Amendment No.188 l

TABLE 3.3-13 DPR-66' EXPLOSIVE GAS MONITORING INSTRUMENTATION 5 MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1. Waste Gas Decay Tanks Monitor a. Oxygen Monitor (2) 31 (0 -AS-GW-110-1,2) 2

- During waste gas decay tank filling operation.

BEAVER VALLEY - UNIT 1 3/4 3-55 Amendment ' No. 188 ~ _.. _. _.,,. - - -.,, _,. - -.,.. _. - _ _.... _.... _ _.

^ c: [ DPR-66 TABLE 3.3-13, (Continued) ACTION STATEMENTS ACTION 27 - (This ACTION-is not used) f i ACTION 28 - (This ACTION is not used) l L! ACTION 29 -' '(This ACTION is not used) E h ' ACTION 30 -- (This ACTION is not used)' ] i ACTION 31 - With the number of channels OPERABLE one less than. required by the Minimum Channels OPERABLE requirement,, i operation of this system may' continue provided grab samples are taken and. analyzed at least once per 24 l hours. With both channels inoperable, operation may continue provided. grab samples are taken and analyzed at_least once per 4 hours during degassing operations and. at .least-once per 24 hours during other-operations. I ACTION 32 - (This ACTION is not used)

l l

i 1 i l l .i l t 5 i 2 o h i BEAVER VALLEY - UNIT 1 3/4 3-56 Amendment No.188 l

.t .s.- ts TABLE 4.3-13 -DPR-66 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL-CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CALIBRATION TEST 1. Waste Gas Decay Tanks Monitor a. Oxygen Monitor D** Q(1) M (0 -AS-GW-110-1,2) 2 During waste gas decay tank filling operation. BEAVER VALLEY - UNIT 1 3/4 3-57 Amendment No.188 [ ~..

l -1 DPR TABLE 4.3-13 1 Continued) TABLE NOTATION (1) The CHANNEL CALIBRATION' shall include the use of standard l i gas samples containing a nominal: 1. One volume percent oxygen, balance nitrogen, and I 2. Four volume percent oxygen, balance nitrogen [ i I f ? i l BEAVER VALLEY - UNIT 1 3/4 3-58 Amendment No.188 -l

i 1 DPR-66I .j i i f t I P i l r Specifications 3.11.1.1 through 3.11.1.3 l have been moved to the OFFSITE DOSE CALCULATION MANUAL. e f L e i L r E t f 4 i i t i 1 i i i l BEAVER VALLEY - UNIT 1 3/4 11-1 Amendment No.188 i 6 i

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) b. BR-TK-6B (Primary Water Storage Tank) c. LW-TK-7A (Steam Generator Drain Tank) 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 suspend all additions of radioactive material to the tank and within 48 hours 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 per 7 days when radioactive materials are being added to least once the tank. BEAVER VALLEY - UNIT 1 3/4 11-2 Amendment No.188 l l

p; y l ij;r ' DPR-66 y; l 1 Specifications 3.11.2.1'through 3.11.2.4 l have been moved to the OFFSITE DOSE. CALCULATION MANUAL. i i f b I T h 1 t I i i i .i t ~ l 1 1 I - BEAVER VALLEY - UNIT 1 3/4 11-3 Amendment No.188

i DPR-66 l RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS-l r GAS STORAGE TANKS l LIMITING CONDITION FOR OPERATION j 3.11.2.5 The quantity of radioactivity contained in each gas storage tank shall.be_ limited to less than or equal to 52,000 curies l noble gases (considered as Xe-133). r . APPLICABILITY: At all times._ ACTION: a. With the quantity'of radioactive. material in any gas storage I tank exceeding the above

limit, immediately suspend all additions of. radioactive material to the tank and within 48 l

hours 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 l 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' hours 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_ j uCi/ml. BEAVER VALLEY - UNIT 1 3/4 11-4 Amendment No.100 l

.5 -__e a ed ,,J 4 m+ .4-4 J 1/ -M4 _9+se4 ->e A h 1 i DPR-66 RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE r 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 td 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 I 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 hours. I b. With the concentration of oxygen in the waste gas holdup 3 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 i 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.188 l ,.~ _

i DPR-66' q i i Specifid:ation 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. I i t r 4 i i f i i f i i i i i f' ? i BEAVER VALLEY - UNIk' 1 3/4 11-6 Amendment No.188 i

73, .i ,c 4 r 1 ' DPR 66: i q .f t i i I i Specifications 3.12.1 through 3.12.3 i have been moved to the OFFSITE DOSE i CALCULATION MANUAL. ? Jj ~l ? a I + r 1.: 'i i aj t l i ) ~-i 'l s ? t 1 BEAVER. VALLEY - UNIT 1 3/4 12-1 Amendment No.188 j . -.. - - ~ - i

DPR 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 mixtures in the waste gas holdup system. The OPERABILITY and use of t'is instrumentation is consistent with the requirements of General h Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. i = i BEAVER VALLEY - UNIT 1 B 3/4 3-4 Amendment No.188

DPR-66 ) 3/4.11 RADIOACTIVE EFFLUENTS i BASES 3/4.11.1 LIQUID EFFLUENTS l l l 3/4.11.1.4 LIOUID HOLDUP TANKS l Restricting the quantity of radioactive material contained in the 1 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. 3/4.11.2 GASEOUS EFFLUENTS I 3/4.11.2.5 GAS STORAGE TANKS l Restricting, the quantity of radioactivity contained in each gas 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 j 0.5 rem. The specified limit restricting the quantity of j 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 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 1 B 3/4 11-1 Amendment No.188 i L Jw -

-DPR-66 ADMINISTRATIVE CONTROLS 6.8.6 The' following programs shall be established, implemented, and maintained: a. Radioactive Effluent Controls Procram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for l maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents 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 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, 2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table 2, Column 2, 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 methodology and parameters in the ODCM, 4)

Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5) Determination of cumulative and projected dose contributions from

adioactive effluents for the.

current calendar quarter and current calendar year in 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 effluent 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.188

l a 'DPR-66' ADMINISTRATIVE CONTROLS i 1 7 )' Limitations on the dose rate resulting1from radio-d . 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 f resulting

from noble-. gases released in gaseous etfluents from each unit ' to. - areas.: beyond the SITE BOUNDARY conforming to Appendix I to 10'CFR Part 50,

.l 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 than1:8-. days in gaseous-effluents released from each unit to areas beyond the-i 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. 1 sources conforming to 40 CFR Part.190. b. -Radioloaical Environmental Monitorina Procram A program -shall be ~ provided to monitor the radiation and-radionuclides 'in the environs of the plant. The program-shall. provide . the highest potential. exposure pathways,. (1) representative measurements of ( radioactivity in and (2)' verification of-the-accuracy of the affluent i monitoring program and modeling.of environmental exposure l pathways.. The program shall (1)'be contained'in the ODCM, (2) conform. to the guidance of Appendix I to 10 CFR Part- -1 50, and (3) include the following: 'l 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 BEAVER VALLEY - UNIT 1 6-15 Amendment No.135 .I ) j ~

\\ DPR-66 ADMINISTRATIVE CONTROLS 3) Participation in an Interlaboratory Comparison Program to ensure that independent checks on the-precision and accuracy of the measurements of radioactive materials i 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 cach 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 l 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. BEAVER VALLEY - UNIT 1 6-16 Amendment No.188 l

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 mram/yr and their associate 2) man-ren exposure according to work and. job functions .(,,9,, reactor operations-and surveillance,Linservice inspection,- routine maintenance, special ' maintenance (describe maintenance), waste processing, and refueling). The-dose assignments to various duty, functions may 1be 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. l 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) i Reactor power history starting 48 hours 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 limit. Each result should (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. l (2) This tabulation supplements the requirements of Section 20.2206: of 10 CFR Part 20. ? BEAVER VALLEY - UNIT 1 6-17 Amendment No.188 l l t

DPR ]

. ADMINISTRATIVE. CONTROLS. c .' ANNUAL REPORTS (Continued) ' include date' and time l of : sampling and the radiciodine concentrations; (3) -Clean-up_ system' flow history starting 48: hours-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 Lwhen 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 DELETED by Amendment No. 84 6.9.1.8 DELETED by Amendment No. 84 6.9.1.9 DELETED by Amendment No. 84 AH]iUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (3)' j 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 i 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. (3) A single submittal may be made for a multi-unit station. BEtNER VALLEY - UNIT 1 6-18 Amendment No.188 l i

DPR-66 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTf4) 6.9.1.11 The Annual Radioactive Effluent Release Report covering 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 documented 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 EVALUATIOh 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 VERSION", February 1982 (Westinghouse Proprietary). Methodology applied for the following Specification: 3.2.2, Heat Flux Hot Channel Factor-FQ(Z) 3. WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES TOPICAL REPORT", September 1974 (Westinghouse Proprietary). Methodology applied for the following Specification: 3.2.1, Axial Flux Difference-Constant Axial Offset Control (4) A single submittal may be made for a multi-unit station. The I 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.

BEAVER VALLEY - UNIT 1 6-19 Amendment No.188 l

I a DPR-66 ADMINIGTRATIVE CONTROLS CORE OPERATING' LIMITS REPORT (Continued) 4. T.

M.. Anderson to K. Kniel~ (Chief of Core Performance Branch,

Attachment:

Operation and Safety j NRC) January 31, 1980 Analysis -Aspects. of an' Improved Load Follow. Package. Methodology applied.for the -following specification: 3.2.1, i Axial Flux Difference-Constant Axial Offset Control l -+ I Standard ' Review

Plan, U. S. Nuclear Regulatory 5.

NUREG-0800,.Section 4.3, Nuclear

Design, July' 1981.

Branch l Commission, Technical Position CPB 4.3-1, Westinghouse Constant Axial l Offset Control (CAOC), Rev. 2, July 1981. Methodology applied j for .the following Specification: 3.2.1, Axial -Flux 1 Difference-Constant Axial Offset Control l The core operating limits shall be determined so.that all applicable i 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, l

for each reload cycle, to the NRC Document Control Desk. l SPECIAL REPORTS .I i 6.9.2 Special reports shall' be submitted to the U. S. Nuclear ] Regulatory Commission, Document Control Desk, within the time period -l specified for each report. These reports shall be submitted i' 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. I b. Inoperable seismic Monitoring Instrumentation, specification 3.3.3.3. t c. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4. i d. Seismic event analysis, Specification 4.3.3.3.2. e. Sealed source leakage in excess of limits, Specification ~ l 4.7.9.1.3. i I

f..

Miscellaneous reporting requirements' specified in the l Action Statements for Appendix C of the ODCM. l l t g. Containment Inspection Report, Specification 4.6.1.6.2. f BEAVER VALLEY - UNIT 1 6-20 Amendment No.183' l f 1 1 a

DPR-66 ADMINISTRATIVE CONTROLS SPECIAL REPORTS (Continued) 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 l 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. i 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. j d. Records-of surveillance activities, inspections and calibrations required by thews Technical Specifications. e. Records of reactor tests an! expnrihants. f. Records of changes made to Operating Procedures. i g. Records of radioactive shipments. i i h. Records of scaled 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: j a. Records and drawing changes reflecting facility design modifications made to systems and equipment described in t he Final Safety Analysis Report. BEAVER VALLEY - UNIT 1 6-21 Amendment No.100 l

p' - N DPR-66 . ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) .b. Records of: new irradiated fuel' inventory, fuel transfers and assemblyfburnup histories, j 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 mater'ial. released' to the environs. f. Records of transient ~ or operational cycles for_ those i facility components designed for a limited number -of' transients or cycles, g. Records of training and qualification for current members f.. of the. plant staff. h. Records of in-service inspections ' performed' pursuant to_ l these Technical Specifications. t 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. l to 10 CFR 50.59.'- k. Records of meetings-of.the OSC and the ORC. 1. Records of the service lives of 'all-hydraulic and l mechanical snubbers including the date at which the service life commences and associated installation and. maintenance records. 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. q 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.

BEAVER VALLEY - UNIT 1 6-22 Amendment No.188 l

DPR-66 ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or "al. arm 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 pos?.ed as a high radiation areaandentrancetheretoshallgg)controlledbyrequiring issuance of a Radiological Work Permit or Radiolr gical Access l Control Permit. Any individual or group of individuel t 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. i 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 l who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing i positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by a facility health physics supervisor l 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 l

maintained under the administrative control of the Shift Supervisor on duty and/or a facility health physics supervisor. l i (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. 88 BEAVER VALLEY - UNIT 1 6-23 Amendment No.1

DPR-66 ADMINISTRATIVE' CONTROLS' 6.13 PROCESS CONTROL PROGRAM (PCP) Changes 1to the PCP: F a.: 'Shall bei documented land 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 evaluationsL ' justifying the change (s) and 2) A' determination that the change will maintain that 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. l BEAVER VALLEY - UNIT 1 6-24 Amendment No.188

ll 'DPR-66 ADMINISTRATIVE CONTROLS <C OFFSITE DOSE CALCULATION MANUAL (ODCM) (Continued)- ~! c. -Shall-be submitted to the. Commission in the fcnan of a' [

complete, legible copy of the entire.ODCM as a part of or

'I 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 tho' affected - pages, clearly indicating -the area of the_page that was changed, and shall indicate. the date (e.g., month / year) the change was j irolemented. 6.16 Moved to the PROCESS CONTROL PROGRAM. t e i i i i I i t i l l I t i BEAVER VALLEY - UNIT 1 6-25 Amendment No.188 l [ i

+ s M E:vq p UNITED STATES 2 S NUCLEAR REGULATORY COMMISSION 3 WASHINGTON, D.C. 20666 4 001 \\, / DUQUESNE LIGHT COMPANY i OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY I THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 70 License No. NPF-73 i 1 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Duquesne Light Company, et al. (the i licensee) dated June 17, 1993, as supplemelited October 20, 1993, and May 23, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I-i B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. N

4; i. l 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, i and paragraph 2.C.(2) of Facility Operating License No. NPF-73 is hereby amended to read as follows: (2) Technical Soecifications The Tech'nical Specifications contained in Appendix A, as revised through Amendment No. 70, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLCO shall operate the facility t in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This license amendment is effective as of the date of its issuance, to be implemented within 60 days. FOR THE NUCLEAR REGULATORY COMMISSION l i udlw 9g John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i Attachment. Changes to the Technical j Specifications Date of Issuance: June 12, 1995 h" l 1

ATTACHMENT TO LICENSE AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 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. l Remove Insert I thru XVII I thru XVI l-5 1-5 1-6 1-6 l-7 1-7 1-8 1-8 3/4 3-60 3/4 3-60 3/4 3-61 3/4 3-61 3/4 3-62 3/4 3-62 3/4 3-63 3/4 3-63 i 3/4 3-64 3/4 3-64 3/4 3-65 3/4 3-65 3/4 3-66 3/4 3-66 3/4 3-67 3/4 3-67 3/4 3-68 3/4 3-69 3/4 3-70 3/4 3-71 3/4 3-72 3/4 3-73 3/4 3-74 3/4 3-75 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 3/4 11-3 3/4 11-3 3/4 11-4 3/4 11-4 [ 3/4 11-5 3/4 11-5 3/4 11-6 3/4 11-6 3/4 11-7 3/4 11-8 3/4 11-9 3/4 11-10 ) 3/4 11-11 3/4 11-12 3/4 11-13 3/4 11-14 3/4 11-15 3/4 11-16 4 I i

i i ATTACHMENT TO LICENSE AMENDMENT NO. 70 FACILITY OPERATING LICENSE NO. NPF-73 [ DOCKET NO. 50-412 I ' Replace the following pages of Appendix A, Technical Specifications, with the i enclosed pages as. indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. Remove Insert 3/4 11-17 3/4 11-18 3/4 11-19 3/4 12-1 3/4 12-1 3/4 12-2 ( 3/4 12-3 3/4 12-4 1 3/4 12-5 i 3/4 12-6 3/4 12-7 3/4 12-8 I 3/4 12-9 3/4 12-10 B 3/4 3-6 B 3/4 3-6 j B 3/4 11-1 B 3/4 11-1 B 3/4 11-2 B 3/4 11-3 B 3/4 11-4 B 3/4 11-5 l B 3/4 12-1 6-13 6-13 6-14 6-14 6-15 6-15 -l 6-16 6 ' 6-17 6-17 i 6-18 6-18 i 6-18a 6-19 6-19 6-20 6-20 6-21 6-21 6-22 6-22 6-23 6-23 6-24 6-24 6-25 i i i

u )

'NPF-73 s

INDEX .l

DEFINITIONS SECTION PAGE

.l 1 - 1'. 0 DEFINITIONS, 1-1 ,1.1 DEFINED TERMS f 1.2 THERMAL POWER. 1......... -.......,..... 1.'3 RATED' THERMAL POWER. 1-1 e 1.4 OPERATIONAL MODE 1-1 i 1.5: ACTION 1 1 1-1, i

1.6 OPERABLE - OPERABILITY 1

1-1 l 1.7 REPORTABLE EVENT f 1.8 CONTAINMENT INTEGRITY. 1 ! f ? 1.9 CHANNEL CALIBRATION... 1-2 1.10 CHANNEL CHECK 1-2 j ii 1.11 CHANNEL FUNCTIONAL TEST 1-2 l 1.12 CORE ALTERATION 1-2 l t 1.13 SHUTDOWN MARGIN 1-2 1.14 LEAKAGE. - 3 1 1.15 DELETED 1.16 DELETED } 1.17 DELETED 1-3 l 1.18-QUADRANT POWER TILT RATIO 1.19 DOSE EQUIVALENT I-131 1-4 i 1 1-4 '1.20 STAGGERED TEST BASIS ,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. 70

+-NPF 1 INDEX DEFINITIONS 'l SECTION EAgg 1-4 1.24 AXIAL FLUX DIFFERENCE _l I -1.25, PHYSICS TESTS 1-5 q 1,.26 E-AVERAGE DISINTEGRATION ENERGY 1-5 1.27 SOURCE CHECK'. 1-5 f l1.28 PROCESS' CONTROL PROGRAM ............. - 5-i 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 'j 1.34 VENTING 1-6 1.35 MAJOR CHANGES 1-6 "i 1.36 MEMBER (S) OF THE PUBLIC. 1-7. 1.37 CORE OPERATING LIMITS REPORT. 1-7 _ TABLE 1.1-OPERATIONAL MODES 1-8 TABLE 1.2 FREQUENCY-NOTATION 1-9 f a SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 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 I 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2-3 BEAVER VALLEY - UNIT 2 II-Amendment No. 70 - l i

l i NPF-73 INDEX k' BASES J SECTION PAGE i 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 { 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL j 3/4.1.1.1 Shutdown Margin - Tavg > 200*F 3/4 1-1 3/4.1.1.2 Shutdown Margin - Tavg $ 200*F 3/4 1-3 3/4.1.1.3 Boron Dilution 3/4 1-4 i 3/4.1.1.4 Moderator Temperature Coefficient (MTC) 3/4 1-5 1 3/4.1.1.5 Minimum Temperature for Criticality. 3/4'l-6 t 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 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 3/4.3.2.8 Borated Water Sources - Operating. 3/4 1-15 i BEAVER VALLEY - UNIT 2 III Amendment No. 70 l

NPF-73) INDEX j _ LLIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE j -[ 3/4.1.2.9 Isolation ofiUnborated Water Sources - _'3/4.1-17

{

Shutdown. 3/4.1.3 . MOVABLE CCNTROL ASSEMBLIES j 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 l ~ 3/4.1.3.6 Control Rod Insertion Limits. .- 3/4 1-25 3/4.2 POWER DISTRIBUTION LIMITS 3/4 2-1~ l-3/4.2.1 AXIAL FLUX DIFFERENCE (AFD) 3/4 2-4 l 3/4.2.2 HEAT FLUX HOT CHANNEL. FACTOR - Fg ( Z)". i 3/4.2.3 NgCLEARENTHALPYHOTCHANNELFACTOR-( F 3/4 2 AH. I 3/4.2.4 QUADRANT POWER TILT. RATIO. 3/4 2-9 j 3/4.2.5 DNB PARAMETERS. 3/4 2 1 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 j 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring. 3/4 3-39 3/4.3.3.2 Movable Incore Detectors. 3/4 3-45 3/4.3.3.3 Seismic Instrumentation. 3/4 3-46 l 'l 3/4.3.3.4 Meteorological Instrumentation. 3/4 3-49 l l BEAVER VALLEY - UNIT 2 IV Amendment No. 70 l I i I

+ l.i ~ -NPF-73 9-INDEX ^ t LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS' SECTION PAGE i3/4.3.3.5 Remote Shutdown Instrumentation. 1.'.~. 3/4 3-52 3/4.3.3.7 Chlorine. Detection Systems. 3/4 3-56 3/4.3.3.8 ' Accident MonitoringLInstrumentation. 3/4 3-57 3/4.3.3.11 Explosive Gas Monitoring Instrumentation. 3/4 3-61 3/4'3-66 3/4.3.4 ' TURBINE OVERSPEED PROTECTION.....

1 3/4.4 REACTOR COOLANT SYSTEM j

3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION j 3/4.4.1.1 Normal Operation.-. 3/4.4-11 1 4 1 3/4.4.1.2 Hot Standby. '3/4'4-2 .3/4.4.1.3 Shutdown. 3/4 4.l 6 3/4.4.1.6 Reactor' Coolant Pump-Startup. 3/4 4-7 f 3/4 4-8 l 3/4.4.2 SAFETY VALVES - SHUTDOWN. t 3/4.4.3 SAFETY VALVES - OPERATING 3/4.4-9 3/4.4.4 PRESSURIZER. 3/4 4-10 e 3/4.4.5 STEAM GENERATORS. 3/4 4-11. i 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE .3/4.4.6.1 Leakage Detection Instrumentation. 3/4 4 ! 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 l 3/4.4.9 PRESSURE / TEMPERATURE LIMITS l 3/4.4.9.1 Reactor Coolant System. 3/4 4-30 l 3/4.4.9.2 Pressurizer. 3/4 4-34 f i BEAVER VALLEY - UNIT 2 V Amendment No. 70 f 'i ..I

1 NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.9.3 Overpressu.e Protection Systems. 3/4 4-35 l - 3/4.4.10 STRUCTURAL INTEGRITY 3/4 4-38_ r 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 2 350*F. 3/4 5-3 avg 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 i 4 BEAVER VALLEY - UNIT 2 VI knendment No. 70 1

NPF-73 INDEX . LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6.4. COMBUSTIBLE GAS CONTROL i 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 3/4 7-12 3/4.7.4 SERVICE WATER SYSTEM-(SWS). 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 i 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE I SYSTEM (SLCRS). 3/4 7-18 3/4.7.9 SEALED SOURCE CONTAMINATION. 3/4 7-20 l 3/4.7.12 SNUBBERS. 3/4 7-24 3/4.7.13 STANDBY SERVICE WATER SYSTEM (SWE). 3/4 7-30 1 BEAVER VALLEY - UNIT 2 VII Amendment No. 70

~. . ~. ~ '/, M 'NPF > INDEX ILIMITING CONDITION;FOR OPERATION-AND' SURVEILLANCE REQUIREMENTS SECTION PAG.E 3/4.8 ELECTRICAL POWER' SYSTEMS ~ -3/4.8.l.. /A.C.: SOURCES' i L3/4"8-1 ] 3/4.8.1.1 Operating. i ' '3/4,8-6 .l '3/4.8.1.2 Shutdown. 3/4.8'.2 -ONSITE POWER DISTRIBUTION SYSTEM 'j 3/4.8.2.1 A.C. Distribution -l 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 i 3/4.9 REFUELING OPERATIONS '3/4.9.1 BORON CONCENTRATION. 3/4 9-1 l 1 3/4.9.2 . INSTRUMENTATION. 3/4 9-2 l 3/4.9.3 DECAY TIME. 3/4 9.............. -.. 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS 3/4 9-4 .3/4'.9.5 COMMUNICATIONS. 3/4 9-5 ' i 3/4.9.6 MANIPULATOR CRANE OPERABILITY. 3/4.9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL 3/4.9-7~ l BUILDING. 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT l CIRCULATION i 3/4.9.8.1 High Water Level 3/4 9-8 3/4.9.8.2 Low Water Level 3/4~9-9 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM. 3/4'9-10 t 3/4.9.10 WATER LEVEL-REACTOR VESSEL. 3/4 9-11 i 3/4.9.11 STORAGE POOL WATER LEVEL. 3/4 9-12 i BEAVER VALLEY - UNIT 2 VIII Amendment No. 70 i .i L y +. ..m-. e

NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 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 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 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 Gaseous Waste Storage Tanks. 3/4 11-4 3/4.11.2.6 Explosive Gas Mixture. 3/4 11-5 BASES SECTION PAGE i 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. 70

~ V NPF-73. 4 INDEX + ~ BASES SECTION RAGE - 3/4.2 POWER DISTRIBUTION LIMITS' B 3/4 2-1 l L ' 3/4.2.1-AXIAL FLUX DIFFERENCE (AFD) 3/4.2.2 AND 3/4.2.3 HEAT FLUX AND NUCLEAR'EN LPY HOT CHANNEL FACTORS Fg(Z) AND H-. B 3/4-2-2 B 3/4 2-5 l. . 3/4.2.4 -QUADRANT POWER TILT RATIO. B 3/4 2-5. 3/4.2.5 DNB PARAMETERS. ( 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 D6tectors. 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 3/4.3.3.7 Chlorine Detection Systems. B 3/4 3-5 3/4.3.3.8 Accident Monitoring Instrumentation. B 3/4 3-6 3/4.3.3.11 Explosive Gas Monitoring Instrumentation. B 3/4 3-6 l 3/4.3.4 TURBINE OVERSPEED PROTECTION B 3/4 3-6 j 3/4.4 REACTOR COOLANT SYSTEM f 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION. B 3/4 4-1 i B 3/4 4-2 3/4.4.2 AND 3/4.4.3 SAFETY VALVES 3/4.4.4 PRESSURIZER. B 3/4 4-2 -l BEAVER VALLEY - UNIT 2 X Amendment No. 70

p t [ G + NPF-73 l l INDEX t -~ BASES-j t SECTION -PAGE t i L 3/4.4.5: STEAM GENERATORS .B 3/4-4-2 l 3/4.4.6. . REACTOR COOLANT' SYSTEM LEAKAGE.... B.3/4,4 = 3/4.'4.7 . CHEMISTRY'.-. B 3/4 4-5 f 3/4.~4.8 SPECIFIC ACTIVITY. B 3/4 4-5 3/4.4.9 ' PRESSURE / TEMPERATURE LIMITS 'B 3/4 4-6 y B 3/4'4-15 i 3/4.'4.10 STRUCTURAL INTEGRITY. r b 3/4.4.11 REACTOR COOLANT SYSTEM RELIEF VALVES. B'3/4 4-16 l l 3/4.4.12 REACTOR COOLANT SYSTEM. HEAD VENTS. B 3/4 4 l l' 3/4.5 EMERGENCY CORE COOLING SYSTEMS'(ECCS) B 3/4 5-1 j 3/4.5.1 ACCUMULATORS. t 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 i

i 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 .f i 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 i 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE l LIMITATION B 3/4 7-3 i i 3/4.7.3 PRIMARY COMPONENT COOLING WATER SYSTEM. B 3/4 7-3 l BEAVER VALLEY - UNIT 2 XI Amendment No. 70

.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 3/4.7.12 SNUBBERS. B 3/4 7-5 I 3/4.7.13 STANDBY SERVICE WATER SYSTEM (SWE). B 3/4 7-6 l l [ 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 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 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 EXHAUST 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 BEAVER VALLEY - UNIT 2 XII Amendment No. 70

NPF-73 i JNDEX BASES EECTION 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 i 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 EFFLUEEIS 3/4.11.1 LIQUID EFFLUENTS. B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS B 3/4 11-1 DESIGN FEATURES 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 1 5.1.5 Flood Control. 5-1 l 5.2 CONTAINMENT 5.2.1 Configuration. 5-1 5.2.2 Design Pressure and Temperature. 5-6 5.2.3 Penetrations. 5-6 BEAVER VALLEY - UNIT 2 XIII Amendment No. ' 70

'i t r i NPF-73 INDEX t DESIGN: FEATURES. 'I i I SECTION P.Af,Z [ i . 5.3-REACTOR-CORE 5.3.1 Fuel Assemblies. 5-6' i 5.3.2 Control Rod Assemblies. 5-6= l 5.4 REACTOR COOLANT SYSTEM - 5.4.1 Design' Pressure and Temperature. 5-6 j 5.4.2 Volume.. 5 ! i 5.5 EMERGENCY CORE COOLING SYSTEMS 5-7 ) 5.6 FUEL STORAGE 5.6.1 Criticality. 5-7 5.6.2-Drainage. 5-7 i I 5.6.3 Capacity. 5-7 i t I 5.7' SEISMIC CLASSIFICATION 5-7 i 5.8 METEOROLOGICAL TOWER LOCATION. 5-7 l i' ADMINISTRATIVE CONTROLS SECTION PAGE l 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION ] 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS. 6-1 i-

6.2.2 UNIT STAFF.

6-1 q 6.2.3 INDEPENDENT SAFETY EVALUATION GROUP (ISEG). 6-2 6.3 FACILITY STAFF OUALIFICATIONS. 6-6 'l BEAVER VALLEY - UNIT 2 XIV Amendment No. 70 ')

~ n u. r NPF-73 3 s INDEX r iADMINISTRATIVE-CONTROLS-SECTION PAgg 16 ! .t.. . ~. 6.4-TRAINING. E. '6.5 REVIEW AND AUDIT I 6.5.1 ONSITE SAFETY COMMITTEE'(OSC) { ..<.z f l6'.5.1.1' ' Function.'.. 6-6 o-Composition. 6 '{ ~6.5.1.2 t 6-7 6.5.1.3 Alternates. 6.5.1.4 Meeting Frequency. 6-7 l

t

'6-7 6.5.1.5 Quorum. 6.5.1.6 Responsibilities. 6-7. l t ~6.5.1.7 Authority. 6-8 1 6.5.1.8 Records. 6-8 i 6.5.2 'OFFSITE REVIEW COMMITTEE (ORC) 6.5.2.1 Function. 6-8 <6. 5. 2. 2 - Composition.. 6-9 f a 16.5.2.3 Alternates... 6-9 5 6-9 6.5.2.4 Consultants.. r 6.5.2.5 Meeting Frequency. 6-9 ',i 6-9' 6.5.2.6 Quorum. 6.5.2.7 Review. 6-9 l r 6.5.2.8 Audits. 6-10 I 6.5.2.9 Authority. 6-11 6.5.2.10 Records. 6-11 i 6.6 REPORTABLE EVENT ACTION. 6-11 ~ i BEAVER VALLEY - UNIT 2 XV Amendment No. 70 i r

.p .s; L 'PF-73l N INDEX i } ADMINISTRATIVE-CONTROLS 'SECTION EAgg 6-12 'I 16.7: SAFETY' LIMIT' VIOLATION. i k6.8 PROCEDURES 6-l'2 - 6.9 REPORTING REQUIREMENTS ~ lL 6.9.1 ROUTINE REPORTS. 6-16 6-16' 6.9.1.1 .Startup Reports................... ' 6. 9.1. 4 - Annual Reports. 6-17I i .6.9.1.6 Monthly Operating Report. 6-18 l AnnualRadiologicalEnvkronmental.. operating-6.9.1.10' Report. 6-19 6.9.1.11 Annual Radioactive Effluent Release Report. '6-19 f 16.9.1.12 . Core' Operating Limits Report. 6-19: 6-20 6.9.2 SPECIAL. REPORTS .......... =.... 6.10 RECORD RETENTION. .6.............'...... l 6.11 RADIATION PROTECTION PROGRAM. 6 1 l 'I '6.12 ' HIGH RADIATION AREA'. 6-23 6.13 PROCESS CONTROL PROGRAM (PCP) 6-24 1 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM). 6-25 1 6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Licuid. Gaseous and Solid) 6-25' { s a t t l t l BEAVER VALLEY - UNIT 2 XVI Amendment No. 70 l i i

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 l instrumentation and 1) described in Chapter 14.0 of the FSAR, 2) I authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission. 5L-AVERAGE DISINTEGRATION ENERGY l 1.26 E shall be the average sum (weighted in proportion to the l concentration of each radionuclide in the reactor coolant at the I time of sampling) of the average beta and gamma energies per I disintegration (in MeV) for isotopes, other than iodines, with half l lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant. l SOURCE CHECK I l 1.27 A SOURCE CHECK shall be the qualitative assessment of channel l response when the channel sensor is exposed to a radioactive source. l l l 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 l

i 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 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. 70

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 1.32 VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines 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. I 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 l

manner that replacement air or gas is required to purify the confinement. yENTING 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 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 Hazards Summary Report and evaluated in the i i BEAVER VALLEY - UNIT 2 1-6 Amendment No. 70 \\

' NPF-73 i DEFINITIONS i L MAJOR CHANGES (Continued) staff's Safety Evaluation Report (SER) (e.g., deletion of evaporators and installation of demineralizers; use of fluidized. Ebed calciner/ incineration in place of' cement j solidification systems)* i 2) Major changes-in the design of radwaste treatment-systems i f(liquid,-

gaseous,

.and solid) that could significantly: ) increase' the ' quantities or activity of effluents released or volumes of solid waste stored or shipped offsite from those l previously considered in the FSAR and SER (e.g., use of-i asphalt system in place of cement); 3) Changes in' system design which may invalidate the accident i analysis as described in the SER (e.g., changes in tank I capacity that would alter the curies released); and i 4) Changes in system design that could potentially result in a j significant increase in occupational exposure of operating parsonnel (e.g., use of temporary equipment without adequate shielding provisions). i 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 i 4 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, .i

railway, or waterway located within the confines of the site l

boundary. This category does include persons who use portions of the' - site for recreational, occupational, or other purposes not j associated with the plant. i 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 l _ operating reload cycle. These cycle-specific core operating limits j shall be determined for each reload cycle in accordance with 6 Specification 6.9.1.12. Plant operation within these operating l [ limits is addressed in individual specifications. i ) BEAVER VALLEY - UNIT 2 1-7 Amendment No. 70 l

b L ypy_73-p TABLE 1.1 OPERATIONAL MODES REACTIVITY % RATED . AVERAGE CONDITION, TH COOLANT 11QDE K,gg POWER M TEMPERATURE l

1. POWER OPERATION 20.99

>5%. 2350*F.

2. STARTUP 20.99 55%

2350*F '3. HOT STANDBY <0.99 0 2350*F.- i 4. HOT SHUTDOWN <0.99 0 350*F >Tavg (; >200*F'

5. COLD SHUTDOWN

<0.99 0 5200*F l 6.. REFUELING (2) 50.95 0 $140*F. I d (1)' Excluding decay heat. l (2) Reactor vessel head unbolted or removed and fuel in the vessel. l l BEAVER VALLEY - UNIT 2 1-8 Amendment No. 70 .j ~

] a ?NPF-7'3 L i

u...

}

+ t .t -. 3 1 i j Specification 3.3.3.9 has been moved to the'

i!

OFFSITE DOSE CALCULATION-MANUAL. Specification 3.3.3.10 has been partially- -l moved to the OFFSITE DOSE' CALCULATION MANUAL l and the remaining part renumbered 3.3.'3.11.- l l ) i l _i l .i t l I I I i i i BEAVER VALLEY - UNIT 2 3/4 3-60 Amendment No. 70 .I i

r. 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 not exceeded. 1 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 the 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. I BEAVER VALLEY - UNIT 2 3/4 3-61 Amendment No. 70 l

TABLE 3-3-13

NPF-73 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) i During waste gas decay tank filling operation. BEAVER VALLEY - UNIT 2 3/4 3-62 Amendment No. 70 ~

~ 'NPF-73 TABLE 3.3-13 (Continued) ACTION STATEMENTS 4 ACTION 27 - (This ACTION is not used) ACTION 28 - (This ACTION is not used) ~ ACTION 29 - (This ACTION is not used) i 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 grab 1 samples are taken and analyzed at least once per 24-hours. With both channels inoperable,' operation may continue provided grab samples are taken and analyzed at least. once per 4 hours during degassing operations. and at least once per 24 hours during other operations. l ACTION 32 - (This ACTION is not used) ACTION 35 (This ACTION is not used) 1 9 4 i i e BEAVER VALLEY - UNIT 2 3/4 3-63 Amendment No. 70 l t i I

V TABLE 4.3-13' 'NPF-73 Explosive Gas Monitorina Instrumentation Surveillance Reauirements. 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) During waste gas decay tank filling operation. BEAVER VALLEY - UNIT 2 3/4 3-64 Amendment No. 70

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 BEAVER VALLEY - UNIT 2 3/4 3-65 Amendment No. 70 l

NPI'-73 L INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION l LIMITING CONDITION FOR OPERATION 3.3.4 At least one Turbine Overspeed Protection System shall be i OPERABLE. APPLICABILITY: MODES 1, 2(1), and 3(1). ACTION: 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, rescore the inoperable valve (s) to OPERABLE status within 72 hours, or close at least one valve in the affected steam line(s) or isolate the turbine from the steam supply within the next 6 hours. b. With the above required Turbine Overspeed Protection System otherwise inoperable, within 6 hours 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. 70 l

i NPF-73 INSTRUMENTATION SURVEILLANCE. REQUIREMENTS (Continued) l

b. By direct observation of the movement of each of the 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 months, 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 CALIBRATION on the turbine overspeed protection systems, and

d. At least once per 40 months by disassembling at least one of each of the above valves and performing 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. L t ? BEAVER VALLEY - UNIT 2 3/4 3-67 Amendment No. 70 l t

NPF-73 j 4. ; i. .i 4 i ? I Specifications 3.11.1.1 through 3.11.1.3 have been moved to the OFFSITE DOSE CALCULATION MANUAL. i i i l t i I i i i i h l i i - t i - I BEAVER VALLEY - UNIT 2 3/4 11-1 Amendment No. 70 i P y w. e

NPF-73 l 3/4.11 RADIOACTIVE EFFLUENTS l 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 miscellaneous temporary outside radioactive liquid storage tank shall be limited to less than or equal to 10 curies, excluding 1 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 hours 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 'he contents to within the specified limits. c 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 2 3/4 11-2 Amendment No. 70 l I

g NPF-73 { i . t ? I l l Specifications 3.11.2.1 through 3.11.2.4. l have been moved to the OFFSITE DOSE t CALCULATION MANUAL. i i t i i i i 4 l .i i i ) i l i-i i 't i i l BEAVER VALLEY - UNIT 2 3/4 11-3 Amendment No. 70 l i

NPF-73 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS 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 l 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

limit, immediately suspend all additions of radioactive material to the tanks and within 48 hours reduce the tanks' l

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 hours when radioactive materials are being added to the tanks. i BEAVER VALLEY - UNIT 2 3/4 11-4 Amendment No. 70 l

i 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 24 by volume l whenever the hydrogen concentration exceeds 4% by volume. At all times APPLICABILITY: 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 e concentration of oxygen to less than or equal to 2% within l l 48 hours. e b. With the concentration of oxygen in the waste gas holdup system greater than 4% by volume and the hydrogen t concentration greater than 4% by volume,.immediately suspend all additions of waste gases to the affected tank r and reduce the concentration of oxygen to less than or equal to 4% by volume, then take action a, above. l c. The provisions of Specification 3.0.3 are not applicable. l 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 l Specification 3.3.3.11 or monitoring in conjunction with its l i associated action statement. I i 4 BEAVER VALLEY - UNIT 2 3/4 11-5 Amendment No. 70 l

y. - -... _.

o.

NPF-73~

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 2 3/4 11-6 Amendment No. 70

4 .NPF-73.. t e ~ Specifications 3.12.1 through 3.12.3 have been moved to the OFFSITE DOSE CALCULATION MANUAL. + i i i f t h i i i i i i j i l BEAVER VALLEY - UNIT 2 3/4 12-1 Amendment No. 70

~. i 'NPF-73 i INSTRUMENTATION j l 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 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 l Recommendations." i -3/4.3.3.11 EXPLOSIVE GAS MONITORING INSTRUMENTATION { This instrumentation includes provisions for monitoring (and f controlling) the concentrations of potentially explosive gas l 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 i protection instrumentation and the turbine speed control valves are l OPERABLE and will protect the turbine from excessive overspeed. i Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures. e I [ i BEAVER VALLEY - UNIT 2 B 3/4 3-6 Amendment No. 70

l 'NPF-73 l 3/4.11 RADIOACTIVE EFFLUENTS j BASES s '3/4.11.1 LIOUID EFFLUENTS i 3/4.11.1.4 LIOUID HOLDUP TANKS i R,estricting the' quantity of. radioactive material' contained'in the l l specified tanks provides assurance that in the event. of an uncontrolled. release of -the tanks'

contents, the resulting 1

concentrations 1 would. be less than the. limits of 10 CFR Part 20, Appendix -B, Table 2, Column 2, at the nearest potable water supply l; and the nearest surface water supply in-an unrestricted area. l 3/4.11'2 GASEOUS EFFLUENTS' l 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 i

of the release will not ' exceed 0.5 rem. The specified limit l 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 j suitable fraction-of the reference value set forth in 10 CFR l l 100.11(a) (1). The curie content limit is applied. individually to-l each gaseous waste storage tank and collectively to the number of unisolated gaseous waste storage tanks. 3/4.11.2.6 EXPLOSIVE GAS MIXTURE l This specification is provided to ensure that the concentration of l potentially explosive gas mixtures contained in the waste gas holdup -i system is maintained below the. flammability limits of hydrogen and oxygen. Isolation of.the affected tank for purposes of purging l and/or-discharge permits the flammable gas concentrations of the tank r to be reduced below the lower explosive limit in a hydrogen rich j system. Maintaining the concentration of hydrogen and oxygen below their flammability limits' provides assurance. that-the releases-of l radioactive materials will be controlled in conformance with the i requirements of General Design Criterion 60 of Appendix-A to 10 CFR l Part 50. i i i l ? BEAVER VALLEY - UNIT 2 B 3/4 11-1 Amendment No. 70 i

'NPF-73~ l ADMINISTRATIVE CONTROLS 7; PROCEDURES-(Continued) 6.8.3 Temporary changes to procedures of 6.8.1-above may'ba made provided:- a. The intent of the original' procedure is not altered. b. The change is approved by two. (2) members of the. plant ] p 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-i 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 1 1 'to obtain and analyze reactor

coolant, radioactive iodines and particulates in plant gaseous affluents, and containment atmosphere samples following an accident.

The program shall include the following: (i) Training of personnel, (ii) Procedures for sampling and analysis, and (lii) Provisions for maintenance of sampling and analysis equipment. 6.8.5 A program for monitoring of secondary water chemistry.to inhibit steam generator tube degradation shall be implemented. This program shall be described in the station chemistry manual and shall include: a. Identification of a sampling schedule for the critical 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 1 BEAVER VALLEY - UNIT 2 6-13 Amendment No. 70

NPF-73 ADMINISTRATIVE CONTROLS i PROCEDURES (Continued) f. A procedure identifying: 1) the authority responsible for the' interpretation of the data, and 2) the sequence and timing of administrative events required to initiate corrective action. 6.6.6 The following programs shall be established, implemented, and maintained: 4 a. Radioactive Effluent Control Procram 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 effluents 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 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, 2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table 2, Crlumn 2, 3) Manitoring, 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 methodology and parameters in.the ODCM, 4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 3 1 BEAVER VALLEY - UNIT 2 6-14 Amendment No. 70 i

NPF-73 ADMINISTRATIVE CONTROLS PROCEDURES (Continued) 5) Determination of cumulative and projected-dose contributions from radioactive effluents for the current calendar quarter and current calendar year in 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 effluent 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, 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, 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. BEAVER VALLEY - UNIT 2 6-15 Amendment No. 70

i lNPF ADMINISTRATIVE CONTROLS 1 PROCEDURES (Continued) '} l -b. Radioloalcal Environmental'Monitorina Procram-l .A program shall be provided to monitor the radiation and. i radionuclides in the. environs of 'the ~ plant. The program shall. . provide (1) representative. measurements-of radioactivity in the highest potential exposure pathways, and t (2) verification of the accuracy of the effluent monitoring l program and modeling of environmental exposure pathways.. The 1 program shall. (1) be contained in theLODCM, (2) conform.to i 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 Census to ensure that changes in the use of l areas at and beyond the SITE BOUNDARY-are identified land i that modifications to the monitoring program are made if-l required by the.results'of this census, and-3) Participation in an Interlaboratory1 Comparison Program -i to -ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in j environmental. sample. matrices are performed as part of the quality assurance program for environmental monitoring. 6.9 REPORTING REQUIREMENTS i I ROUTINE REPORTS l d 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be J 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 j

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. 70 l m y e-p w pr-- m y-y w r-wm-m

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. I1) ANNUAL REPORTS 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 l personnel (including contractors) receiving exposure greater than 100 mrem /yr and their associate 2) man-rem exposure a according to work and job functions (e.g., reactor I 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 (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 2 6-17 Amendment No. 70 l

NPF-73 . ADMINISTRATIVE CONTROLS + - ANNUAL REPORTS (Continued) dosimeter, .TLD, or-film badge. measurements. Small exposures i totalling less than-20-percent of the individual total dose s need not be accounted-for.- In the aggregate, at least 80 percent of the total whole body dose received from external-l 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 hours prior'to the first sample in-which the ~1imit 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 theilimit. Each' result should include date and time of sampling and the radioiodine concentrations; (3)- Clean-up system flow history. starting 48 hours prior: to the first sample-in which' the limit was. exceeded; (4) Graph of.the I-131 concentrationLand 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-radiciodine 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. 70 l w.2 -,gy i,e -w-w 14-m-m.- - - - - - < -- - + - - - - - -. - - -

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) 6.9.1.11 The Annual Radioactive Effluent Release Report covering 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 l 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 (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. BEAVER VALLEY - UNIT 2 6-19 Amendment No. 70

t t NPF-73 [ -ADMINISTRATIVE-CONTROLS' L CORE' OPERATING LIMITS REPORT-(Continued) ? .l 2. WCAP-9220-P-A,. ~Rev. 1, " WESTINGHOUSE ECCS:. EVALUATION 2 MODEL-1981 VERSION", . February. 1982 (Westinghouse Proprietary). ' Methodology applied for the following. Specification: 3.2.2, Heat Flux Hot Channel Factor-F (Z). j g 3.' WCAP-8385, " POWER DISTRIBUTION CONTROL, AND LOAD:FOLLOWING-TOPICAL. REPORT",_ September 1974 (Westinghouse PROCEDURES Proprietary). Methodology applied for the

following j

Specification; 3.2.1, Axial ' Flux Difference-Constant Axial. j Offset control. 4.- T. M. Anderson to K. Kniel (Chief ofl 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 l Commission, Section 4.3, Nuclear Design,~ July 1981.. Branch Technical Position' CPB 4.3-1, Westinghousef Constant Axial Offset. Control (CAOC), Rev. 2, July 1981. Methodology applied, i for the following. ' Specification: 3.2.1, Axial Flux, l Difference-Constant Axial' Offset Control. l. l The core operating' limits shall:be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic i

limits, ECCS

limits, nuclear limits such as shutdown margin,.and i

transient and accident analysis ~ limits) of the safety analysis-are met. The CORE OPERATING LIMITS

REPORT, including any mid-cycle I

revisions or supplements-thereto, shall be provided upon issuance,- for each reload cycle,-to the NRC Document Control-Desk. 't SPECIAL REPORTS 6.9.2 Special reports 'shall be submitted to.the U.S. Nuclear Regulatory ' Commission, Document Control Desk within the time period i specified for each-report. These reports shall'ba 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. I l i I i BEAVER VALLEY - UNIT 2 6-20 Amendment No. 70 l

NPF-73 ' ADMINISTRATIVE CONTROLS SPECIAL REPORTS (Continued) ] 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. l 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. h. Steam generator tube inservice inspection, Specification 4.4.5.5. i. Inoperable accident monitoring, Specification 3.3.3.8. j. Liquid Hold-Up Tanks, Specification 3.11.1.4. k. Gas Storage Tanks, Specification 3.11.2.5. i i 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. 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. e i BEAVER VALLEY - UNIT 2 6-21 Amendment No. 70 l

NPF-73 ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) 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 to systems and equipment described in the Final Safety Analysis Report. 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. i BEAVER VALLEY - UNIT 2 6-22 Amendment No. 70 l

rl ' j NPF-73' ADMINISTRATIVE CONTROLS' i RECORD RETENTION (Continued) l i 1.. Records of.the service lives of,all hydraulic and mechanical 'j snubbers including-the date at which the service life commences' and associated installation and' maintenance-records.

m..

Records of analyses required by the Radiological -l 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 consistant with the requirements of 10- CFR Part 20 and shall be l

approved, maintained and adhered to for all operations involving.

personnel radiation exposure. 6.12 HIGH RADIATION AREA 1 6.12.1 In lieu of the " control device" or " alarm signal" required by 1 paragraph 20.1601 of 10 CFR 20, each high radiation area in which theJ l I intensity of radiation is greater than 100 mrem /hr but less than 1000 mram/hr shall be barricaded and. conspicuously posted as a high j radiation area.andentrancetheretoshall(gpcontrolledbyrequiring-I- a Radiological ' Work Permit - or Radiological Access issuance of 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 1 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. 70 l j

i t 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. I This individual shall be responsible for providing positive l-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 Radiclogical 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. l 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. 1 i BEAVER VALLEY - UNIT 2 6-24 Amendment No. 70 l - -- J

NPF-73 ADMINISTRATIVE CONTROLS 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) Changes to the ODCM: a. Shall be documented and records et reviews performed shall lxn 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 tne 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. 52,5. Moved to the PROCESS CONTROL PROGRAM. BEAVER VALLEY - UNIT 2 6-25 Amendment No. 70 l ,}}

NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301

Contents

Text

Attachment:

Attachment:

Attachment:

Navigation menu

NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301

Text

Attachment:

Attachment:

Attachment:

Navigation menu

Search