Text

Proposed Tech Spec Changes,Updating Index,Deleting Blank Pages & Revising Administrative Controls of Section 6 to Reflect Nuclear Group Reorganization.No Significant Hazards Determination Encl
	ML20137L991
Person / Time
Site:	Beaver Valley
Issue date:	01/15/1986
From:	; DUQUESNE LIGHT CO.
To:	;
Shared Package
ML20137L966	List: ML20137L963; ML20137L979; ML20137L991;
References
	NUDOCS 8601280163
	Download: ML20137L991 (53)
	v • d • e

s 4

ATTACHMENT A Revise Appendix A as follows:

Remove Pages Insert Pages Comments I thru XVIIa I thru XXVI Revised Index 3/4 1-26 -

Deleted 3/4 4-29 -

Deleted 3/4 4-30 -

Deleted 3/4 4-31 3/4 4-29 Renumbered 3/4 5-8 -

Deleted 3/4 7-23 3/4 7-23 added (next pg. is 3/4 7-26) 3/4 7-24 -

Deleted 3/4 7-25 -

Deleted 3/4 11-16 3/4 11-16 added (next og, is 3/4 11-18) 3/4 11-17 -

Deleted 3/4 11-18 3/4 11-18 added (next pg. is 3/4 11-20) 3/4 11-19 -

Deleted 6-15 6-15 added info. from pages 6-16/

6-17, 6-18, 6-19 and added (next page is 6-20) 6-16/6-17 -

Deleted 6-18 -

Deleted 6-19 -

Deleted 6-1 6-1 Reorganization 6-la 6-la Reorganization 6-2 6-2 Reorganization 6-3 6-3 Reorganization 6-4 6-4 Reorganization 8601280163 DR 860115 ADOCK 05000334 PDR

s Attachment A

Page 2 Remove Pages Insert Pages Comments

6-5 6-5 Reorganization 6-6 6-6 Reorganization 6-7 6-7 Reorganization 6-8 6-8 Reoganization 6-9 6-9 Reorganization.

i 6-11 6-11 Reorganization 6-12 6-12 Reorganization 6-13 6-13 Reorganization 4 6-31 6-31 Reorganization 6-30 6-30 Correct a typographical error Section 6.13.3 to 6.16.3 83/4 11-2 B3/4 11-2 Correct a typographical error t

s 1NDEX DEFINITIONS SECTION ,

PAGE 1.0 DEFINITIONS Defined Terms . . . . . . . . . . . . . . . . . . ... . . . 1-1 Thermal Power . . . . . . . . . . . . . . . . . . . . . . . 1-1 Rated Thermal Power . . . . . . . . . . . . . . . . . . . . 1-1 Operational Mode ..................... 1-1 Action .......................... 1-1 Operable - Operability .................. 1-1

. Reportable Event ..................... 1-2 Containment Integrity . . . . . . . . . . . . . . . . . . . 1-2 Channel Calibration . . . . . . . . . . . . . . . . . . . . 1-2 Channel Check . . . . . . . . . . . . . . . . . . . . . . . 1-2 Channel Functional Test . . . . . . . . . . . . . . . . . . 1-3 Core Alteration . . . . . . . . . . . . . . . . . . . . . . 1-3 Shutdown Margin . . . . . . . . . . . . . . . . . . . . . . 1-3 Identified Leakage .................... 1-3 Unidentified Leakage . . . . . . . . . . . . . . . . . -. . 1-3 Pressure Boundary' Leakage . . . . . . . . . . . . . . . . . 1-4 Controlled Leakage .................... 1-4 Quadrant Power Til t Ratio . . . . . . . . . . . . . . . . 1-4 Dose Equivalent I-131 . . . . . . ... . . . . . . . . . . . 1-4 Staggered Test Basis ................... 1-4 Frequency Notation .................... 1-4 Reactor Trip System Response Time ............ 1-5 Engineered Safety Feature Response Time . . . . . . . . . . 1-5 BEAVER VALLEY - UNIT 1 I

DEFINITIONS SECTION PAGE Axial Fl ux Di fference . . . . . . . . . . . . . . . , . . . . . 1-5 Physics Tests . . . . . . . . . .. .............. 1-5 E-Average Disintegration Energy . . . . . . . . . . . . . . . . 1-5 Source Check . . . . . . . . . . . . . . . . . . ........ 1-6 Process Control Program . . . . . . . . . . . . . . . . . . . . 1-6 Solidification. . . . . . . . . . . . . . . . . . . . . . . . . 1-6 Off-Site Dose Calculation Manual (0DCM) . . . . . . . . . . . . 1-6

~

Gaseous Radwaste Treatment System . . . . . . . . . . . . . . . 1-6 Ventilation Exhaust Treatment System ............. 1-6 Purge - Purging . . . . . . . . . . . . . . . . . . . . . . . . 1-7 Venting ........................... 1-7 Major Changes . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 Member (s) of the Public . . . . . . . . . .-. . . . . . . . . . 1-8 Operational Modes (Table 1.1)'. . . . . . . . . . . . . . . ... 1-9 Frequency Notation (Table 1.2)' . . . . . . . . . . ... . . . . 1-10 BEAVER VALLEY - UNIT 1 II

INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 Rea c to r Co re . . . . . . . . . . . . . . . . . . . . . . 2-1 2.1.2 Reactor Coolant System Pressure ............ 2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 Reactor Trip System Instrumentation Setpoints . . . . . . 2-5 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 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 Reactor Trip Setpoints . . . . . . . . . . . . . . . . . - B 2-3 BEAVER VALLEY - UNIT 1 III

INDEX l

i

. l LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION -PAGE 1,

3/4.0 APPLICABILITY ........................ 3/4 0-1 i

3/4.1 REACTIVITY CONTROL SYSTEMS

3/4.1.1 B0 RATION. CONTROL i 3/4.1.1.1 Shutdown Margin - T avg > 200 F ............ 3/4 1-1

3/4.1.1.2 Shutdown Margin - T < 200 F ............ 3/4 1-3 avg 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 j 3/4.1.2.1 Flow Paths - Shutdown . . . . . . . . . . . . . . . . . 3/4 1-7 I 3/4.1.7.2 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 1

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 i 3/4.1.2.8 Borated Water Sources - Operating . . . . . . . .. . . . 3/4 1-16 3/4.1.3 MOVABLE CONTROL ASSEMBLIES 3/4.1.3.1 Group Height ..................... 3/4 1-18 3/4.1.3.2 Position Indication Systems - Operating . . . . . . . . 3/4 1-20 3/4.1.3.3 Position Indication System - Shutdown . . . . . . . . . 3/4 1-21 3/4.1.3.4 Rod Drop Time . . . . . . . . . . . . . . . . . . . . . 3/4 1 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 BEAVER VALLEY - UNIT 1 IV i

- - _ _ . _ - - ~ . _ _ . , _ _ , _ . - . _ . . - . ..- - . . . - - _ . , . . . . . . . . . . . . - - , , . .

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE . . . . . . . . . . . . . . . . . . 3/4 2-1 3/4.2.2 HEAT FLUX H0T CHANNEL FACTOR ............. 3/4 2-5 3/4.2.3 NUCLEAR ENTHALPY H0T CHANNEL FACTOR-. . . . . . . . . . 3/4 2-8 3/4.2.4 QUADRANT POWER TILT RADIO . . . . . . . . . . . . . . . 3/4 2-10 3/4.2.5 DNB PARAMETERS .................... 3/4 2-12 i

3/4.3 INSTRUMENTATION :

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION . . . . . . . . . . 3/4 3-1 l 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRV-1 MENTATION . . . . . . . . . . . . . . . . . . . . . . 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 A

4 3/4.3.3.5 Remote Shutdown Instrumentation . . . . . .. ...... 3/4 3-44 3/4.3.3.6 Fire Detection Instrumentation ............ 3/4 3-47

{ .

j 3/4.3.3.7 Chlorine Detection Systems .............. 3/4 3-49

} 3/4.3.3.8 Accident Monitoring Instrumentation . . . . . . . . . . 3/4 3-50 1

3/4.3.3.9 Radioactive Liquid Effluent Monitoring Instrumentation. 3/4 3-53 1

3/4.3.3.10 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4 3-59 BEAVER VALLEY - UNIT 1 V i

l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS 3/4.4.1.1 Normal Operation ................... 3/4 4-1 3/4.4.1.2 Hot Standby . . . . . . . . . . . . . . . . . . . . . . 3/4 4-2b 3/4.4.1.3 Shutdown ....................... 3/4 4-2c 3/4.4.1.4 Isolated Loop . . . . . . . . . . . . . . . . . . . . . 3/4 4-3 3/4.4.1.5 Isolated Loop Startup . . . . . . . . . . . . . . . . . 3/4 4-4 3/4.4.1.6 Reactor Coolant Pump Startup ............. 3/4 4-4a 3/4.4.2 SAFETY VALVES - SHUTDOWN ............... 3/4 4-5 3/4.4.3 SAFETY VALVES - OPERATING , . . . . . . . . . . . . . . 3/.",4-6 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 Systems . . . . . . . . . . . . . . . 3/4 4-11 3/4.4.6.2 Operational Leakage . . . . . . . . . . . . . . . . . . 3/4 4-13 3/4.4.6.3 Pressure Isolation Valves . . . . . . . . . . . . . . . 3/4 4-14a 3/4.4.7 CHEMISTRY . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-15 3/4.4.8 SPECIFIC ACTIVITY . . . . . . . . . . . . . . . . . . . 3/4 4-18 3/4.4.9 PRESSURE / TEMPERATURE LIMITS 3/4.4.9.1 Reactor Coolant System ................ 3/4 4-22 BEAVER VALLEY - UNIT 1 VI 4

TNDEX 1

LIMITING CONDITIONS F0R.0PERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.9.2- Pressurizer . . . . . . . . . . . ... . . . . . . . . . 3/4 4-27

3/4.4.9.3 Overpressure Protection Systems . . . . . . . . . . . . 3/4 4-27a f 3/4.4.10 STRUCTURAL INTEGRITY - ASME Code Class 1, 2 and 3

.)

Components ...................... 3/4 4-28 3/4.4.11 RELIEF VALVES . . . . . . . . . . . . . . . . . . . . . 3/4 4-29 3/4.5 EMERGENCY-CORE COOLING SYSTEMS (ECCS) ,

3/4.5.1 ACCUMULATORS ..................... 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,yg 1 350 F ............ 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T avg

< 350*F ............ 3/4 5-6 3/4.5.4 BORON INJECTION SYSTEM 3/4.5.4.1.1 Boron Injection Tank 1 350 F . . . . . . . . . . . . . 3/4 5-7 l 3.4.5.4.1.2 Boron Injection Tank < 350 F . . . . . . . . . . . . . 3/4 5-7a 3/4.5.5 Deleted by Amendment No. 75 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 l 3/4.6.1.4 Internal Pressure . . . . . . . . . . . . . . . . . . . 3/4 6-6 3/4.6.1.5 Ai r Tempe ra tu re . . . . . . . . . . . . . . . . . . . . 3/4 6-8

] 3/4.6.1.6 Containment Structural Integrity ........... 3/4 6-10 I

! BEAVER VALLEY - UNIT 1 VII

_ , , . _ _ _ .- ,,._,_._m.,. ____-..,_._,,.,m.,,-,_,_,_ _ . . _ . , ~ , _ , _ , , , , . _ _ . _ , _ _ , . _ , _ _ , . _ _ _ _ , , - - _ , _ , _ , . _ , . . , , . . _ _ _ _ _ , ~ , , , . _

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 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 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 3/4.6.4.3 Hydrogen Pu rge System . . . . . . . . . . . . . . . . . 3/4 6-23 3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM 3/4.6.5.1 Steam Jet Air Ejector . . . . . . . . . . . . . . . . . 3/4 6-25 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 Safety Valves . . . . . . . . . . . . . . . . . . . . . 3/4 7-1 3/4.7.1.2 Auxiliary Feedwater System .............. 3/4 7-5 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 RIVER WATER SYSTEM .................. 3/4 7-13 3/4.7.5 ULTIMATE HEAT SINK - OHIO RIVER . . . . . . . . . . . . 3/4 7-14 BEAVER VALLEY - UNIT 1 VIII

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLAhtm REQUIREMENTS SECTION PAGE 3/4.7.6 FLOOD PROTECTION ................... 3/4 7-15 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS . . . . . . 3/4 7-16 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM . . . . 3/4 7-19 3/4.7.9 SEALED SOURCE CONTAMINATION . . . . . . . . . . . . . . 3/4 7-22 3/4.7.10 Deleted by Amendment No. 43 3/4.7.11 Deleted by Amendment- No. 43 3/4.7.12 SNUBBERS ....................... 3/4 7-26 3/4.7.13 AUXILIARY. RIVER WATER SYSTEM ............. 3/4 7-34 3/4.7.14 FIRE SUPPRESSION SYSTEMS 3/4.7.14.1 Fire Suppression Water System . . . . . . . . . . . . . 3/4 7-35 3/4.7.14.2 Spray and/or Sprinkler System . . . . . . . . . . . . . 3/4 7-39 3/4.7.14.3 Low Pressure2 C0 System . . . . . . . . . . . . . . . . 3/4 7-41 3/4.7.14.4 Fire Hose Stations .................. 3/4 7-42 3/4.7.14.5 Halon Systems . . . . . . . . . . . . . . . . . . . . . 3/4 7-43 3/4.7.15 FIRE RATED ASSEMBLIES . . . . . . . . . . . . . . . . . 3/4 7-44 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 3/4.8.1.1 Operating . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-1 3/4.8.1.2 Shutdown ....................... 3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS 3/4.8.2.1 A.C. Distribution - Operating . . . . . . . . . . . . . 3/4 8-6 BEAVER VALLEY - UNIT 1 IX

i 1

1NDEX i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

{ SECTION PAGE i

! 3/4.8.2.2 A.C. Distribution - Shutdown .. ............ 3/4 8-7 .

I I 3/4.8.2.3 D.C. Distribution - Operating . . . . . . . . . . . . . 3/4 8-8 i

i 3/4.8.2.4 D.C. Distribution - Shutdown ............. 3/4 8-10 4

i

! 3/4.9 REFUELING OPERATIONS r

4

{ 3/4.9.1 BORON CONCENTRATION . . . . . . . . . . . . . . . . . . 3/4 9-1 ;

l 3/4.9.2 INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . 3/4 9-2 j 3/4.9.3 DECAY TIME ...................... 3/4 9-3 j 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS . . . . . . . . . . . 3/4 9-4 j 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 P0OL BUILDING . . . . 3/4 9-7 1, 3/4.9.8.1 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION . . . . . 3/4 9-8 j 3/4.9.8.2 LOW WATER LEVEL . . . . . . . . . . . . . . . . . . . . 3/4 9-8a j 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 P0OL WATER LEVEL ............... 3/4 9-11

! 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM - FUEL MOVEMENT ... 3/4 9-12 j 3/4.9.13 '

FUEL B'JILDING VENTILATION SYSTEM - FUEL STORAGE . . . . 3/4 9-13' 1

i 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10'.1 SHUTDOWN MARGIN . . . . . . . . . . . . . . . . . . . . 3/4 10-1 j 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS . 3/4 10-2 BEAVER VALLEY - UNIT 1 X

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE l

3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS - REACTOR CRITICALITY. 3/4 10-4 3/4.10.4 PHYSICS TESTS . . . . . . . . . . . . . . . . . . . . . 3/4 10-6 3/4.10.5 N0 FLOW TESTS . . . . . . . . . . . . . . . . . . . . . 3/4 10-7 3/4.11 RADI0 ACTIVE EFFLUENTS 1 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 Concentration . . . . . . . . . . . . . . . . . . . . . 3/4 11-1 3/4.11.1.2 Dose ......................... 3/4 11-6 3/4.11.1.3 Liquid Waste Treatment ................ 3/4 11-8 3/4.11.1.4 Liquid Holdup Tanks . . . . . . . . . . . . . . . . . . 3/4 11-10 3/4.11.2 GASE0US EFFLUENTS 3/4.11.2.1 Dose Rate . . . . . . . . . . . . . . . . . . . . . . . 3/4 11-11 3/4.11.2.2 Dose - Noble Gases .................. 3/4 11-15 4 3/4.11.2.3 Dose - Radiciodines, Particulates, and Radionuclides Other than Noble Gases . . . . . . . . . . . . . . . . . . .

3/4 11-16 3/4.11.2.4 Gaseous Radwaste Treatment .............. 3/4 11-18 3/4.11.2.5 Gas Storage Tanks . . . . . . . . . . . . . . . . . . . 3/4 11-20 3/4.11.2.6 Explosive Gas Mixture . . . . . . . . . . . . . . . . . 3/4 11-21 3/4.11.3 SOLID RADI0 ACTIVE WASTE . . . . . . . . . . . . . . . . 3/4 11-22 3/4.11.4 TOTAL DOSE ...................... 3/4 11-23 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM .................. 3/4 12-1

{ 3/4.12.2 LAND USE CENSUS . . . . . . . . . . . . . . . . . . . . 3/4 12-10 3/4.12.3 INTERLABORATORY COMPARIS0N PROGRAM .......... 3/4 12-12 i

BEAVER VALLEY - UNIT 1 XI i

i

INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY ....................... B 3/4 0-1 l

4 3/4.1 REACTIVITY CONTROL SYSTEMS

3/4.1.1 B0 RATION CONTROL ................... B 3/4 1-1 3/4.1.2 B0 RATION SYSTEMS ................... B 3/4 1-2 3/4.1.3 M0VABLE CONTROL ASSEMBLIES .............. B 3/4'l-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE . . . . . . . . . . . . . . . . . B 3/4 2-1 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 OUARDRANT POWER TILT RATIO . . . . . . . . . . . . . . . B 3/4 2-5 3/4.2.5 DNB PARAMETERS .................... B 3/4 2-6 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 3/4.3.3 MONITORING INSTRUMENTATION .............. B 3/4 3-2 i

l 3/4.3.3.1 Radiation Monitoring Instrumentation ......... B 3/4 3-2 3/4.3.3.2 Movable 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 3/4.3.3.6 Fire Detection Instrumentation ............ B 3/4 3-3 BEAVER VALLEY - UNIT 1 XII i

INDEX BASES j SECTION PAGE 3/4.3.3.7 Chlorine Detection Systems .............. B 3/4 3-3 3/4.3.3.8 Accident Monitoring Instrumentation . . . . . . . . . . B 3/4 3-3 3/4.3.3.9 Radioactive Liquid Effluent Monitoring Instrumentation. B 3/4 3-4 3/4.3.3.10 Radioactive Gaseous Effluent 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 1 3/4.4.5 STEAM GENERATORS ................... B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE ............ B 3/4 4-3 3/4.4.6.1 Leakage Detection System ............... B 3/4 4-3 3/4.4.6.2 Operational Leakage . . . . . . . . . . . . . . . . . . B 3/4 4-3 3/4.4.7 CHEMISTRY . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-4 4

3/4.4.8 SPECIFIC ACTIVITY . . . . . . . . . . . . . . . . . . E 3/4 4-4 3/4.4.9 PRESSURE / TEMPERATURE LIMITS . . . . . . . . . . . . . . B 3/4 4-5 3/4.4.10 STRUCTURAL INTEGRITY ................. B 3/4 4-10 4

3/4.4.11 RELIEF VALVES . . . . . . . . . . . . . . . . . . . . . B 3/4 4-10 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 ACCUMULATORS ..................... B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS . . . . . . . . . . . . . . . B 3/4 5-1 1

BEAVER VALLEY - UNIT 1 XIII l

INDEX BASES 1

SECTION PAGE 3/4.5.4 BORON INJECTION SYSTEM ................ B 3/4 5-1 3/4.5.5 (MovedteBasesSection3/4.1.2) 1 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 Airlocks ................ 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 3/4.6.2.2 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 3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM 3/4.6.5.1 Steam Jet Air Ejector . . . . . . . . . . . . . . . . B 3/4 6-3 3/4.6.5.2 Deleted by Amendment No. 78.

i 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 Safety Valves . . . . . . . . . . . . . . . . . . . . B 3/4 7-1 BEAVER VALLEY - UNIT 1 XIV l

-. _- - .= . - . -- .- ._ - _ - - - - _ . - . . . ~ .. . .

i INDEX l

BASES-i h SECTION PAGE i

1 .

1 i

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 7 3/4.7.1.4 Activity ...................... B 3/4 7-3 3/4.7.1.5 Main Steam Line Isolation Valves .......... B 3/4 7-3 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION . . . B 3/4 7-4 j 3/4.7.3 COMPONENT COOLING WATER SYSTEM ........... B 3/4 7-4 i

3/4.7.4 RIVER WATER SYSTEM ................. .

B 3/4 7-4

3/4.7.5 ULTIMATE HEAT SINK ................. B 3/4 7-4 I L j 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 1

j 3/4.7.8 SUPPLEMENTAL LEAK COLLECTION AND RELEASE SYSTEM . . . B 3/4 7-5 I ,

3/4 7.9 SEALED SOURCE CONTAMINATION . . . . . . . . . . . . . B 3/4 7-5 3/4.7.10 and 3/4.7.11 Deleted by Amendment No. 43 4

3/4.7.12 SNUBBERS ...................... B 3/4 7-6 .

1 3/4.7.13 AUXILIARY RIVER WATER SYSTEM ............ B 3/4 7-7 i

3/4.7.14 FIRE SUPPRESSION SYSTEMS .............. B 3/4 7-7

! 3/4.7.15 FIRE RATED ASSEMBLIES . . . . . . . . . . . . . . . . B 3/4 7-7 i

i j 3/4.8 ELECTRICAL. POWER SYSTEMS 3/4.8.1 and 3/4.8.2 A.C. SOURCES, D. C. SOURCES AND ONSITE POWER I DISTRIBUTION SYSTEMS ................ B 3/4 8-1 4

I i

i BEAVER VALLEY - UNIT 1 XV L

i 1

l 1

INDEX BASES SECTION PAGE

3/4.9 REFUELING OPERATIONS i 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 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 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND STORAGE P0OL ........................ B 3/4 9-3 3/4.9.12 and 3/4.9.13 FUEL BUILDING VENTILATION SYSTEM .... B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN . . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS B 3/4 10-1 3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS-REACTOR CRITICALITY. B 3/4 10-1 3/4.10.4 PHYSICS TESTS . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.5 NO FLOW TESTS . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 4

BEAVER VALLEY - UNIT 1 XVI

INDEX BASES SECTION PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 Concentration ................... B 3/4 11-1 3/4.11.1.2 Dose ........................ B 3/4 11-1 3/4.11.1.3 Liquid Waste Treatment ............... B 3/4 11-2 3/4.11.1.4 Liquid Holdup Tanks . . . . . . . . . . . . . . . . . B 3/4'11-2 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 Dose Rate . . . . . . . . . . . . . . . . . . . . . . B 3/4 11-2 3/4.11.2.2 Dose, Noble Gases . . . . . . . . . . . . . . . . . . B 3/4 11-3 3/4.11.2.3 Dose, Radiciodines, Radioactive Material in Particulate Form and Radionuclides other than Noble Gases . . . . B 3/4 11-4 3/4.11.2.4 Gaseou; Radwaste Treatment ............. B 3/4 11-5 3/4.11.2.5 Gas Storage Tanks . . . . . . . . . . . . . . . . . . B 3/4 11-5 3/4.11.2.6 Explosive Gas Mixture . . . . . . . . . . . . . . . . B 3/4 11-5 3/4.11.3 SOLID RADI0 ACTIVE WASTE . . . . . . . . . . . . . . . B 3/4 11-6 3/4.11.4 TOTAL DOSE ,.................... B 3/4 11-6 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM ................. B 3/4 12-1 3/4.12.2 LAND USE CENSUS . . . . . . . . . . . . . . . . . . . B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARIS0N PROGRAM ......... B 3/4 12-1 BEAVER VALLEY - UNIT 1 XVII

INDEX 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 5.1.5 Flood Control . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.2 CONTAINMENT 5.2.1 Configuration . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.2.2 Design Pressure and Temperature . . . . . . . . . . . . . . 5-4 5.2.3 Penetrations ....................... 5-4 5.3 REACTOR CORE 5.3.1 Fuel Assemblies . . . . . . . . . . . . . . . . . . . . . . 5-4 5.3.2 Control Rod Assemblies .................. 5-4 5.4 REACTOR COOLANT SYSTEMS 5.4.1 Design Pressure and Temperature . . . . . . . . . . . . . . 5-5 5.4.2 Volume .......................... 5-5 5.5 EMERGENCY CORE COOLING SYSTEMS . . . . . . . . . . . . . . . . 5-5 5.6 FUEL STORAGE 5.6.1 Criticality . . . . . . . . . . . . . . . . . . . . . . . . 5-5 5.6.2 Drainage ......................... 5-5 5.6.3 Capacity ......................... 5-6 5.7 SEISMIC CLASSIFICATION . . . . . . . . . . . . . . . . . . . . 5-6 5.8 METEOROLOGICAL TOWER LOCATION ................ 5-6 BEAVER VALLEY - UNIT 1 XVIII

a INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY . . . . . . . . . . . . . . . . . . . . . . 6-1 6.2 ORGANIZATION 6.2.1 Offsite ...................... 6-1 6.2.2 Facility Staff ................... 6-1 l

6.3 FACILITY STAFF QUALIFICATIONS .............. 6-5 6.4 TRAINING ........................ 6-5 6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY CCFNITTEE (OSC) 6.5.1.1 Function ...................... 6-5 6.5.1.2 Composition . . . . . . . . . . . . . . . . . . . . . 6-5 6.5.1.3 Alternates ..................... 6-6 6.5.1.4 Meeting Frequency . . . . . . . . . . . . . . . . . . 6-6 6.5.1.5 Quorum ....................... 6-6 6.5.1.6 Responsibilities .................. 6-6 I

6.5.1.7 Authority . . . . . . . . . . . . . . . . . . . . . . 6-7 6.5.1.8 Records . . . . . . . . . . . . . . . . . . . . . . . 6-7 i

6.5.2 0FFSITEREVIEWCOMMITTEE(ORC) 6.5.2.1 Function ...................... 6-7 6.5.2.2 Composition . . . . . . . . . . . . . . . . . . . . . 6-8 6.5.2.3 Alternates ..................... 6-8 BEAVER VALLEY - UNIT 1 XIX

1NDEX ADMINISTRATIVE CONTROLS SECTION PAGE 1

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 Au t h o ri ty . . . . . . . . . . . . . . . . . . . . . . 6-11 6.5.2.10 Records . . . . . . . . . . . . . . . . . . . . . . . 6-11 6.6 REPORTABLE EVENT ACTION ................. 6-11 6.7 SAFETY LIMIT VIOLATION . . . . . . . . . . . . . . . . . . 6-12 6.8 PROCEDURES . . . . . . . . . . . . . . . . . . . . . . . . 6-12 6.9 REPORTING REQUIREMENTS . . . . . . ........... 6-13 6.9.1 Routine Reports .................. 6-13 6.9.1,2,3 Startup Report .................. 6-13 6.9.1.4,5 Annual Reports .................. 6-14 6.9.1.6 Monthly Operating Report .............. 6-15 6.9.1.7,8,9 Deleted by Amendment No. 84 i

6.9.1.10,11 Annual Radiological Environmental Report . . . . . 6-15

6.9.1.12,13 Semi-Annual Radioactive Effluent Release Report . 6-21 l

6.9.1.14 Radial Peaking Factor Limit Report ......... 6-22 !

i l

BEAVER VALLEY - UNIT 1 XX l

INDEX t

ADMINISTRATIVE CONTROLS

{

, SECTION PAGE t

I

. 6.9.2 SPECIAL REPORTS .................... 6-22

, 6.10 RECORD RETENTION ,................... 6-23 6.11 RADIATION PROTECTION PROGRAM .............. 6-25 i 6.12 HIGH RADIATION AREA . . . . . . . . . . . . . . . . . . 6-25 i

6.13 Deleted by Amendment No. 95 1

6.14 PROCESS CONTROL PROGRAM (PCP) . . . . . . . . . . . . . . 6-27 6.15 0FFSITE DOSE CALCULATION MANUAL . . . . . . . . . . .. 6-27

6.16 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS .. 6-28 i

6.17 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . . . . . . 6-31 4

1 i ;

1 i

l l

l ?

I l

f I BEAVER VALLEY - UNIT 1 XXI 1

- _- _. _ - . . _ - _ _. =-=

TABLE fNDEX TABLE TITLE PAGE 2.2-1 Reactor Trip System Instrumentation Setpoints 2-6 3.1-1 Accident Analyses Requiring Re-evaluation in the 3/4 1-19A event of an Inoperable Full or Part Length Rod 3.2-1 DNB Parameters 3/4 2-13 3.3-1 Reactor Trip System Instrumentation 3/4 3-2 3.3-2 Reactor Trip System Instrumentation Response Times 3/4 3-9 i

4.3-1 Reactor Trio System Instrumentation Surveillance 3/4 3-11 Requirements 3.3-3 Engineered Safety Features Actuation System 3/4 3-15 Instrumentation 3.3-4 Engineered Safety Features Actuation System 3/4 3-22 Instrumentation Trio Setpoints 3.3-5 Engineered Safety Feature Response Times 3/4 3-25 4.3-2 Engineered Safety Feature Actuation System 3/4 3-29 Instrumentation Surveillance Reautrements 3.3-6 Radiation Monitoring Instrumentation 3/4 3-34 4.3-3 Radiation Monitoring Instrumentation Surveil- 3/4 3-36 lance Reautrements 1

3.3-7 Seismic Monitoring Instrumentation 3/4 3-39 4.3-4 Seismic Monitoring Instrumentation Surveillance 3/4 3-40 Requirements j 3.3-8 Meteorological Monitoring Instrumentation 3/4 3-42

, 4.3-5 Meteorological Monitoring Instrumentation Sur- 3/4 3-43

) veillance Requirements 3.3-9 Remote Shutdown Panel Monitoring Instrumentation 3/4 3-45 l'

4.3-6 Remote Shutdown Monitoring Instrumentation Sur- 3/4 3-46 i veillance Requirements 1 3.3-10 Fire Detection Instruments 3/4 3-48 i

j 3.3-11 Accident Monitoring Instrumentation 3/4 3-51 1

i k

l XXII

Table Index TABLE TITLE PAGE 4.3-7 Accident Monitoring Instrumentation Surveillance 3/4 3-52 Requirements 3.3-12 Radioactive Liquid Effluent Monitoring Instru- 3/4 3-54 mentation 4.3-12 Radioactive Liquid Effluent Monitoring Instru- 3/4 3-57 mentation Surveillance Requirements 3.3-13 Radioactive Gaseous Effluent Monitoring Instru- 3/4 3-60 mentation l

4.3-13 Radioactive Gaseous Effluent Monitoring Instru- 3/4 3-65 mentation Surveillance Requirements 4.4-1 Minimum Number of Steam Generators to be Inspected 3/4 4-10c Ouring Inservice Inspection 4.4-2 Steam Generator Tube Inspection 3/4 4-10d

4.4-3 Reactor Coolant System Pressure Isolation Valves 3/4 4-14c 4

3.4-1 Reactor Coolant System Chemistry Limits 3/4 4-16 4.4-10 Reactor Coolant System Chemistry Limits Sur- 3/4 4-17 eillance Requirements 4.4-12 Primary Coolant Specific Activity Sample and 3/4 4-20 j Analysis Program 4.4-3 Reactor Vessel Material Irradiation Surveillance 3/4 4-26 j Schedule 3.6-1 Containment Penetrations 3/4 6-19a 3.7-1 Maximum Allowable Power Range Neutron Flux High 3/4 7-2 Setpoint With Inoperable Steamline Safety Valves During 3 Loop Operation 3.7-2 Maximum Allowable Power Range Neutron Flux High 3/4 7-3 Setpoint with Inoperable Steamline Safety Valves During 2 Loop Operation 4.7-1 Steamline Safety Valves Per Loop 3/4 7-4 4.1-2 Secondary Coolant System Specific Activity Sample 3/4 7-9 and Analysis System

)

3.8-1 Battery Surveillance Requirements 3/4 8-9a XXI!!

Table Index TABLE TITLE PAGE 4.11-1 Radioactive Liquid Waste Sampling and Analysis 3/4 11-3 Program 4.11-2 Radioactive Gaseous Waste Sampling and Analysis 3/4 11-13 Program 3.12-1 Radiological Environmental Monitoring Program 3/4 12-3 3.12-2 Reporting Levels for Radioactivity Concentrations 3/4 12-6 in Environmental Samples 4.12-1 Maximum Values for the Lower Limits of Detection 3/4 12-7 8 3/4.4-1 Reactor Vessel Toughness Data (unirradiated) B 3/4 4-7 6.2-1 Minimum Shift Crew Composition 6-4 6.9-1 Environmental Radiological Monitoring Program 6-20 Surmary l

1 i

XXIV

Figure Index FIGURE TITLE PAGE 4

2.1-1 Reactor Core Safety Limit - Three Loops in 2-2 l doeration 2.1-2 Reactor Core Safety Limit - Two Loops in Opera- 2-3 tion (One Loop Isolated) 2.1-3 Reactor Core Safety Limit - Two Loops in Opera- 2-4 j tion (No Isolated Loop)

~

3.1-1 Rod Group Insertion Limits Versus Thermal Power 3/4 1-24

- Three Loop Operation l

3.1-2 Rod Group Insertion Limits Versus Thermal Power 3/4 1-25

) - Two Loop Operation 3.2-1 Axial Flux Difference Limits as a Function of 3/4 2-4 i Rated Thermal Power

, 3.2-2 K(z) - Normalized Fn(z) as a function of Core 3/4 2-7. ,

j Height

) 3.2-4 Rod Bow Penalty as a Function of Burnup 3/4 2-9a 4

3.4-1 Dose Equivalent I-131 Primary Coolant Specific 3/4 4-21 Activity Limit Versus Percent of Rated Thermal Power with the Primary Coolant Specific Activity > 1.0 4 uCi/ gram Dose Equivalent I-131

! 3.4-2 Beaver Valley Unit No. 1 Reactor Coolant System 3/4 4-24 Heatup Limitations Applicable for the First 6 EFPY 3.4-3 Beaver Valley Unit No. 1 Reactor Coolant System 3/4 4-25 i Cooldown Limitations Applicable for the First 6 EFPY

! 3.6-1 Maximum Allowable Primary Containment Air Pressure 3/4 6-7 Versus River Water Temperature and RWST Water Temp-erature f

B 3/4.2-1 Typical Indicated Axial Flux Difference Versus B 3/4 2-3 Thermal Power at BOL, B 3/4.4-1 Fast Neutron Fluence (E>l Mev) as a Function of B 3/4 4-6a Full Power Service Life

! B 3/4.4-2 Effect of Fluence, Copper Content, and Phosphorus B 3/4 4-6b i

Content on ARTNDT for Reactor Vessel Steels Per j Reg. Guide 1.99 I

XXV i

Figure Index s

4 FIGURE TITLE PAGE 5.1-1 Site Boundary for Gaseous Effluents for the 5-lb .

Beaver Valley Power.Statico !

5.1-2 . Site Boundary for Liquid Efluents for the Beaver- 5-Ic ,

Valley Power Station 5.1-3 ExcMusionsArea-BeaverValleyPowerStation 5-1d 5.1-4 Low Population Zone - Beaver Valley Power Station 5-le 5.1-5 Gaseous Release Points - Beaver Valley Power 5-2 J Station j

5.1-6 Liquid Release Points - Beaver Valley Power 5-3 Station l

6.2-1 Corporate Organization (Partial) 6-2 t 6.2-2 Facility Organization 6-3 -

i 1~

i l $'

.s l

l XXVI i

I i

REACTOR COOLANT SYSTEM 3/4.~4.11 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.1.1 -(Two) power operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3 ACTION:

a. With less than 2 PORV(s) operable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore two PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.11.1 Each PORV shall be demonstrated OPERABLE:

a. At least once per 31 days by performance of a CHANNEL CHECK of the position indication, excluding valve operation and

b. By performance of- a CHANNEL CALIBRATION in accordance with Table 4.3-7 on the operable PORV(s) Control Channel (s).

4.4.11.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel.

4.4.11.3 The emergency power supply for the PORVs and block valves shall be demonstrated OPERABLE at least once per 18 months by operating the valves through a complete cycle of full travel.

l BEAVER VALLEY - UNIT 1 3/4 4-29 l PROPOSED WORDING

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

a. Source in use (excluding startup ~ sources previou iy subjected to core flux) - At least once per six months for all sealed sources containing radioactive materials.

1. With a half-life greater than 19 iays (excluding Hydrogen 3) and

2. In any form other than gas.

b. Stored sources not in use -

Each. sealed source shall be tested prior to use or transfer to another licensee unless tested within the previous six months. Sealed-sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

c. Startup sources - Each sealed startup source shall be tested prior to being subjected to core flux and following repair or maintenance to the source.

4.7.9.1.3 Reports - A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days if source leakage tests reveal the presence of 1 0.005_microcuries of removable contamination.

BEAVER VALLEY - Unit 1 3/4 7-23 (next page is 3/4 7-26) l PROPOSED WORDING i

. ,-. . ~ . _ _ _ , -. , . . . _ _ . _ _ , . , .

RADIOACTIVE EFFLUENTS DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION I

3.11.2.3 The dose to MEMBER (S) OF THE PUBLIC from radiciodines and radioactive materials in particulate form (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released from the site (see Figure 5.1-1) shall be limited to the following:

a. During any calendar quarter to 1 7.5 mrem to any organ, and

b. During any calendar year to 1 15 mrem to any organ.

APPLICABILITY: At all times ACTION:

a. With the calculated dose from the release of radiciodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6 . 9.-2 , a Special Report, which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits,

b. The provisions of Specifications 3.0.3 and ~3.0.4 are not.

applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations. Cumulative dose contributions shall be determined in accordance with the ODCM at least once every 31 days.

7 l

BEAVER VALLEY - UNIT 1 3/4 11-16 (next page is 3/4.11-18) l PROPOSED WORDING t

- _ _ _ _ . . _ . _ _ . _ _ , . _ , - - . ~ . _ . , . .,..._,_ _.. _._-- _-. _ .. _ , _ - , - -

9 l -

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioact'ive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases

! from the site (see Figure 5.1-1), when averaged over 31 days, would exceed. 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation.

The ' appropriate portions of tqe Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-1) when averaged over 31 days would exceed 0.3 mrem to any organ.

APPLICABILITY: At all times.

ACTION

a. With gaseous waste being discharged without treatment and in excess of the above limits, prepare and subm.t to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability, 3

2. Action (s) taken to restore the inoperable equipment to operational status, and

3. Summary description of action (s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 ' Doses due to gaseous releases from the site shall be J projected at least once per 31 days, in accordance with the ODCM.

't BEAVER VALLEY - UNIT 1 3/4 11-18 (next page is 3/4 11-20) l

-PROPOSED WORDING

ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and' Program Control, U. S. Nuclear Regulatory Commission, Washington, DC 20555, with a copy to the Regional Office, submitted no later than the 15th of each month following the calendar month covered by the report.

6.9.1.7 DELETED 6.9.1.8 DELETED 6.9.1.9 DELETED ANNUAL RADIOLOGICAL ENVIRONMENTAL REPORT 8 6.9.1.10 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year and will include reporting any deviations not reported under 6.9.2 with respect to the Radiological Effluent Technical Specifications.

6.9.1.11 The annual radiological environmental reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports, and an assessment of the observed impacts of the . plant operation on the environment. The_ reports shall also include the results of the land use censuses required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental samples taken during the report period.

In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

3 A single submittal may be made for a multiple unit site. .The submittal should combine these sections that are common to both units.

BEAVER VALLEY - UNIT 1 6-15 (next page is 6-20)

PROPOSED WORDING l

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility l operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION CORPORATE l 6.2.1 The corporate organization for facility management and l technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The facility organization shall be as shown on Figure 6.2-2 and:

a. Each on duty shift shall be composed of at least-the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Operator shall be in the control room when fuel is in the reactor.

c. At least two licensed Operators shall be in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d. An individual qualified in radiation protection procedures shall be onsite when fuel is in the reactor,

e. ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f. A Fire Brigade of at least 5 members shall be maintained on site at all times. The Fire Brigade shall not include 3 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

g. Administrative procedures shall be developed and implemented to limit the working hours of unit staff 'who perform safety-related functions; senior reactor. operators, reactor operators, radiation control technicians, auxiliary operators, meter and control repairman, and all personnel actually performing work on safety related equipment.

BEAVER VALLEY - UNIT 1 6-1 PROPOSED WORDING l

1

ADMINISTRATIVE CONTROLS (Continued)

The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the plant is operating. However, in the event'that unforseen problems require substantial amounts of overtime to be .used, or during extended periods of shutdown for refueling, major maintenance or. major plant modifications, on a temporary basis, the following guidelines shall be followed:

a. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.

b. An individual should not be permitted to work more than 16 hours in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any seven day period, all excluding shift turnover time.

c. A break of at least eight hours should be allowed between work periods, including shift turnover time.

d. Except during extended shutdown periods, the use of overtime should be considered 'on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Plant Manager or predesignated alternate, or higher l levels of management. Authorized deviations to the working hour guidelines shall be documented and available for NRC review.

BEAVER VALLEY - UNIT 1 6-la PROPOSED WORDING I -

a

. DUQUESNE LIGHT CCMPANY I NUCLEAR CRCUP i NUCLEAR GROUP VICE PRESIDENT

_ l SPECM ORC NUCLEAR PROJECTS VICE PRESIDENT l

I I I I NUCLEAR NUCLEAR NUCLEAR QUALITY ENG & CONS OPE R ATIONS SERVICES ASSURANCE GENERAL -' GENERAL GENERAL -

MANAGER MANAGER MANAGER MANAGER l

3

, 5 NUCLEAR SUDGET & QUAllTY $-

! ENGINEERING L CONTROL g

' , ~.

MANAGER DIRECTOR DiMCTOR g 9

T*

HQ

'I W<

NUCLEAR TECHNICAL RADIOLOGICAL PRESERVICE $E CONSTRUCTION SERVICE S

& INSERVICI EO

_ _ CONTROL -

INSPECTION - W MANAGER MANAGER MANAGER "

DINtCTOR k

_a 2 8

. o MANAGEMENT t LANNING ADMIN SERVICES & OUTAGE ' "

MANAGER

_ SERVICES ,

MANAGEMENT MANAGER DIRECTOR DIRECTOR E NGINEE RING SHIPPINGPORT

~

INFORMATION DECON & DECOM NUCLEAR

QA OPERATIONS SERVICES REP SAFETY - '

DIRECTOR MANAGER MANAGER NUCLEAR TRAINING _

MANAGER E

i FIRE PROTECTION PROGRAM RESPONSISILITY l

I SEAVER VALLEY - UNIT 1 6-2 PROPOSED

Af8I(LOBIDL TEDWICfL CIBITEL --------- FUtif ---------- !EWIES -

M IWEER IWWER I

NWIIBl STEF TESTIps MTERIAL f8e OEMT!WS MINTBWCE -

IK -

IIS PUtn IW8E3Enf _

AlWIRTI(BI -

DIECTM DIEET0lt DIRECTM EE0 gnu DIRECT 0n TEDellCIfts DIIEETOR M

STATI(31 E D WIID L -

CGWUER MTERIR.

OEMTIWS MINTBRE OPEMTI(BE -

TESTildi CGITIHL SupEMIEIR ENEWISOR ElpEWIlpt fte PUBIT STEF PEFONWE STEF leELERit IEDWIIDL (IBWUTBt pUtiT WIFT MINTB W E OPEMTI(ps D O ISTRY _

EFEWIRIAS STEF STET DIECT0lt MX1 ERR MINTBREE IE putti STATIM FulENel MINTBRE - DOISTW (PEMTIIS ENEWIEIR STffF FWENDI IEDel!G IE TEDWICfL MX1 Erit MINTBWG fEVIS0llY C3iTIIL STIFF BEllEBilldi OPEMT0lE ELEETRIDL RNEWI! Ell MINTB S E -

SPEWIER IE RJIILIRRY FIIEppi !MIFT (FEMTOM TEDWICfL ELIETRIDL IWYIElm MillTBSE STIFF ICrS PUDIT i

N ~

MINTBIICE IE EVIDI FIMIEtt OLISMTISI - DIIECTult SNEWIER ELIETRICIftS 100 DLIBMTIGI STfFF IK FDEW1 FACILITY ORGANI"ATION FIGURE G.2-2 BEAVER VALLEY - UNIT 1 6-3 - 8EF8 --

PROPOSED WORDING

. __ . -= . - _ _ - - -

i .

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #

. SINGLE UNIT FACILITY L7. CENSE CATEGORY APPLICABLE MODES i QUALIFICATIONS : 1, 2, 3 AND 4 5 AND 6

. . i

. . . . . .- _ . m . ........................... ..... ... - .......................................

SRO* 2 1**

RO 2 1 l Non-Licensed Auxiliary Operator 2 1

) Shift Technical Advisor 1 None Required i ,

Includes the Licensed Senior Reactor Operator serving as the Shift Supervisor.

1

- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE OPERATIONS.

a 1

d Shift crew composition may be one less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

This provision does not permit any shift crew pos'ition to be unmanned upon shift change due to an oncoming shift crewman.being late or absent.

i BEAVER VALLEY - UNIT 1 6-4 PROPOSED WORDING i

i

,,-.-,,.nn----,,, -cv,-r--,,----m, -r-n, .,,,..-~,n-ww-n,----,r-s-,,-m.,--~m--v,---, ,,n-,,-,. , , - ,

, ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility and Radiation Protection staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Radiological Control Manager l who shall meet or exceed the qualifications of Regulatory Guide 1.8,-

September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility ste.ff shall be maintained under the direction of the Nuclear Training Manager and shall meet or exceed the' requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A Training program for the Emergency Squad shall be maintained under the direction of the Nuclear Training Manager and shall mee?. or exceed the requirements of Section 27 of the NFPA Code-1975.

6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC)

FUNCTION 6.5.1.1 The OSC shall function to advise the Plant Manager on all l matters related to nuclear safety.

COMPOSITION 6.5.1.2 The OSC shall be composed of the:

Chairman: Plant Safety Review Director Member: Senior Licensed Operator Member: Radiation Control Foreman Member: Engineer (Maintenance)

Member Engineer (Nuclear Engineering)

Member Engineer (Testing & Plant Performance)

Member shift Technical Advisor Member Chemistry Representative Member Quality Control Coordinator Member Engineer (I&C)

NOTE: The chairman of the OSC shall appoint an individual from each of the above listed job categories to serve as a member of the OSC for a period of at least 6 months.

NOTE: OSC members and alternates shall meet or exceed the minimum l qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The SRO shall meet the qualifications of Section 4.2.2 and the Maintenance Engineer will. meet the qualifications of Section 4.2.3.

BEAVER VALLLEY - UNIT 1 6-5 PROPOSED WORDING i

q ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the OSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in OSC activities at any one time.

MEETING FREQUENCY 6.5.1.4 The OSC shall meet at least once per calendar month and as convened by the OSC Chairman or his designated alternate.

QUORUM 6.5.1.5 A quorum of the OSC shall consist of the Chairman or his designated alternate and 'at least one half of the members including l alternates.

RESPONSIBILITIES 6.5.1.6 The OSC shall be responsible for:

a. Review of 1) all procedures required by Specification 6.8 and changes of intent thereto, 2) any other proposed procedures or changes thereto as determined by the plant Manager to affect nuclear safety.

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to Appendix "A" Technical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e. Investigation of all violations of the Technical Specifications including the~ preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Nuclear Operations General Manager and to l the Chairman of the Offsite Review Committee.

f. Review of all REPORTABLE EVENTS.

g. Review of facility operations to detect potential safety hazards.

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Offsite Review Committee.

BEAVER VALLEY - UNIT 1 6-6 PROPOSED WORDING

-ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The OSC shall:

a. Recommend to the Plant Manager written approval or l disapproval of items considered under 6.5.1.6(a) through (d) above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through-(e) above constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Nuclear Operations General Manager and the Offsite Review Committee of disagreement betWG6n the Osc and the Plant Manager; however, the Plant Manager shall have responsibility for I resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The OSC shall maintain written minutes of each meeting and-copies shall be provided~ to the Nuclear Operations General Manager l and Chairman of the Offsite Review Committee.

6.5.2 OFFSITE REVIEW COMMITTEE (ORC)

FUNCTIO:!

6.5.2.1 The ORC shall . function to provide independent review and audit of designated activities in the areas of:

a. nuclear power plant operations

b. nuclear engineering

c. chemistry and radiochemistry

d. metallurgy

e. instrumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices BEAVER VALLEY - UNIT 1 6-7 PROPOSED WORDING t

ADMINISTRATIVE CONTROLS I

COMPOSITION 6.5.2.2 The ORC shall be composed of the:

Chairman: Vice President, Nuclear 4

Vice Chairman: Nuclear Services General Manager Member: Nuclear Operations General Manager Member: Nuclear and Mechanical Engineering-Director .

Member: Materials and Standards Engineering Director Member: Nuclear Engineering Manager Site Service Manager, Westinghouse -

Member:

Electric Corporation Member: Quality Assurance Manager Member: Effluent Controls and Environmental Monitoring Director Member: Plant Manager Member: Outside Consultant, Chemistry and Radiochemistry Member: Outside Consultant, Operations and Maintenance ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the ORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in ORC activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the ORC Chairman to provide expert advice to the ORC.

BEAVER VALLEY - UNIT 1 6-8 PROPOSED WORDING

. ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.2.5 The ORC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.

QUORUM 6.5.2.6 A quorum of ORC shall. consist of the Cha!.rman or~his designated alternate and at least one half of the members including l alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.

REVIEW 6.5.2.7 The ORC shall review:

a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

d. Proposed changes in Technical Specifications or licenses.

e. Violations of applicable- statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.

f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.

g. All REPORTABLE EVENTS

! h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.

i. Reports and meeting minutes of the OSC.

j. The results of the Radiological Monitoring Program, annual report provided in accordance with specification 6.9.1.10.

BEAVER _ VALLEY - UNIT 1 6-9 PROPOSED WORDING

ADMINISTRATIVE CONTROLS AUDITS (Continued) 6.5.2.9 The ORC shall report to and advise the Vice President, Nuclear on those areas of responsiblity specified in Section 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of ORC activities shall be prepared, approved and distributed as indicated by the following:

a. Minutes of each ORC meeting shall be prepared for and approved by the ORC Chairman or Vice-Chairman within 14 working days l following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be documented in the ORC meeting minutes. l

c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President, Nuclear and to the management positions responsible for the areas audited within 30 days after completion of the audit.-

l 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified in accordance with 10 CFR 50.72 and/or a report be submitted pursuant to the requirements of Section 50.73 to 1G FR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the OSC, and results -

of this review shall be submitted to the ORC.

BEAVER VALLEY - UNIT 1- 6-11 PROPOSED WORDING 1

ADMINISTRATIVE CONTROLS-

6.7 SAFETY LIMIT VIOLATION i

6.7.1 The following actions shall be taken in the evrat a safety Limit is violated:

! a. The facility shall be placed in at least HOT STANDBY within~one (1) hour.

} b. The Safety Limit violation shall be reported to the Commission, i the Nuclear Operations General Manager and to the ORC within 24 l hours.

l- ,

l c. A Safety Limit Violation Report shall be prepared. The report j shall be reviewed. by the on-Site Safety Committee (OSC). This ,

1 report shall describe (1) applicable circumstances preceding the.

violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence,

d. The Safety Limit Violation Report shall be submitted to the-

> Commission,, the ORC and the Nuclear Operations General Manager l

within 14 days of the violation.

I 6.8 PROCEDURES

! L j 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

i j a. The applicable procedures recommended in Appendix "A" of j Regulatory Guide 1.33, November 1972.

b. Refueling operations.

i.

c. Surveillance and test activities of safety related equipment.

t i

! d. Security Plan implementation.

I i e.. Emergency Plan implementation.

i f. Fire Protection Program implementation. I I

j g. PROCESS CONTROL PROGRAM implementation !

l l h. OFFSITE DOSE CALCULATION MANUAL implementation. l l ,

l !

6.8.2 Eaca ' procedure and~ administrative policy of 6.8.1 above and i changes of intent thereto, shall be reviewed by the OSC and approved .

1 by the Plant Manager, predesignated alternate or a predesignated '

i Manager to whom the Plant Manager has assigned in writing the

, responsibility for review and approval of specific subjects j considered by the committee, as applicable.-

I k BEAVER VALLEY - UNIT 1 6-12 PROPOSED WORDING-i

ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

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

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

c. The change is documented, reviewed by the OSC and approved by the Plant Manager within 14 days of implementation. l 6.9 REPORTING REQUIREMENTS 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 Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

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

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

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

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

BEAVER VALLEY - UNIT 1 6-13 PROPOSED WORDING

ADMINISTRATIVE CONTROLS 6.17 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Nuclear Services General Manager delegates the responsibility for the Radiological Environmental Monitoring Program to the Radiological Control Manager (Figure 6.2-1) or his designated alternate.

The Radiological Control Manager is responsible for administering the l offsite Radiological Environmental Monitoring Program. He shall determine that the sampling program is being implemented as described-to verify that the environment is adequately protected under existing procedures. He shall also have the responsibility for establishing, implementing, maintaining and approving offsite environmental program sampling, analyses and calibration procedures.

BEAVER VALLEY - UNIT 1 6-31 PROPOSED WORDING

O O

ADMINISTRATIVE CONTROLS 6.16.3 Background of what constitutes " MAJOR CHANGES" to radioactive l waste systems (liquid, gaseous, and solid).

A. Background

1. 10 CFR Part 50, Section 50.34a(a) requires that each application to construct a nuclear power reactor provide a description of the ~ equipment installed to' maintain control over radioactive material in gaseous and liquid effluents produced during normal reactor operations including operational occurrences.

2.- 10 CFR Part 50, Section 50.34a(b)(2) requires that each application to construct a nuclear power reactor provide an estimate of the quantity of radionuclides expected to be released annually to unrestricted areas in liquid and gaseous effluents produced during normal reactor operation.

3. 10 CFR Par't '50, Section 50.34a(3) requires that each application to construct a nuclear power reactor provide a description- of the provisions for packaging, storage and shipment offsite of solid waste containing radioactive

materials resulting from treatment of gaseous and liquid effluents and from other sources.

4. 10 CFR Part 50, Section 50.34a(3)(c) requires that each application to operate a nuclear power reactor shall include (1) a description of the equipment and procedures for the control of gaseous and liquid effluents and for the maintenance and use of equipment' installed in radioactive waste systems and (2) a revised estimate of the information required in (b)(2) if the expected releases and exposures differ significantly from the estimate submitted in the application for a construction permit.

5. The Regulatory staff's Safety Evaluation Report and amendments thereto issued prior to the issuance of an operating license contains a description of the radioactive waste systems' installed in the nuclear power reactor and a 1 detailed evaluation (including estimated releases of radioactive materials in -liquid and gaseous waste and quantities of solid waste produced from normal operation, estimated annual maximum exposures to an individual in the unrestricted area and estimated exposures to the general population) which shows the capability of these systems to meet the appropriate regulations.

BEAVER VALLEY - UNIT 1 6-30 PROPOSED WORDING i

4 3/4.11 RADIOACTIVE EFFLUENTS BASES Revision 1, October, 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

This specification applies to the release of liquid effluents from Beaver Valley Power Station, Unit No. 1. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

3/4.11.1.3 LIQUID WASTE TREATMENT The requirements that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid .radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents. This specification applies to Beaver Valley Power Station, Unit No. 1.

3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that 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 II, Column l 2, at the nearest portable water supply and the nearest surface water supply in an unrestricted area.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose at anytime at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 BEAVER VALLEY - UNIT 1 B 3/4 11-2 PROPOSED WORDING

V ATTACHMENT B No Significant Hazard Determination Proposed Change Request No. 106 amends the Beaver Valley Power Station, Unit No. 1 Technical Specification Administration Controls section to reflect the Nuclear Group reorganization, update the index and delete blank pages.

Description of amendment request: The proposed amendment would update the technical specification index to reflect the current status of the technical specifications. Blank pages are proposed to be deleted. Section 6, Administrative Controls has been revised to reflect the Nuclear Group reorganization. The following changes are proposed:

The index, pages I through XXVI has been updated and includes Tables and Figures.

The following pages have bean revised to remove blank pages:

page Change 3/4 1-26 deleted a blank page 3/4 4-29 deleted a blank page 3/4 4-30 deleted a blank page 3/4 4-31 renumbered to 3/4 4-29 3/4 5-8 deleted a blank page 3/4 7-23 added a note (next page is 7-26) 3/4 7-24 deleted a blank page 3/4 7-25 deleted a blank page 3/4 11-16 added a note (next page is 3/4 11-18) 3/4 11-17 deleted a blank page 3/4 11-18 added a note (next page is 3/4 11-20) 3/4 11-19 deleted a blank page 6-15 Sections 6.9.1.9, 6.9.1.10 and 6.9.1.11 were moved to page 6-15, therefore, pages 6-16/6-17, 6-18 and 6-19 are no longer required; added a note (next page is 6-20) since the above pages would be deleted.

( Attachment B Pago 2 Sections 6.1.1,6.2.2(g),6.5.1.1,6.5.1.6(a),6.5.1.7(a),6.5.1.7(c),

6.8.2, 6.8.3(c) revised the title Plant Superintendent to Plant Manager.

Section 6.2 and 6.2.1, changed "Offsite Organization" to specify

" Corporate Organization".

Figure 6.2-1, revised the titles of the next level'of management reporting to the General Managers and incorporated the next level of management reporting to the Quality Assurance Manager. The title of this figure has been revised to "Corprrate Organization (Partial)".

Figure 6.2-2, revised the Facility Organization chart to identify the new titles of the personnel reporting to the Plant Manager and Technical Services Manager.

Table 6.2-1, deleted the ## note, this note was a temporaiy change to allow plant operation with one reactor operator to fulfill the minimum shift crew requirements until December 1, 1983. This condition has expired.

Sections 6.3.1 and 6.17, revised the title Radiological Operations Coordinator to Radiological Control Manager.

Section 6.4.1 and 6.4.2, revised the title Director, Nuclear Division Training to Nuclear Training Manager. Section 6.4.2 has also been revised to correct a typographical error to NFPA-1975.

Section 6.5.1.2, revised the titles of the OSC membership to reflect the new titles specified by the reorganization. The second note was also revised to require OSC alternate members to meet the same minimum qualifications as the OSC members.

Sections 6.5.1.6.a and 6.8.2, revise ' the. 0SC review requirements to specify changes "of intent", this woJ,d decrease the OSC work load by reducing the changes that must be reviewed by the OSC; such as correcting typographical errors, reformatting procedures and other changes not affecting the purpose for which the procedure is performed.

Section 6.5.1.6(e), 6.5.1.7(c), 6.5.1.8, 6.7.1(b), 6.7.1(d), revised the title Manager of Nuclear Operations to Nuclear Operations General Manager.

Section 6.5.2.2, revised the titles of the ORC membership to reflect the new titles specified by the reorganization.

Section 6.5.1.5, revised the number of OSC members required to fulfill l

a quorum and specify a quorum will consist of at least one half of the members.

Section 6.5.2.6, revised the number of ORC members required to fulfill a quorum to specify a quorum will consist of at least half of the l members.

Attachment B Page.3 4

i l

Section 6.5.2.7(j), revised this ORC review requirement to reference j the Radiological Environmental Monitoring Program and annual report provided in accordance with specification 6.9.1.10.

i Section 6.5.2.10.a. has been revised to require preparation and j approval of the ORC meeting minutes within 14 working days following each meeting. This change would allow adequate time for preparation, review and approval of the minutes in consideration of vacations, holidays, weekends and the additional level of approval required in accordance with the reorganization. In addition, this section has been revised to allow the ORC Vice-Chairman to review and approve the ORC meeting minutes.

Section 6.5.2.10.b has been revised to require the reports of reviews

encompassed by Section 6.5.2.7 to be documented in the ORC meeting minutes.

Section 6.5.2.10.d has been deleted since the Vice President, Nuclear is the ORC chairman and performs the ORC meeting minute review and approval.

Section 6.13.3, to correct a typographical error; this was renumbered to 6.16.3.

l Section 6.17, revised the title Manager of Nuclear Safety and

Licensing to Nuclear Services General Manager.

Section B 3/4 11.1.4, to correct a typographical error 10CFR20 Appendix.A was revised to Appendix B.

Basis for proposed no significant hazards consideration determination: The proposed amendment is considered to be administrative in nature since updating the index, deleting blank pages and the reorganization, includin~g title changes and minor editorial revisions will have no adverse effect on the safe operation i of the plant.

Based on the criteria for defining no significant hazards consideration setforth in 10CFR 50.92(c), plant operation in accordance with the proposed 4

amendment would not:

i (1) involve a significant increase in the probability or consequences of an

accident previously evaluated since the changes are administrative in l nature and the title changes and minor editorial revisions will have no

adverse affect on the safe operation of the plant. The OSC and ORC I membership will continue to perform the required functions and maintain a sufficient level of personnel experience to provide the required review capability.

(2) create the possibility of a new or different kind of accident from any -

previously evaluated since no change in plant operations or to equipment or components is required; the changes reflect the Nuclear Group reorganization and will not affect the safe operation of the plant.

l 1

. Attachment B Pcge 4 (3) involve a significant reduction in the margin of safety since the changes are administrative in nature, will not affect the safe operation of the 4

plant and do not affect the bases for any technical specification.

Therefore, based on the above, it is proposed to characterize the-change as involving a no significant hazard consideration.

d J

J r

I i

l t

-

ML20137L991

Text

Navigation menu

Search