ML20073L527

Amend 68 to License NPF-38,changing TS by Removing TS on Radioactive Effluents & Radiological Environ Monitoring & Relocating Specs on Solid Radwastes to Process Control Program,Per Generic Ltr 89-01

ML20073L527
Person / Time
Site:	Waterford
Issue date:	04/24/1991
From:	Quay T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20073L532	List: ML20073L527 ML20073L535
References
GL-89-01, GL-89-1, NUDOCS 9105140007
Download: ML20073L527 (51)

Text

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UNITED STATES g

NUCLEAR REGULATORY COMMISSION

'sl W ASHINGTON, D. C. 20555

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ENTERGY OPERATIONS, INC.

DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 68 License No. NPF-38 j

1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Entergy Operations, Inc.

(the licensee) dated December 7, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, i

as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reesonable 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.

9103140007 910424 PDR ADOCK 05000382 P

PDR

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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.

NPF-38 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 68, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Frotection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NDCLEAR REGULATORY COMMISSION c) n,

.h4T 0[*

e Theodore R. Quay, Director Project Directorate IV-1 Division of Reactor Projects III, IV, and V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 24,1991

I ATTAEHMENT TO LICENSE AMENDMENT NO. 6R TO FAClllTY OPERATING LICENSE NO. NPT-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

The corresponding overlesf pages are also provided to maintain document completeness.

P REMOVE PAGES INSERT PAGES 11 11 V

V X

X XIV XIV XVII XVil XVill XV111 XXI XXI XXII XX11 l

1-4 14 l

1-5 1-5 l

1 -7 1-7 3/4 3-55 3/4 3-55 3/4 3-56 3/4 3-57 3/4 3-58 3/4 3-59 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 3/4 3-64 3/4 3-64 3/4 3-65 3/4 3-55 3/4 3-66 3/4 3 66 i

3/4 3-67 3/4 3-67 3/4 11-1 3/4 11-1 3/4 11-2 1

3/4 11-3 l

3/4 11-3a i

3/4 11-4 l

3/4 11-5 3/4 11-Sa 3/4 11-6 3/4 11-7 3/4 11-9 3/4 11-9 3/4 11-10 3/4-11-11 3/4 11-12 0/4 11-13

1

Page #2 MMOVEPAGES 1HSERT PAGES 3/4 11-14 3/4 11-15 3/4 11-18 3/4 11-19 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 3/4 12-13 3/4 12-14 B 3/4 3-4 B 3/4 3-4 B 3/4 11-1 B 3/4 11-1 B 3/4 11-2 B 3/4 11-2 B 3/4 11-3 B 3/4 11-3 B 3/4 11-4 B 3/4 11-5 B 3/4 11-6 B 3/4 11-7 B 3/4 12-1 B 3/4 12-2 6-16a 6-16b 6-18 6-18 6-19 6-19 6-20 6-20 6-22 6-22 6-23 6-23 6-24 6-24 6-25

I l

j INDEX I

I DEFINITIONS l

SECTION PAGE 4

l 1.0 DEFINITIONS 1.1 ACTI0N......................................................

1-1

1. 2 AXIAL SHAPE INDEX...........................................

1-1 1.3 AZINUTHAL POWER TILT........................................

1-1 1.4 CH ANN E L CA L I B RAT I O N.........................................

1-1 1.5 CHANNEL CHECK...............................................

1-1 1.6 CHANNEL FUNCTIONAL TEST.....................................

1-2

1. 7 CONTAINHENT INTEGRITY..................................... 7 1-2 1.8 CONTROLLED LEAKAGE..........................................

1-2 1.9 C' OREALTERATION.............................................

1-3 1.10 DOSE EQUIVALENT I-131.......................................

1-3 1.11 T-AVERAGE DISINTEGRATION ENERGY.............................

1-3 1.22 ENGINEERED SAFETY FEATURES RESPONSE TIME....................

1-3 1.13 FREQUENCY N0TATION..........................................

1-3 1.14 IDENTIFIED LEAKAGE..........................................

1-3 1.15 MEMBER (S) 0F THE PUBLIC,....................................

1-4 1.16 0FFSITE DOSE CALCULATION MANUAL.............................

1-4 1.17 OPERABLE - OPERABILITY......................................

1-4 t

I 1.18 O P E RAT I O NA L MO D E - H0 D E.....................................

1-4 1.19 PHYSICS TESTS...............................................

1-5 1.20 PLANAR RADIAL PEAKING FACTOR - F 1-5 xy..........................

1.21 PRESSURE BOUNDARY LEAKAGE...................................

1-5 1.22 PROCESS CONTROL PR0 GRAM.....................................

1-5 1.23 PURGE -

PURGING.............................................

1-5 1.24 RATED THERMAL P0WER.........................................

1-6 1.25 REACTOR TRIP SYSTEM RESPONSE TIME...........................

1-6 1.26 REPORTABLE EVENT.........................

1-6 1.27 SHIELD BUILDING INTEGRITY...................................

1-6 l

1.28 SHUTDOWN MARGIN.............................................

1-6 l

l WATERFORD - UNIT 3 I

t l

l

I INDEX DEFINITIONS (Continued)

J SECTION PAGE l

1.29 SITE BOUNDARY...............................................

1-7 1.30 SOFTWARE....................................................

1-7 1.31 oEtETEo.....................................................

1-7 l

1.32 SOURCE CHECK................................................

1-7 1.33 STAGGERED TEST BASIS........................................

1-7 1.34 THERHAL P0WER...............................................

1-7 1.35 UNIDENTIFIED LEAKAGE........................................

1-7 1.36 UNRESTRICTED AREA...........................................

1-8 1.37 VENTILATION EXHAUST TREATMENT SYSTEM........................

1-8 1,38 VENTING.....................................................

1-8 1.39 WASTE GAS HOLDUP SYSTEM.....................................

1-8 l

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WATERFORD - UNIT 3 II Amendment No. 68 l

INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS j

i SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE........................................

3/4 2-1 j

3/4.2.2 PLANAR RADIAL PEAKING FACT 0RS...........................

3/4 2-3 3/4.2.3 AZIMUTHAL POWER TILT....................................

3/4 2-4 3/4.2.4 DNBR MARGIN.............................................

3/4 2-6 3/4.2.5 RCS FLOW RATE...........................................

3/4 2-10 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE....................

3/4 2-11 l

3/4.2.7 AXIAL SHAPE INDEX.......................................

3/4 2-12 3/4.2.8 PRESSURIZER PRESSURE....................................

3/4 2-13 i

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION......................

3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION........................

3/4 3-13 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION.................

3/4 3-28 l

INCORE DETECTORS.....................................

3/4 3-34 l

SEISHIC INSTRUMENTATION..............................

3/4 3-35 HETEOR0 LOGICAL INSTRUMENTATION.......................

3/4 3-38 REMOTE SHUTDOWN INSTRUMENTATION......................

3/4 3-41 ACCIDENT MONITORING INSTRUMENTATION..................

3/4 3-44 CHEMICAL DETECTION SYSTEMS....................,......

3/4 3-47 LOOSE-PART DETECTION INSTRUMENTATION.................

3/4 3-54 l

l EXPLOSIVE GAS MONITORING INSTRUMENTATION.............

3/4 3-60 3/4.3.4 TURBINE OVERSPEED PROTECTION............................

3/4 3-68 l

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WATERFORD - UNIT 3 V

Amendment No. 50.60 1

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INDEX i

LIMITING CONDITION FOR OPERATION AND SURVE1LLANCE DEQUIREMENTS i

SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR C00LART LOOPS AND COOLANT CIRCULATION ST ARTUP AND POWE R O P E RAT!0N.............................

3/4 4 1 HOT STANDBY.............................................

3/4 4 2 HOT SHUTD0WN............................................

3/4 4 3 COLD SHUTDOWN - LOOPS FILLED............................

3/4 4 5 COLD SHUTDOWN - LOOPS NOT FILLED........................

3/4 4 6 3/4.4.2 SAFETY VALVES S H UT D0 WN.............................................

3/4 4 7 OPERATING............................................

3/4 4 8 3/4.4.3 PRESSURIZER PRESSURIZER..........................................

3/4 4 9 AUXILIARY............................................

3/4 4 9a 3/4.4.4 S T E AM G E N E RAT O R S........................................

3/4 4-10 3,/4. 4. 5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS............................

3/4 4 17 O P E RATI ON A L L E A KAG E..................................

3/4 4 18 3/4.4.6 CHEMISTRY...............................................

3/4 4 21 3/4.4.7 SPECIFIC ACTIVITY.......................................

3/4 4 24 3/4.4.8 PRESSURE / TEMPERATURE LIMITS 9

l REACTOR COOLANT SYSTEM...............................

3/4 4 28 PRESSURIZER HEATUP/C00LDOWN..........................

3/4 4-33 7.'

OVERPRESSURE PROTECTION SYSTEMS......................

3/4 4-34 3/4.4.9 STRUCTURAL INTEGR!TY....................................

3/4 4-36 3/4.4.10 REACTOR COOLANT SYSTEM VENTS...........

3/4 4 37 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS..................................

3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - Modes 1, 2, and 3....................

3/4 5-3 i

l 3/4.5.3 ECCS SUBSYSTEMS - Modes 3 and 4........................

3/4 5 8 l

3/4.5.4 REFUELING WATER STORAGE P00L............................

3/4 5 9 l

WATERFORD - UNIT 3 VI Amendment No. 22,34

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.8 _ ELECTRICAL POWER SYSTEMS (Continued) 3/4.8.3 ONSITE P9WER DISTRIBUTION SYSTEMS 0PERATINC............................................

3/4 8-13 S H U T P 0 VN.............................................

3/4 8-15 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES.................................

3/4 8-16 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND BYPASS DEVICES.................................

3/4 8-52 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.....................................

3/4 9-1 3/4.9.2 INSTRUMENTATION.........................................

3/4 9-2 3/4.9.3 DECAY TIME..............................................

3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.,.....................

3/4 9-4 3/4.9.5 COMMUNICATIONS..........................................

3/4 9-5 3/4.9.6 REFUELING RACHINE.......................................

3/4 9-6 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING...................

3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL.....................................

3/4 9-8 LOW WATER LEVEL......................................

3/4 9-9 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM................

3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL FUEL ASSEMBLIES......................................

3/4 9-11 CEAs.................................................

3/4 9-12 3/4.9.11 WATER LEVEL - SPENT FUEL P00L...........................

3/4 9-13 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM...............

3/4 9-14 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN HARGIN.........................................

3/4 10-1 WATERFORD - UNIT 3 IX

I INDEX LIMITING CONDITIONS FOR OPERATIONS AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.10 SPECI AL TEST EXCEPTIONS (Continued) 3/4.10.2 M10, GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS............................

3/4 10-2 3/4.10.3 REACTOR COOLANT L00PS...................................

3/4 10-3 3/4.10.4 CENTER CEA MISAllGNMENT.................................

3/4 10-4 3/4.10.5 NATURAL CIRCULATION TESTING.............................

3/4 10-5 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS i

LIQUID HOLDUP TANKS.....................................

3/4 11-8 3/4.11.2 GASEOUS EFFLUENTS i

EXPLOSIVE GAS MIXTURE..................................

3/4 11-16 GAS STORAGE TANKS......................................

3/4 11-17 WATERFORD - UNIT 3 X

Amendment No. 68

1 INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 COMPONENT COOLING WATER and AUXILIARY COMPONENT COOLING WATER SYSTEMS.................................

B 3/4 7-3 3/4.7.4 ULTIMATE HEAT SINK....................................

B 3/4 7-4 3/4.7.S FLOOD PROTECTION......................................

B 3/4 7-4 3/4.7.6 CONTROL ROOH AIR CONDITIONING SYSTEM..................

B 3/4 7-4 3/4.7.7 CONTROLLED VENTILATION AREA SYSTEM....................

B 3/4 7-4 3/4.7.8 SNUBBERS..............................................

B 3/4 7-5 3/4.7.9 SEALED SOURCE CONTAMINATION...........................

B 3/4 7-7 I

3/4.7.12 ESSENTIAL SERVICES CHILLED WATER SYSTEM...............

B 3/4 7-8 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and ON51TE POWER DISTRIBUTION SYSTEMS..............

B 3/4 8 1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...............

B 3/4 8-3 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 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.S C0KMUNICATIONS........................................

B 3/4 9-1 3/4.9.6 REFUELING HACHIhE.....................................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING.................

B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION..............

B 3/4 0-2 1

WATERFORD - UNIT 3 XIII Amendment No. 50

,INDEX BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS (Continued) 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM..............

B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and S P E NT FU E L P00 L.......................................

B 3/4 9-3 3/4.9.12 FUEL HANDLING 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 MTC, GROUP HEIGHT, INSERTION, AND i

POWER DISTRIBUTION LIMITS...........................

B 3/4 10-1 3/4.10.3 REACTOR COOLANT L00PS.................................

B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT...............................

B 3/4 10-1 3/4.10.5 NATURAL CIRCULATION TESTING...........................

B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.......................................

B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS......................................

B 3/4 11-3 i

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WATERFORD - UNIT 3 X I ','

Amendment No. 68 l

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INDEX ADMINISTRATIVE CONTROLS S.ECTION PAGE l

l 6.5.2 SAFETY REVIEW COMMITTEE...................................

6-10 FUNCTION...............................................

6-10 COMP 051 TION............................................

6-10 ALTERNATES.............................................

6-10 CONSULTANTS............................................

6-10 MEETING FREQUENCY......................................

6-11 QU0 RUM.................................................

6-11 REVIEW.................................................

6-11 AUDITS.................................................

6-12 AUTHORITY..............................................

6-13 REC 0RDS................................................

6-13 l

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l 6.6 REPORTABLE EVENT ACTI0N.....................................

6-13 6.7 SAFETY LIMIT VIOLATION......................................

6-13 6.8 PROCEDURES AND PR0 GRAMS.....................................

6-14 i

j 6.9 REPORTING REQUIREMENTS......................................

6-17 i

l 6.9.1 ROUTINE REP 0RTS...........................................

6-17 l

STARTUP REP 0RT.........................................

6-17 l

ANNUAL REP 0RTS.........................................

6-17 MONTHLY OPERATING REP 0RT...............................

6-18 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.....

6-18 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT.........

6-19 INDUSTRIAL SURVEY OF T0XIC CHEMICALS REPORT............

6-20 6.9.2 SPECIAL REP 0RTS...........................................

6-20

)

l 6.10 RECORD RETENTION...........................................

6-20 i

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l WATERFORD - UNIT 3 XVII Amendment No. 68

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4 INDEX t.DMINISTRATIVE CONTROLS SECTION PAGE 6.11 RADIATION PROTECTION PR0 GRAM...............................

6-22 6.12 HIGH RADIATION AREA........................................

6-22 i

6.13 PROCESS CONTROL PR0 GRAM....................................

6*23 6.14 0FFSITE DOSE CALCULATION MANUAL............................

6-24 l

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WATERFORD - UNIT 3 XVIII Amendment No. 68

INDEX LIST OF TABLES (Continued)

TABLE PAGE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3-40 3.3-9 REMOTE SHUTDOWN INSTRUMENTATION......

3/4 3-42 4.3-6 REMOTE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................

3/4 3-43 3.3-10 ACCIDENT MONITORING INSTRUMENTATION...................

3/4 3-45 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

3/4 3-46 3.3-12 DELETED...............................................

3/4 3-56 4.3-8 DELETED..............................................

3/4 3-58 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION.............

3/4 3-61 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................

3/4 3-65 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION..........................

3/4 4-15 4.4-2 STEAM GENERATOR TUBE INSPECT 10N.......................

3/4 4-16 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES......

3/4 4-20 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY......................

3/4 4-22 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS.............................

3/4 4-23 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM..................................

3/4 4-26 4.4-5 REACTOR VESSEL MATERIAL SURV:ILLANCE PROGRAM - WITHDRAWAL SCHEDULE.........................

3/4 4-32 3.6-1 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS............

3/4 6-5 3.6-2 CONTAINMENT ISOLATION VALVES..........................

3/4 6-21 WATERFORD - UNIT 3 XXI Amendment No. 9, 50, 68

INDEX l

LIST OF TABLES (Continued)

TABLE PAGE 3.7-1 STEAM LINE SAFETY VALVES PER L00P.....................

3/4 7-2 3.7-2 HAXIMUM ALLOWABLE LINEAR POWER LEVEL - HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS..........

3/4 7-3 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM..........................

3/4 7-8 3.7-3 ULTIMATE HEAT SINK MINIMUM FAN REQUIREMENTS..........

3/4 7-14 4.8-1 DIESEL GENERATOR TEST SCHEDULE.......................

3/4 8-7 4.8-la ADDITIONAL RELIABILITY ACTIONS.......................

3/4 8-7a 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS....................

3/4 8-11 3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES...................................

3/4 8-18 3.8-2 MOTOR-0PERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES.....................

3/4 8-53 I

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WATERFORD - UNIT 3 XXII Amendment No. 9, 23, 50, 68 1

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DEFINITIONS w

CORE ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.

l DOSE EQUIVALENT l-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/

gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,1-132, I-133,1-134, and I-135 actually present.

1 The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."

E - AVE' RAGE DISINTEGRATION ENERGY 1.11 I shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopen other than iodines, with half-lives greater than 15 minutes, iking up at least 95% of the total noniodine activity in the coolant.

ENGINEERED SAFETY FEATURES RESPONSE TIME 1.12 The ENGINEERED SAFETY FEATURES RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).

Times shall include diesel generator starting and sequence loading delays where applicable.

FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

a.

Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured, and conducted to a sump or collecting tank, or i

WATERFORD - UNIT 3 1-3

• l t

t DEFINITIONS IDENTIFIED LEAKAGE (Continued) b.

Leakage into the containment atmosphere from sources that are both i

specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.

Reactor Coolant System leakage through a steam generator to the secondary system.

MEMBER (S) 0F THE PUBLIC 1.15 HEMBER(5) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant.

This category does not include employees of the licensee, its contractors, or vendors.

Also. excluded from this category i

are persons who enter the site to service equipment or make deliveries.

This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

0FFSITE DOSE CALCULATION MANUAL (ODCM) l 1.16 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmen-tal Raalological Monitoring Program.

The ODCM shall also contain (1) the Radio-active Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be-included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Specification 6.9.1.7 and 6.9.1.8.

OPERABLE - OPERABILITY 1.17 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when,it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system. subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE 1.18 An OPERATIONAL-MODE (i.e. MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor-coolant temperature specified in Table 1.2.

L WATERFORD - UNIT 3_

1-4 Amendment _No. 68

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DEFINITIONS PHYSICS TESTS 1.19 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PLANAR RADIAL PEAKING FACTOR - Fyy 1.20 The PLANAR RADIAL PEAKING FACTOR is the ratio of the peak to plane average power density of the individual fuel rods in a given horizontal plane, excluding the effects of azimuthal tilt.

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)

PRESSURE BOUNDARY LEAKAGE 1.21 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube i

leakage) through a non isolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

PROCESS CONTROL PROGRAM (PCP) 1.22 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that process-ing 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.

PURGE - PURGING 1.23 PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentra-l tion or other operating condition, in such a manner that replacement air or l

gas is required to purify the confinement.

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WATERFORD - UNIT 3 1-5 Amendment No. 68

.m DEFINITIONS RATED THERMAL POWER 1.24 RATED THERHAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3390 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.25 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

REPORTABLE EVENT 1.26 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

SHIELD BUILDING INTEGRITY 1.27 SHIELD BUILDING INTEGRITY shall exist when:

a.

Each door in each access opening is closed except when the access opening is being used for normal transit entry and exit, then at least one door shall be closed, b.

The shield building filtration system is in compliance with the requirements of Specification 3.6.6.1, and c.

The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0-rings) is OPERABLE.

SHUTOOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a.

No change in part-length control element assembly position, and b.

All full-length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn.

I WATERFORD - UNIT 3 1-6 L

DEFINITIONS SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor t,therwise controlled by the licensee.

SOFTWARE 1.30 The digital computer SOFTWARE for the reactor protection system shall be the program codes including their associated data, documentation, and procedures.

1.31 Definition 1.31 has been deleted.

l SOURCE CHECK 1.32 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is es. posed to a source of increased radioactivity.-

STAGGERED TEST BASIS 1.33 A STAGGERED TEST BASIS shall consist of:

a.

A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and b.

The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER l

1.34 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

UNIDENTIFIED LEAKAGE 1.35 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.

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l WATERFORD - UNIT 3 1-7 Amendment No. 68

DEFINITIONS UNRESTRICTED AREA 1.36 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, com-mercial, institutional, and/or recreational nurposes.

VENTILATION EXHAUST TREATMENT SYSTEM 1.37 A VENTILATION EXHAUST TREATMENT SYSTEM shall be 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 particu-lates 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 EXHAUS1 TREATMENT SYSTEM components.

VENTING _

1,38 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not pro-vided or required during VENTING.

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

WASTE GAS HOLDUP SYSTEM 1.39 A WASTE GAS HOLDUP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting 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.

WATERFORD - UNIT 3 1-8

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Pages 3/4 3-55 through 3-59 have been deleted.

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WATERFORD - UNIT 3 3/4 3-55 AMEN 0 MENT NO. 27' 68 Next page is 3/4 3-60

l INSTRUMENTATI?]

EXPLOSIVE GAS HONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.11 The explosive gas monitoring instrumentation channels shown in l

l Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.

l APPLICABILITY:

As shown in Table 3.3-13.

ACTION:

a.

With an explosive gas monitoring instrumentation channel alarm / trip l

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 l

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 Specifications 3.0.3 and 3.0.4 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 4.3-9.

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l WATERFORD - UNIT 3 3/4 3-60 AMENDMENT NO. Z7, 68 i

TABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRLHENTATION l

MINIMUM CHAhWELS o

INSTRUMENT OPERABLE APPLICABILITY ACTION l

E L

WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS Z

MONITORING SYSTEM 38 w

1 a.

Hydrogen Monitor 40 2

b.

Oxygen Monitors R

n E

E9e2 5

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l NO I

8 0

T 3

4 CA Y

T I

L I

B A

C I

L PPA N

O I

TA TN EM S

U L

R E

T N

S NE 3

N AL 1

I HB CA 3

G R

1 2

N ME 3

I UP R

MO E

O I

L T

N B

I I

A N

M T

OM SAG EV S

I A

S G

O L

E P

V X

I E

SO L

PXE M

ET r

S o

s Y

t r

S i

o M

n t

PE o

i T

UT M

n N

DS o

E LY n

M M

OS e

U H

g n

R G

o e

T SN r

g S

AI d

y N

GR y

x I

O H

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b 1

5 ;;; A @o. E q w t'.

T N 2M 2._ 5.

Page 3/4 3-62 has been deleted.

WATERFORD - UNIT 3 3/4 3-62 AMENDMENT HO.68

TABLE 3.3-13 (Continued)

TABLE NOTATIONS

• Not used.

l

• • During WASTE GAS HOLDVP SYSTEM operation.

1 ACTION STATEMENTS ACTION 35 - ACTION 35 has been deleted ACTION 36 - ACTION 36 has been deleted ACTION 37 - ACTION 37 has been deleted ACTION 38 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the WASTE GAS HOLDUP SYSTEM may continue provided best efforts are made to repair the instrument and that grab semples are collected at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the onservice gas decay tank.

4 ACTION 39 - ACTION 39 has been deleted l

ACTION 40 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the WASTE GAS HOLOUP SYSTEM may continue provided best efforts are made to repair the instrument and that the system is sampled by either the remaining monitor or by a grab sample at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the oxygen concentration remains less than 2%.

If there are no monitors OPERABLE, WASTE GAS HOLOUP SYSTEM operation may continue provided best efforts are made to return at least one channel to OPERABLE status and that a grab sample is taken and analyzed from the onservice gas decay tank at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the oxygen concentration remains less than 1%.

With oxygen concentration exceeding 1%, reduce the oxygen concentration to less than 1% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

WATERFORD - UNIT 3 3/4 3-63 AMENDMENT NO.17, 68

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Page 3/4 3 64 has been deleted WATERFORD - UNIT 3 3/4 3-64 AMEN 0 MENT NO. 17, 68

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r TABLE 4.3-9 D

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EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l~

8 l

CHANNEL MODES IN WHICH i

CHANNEL-SOURCE CHANNEL' FUNCTIONAL SURVEILLANCE.

e c-INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED l

5 l

1.

WASTE GAS HOLDUP SYSTEM EXPLOSIVE l

GAS MONITORING SYSTEM a.

Hydrogen Monitor D

N.A.

Q(4)

M b.

Oxygen Monitors D

N.A.

Q(5)

M s"

L%

W

' h 4

I

- R L si 9

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L5 i

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Page 3/4 3-56 has been deleted l

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WATERFORD - UNIT 3 3/4 3-66 AMENDMENT NO, 68

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TABLE 4.3-9 (Continued)

TABLE NOTATIONS

• Not used.

)

• • During WASTE GAS HOLDUP SYSTEM operation.

(1) Note I has been deleted (2) Note 2 has been deleted (3) Note 3 has been deleted

{

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

1.

Zera volume percent hydrogen, balance nitrogen, and 2.

Four volume percent hydrogen, balance nitrogan, (5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1.

Zero volume percent oxygen, balance nitrogen, and 2.

Four volume percent oxygen, balance nitrogen.

(6) Note 6 has been deleted.

l WATERFORD - UNIT 3 3/4 3-67 AMENDMENT NO. 68

INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CCHDITION FOR OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE.

APPLICABILITY:

MODES 1, 2*, and 3*.

ACTION:

a.

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

j b.

With the above required overspeed protection system otherwise inoperable, j

with 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> isolate the turbine from the steam supply, j

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.

At least once per 31 days by cycling each of the following valves through at least one complete cycle from the running position.

1.

Four high pressure throttle valves.

2.

Four high pressure governor valves.

3.

Six low pressure reheat stop valves.

4.

Six low pressure reheat intercept valves, b.

At least once per 31 days by direct observation of the movement of each of the above valves through one complete cycle from the running position.

c.

At least once per 18 months by performance of a CHANNEL CALIBRATION on the turbine overspeed protection systems.

d.

At least once per 40 months by disassembling at least ene 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 corrosion.

e.

At least once per 40 operating months by inspecting the installed light low pressure turbine discs, and at least once per 60 operating months by inspecting the installed heavy low pressure turbine discs.

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• With any main steam isolation valve and/or any main 3 team line isolation valve bypass valve not fully closed.

WATERFORD - UNIT 3 3/4 3-68 Amendment No.30 l

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Pages 3/4 11-1 through 11-7 have been deleted.

l WATERFORD - UNIT 3 3/4 11-1 AMEN 0 MENT NO. 17, 68 Next page is 3/4 11-8

RA,DI0 ACTIVE EFFLUENTS j

LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION i

i 3.11.1.4 The quantity of radioactive material contained in each of the I

following unprotected outdoor tanks shall be limited to less than or equal to 1

1,57 x 10 2 curies,* excluding tritium and dissolved or entrained noble gases.

For outside temporary storage tanks, the curie content shall be limited such that a rupture will not result in exceeding 10 CFR Part 20 limits at the UNRESTRICTED AREA boundary.

a.

PW5T b.

Outside temporary tank j

APPLICABILITY:

At all times.

l 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, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.11.1.4 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.

i of 2 x 10 5 pCi/mL Cesium-137

• Based on 80% tank capacity and an MPC, Table II.

equivalent, 10 CFR Part 20, Appendix B, l

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l WATERFORD - UNIT 3 3/4 11-8

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l Pages 3/4 11-9 through 11-15 have been deleted.

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i WATERFORD - UNIT 3 3/4 11-9 AMENDMENT NO. 68 Next page is 3/4 11-16

n_-.-.- -

4 RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be

- limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY:

At all times.

ACTION:

a.

With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 2% by volume but less than or equal-to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, b.

With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume,-immediately suspend all additions of waste gases to the system and immediately reduce the concentration of oxygen to less than or equal to 4% by volume and then take the ACTION in a.

above, c.

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

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen'in the WASTE GAS HOLDUP SYSTEM shall-be determined to be within the above limits by monitoring the waste gases in the WASTE GAS HOLOUP SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.11.

I-WATERFORD - UNIT 3 3/4 11-16

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 8.5 x 104 curies noble gases (considered as Xe-133).

APPLICABILITY:

At all times.

ACTION, With the quantity of radioactive material in any gas storage tank a.

exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank on-service shall be determined to be within the above limit at least once per 7 days until the quantity exceeds 4.25 x 104 curies noble gases (50% of allowed limit) and then at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.

Tanks isolated for decay will be sampled to verify above limit is met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following removal from service.

WATERFORD - UNIT 3 3/4 11-17

4 4

Pages 3/411-18 and 11-19 have been deleted.

WATERFORD - UNIT 3 3/4 11-18 AMENDMENT NO. 68

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INSTRUMENTATION BASES 3/4.3.3.10 This section has been deleted.

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

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

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

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I WATERFORD - UNIT 3 B 3/4 3-4 Amendment No. 68

3/4.11 RADIDACTIVE EFFLUENTS BASES-3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 This section deleted.

3/4.11.1.2 This section deleted.

3/4.11.1.3 This section deleted.

3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

Restricting the quantity of radioactive material contained in the specified tanks provides 63Gurance that in the event of an uncontrolled release of the tank's contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

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il' WATERFORD - UNIT 3 8 3/4 11-1 Amendment No. 68

Page B 3/4 11-2 has been deleted.

I WATERFORD - UNIT 3 8 3/4 11-2 Amendment No. 68

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RADI0AC1IVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 This section is deleted.

3/4.11.2.2 This section is deleted.

3/4.11.2.3 This section is deleted.

3/4.11.2.4 This section is deleted.

3/4.11.2.5 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.

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.

3/4.11.2.6 GAS STORAGE TANKS This specification considers postulated radioactive releases due to a waste gas system leak or failure, and limits the quantity of radioactivity centained in each pressurized gas storage tank in the WASTE GAS HOLDUP SYSTEM to assure that a release would be substantially below the guidelines of 10 CFR Part 100 for a postulated event.

Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest exclusion area boundary will not exceed 0.5 rem.

This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0800, July 1981.

WATERFORD - UNIT 3 8 3/4 11-3 Amendment No.68

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ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) f.

Radioactive Effluent Controls Program 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 lir..its are exceeded.

The program shall include the following elements:

1.

Limitations on the operability of radioact.ve 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 II, Column 2, 3.

Monitoring, sampling,-and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, 4.

Limitations on the annual and quarterly doses er dose commitment ta a MEMBER OF THE PUBLIC from radioactive materials in liquid efiluents 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 radioactive effluents for the current calendar quarter and current calendar year i_n 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 :q CFR Part 50, 7.

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE B0UNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 1

kATERFORD - UNIT 3 6-16a AMENDMENT NO. 68

- < - ~,,,.

-~

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+,

o ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.4 f.

Radioactive Effluent Controls Program (Continued) 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 radio-nuclides 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, and 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.

g.

Radioloaical Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.

The program shall provide (1) represen-tative measurements of radioactivity in the highest potential exposure

. pathways, and (2) verification of the accuracy of the effluent moni-toring program and modeling of environmental exposure pathways.

The program shall-(1) be' contained in-the ODCM, (2) conform to the guid-ance 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 areas at and beyond.the SITE-BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3.

Participation in a-Interlaboratory Comparison Program to ensure that independent checks on the precision and-accuracy of the measurement of radioactive materials in environmental sample i

matrices are performed as part of the quality assurance program l

for environmental monitoring.

WATERFORD - UNIT 3 6-16b AMENDMENT NO. 68

• ADMINISTRATIVE CONTROLS 4

MONTHLY OPERATING REPORTS 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.7 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May I of each year.

The report shall include summaries, interpretations, and analysis of trends of the results of the Radiolo0ical Environmental Moni-toring Program for the reporting period.

The material provided shall be con-sictent 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.

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l WATERFORD - UNIT 3 6-18 AMENDMENT N0. 68

ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.8-The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 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.

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WATERFORD - UNIT 3 6-19 AMENDMENT NO. 68 l

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ADMINISTRATIVE CONTROLS INDUSTRIAL SURVEY OF T0XIC OR HAZARDOUS CHEMICALS REPORT 1

6,9.1.9 Surveys and analyses of major industries in the vicinity of Waterford 3 which could have significant inventories of toxic chemicals onsite to determine impact on safety shall be performed and submitted to the Commission at least once every 4 years.

6.9.1.10 A-survey of major pipelines (> 4 inches) within a 2-mile radius of Waterford 3, which contain explosive or flammable materials and may represent a hazard to Waterford 3, including scaled engineering drawings or maps which indicate the pipeline locations, shall be performed and submitted to the Commission at least once every 4 years.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

WATERFORD - UNIT 3 6-20 AMENDMENT N0. 68

.o ADMINISTRATIVE CONTROLS RECORD RETENTIOj (Continued) 6.10.2 The following records shall be retained for at least 5 years:

Records and logs of unit operation covering time interval at each a.

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.

Records of changes made to the procedures required by Specification 6.8.1.

e.

f.

Records of radioactive shipments.

g.

Records of sealed source and fission detector leak tests and results.

h.

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

6.10.3 The following records shall be retained for the duration of the unit Operating License:

a.

Records and drawing changes reflecting unit design modifications i

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

b.

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

c.

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

d.

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

e.

Records of transient or operational cycles for those unit components identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

g.

Records of training and qualification for current members of the unit staff.

h.

Records of inservice inspections performed pursuant to these Technical Specifications.

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\\!ATERFORD - UNIT 3 6-21 i

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ADMINISTRATIVE CON 1ROLS RECORD RETENTION (Continued) 1.

Records of quality assurance activities required by the QA Manual, j.

Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the PORC and the SRC.

1.

Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records.

m.

Records of secondary water sampling and water quality.

n.

Records of audits performed under the requirements of Specification 6.5.2.8.

o.

Records of analyses required by the radiological environmental monitoring program that would permit evaluation of the accuracy of the analysis at a later date.

This should include procedures effective at specified times and QA records showing that these procedures were followed.

p.

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

6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consis-tent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the inten-sity of radiation is greater than 100 mrem /h but less than 1000 mrtm/h shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)*.

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.

• Health physics personnel or personnel escorted by health physics personnel shall be exempt f rom the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

WATERFORD - UNIT 3 6-22 AMENDMENT NO. 68 l

ADh1NISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) 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.

A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activi-ties within the area and shall perform periodic radiation surveil-lance at the frequency specified by the facility Radiation Protection Supierintendant-Nuclear in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of tha body could receive in one hour a dose greater than 10000 mrems* shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision.

Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrems* that are located within large areas, such as PWR containment, where no enclosure exists for purposes of lock-ing, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

In lieu of the stay time specifica-tion of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by persorael qualified in radiation protection procedures to provide positive ex90sure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6,13.2 Licensee-initiated changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p.

This documentation shall contain:

1.

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

• Measurement made at 18 inches from source of radioactivity.

WATERFORD - UNIT 3 6-23 AMENDMENT NO.68

ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued) 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 PORC and the approval of the Plant Manager.

6.14 0FFSITE 00SE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.

6.14.2 Licensee-initiated changes to the ODCil:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p.

This document 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 20.106, 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.

l b.

-Shall become effective after review and acceptance by the PORC and i-the approval of the Plant Manager.

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 Semiannual Radioactive Effluent Release Report for the period of the-report in which any change to the 00CM 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.

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l WATERFORD - UNIT 3 6-24 AMENDMENT ND. 68 l