Text

Technical Specifications, Amendment 188
	ML030940420
Person / Time
Site:	Waterford
Issue date:	04/03/2003
From:	Kalyanam N; NRC/NRR/DLPM/LPD4
To:	Venable J; Entergy Operations
Shared Package
ML030930337	List: ML030930318; ML030940420;
References
	TAC MB7150
	Download: ML030940420 (50)
	v • d • e

A UNITED STATES NUCLEAR REGULATORY COMMISSION 0

WASHINGTON, D.C. 20555-0001 April 3, 2003 Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 - ISSUANCE OF AMENDMENT RE: CORRECTIONS AND CLARIFICATIONS TO VARIOUS TECHNICAL SPECIFICATION PAGES (TAC NO. MB7150)

Dear Mr. Venable:

The Commission has issued the enclosed Amendment No. 188 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3 (Waterford 3). The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated December 20, 2002.

The amendment makes several administrative changes to the Waterford 3 TSs, to revise, delete, correct, or clarify certain titles, page numbers, and heading information. The amendment also revises personnel and committee titles that have been changed, revises administrative reporting requirements to conform to 10 CFR 50.4, and deletes redundant or unnecessary requirements from TSs 5.4, 6.6, and 6.7.

A copy of our related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely, N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382

Enclosures:

1. Amendment No. 188 to NPF-38

2. Safety Evaluation cc w/encls: See next page

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY OPERATIONS. INC.

DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 188 License No. NPF-38

1.

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

A.

The application for amendment by Entergy Operations, Inc. (EOI) dated December 20, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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. 188, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 3, 2003

ATTACHMENT TO LICENSE AMENDMENT NO. 188 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert V

V VI VI VII VIl Vil Vill Xi Xi XII Xii XIII XilI XIV XIV XV XV XVI XVI XVII XVII XVIII XVIII XIX XIX XX XX XXI XXI XXII XXII 2-1 2-1 3/4 3-4a 3/4 3-4a 3/4 3-17 3/4 3-17 3/4 3-18a 3/4 3-18a 3/4 4-32 3/4 4-32 3/4 7-16 3/4 7-16 3/4 7-18 3/4 7-18 3/4 7-18a 3/4 7-18a 314 7-18b 3/4 7-18b 3/4 7-18c 3/4 7-18c 3/4 8-7 3/4 8-7 3/4 11-18 5-5 5-5 5-6 5-6 6-2a 6-2a 6-5 6-5 6-6 6-6 6-8 6-8 6-13 6-14 6-14 6-17 6-17 6-18 6-18 6-20a 6-20a

INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE............................................

3/4 2-1 314.2.2 PLANAR RADIAL PEAKING FACTORS - F.....................

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

3/4 2-4 314.2.4 DNBR MARGIN............................................

314 2-6 3/4.2.5 RCS FLOW RATE............................................

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

3/4 2-11 314.2.7 AXIAL SHAPE INDEX............................................

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

3/4 2-13 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 REMOTE SHUTDOWN INSTRUMENTATION.................

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

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

3/4 3-47 EXPLOSIVE GAS MONITORING INSTRUMENTATION...

3/4 3-60 3/4.3.4 DELETED............................................

3/4 3-68 WATERFORD - UNIT 3 V

AMENDMENT NO. O9.68,1930194,107,4112,188

INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION.

3/4 4-1 HOT STANDBY.

3/4 4-2 HOT SHUTDOWN.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 SHUTDOW N.....................................................................

314 4-7 OPERATING.....................................................................

3/4 4-8 314.4.3 PRESSURIZER PRESSURIZER.................................................................

3/4 4-9 AUXILIARY SPRAY............................................

3/4 4-9a 3/4.4.4 STEAM GENERATORS............................................

3/4 4-10 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS.................................

3/4 4-17 OPERATIONAL LEAKAGE............................................

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

3/4 4-28 PRESSURIZER HEATUP/COOLDOWN.........................

314 4-33 OVERPRESSURE PROTECTION SYSTEMS................

3/4 4-34 3/4.4.9 STRUCTURAL INTEGRITY...........................................

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 3/4.5.3 ECCS SUBSYSTEMS - Modes 3 and 4.3/4 5-8 3/4.5.4 REFUELING WATER STORAGE POOL.3/4 5-9 WATERFORD - UNIT 3 VI AMENDMENT NO. 2,,34,188

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 314.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY.3/4 6-1 CONTAINMENT LEAKAGE.3/4 6-2 CONTAINMENT AIR LOCKS.3/4 6-9 INTERNAL PRESSURE.3/4 6-11 AIR TEMPERATURE.3/4 6-13 CONTAINMENT VESSEL STRUCTURAL INTEGRITY 3/4 6-14 CONTAINMENT VENTILATION SYSTEM.

314 6-15 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM....................................

3/4 6-16 CONTAINMENT COOLING SYSTEM...............................

3/4 6-18 3/4.6.3 CONTAINMENT ISOLATION VALVES.................................

3/4 6-19 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS............................................

3/4 6-34 ELECTRIC HYDROGEN RECOMBINERS - W.................

3/4 6-35 3/4.6.5 VACUUM RELIEF VALVES............................................

3/4 6-36 3/4.6.6 SECONDARY CONTAINMENT SHIELD BUILDING VENTILATION SYSTEM.3/4 6-37 SHIELD BUILDING INTEGRITY.

314 6-40 SHIELD BUILDING STRUCTURAL INTEGRITY.3/4 6-41 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES.3/4 7-1 EMERGENCY FEEDWATER SYSTEM.3/4 7-4 CONDENSATE STORAGE POOL.3/4 7-6 WATERFORD - UNIT 3 Vil AMENDMENT NC). 188

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued)

ACTIVITY...........................................................................

3/4 7-7 MAIN STEAM LINE ISOLATION VALVES..........................

314 7-9 MAIN FEEDWATER ISOLATION VALVES.......................

3/4 7-9a 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION........................................................................

3/4 7-10 3/4.7.3 COMPONENT COOLING WATER AND AUXILIARY COMPONENT COOLING WATER SYSTEMS.................

3/4 7-11 3/4.7.4 ULTIMATE HEAT SINK............................................

3/4 7-12 3/4.7.5 FLOOD PROTECTION............................................

3/4 7-15 3/4.7.6 CONTROL ROOM AIR CONDITIONING SYSTEM.............

3/4 7-16 CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM - OPERATING............................................

3/4 7-16 CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM - SHUTDOWN............................................

3/4 7-18 CONTROL ROOM AIR TEMPERATURE - OPERATING 314 7-18a CONTROL ROOM AIR TEMPERATURE - SHUTDOWN 3/4 7-18b CONTROL ROOM ISOLATION AND PRESSURIZATION 3/4 7-18c 3/4.7.7 CONTROLLED VENTILATION AREA SYSTEM.................

3/4 7-19 3/4.7.8 SNUBBERS..........................................

3/4 7-21 3/4.7.9 SEALED SOURCE CONTAMINATION................................

3/4 7-27 3/4.7.12 ESSENTIAL SERVICES CHILLED WATER SYSTEM........

3/4 7-43 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING.....................................................................

3/4 8-1 SHUTDOW N.....................................................................

3/4 8-8 3/4.8.2 D.C. SOURCES OPERATING.....................................................................

3/4 8-9 SHUTDOWN.....................................................................

3/4 8-12 WATERFORD UNIT 3 Villl AMENDMENT NO. 50,16e7,188

BASES SECTION PAGE 3/4.0 APPLICABILITY......................................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BO14TION CONTROL.......................................................

B 3/4 1-1 3/4.1.2 BORATION SYSTEMS........................................................

B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES.................................

B 3/4 1-3 3/4 2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE............................................................

B 3/4 2-1 3/4.2.2 PLANAR RADIAL PEAKING FACTORS - Fv....................

B 3/4 2-2 3/4.2.3 AZIMUTHAL POWER TILT - Tq.B 3/4 2-2 3/4.2.4 DNBR MARGIN....................................................................

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

B 3/4 2-4 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE B 3/4 2-4 3/4.2.7 AXIAL SHAPE INDEX...........................................................

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

B 3/4 2-4 3/4 3 INSTRUMENTATION 3/4.3.1 and 3/4.3 2 REACTOR PROTECTIVE and ENGINEERED SAFETY FEATURES ACTUATION SYSTEMS INSTRUMENTATION............................................................

B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION....................................

B 3/4 3-2 3/4 4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION...................................................................

B 3/4 4-1 3/4.4.2 SAFETY VALVES.................................................................

B 3/4 4-1 3/4.4.3 PRESSURIZER.B 3/4 4-2 3/4.4.4 STEAM GENERATORS.......................................................

B 3/4 4-2 WATERFORD - UNIT 3 XI AMENDMENT NO. 188

INDEX BASES SECTION PAGE 3/4 4 REACTOR COOLANT SYSTEM (Continued) 314.4.5 REACTOR COOLANT SYSTEM LEAKAGE.......................

B 3/4 4-4 3/4.4.6 CHEMISTRY.............................................

B 3/4 4-4 3/4.4.7 SPECIFIC ACTIVITY.............................................................

B 3/4 4-5 3/4.4.8 PRESSUREITEMPERATURE LIMITS.................................

B 3/4 4-6 3/4.4.9 STRUCTURAL INTEGRITY..................................................

B 3/4 4-11 3/4.4.10 REACTOR COOLANT SYSTEM VENTS............................

B 3/4 4-11 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS................................................

B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS.............................................

B 3/4 5-1b 3/4.5.4 REFUELING WATER STORAGE POOL.B 3/4 5-3 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT....................................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS..............

B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES...................................

B 3/4 6-5 3/4.6.4 COMBUSTIBLE GAS CONTROL..........................................

B 3/4 6-6 3/4.6.5 VACUUM RELIEF VALVES....................................................

B 3/4 6-6 314.6.6 SECONDARY CONTAINMENT.............................................

B 3/4 6-7 314.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE...................................................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION........................................................................

B 3/4 7-3d WATERFORD - UNIT 3 X~l AMENDMENT NO. 188

INDEX SECTION 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 COMPONENT COOLING WATER AND AUXILIARY COMPONENT COOLING WATER SYSTEMS.

3/4.7.4 ULTIMATE HEAT SINK.........................................................

3/4.7.5 FLOOD PROTECTION.

3/4.7.6 CONTROL ROOM AIR CONDITIONING SYSTEM.

3/4.7.7 CONTROLLED VENTILATION AREA SYSTEM.

3/4.7.8 SNUBBERS.

314.7.9 SEALED SOURCE CONTAMINATION.

314.7.12 ESSENTIAL SERVICES CHILLED WATER SYSTEM.

PAGE B 3/4 7-3d B 3/4 7-4 B 3/4 7-4a B 3/4 7-4a B 314 7-4c B 314 7-5 B 3/4 7-7 B 3/4 7-7 B 3/4 8-1 B 3/4 8-3 I

I 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 314.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and ONSITE POWER DISTRIBUTION SYSTEMS..................

3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.......

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.

3/4.9.2 INSTRUMENTATION.

314.9.3 DECAY TIME.

314.9.4 CONTAINMENT BUILDING PENETRATIONS.

314.9.5 COMMUNICATIONS.

3/4.9.6 REFUELING MACHINE.

3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING.

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION..

B 3/4 9-1 B 3/4 9-1 B 3/4 9-1 B 314 9-1 B 3/4 9-1 B 3/4 9-2 B 314 9-2 B 3/4 9-2 WATERFORD - UNIT 3 Xlll AMENDMENT NO.-Se,188

INDEX BASES SECTION PAGE 314.9 REFUELING OPERATIONS (Continued) 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM.....

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and SPENT FUEL POOL............................................................

B 3/4 9-2 B 3/4 9-3 I

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 3/4.10.2 3/4.10.3 3/4.10.4 3/4.10.5 SHUTDOWN MARGIN.........................................................

MTC, GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS.......................................

REACTOR COOLANT LOOPS...........................................

CENTER CEA MISALIGNMENT......................................

NATURAL CIRCULATION TESTING....................................

B 3/4 10-1 B 3/4 10-1 B 3/4 10-1 B 3/4 10-1 B 3/4 10-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 3/4.11.2 LIQUID EFFLUENTS............................................................

GASEOUS EFFLUENTS......................................................

B 3/4 11-1 B 3/4 11-3 WATERFORD - UNIT 3 XIV AMENDMENT NO 68,-176, 188

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE 5.1.1 EXCLUSION AREA............................................

5-1 5.1.2 LOW POPULATION ZONE............................................

5-1 5.1.3 MAP DEFINING UNRESTRICTED AREAS FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS.5-1 5.2 CONTAINMENT 5.2.1 CONFIGURATION.5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE.5-1 5 3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES.

5-5 5.3.2 CONTROL ELEMENT ASSEMBLIES.5-5 5.4 NOT USED 5 5 METEORLOGICAL TOWERS LOCATION.5-5 5.6 FUEL STORAGE 5.6.1 CRITICALITY.5-6 5.6.3 DRAINAGE.5-6 5.6.4 CAPACITY.5-6 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS.5-6 WATERFORD - UNIT 3 XV AMENDMENT NO. 188

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY......................................................

6-1 6.2 ORGANIZATION......................................................

6-1 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS.................................

6-1 l 6.2.2 UNIT STAFF......................................................

6-1 6.2.3 NOT USED I

6.2.4 SHIFT TECHNICAL ADVISOR.....................................................

6-6 6 3 UNIT STAFF QUALIFICATIONS......................................................

6-7 6.4 TRAINING......................................................

6-7 6 5 NOTUSED I

WATERFORD - UNIT 3 XVI AMENDMENT NO. 188

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 NOT USED I

6.7 NOT USED I

6.8 PROCEDURES AND PROGRAMS.................................................

6-14 6.9 REPORTING REQUIREMENTS.....................................................

6-17 6.9.1 ROUTINE REPORTS.....................................................

6-17 l STARTUP REPORT.....................................................

6-17 ANNUAL REPORTS.....................................................

6-17 MONTHLY OPERATING REPORT........................................

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

6-18 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6-19 INDUSTRIAL SURVEY OF TOXIC CHEMICALS REPORT 6-20 CORE OPERATING LIMITS REPORT COLR..................

6-20 6.9.2 SPECIAL REPORTS.....................................................

6-20a 610 NOT USED WATERFORD - UNIT 3 XVII AMENDMENT NO. 68,84,142, 188

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6 11 RADIATION PROTECTION PROGRAM........................................

6-22 612 HIGH RADIATION AREA.....................................................

6-22 613 PROCESS CONTROL PROGRAM (PCP)....................................

6-23 l 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM).....................

6-24 l 6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM..............

6-24 616 TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM.

6-26 WATERFORD - UNIT 3 XVIIl AMENDMENT NO. 68, 1,4, 11,188

INDEX LIST OF FIGURES FIGURE PAGE 3.1-1 REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION...................................................................

3/4 1-13 3.4-1 DELETED.

3/4 4-27 3.4-2 REACTOR COOLANT SYSTEM PRESSURE - TEMPERATURE LIMITS 0-16 EFPY (HEATUP).3/4 4-30 3.4-3 REACTOR COOLANT SYSTEM PRESSURE -TEMPERATURE LIMITS 0-16 EFPY (COOLDOWN).3/4 4-31 3.6-1 DELETED.3/4 6-12 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST 3/4 7-26 5.1-1 EXCLUSION AREA.5-2 5.1-2 LOW POPULATION ZONE.5-3 5.1-3 SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS.

5-4 5.6-1 ALTERNATIVE CHECKERBOARD ARRANGEMENTS.5-6a 5.6-2 ACCEPTABLE BURNUP DOMAIN FOR UNRESTRICTED STORAGE OF SPENT FUEL IN REGION 2.5-6b 5.6-3 ACCEPTABLE BURNUP DOMAIN FOR SPENT FUEL IN CHECKERBOARD ARRANGEMENT WITH FUEL OF 5%,'0 ENRICHMENT (OR LESS) AT 27 MWD/KgU.5-6c 6.2-1 DELETED.6-3 6.2-2 DELETED.

6-4 WATERFORD - UNIT 3 XIX AMENDMENT NO. 13,27, 102,104,188

INDEX LIST OF TABLES TABLE 1.1 1.2 2.2-1 FREQUENCY NOTATION...........................................................

OPERATIONAL MODES.............................................................

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS.......................................................................................

PAGE 1-9 1-10 2-3 I

3.3-1 REACTOR PROTECTIVE INSTRUMENTATION........................

4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS.....................................................................

3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION................................................................

3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES........................................

4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS......

3.3-6 RADIATION MONITORING INSTRUMENTATION.......................

4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.........................................

3/4 3-3 3/4 3-10 3/4 3-14 3/4 3-19 3/4 3-25 3/4 3-29 3/4 3-32 WATERFORD - UNIT 3 XX AMENDMENT NO. 9,94,102, 112 188

INDEX LIST OF TABLES (Continued)

TABLE PAGE 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 3.3-13 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 INSPECTION..............................

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.......................................

314 4-23 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM...................................................

3/4 4-25 WATERFORD - UNIT 3 XXI AMENDMENT NO. 9,58,C6,75,106, 112,184,188

INDEX LIST OF TABLES (Continued)

TABLE lPAGE 3.7-1 STEAM LINE SAFETY VALVES PER LOOP.............................

3/4 7-2 3.7-2 MAXIMUM 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 PROGRAM....................................

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

3/4 7-14 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL............................

3/4 7-21a 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS.........................

3/4 8-11 WATERFORD - UNIT 3 XXII AMENDMENT NO. 9, 23, 5, C8, 76, 188

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE DNBR 2.1.1.1 The DNBR of the reactor core shall be maintained greater than or equal to 1.26.

APPLICABILITY: MODES l and 2.

ACTION:

Whenever the DNBR of the reactor has decreased to less than 1.26, be in HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

PEAK FUEL CENTERLINE TEMPERATURE 2.1.1.2 The peak fuel centerline temperature shall be maintained less than 5080'F (decreasing by 58'F per 10,000 MWD/MTU for burnup and adjusting for burnable poisons per CENPD-382-P-A.)

APPLICABILITY: MODES I and 2.

ACTION:

Whenever the peak fuel centerline temperature has equaled or exceeded 50800F (decreasing by 58*F per 10,000 MWDIMTU for bumup and adjusting for burnable poisons per CENPD-382-P-A),

be in HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2750 psia.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

ACTION:

MODES I and 2 Whenever the Reactor Coolant System pressure has exceeded 2750 psia, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

MODES 3, 4, and 5 Whenever the Reactor Coolant System pressure has exceeded 2750 psia, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.

WATERFORD - UNIT 3 2-1 AMENDMENT NO. 12,181, 188

TABLE 3.3-1 (Continued)

TABLE NOTATION ACTION STATEMENTS ACTION 1 -

ACTION 2 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or 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/or open the protective system trip breakers.

With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be documented by the On-Site Safety Review Committee in accordance with plant administrative procedures. The channel shall be returned to OPERABLE status prior to STARTUP following the next COLD SHUTDOWN.

I WATERFORD - UNIT 3 3/4 3-4a AMENDMENT NO. 447188

TABLE 3 3-3 (Continued)

TABLE NOTATION (a)

Trip function may be bypassed in this MODE when pressurizer pressure is less than 400 psia; bypass shall be automatically removed when pressurizer pressure is greater than or equal to 500 psia.

(b)

An SIAS signal is first necessary to enable CSAS logic.

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 12 ACTION 13 With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or 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 .

With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION and/or operation in the other applicable MODE(S) may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be documented by the On-Site Safety Review Committee in accordance with plant administrative procedures.

The channel shall be returned to OPERABLE status no later than prior to entry into the applicable MODE(S) following the next COLD SHUTDOWN.

I With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below:

Process Measurement Circuit Functional Unit Bypassed/Tripped

1.

Containment Pressure - High

2.

Steam Generator Pressure -

Low Containment Pressure - High (ESF)

Containment Pressure - High (RPS)

Steam Generator Pressure - Low Steam Generator &P 1 and 2 (EFAS)

WATERFORD - UNIT 3 3/4 3-17 AMENDMENT NO. 109,154, 188

TABLE 3.3-3 (Continued)

TABLE NOTATION ACTION 17 ACTION 18 ACTION 19 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the tripped (D.C Relay energized) condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the remaining Emergency Diesel Generator is OPERABLE, and the inoperable channel is restored to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . 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 COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . The surveillance requirements of Table 4.3-2 are waived for all channels while this action requirement is in effect.

With more than one channel inoperable, or if the inoperable channel cannot be placed in the trip (D.C. Relay energized) condition, declare the associated Emergency Diesel Generator inoperable and take the ACTION required by Specification 3.8.1.1. The surveillance requirements of Table 4.3-2 are waived for all channels while this action requirement is in effect.

With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION and/or operation in the other applicable MODE(S) may continue, provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour:

a.

If the inoperable channel is to remain in the bypassed condition, the desirability of maintaining this channel in the bypassed condition shall be documented by the On-Site Safety Review Committee in accordance with plant administrative procedures. The channel shall be returned to OPERABLE status no later than prior to entry into the applicable MODE(S) following the next COLD SHUTDOWN.

b.

If the inoperable channel is required to be placed in the tripped condition, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months either restore the channel to OPERABLE status or place the channel in the bypassed condition. If the tripped channel can not be returned to OPERABLE status in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , 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 or place the tripped channel in bypass.

With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below:

I WATERFORD - UNIT 3 3/4 3-18a AMENDMENT NO. 47, 143, -54,188

The Page Not Used I

WATERFORD - UNIT 3 3/4 4-32 AMENDMENT NO. 6, 16, 188

PLANT SYSTEMS 3/4.7.6 CONTROL ROOM AIR CONDITIONING SYSTEM CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM - OPERATING LIMITING CONDITION FOR OPERATION 3.7.6.1 Both control room emergency air filtration trains (S-8) shall be OPERABLE.

APPLICABILITY*: MODES 1, 2, 3, and 4.

ACTION:

a.

With one control room emergency air filtration train inoperable, either restore the inoperable train to OPERABLE status within 7 days or 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 both control room emergency air filtration trains inoperable, restore one train to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or 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 4.7.6.1 Each control room air filtration train (S-8) shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters on.

b.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

1.

Verifying that the filtration train satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.5.c, and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 4225 cfm +/-10%.

During movement of irradiated fuel assemblies, TS 3.7.6.2 is also applicable.

WATERFORD - UNIT 3 3/4 7-16 AMENDMENT NO. 115,149, 170, 1B8

PLANT SYSTEMS CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.7.6.2 Two control room emergency air filtration trains (S-8) shall be OPERABLE.

APPLICABILITY: MODES 5 and 6, and during movement of irradiated fuel assemblies.

ACTION:

a.

With one control room emergency air filtration system inoperable, restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE control room emergency air filtration system in the recirculation mode.

b.

With both control room emergency air filtration systems inoperable, or with the OPERABLE control room emergency air filtration system, required to be in the recirculation mode by ACTION a, not capable of being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS and movement of irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS 4.7.6.2 The control room emergency air filtration trains (S-8) shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.7.6.1.

WATERFORD - UNIT 3 3/4 7-18 AMENDMENT NO. 115,149, 188

PLANT SYSTEMS CONTROL ROOM AIR TEMPERATURE - OPERATING LIMITING CONDITION FOR OPERATION 3.7.6.3 Two independent control room air conditioning units shall be OPERABLE.

APPLICABILITY*: MODES 1, 2, 3, and 4.

ACTION:

a.

With one control room air conditioning unit inoperable, restore the inoperable unit to OPERABLE status within 7 days or be in 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 two control room air conditioning units inoperable, return one unit to an OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in 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 4.7.6.3 Each control room air conditioning unit shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the operating control room air conditioning unit is maintaining average control room air temperature less than or equal to 800F.

b.

At least quarterly, if not performed within the last quarter, by verifying that each control room air conditioning unit starts and operates for at least 15 minutes.

'During movement of irradiated fuel assemblies, TS 3.7.6.4 is also applicable.

WATERFORD - UNIT 3 3/4 7-18a AMENDMENT NO.11 5,149, 188

PLANT SYSTEMS CONTROL ROOM AIR TEMPERATURE - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.7.6.4 Two independent control room air conditioning units shall be OPERABLE.

APPLICABILITY: MODES 5 and 6, and during movement of irradiated fuel assemblies.

ACTION:

a.

With one control room air conditioning unit inoperable, restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE control room air conditioning unit.

b.

With both control room air conditioning units inoperable, or with the OPERABLE control room air conditioning unit, required to be in operation by ACTION a, not capable of being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS and movement of irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS 4.7.6.4 The control room air conditioning units shall be demonstrated OPERABLE per the Surveillance Requirements of 4.7.6.3.

WATERFORD - UNIT 3 314 7-18b AMENDMENT NO. 115,149,188

PLANT SYSTEMS CONTROL ROOM ISOLATION AND PRESSURIZATION LIMITING CONDITION FOR OPERATION 3.7.6.5 The control room envelope isolation and pressurization boundaries shall be OPERABLE.

APPLICABILITY: All MODES and during movement of irradiated fuel assemblies.

ACTION:

a.

With either control room envelope isolation valve in a normal outside air flow path inoperable, maintain at least one isolation valve in the flowpath OPERABLE, and either restore the inoperable valve to OPERABLE status with 7 days or isolate the affected flow path within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With any Control Room Emergency Filter Outside Air Intake valve(s) inoperable, maintain at least one of the series isolation valves in a flowpath OPERABLE, and either restore the inoperable valve(s) to OPERABLE status within 7 days or isolate the affected flow path within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With more than one Control Room Emergency Filter Outside Air Intake flow path inoperable, maintain at least one flow path per intake operable and restore an additional flow path to operable status within 7 days or, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d.

With the control room envelope inoperable as a result of causes other than those addressed by ACTION (a), (b), or (c) above:

1.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the control room envelope is inoperable, verify that the Emergency Breathing Airbanks pressure is greater than or equal to 1800 psig.

2.

MODES 1-4:

a.

If the cause of control room envelope inoperability is due to a known breach in the envelope of less than or equal to one square foot total area or the breach is associated with a permanent sealing mechanism (e.g., blocking open or removing a door) then operation may continue for up to 7 days after the control room envelope is declared inoperable. Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

WATERFORD - UNIT 3 3/4 7-18c AMENDMENT NO. 115,149,188

THIS PAGE NOT USED I

WATERFORD - UNIT 3 314 8-7 AMENDMENT NO. 23,71,12,, 188

DESIGN FEATURES 5 3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing a maximum of 236 fuel rods clad with Zircaloy-4. Each fuel rod shall have a nominal active fuel length of 150 inches and contain a nominal total weight of 1830 grams uranium. The initial core loading shall have a maximum enrichment of 2.91 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading. Assemblies shall have a maximum nominal enrichment of 5.0 weight percent U-235 and meet the final storage requirements described in Section 5.6.

CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 87 control element assemblies.

5 4 NOT USED 5 5 METEOROLOGICAL TOWERS LOCATION 5.5.1 The primary and backup meteorological towers shall be located as shown on Figure 5.1-1.

WATERFORD - UNIT 3 5-5 AMENDMENT NO.0 4G,!44,182, 188

DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:

a.

A normal kef of less that or equal to 0.95 when flooded with unborated water, which includes a conservative allowance for uncertainties.

b.

A nominal 10.185 inch center-to-center distance between fuel assemblies placed in Region 1 (cask storage pit) spent fuel storage racks.

c.

A nominal 8.692 inch center-to-center distance between fuel assemblies in the Region 2 (spent fuel pool and refueling canal) racks, except for the four southern-most racks in the spent fuel pool which have an increased N-S center-to-center nominal distance of 8.892 inches.

d.

New or partially spent fuel assemblies may be allowed unrestricted storage in Region 1 racks.

e.

New fuel assemblies may be stored in the Region 2 racks provided that they are stored in a "checkerboard pattern" as illustrated in Figure 5.6-1.

f.

Partially spent fuel assemblies with a discharge bumup in the 'acceptable range" of Figure 5.6-2 may be allowed unrestricted storage in the Region 2 racks.

g.

Partially spent fuel assemblies with a discharge burnup in the "unacceptable range" of Figure 5.6-2 may be stored in the Region 2 racks provided that they are stored in a "checkerboard pattern", as illustrated in Figure 5.6-1, with spent fuel in the "acceptable range" of Figure 5.6-3.

5.6.2 The keff for new fuel stored in the new fuel storage racks shall be less than or equal to 0.95 when flooded with unborated water and shall not exceed 0.98 when aqueous foam moderation is assumed.

DRAINAGE 5.6.3 The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation +40.0 MSL. When fuel is being stored in the cask storage pit and/or the refueling canal, these areas will also be maintained at +40.0 MSL.

CAPACITY 5.6.4 The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 1849 fuel assemblies in the main pool, 255 fuel assemblies in the cask storage pit and after permanent plant shutdown 294 fuel assemblies in the refueling canal. The heat load from spent fuel stored in the refueling canal racks shall not exceed 1.72x1OE6 BTU/Hr. Fuel shall not be stored in the spent fuel racks in the cask storage pit or the refueling canal unless all of the racks are installed in each respective area per the design.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

WATERFORD - UNIT 3 5-6 AMENDMENT NO. 108,144,188

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued)

4.

Except during extended shutdown periods, the use of overtime shall 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 General Manager Plant Operations, or designee, or higher levels of management in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime will be reviewed monthly by the General Manager Plant Operations or his designee to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

f.

The Operations Manager or the Assistant Operations Manager (Shift) shall hold a senior reactor operator license.

WATERFORD - UNIT 3 6-2a AMENDMENT NO. 18,41,58,63,144,188

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODF

1. 2 34 OR 4 MODEn :s n;ri

(

Mflfl flP R SM SRO RO AO STA I

1

2 21*

I None 1

1 None I

SM SRO RO AO STA Shift Manager with a Senior Operator License Individual with a Senior Operator License Individual with an Operator License Auxiliary Operator Shift Technical Advisor Except for the Shift Manager, the shift crew composition may be one less than the minimum requirements of Table 6.2-1 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 position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

During any absence of the Shift Manager from the control room while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid Senior Operator license shall be designated to assume the control room command function. During any absence of the Shift Manager from the control room while the unit is in MODE 5 or 6, an individual with a valid Senior Operator or Operator license shall be designated to assume the control room command function.

An individual with SRO/STA qualifications can satisfy the SM/STA or SRO/STA position requirements simultaneously.

WATERFORD - UNIT 3 6-5 AMENDMENT NO. 7,146, 188

ADMINISTRATIVE CONTROLS 6.2.3 Not Used 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Manager in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. The STA shall meet the requirements of either Option 1 or 2 as shown below:

a.

Option 1 - Combined SROISTA Position. This option is satisfied by assigning an individual with the following qualifications to each operating shift crew as one of the SRO's required by 10 CFR 50.54(m) (2) (i):

Not responsible for sign-off function.

WATERFORD - UNIT 3 6-6 AMENDMENT NO. 18,63,83,146, 188

Pages 6-9 through page 6-13 not used I

WATERFORD - UNIT 3 6-8 Next Page is 6-14 AMENDMENT NO. 18, 63,-9S,

ei,1-g, 188 I

ADMINISTRATIVE CONTROLS 6.6 NOT USED 6.7 NOT USED 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978 and Emergency Operating Procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in Generic Letter 82-33.

b.

Refueling operations.

c.

Surveillance and test activities of safety-related equipment.

d.

Not used.

e.

Not used.

f.

Fire Protection Program implementation.

g.

Modification of Core Protection Calculator (CPC) Addressable Constants, including independent verification of modified constants.

NOTES:

(1)

Modification to the CPC addressable constants based on information obtained through the Plant Computer - CPC data link shall not be made without prior approval of the On-Site Safety Review Committee.

(2)

Modifications to the CPC software (including algorithm changes and changes in fuel cycle specific data) shall be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Procedure," that has been determined to be applicable to the facility. Additions or deletions to CPC Addressable Constants or changes to Addressable Constant software limits values shall not be implemented without prior NRC approval.

h.

Administrative procedures implementing the overtime guidelines of Specification 6.2.2e., including provisions for documentation of deviations.

i.

PROCESS CONTROL PROGRAM implementation.

WATERFORD - UNIT 3 6-14 AMENDMENT NO. 5, 61, 63, 100, 109,

45I, 188

ADMINISTRATIVE CONTROLS 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 The following reports shall be submitted in accordance with 10 CFR 50.4.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall 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 required in license conditions based on other commitments shall be included in this report.

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

ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

The results of specific activity analysis in which the primary coolant exceed the limits of Specification 3.4.7 shall be submitted annually in accordance with the aforementioned time frame. The following information shall be included:

W A TE RF ORD -U NIT 3 6-17 AMENDMENT NO. 8, 11 G. 188

ADMINISTRATIVE CONTROLS 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, no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIORNMENTAL 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 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

WATERFORD - UNIT 3 6-18 AMENDMENT NO.-6B, 188

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT COLR (Continued)

6) "CESEC - Digital Simulation for a Combustion Engineering Nuclear Steam Supply System," CENPD-107, December 1981. (Methodology for Specification 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.1 for Movable Control Assemblies -

CEA Position, 3.1.3.6 for Regulating and group P CEA Insertion Limits, and 3.2.3 for Azimuthal Power Tilt).

7) "Qualification of Reactor Physics Methods for the Pressurized Water Reactors of the Entergy System," ENEAD-01-P, Revision 0. (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins, 3.1.1.3 for MTC, 3.1.3.6 for Regulating and group P CEA Insertion Limits, 3.1.2.9 Boron Dilution (Calculation of CBC & IBW), and 3.9.1 Boron Concentration).

6.9.1.11.2 The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.11.3 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report.

6.10 Not Used WATERFORD - UNIT 3 6-20a AMENDMENT NO. *2,146,15-,1, 188

NUC A

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 188 TO FACILITY OPERATING LICENSE NO. NPF-38 ENTERGY OPERATIONS, INC.

WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382

1.0 INTRODUCTION

By application dated December 20, 2002, Entergy Operations, Inc. (the licensee), submitted a request for changes to the Waterford Steam Electric Station, Unit 3 (Waterford 3) Technical Specifications (TSs). The requested changes would make several administrative changes to the Waterford 3 TSs to revise, delete, correct, or clarify certain titles, page numbers, and heading information. The amendment would also revise personnel and committee titles that have been changed, revise administrative reporting requirements to conform to 10 CFR 50.4, and delete redundant or unnecessary requirements from TSs 5.4, 6.6, and 6.7.

2.0 REGULATORY EVALUATION

The regulations at 10 CFR 50.4 provide direction regarding written communications, and include address requirements, distribution requirements, form of communications, delivery of communications, and the regulation governing submission.

Pursuant to 10 CFR 50.36(c)(1) on Safety limits, limiting safety system settings, and limiting control settings, "... If any safety limit is exceeded, the reactor must be shut down. The licencee shall notify the Commission, review the matter, and record the results of the review..."

and "For these reactors, the licensee shall notify the Commission as required by § 50.72 and submit a Licensee Event Report to the Commission as required by § 50.73..." The regulations at 10 CFR 50.36(c)(5) on administrative controls states "Administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. Each licensee shall submit any reports to the Commission pursuant to approved technical specifications as specified in § 50.4."

The regulations at 10 CFR 50.72 address the immediate notification requirements for operating nuclear power reactors for general events and non-emergency events under one-hour, four-hour, and eight-hour classifications. The licensee event report system is discussed in 10 CFR 50.73.

The rest of the changes in the proposed amendment are administrative in nature and make editorial corrections; therefore, there are no specific regulatory requirements associated with the proposed amendment.

3.0 TECHNICAL EVALUATION

The changes requested by the licensee have been numbered as 3.1, 3.2, etc., and grouped as far as possible such that the review and resolution cover one or more changes.

3.1 INDEX page V: add "- Fg"to PLANAR RADIAL PEAKING FACTORS title and "- Tc to AZIMUTHAL POWER TILT title to match with titles on pages 3/4 2-3 and 3/4 2-4, respectively.

3.2 INDEX page VI: indent subsections under 3/4.4.1 to match format on page and add

'SPRAY" to AUXILIARY title under 3/4.4.3 to match the title on page 3/4 4-9a, which was added in Amendment 22.

3.3 INDEX page VII: add "-W" to ELECTRIC HYDROGEN RECOMBINERS title to match the title on page 3/4 6-35.

3.4 INDEX page Vil: add identification for TS 3/4.7.6 CONTROL ROOM AIR CONDITIONING SYSTEM subsections: CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM - OPERATING, CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM - SHUTDOWN, CONTROL ROOM AIR TEMPERATURE -

OPERATING, CONTROL ROOM AIR TEMPERATURE - SHUTDOWN, and CONTROL ROOM ISOLATION AND PRESSURIZATION with corresponding page numbers. These index additions reflect changes made in Amendment 115. Also, indent 3/4.8.2 D.C. SOURCES to match page format.

3.5 INDEX page XI: add "- FO," to PLANAR RADIAL PEAKING FACTORS title to match title on page B 3/4 2-2, add "-Tv to AZIMUTHAL POWER TILT title to match title on page B 3/4 2-2, correct page number for MONITORING INSTRUMENTATION from B 3/4 3-1 to B 3/4 3-2, and delete 3/4.3.4 TURBINE OVERSPEED PROTECTION reference as there is no place holder for this bases section, which was deleted in Amendment 103.

3.6 INDEX page XII: Revise page number for ECCS SUBSYSTEMS to read B 3/4 5-1b, revise page number for REFUELING WATER STORAGE POOL to read B 3/4 5-3, revise page number for CONTAINMENT ISOLATION VALVES to read B 3/4 6-5, revise page number for COMBUSTIBLE GAS CONTROL to read B 3/4 6-6, revise page number for VACUUM RELIEF VALVES to read B 3/4 6-6, revise page number for SECONDARY CONTAINMENT to read B 3/4 6-7, and revise page number for STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION to read B 3/4 7-3d1.

3.7 INDEX page XIII: capitalize "and" to be consistent with the title for 3/4.7.3, COMPONENT COOLING WATER AND AUXILIARY COMPONENT COOLING WATER SYSTEMS and revise page number to read B 3/4 7-3d', revise page number for FLOOD PROTECTION to read B 3/4 7-4a, revise page number for CONTROL ROOM AIR CONDITIONING SYSTEM to read B 3/4 7-4a, revise page number for CONTROLLED VENTILATION AREA SYSTEM to read B 3/4 7-4c, and revise page number for ESSENTIAL SERVICES CHILLED WATER SYSTEM to read B 3/4 7-7.

3.8 INDEX page XIV: delete "3/4.9.12 DELETED.... B 3/4 9-3" as there is no place holder for this section, which was deleted in Amendment 176.

3.9 INDEX page XV: delete section 5.4 title REACTOR COOLANT SYSTEM and insert "NOT USED," and delete subsections 5.4.1 and 5.4.2 to agree with requested change to page 5-5 below. Add an "S" to LIMIT in the COMPONENT CYCLIC OR TRANSIENT LIMIT title to match the title on page 5-6.

3.10 INDEX page XVI: add "AND ONSITE ORGANIZATIONS" after OFFSITE in the title for SECTION 6.2.1 to match the title on page 6-1; delete titles, subtitles, and subtitle page numbers after Section 6.2.3 and insert 'NOT USED" to agree with change made in Amendment 146; delete REVIEW AND AUDIT after Section 6.5 and replace with "NOT USED", and delete Section 6.5.1 in its entirety to agree with changes made in Amendment 109. These changes match the index with the cited TS page and previously approved changes.

3.11 INDEX page XVII: delete Section 6.5.2 in its entirety to agree with changes made in Amendment 109; delete Section 6.6 title REPORTABLE EVENT ACTION and page number, and insert "NOT USED" to agree with changes proposed in this amendment; delete Section 6.7 title SAFETY LIMIT VIOLATION and page number, and insert "NOT USED" to agree with changes proposed in this amendment; revise page number for REPORTING REQUIREMENTS to read 6-17; revise page number for ROUTINE REPORTS to read 6-17; insert 'COLR" after CORE OPERATING LIMITS REPORT; and

'In the TS markup pages submitted by the licensee, index page XII provides the page number for Section 3/4.7.2 - STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION as B 3/4 7-3b and index page XIII provides the page number for Section 3/4.7.3 -

COMPONENT COOLING WATER AND AUXILIARY COMPONENT COOLING WATER SYSTEMS as B 3/4 7-3b. However, Bases Change No. 15 added two new sections, under the headings "Credited Non-Safety Related Support Systems for MFIV [Main Feedwater Isolation Valve] Operability" and "RTO [Reactor Trip Override] and AFW [Auxiliary Feedwater] Pump HDPT [High Discharge Pressure Trip] Test Requirements" which caused the page numbers for Section 3/4.7.2 and Section 3/4.7.3 to change to B 3/4 7-3d. The staff finds the discrepancy minor and therefore acceptable.

delete Section 6.10 title RECORD RETENTION and page number, and insert "NOT USED" to agree with changes made in Amendment 146.

3.12 INDEX page XVIII: add "(PCP)" after PROCESS CONTROL PROGRAM and "(ODCM)"

after OFFSITE DOSE CALCULATION MANUAL to match titles on pages 6-23 and 6-24, respectively.

3.13 INDEX page XIX: change Figure 3.4-2 and Figure 3.4-3 titles to delete PRESSURE/TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS and insert "PRESSURE-TEMPERATURE LIMITS 0-16 EFPY" after REACTOR COOLANT SYSTEM to match titles of corresponding figures on pages 3/4 4-30 and 4-31 that were revised in Amendment 160; add Figure "3.6-1 DELETED...3/4 6-12" to reflect the place holder for the figure that was deleted in Amendment 27; insert titles for Figures 5.6-1, 5.6-2, and 5.6-3 with respective page numbers after FIGURE 5.1-3 to reflect the figures added by Amendment 144; and in FIGURES 6.2-1 and 6.2-2 replace the titles with words "DELETED" to reflect the place holders for the tables deleted by Amendment 41.

3.14 INDEX page XX: delete Table 2.2-2 title and page number to reflect the disposition of the table, which was deleted in Amendment 5.

3.15 INDEX page XXI: delete Table 3.3-12 and 4.3-8, the words "DELETED", and associated page numbers as there are no longer any place holders for these tables, which were deleted in Amendment 68.

3.16 INDEX page XXII: add "PER TRAIN" after ULTIMATE HEAT SINK MINIMUM FAN REQUIREMENTS, insert Table "4.7-2 SNUBBER VISUAL INSPECTION INTERVAL...3/4 7-21 a" after Table 3.7-3 to reflect the table added by Amendment 73, and delete information related to Tables 4.8-1 and 4.8-1a which were deleted per Amendment 126.

The changes described in 3.1 through 3.16 are changes made to the INDEX pages, to agree with the text in the respective sections which were either previously approved by various amendment requests or are changes that are detailed in this request. These are corrections, clarifications, and/or updates to the INDEX pages and do not change the technical content, intent, or interpretation of the TS and, therefore, the staff finds these changes to be acceptable.

3.17 Page 2-1: delete ", and comply with the requirements of Specification 6.7.1" in four ACTION statements.

TS 6.7.1 contains actions to be taken in the event of a Safety Limit Violation. These actions require that the NRC Operations Center be notified by telephone as soon as possible and in all cases within one hour, and the Vice President of Operations and the Safety Review Committee (SRC) within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following any such violation. Further, a report describing applicable circumstances preceding the violation; effects of the violation on the facility components, systems, or structure; and corrective action taken to prevent recurrence of the violation must be submitted to the Commission, SRC, and the Vice President of Operations within 14 days of the violation. TS 6.7.1 also requires that critical operation of the unit not be resumed until authorized by the Commission.

The licensee states that these requirements are after-the-fact notifications and reviews, and are not required to assure the safe operation of the facility. These requirements are duplicated in 10 CFR 50.36, 10 CFR 50.72, and 10 CFR 50.73, except the telephone notification to the NRC Operations Center may be made within four hours, as set forth in 10 CFR 50.72(b)(2),

LERs under 10 CFR 50.73 may be submitted within sixty days. Because Waterford 3 is still required to meet these regulations, repetition of the requirements in the TSs is not needed.

Additionally, these changes are consistent with NUREG-1 432, Revision 2, as modified by TSTF-5, Revision 1. The removal of the statements from TS Safety Limit Action 2.1.1.1, Safety Limit Action 2.1.1.2, and Safety Limit Action 2.1.2, and conforming change made to page 2-1, are administrative changes, do not change the technical content, intent, or interpretation of these of the TS and do not relieve the licensee of any obligations except to extend reporting time to that which is specified in the regulations. Therefore, the staff finds these changes to be acceptable.

3.18 Page 3/4 3-4a: ACTION 2 change Plant Operations Review Committee to "On-Site Safety Review Committee" to reflect correct title.

3.19 Page 3/4 3-17: ACTION 13 change Plant Operations Review to "On-Site Safety Review" to reflect correct title.

3.20 Page 3/4 3-18a: ACTION 19a change Plant Operations to "On-Site Safety" to reflect correct title.

The licensee states that these revisions correct obsolete position or committee titles and the changes are as a result of internal efforts to standardize certain position or committee titles within the licensee organization. The staff considers the changes to be editorial in nature, and finds them to be acceptable.

3.21 Page 3/4 4-32: delete information on this page and insert "THIS PAGE NOT USED" for consistent format; also, rotate the page from landscape to portrait format.

The staff considers the change to be editorial in nature, and finds it to be acceptable.

3.22 Page 3/4 7-16: change title after 'PLANT SYSTEMS" to read "3/4 7.6 CONTROL ROOM AIR CONDITIONING SYSTEM" and add "CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM - OPERATING" before LIMITING CONDITION FOR OPERATION to better conform to the TS format.

3.23 Page 3/4 7-18: delete "3/4.7.6.2" above LIMITING CONDITION FOR OPERATION and change title to read "CONTROL ROOM EMERGENCY AIR FILTRATION SYSTEM -

SHUTDOWN" to better conform to the TS format.

3.24 Page 3/4 7-18a: delete "3/4.7.6.3" above LIMITING CONDITION FOR OPERATION and change title to read "CONTROL ROOM AIR TEMPERATURE - OPERATING" to better conform to the TS format.

3.25 Page 3/4 7-18b: delete "3/4.7.6.4" above LIMITING CONDITION FOR OPERATION and change title to read "CONTROL ROOM AIR TEMPERATURE - SHUTDOWN" to better conform to the TS format.

3.26 Page 3/4 7-18c: delete "3/4.7.6.5" above LIMITING CONDITION FOR OPERATION to better conform to the TS format.

3.27 Page 3/4 8-7: delete information on this page and insert "THIS PAGE NOT USED" for consistent format.

3.28 Page 3/4 11-18: delete page in its entirety as it is at the end of the section and is not needed as a place holder.

The staff considers these changes to be editorial in nature and therefore acceptable.

3.29 Page 5.5: delete Section 5.4 title REACTOR COOLANT SYSTEM and insert "NOT USED;" delete Section 5.4.1 DESIGN PRESSURE AND TEMPERATURE and Section 5.4.2 VOLUME in their entirety to conform to NUREG-1432, Revision 2, "Standard Technical Specifications - Combustion Engineering Plants" which no longer includes this information in the DESIGN FEATURES section.

The licensee states that the Reactor Coolant System (RCS) volume contained in TS 5.4.2 is consistent with the nominal design value listed in the Final Safety Analysis Report (FSAR)

Table 5.1-2 and Table 5.1-3, and the other references throughout the FSAR are correct. Prior to Tho, reduction change, approved in Amendment 120, FSAR Table 5.1-2 listed the average operating temperature, Ta.g as 582.1 OF, which matches with the value in TS 5.4.2. However, following the ThOt reduction change, this number was revised to 574 OF in the FSAR table but not in the TS. The temperature in TS 5.4.2 is a nominal temperature at which the RCS volume was originally calculated. The approximately 8 0F change has a negligible effect on the RCS volume. Since the nominal temperature is not a controlling temperature for plant operation, the current nominal value of Tavg was determined to be adequate until such time as the TS was amended to delete TS 5.4. The deletion of these sections is consistent with NUREG-1432, Revision 2 and 10 CFR 50.36(c)(4).

The staff agrees with the changes proposed by the licensee and finds the changes acceptable.

3.30 Page 5.6: correct spelling of refuelling to "refueling" in Section 5.6.1.c and correct spelling of accceptable to "acceptable" in Section 5.6.1.f.

The proposed changes correct existing spelling errors and the staff finds them acceptable.

3.31 Page 6-2a ADMINISTRATIVE CONTROLS paragraph f.: change Operations Superintendent to "Assistant Operations Manager (Shift)" to reflect correct title.

The proposed change involves correction to the title. While in the markup of the TS pages in the application dated December 20, 2002, the change is shown as "Assistant Operations Manager (shift)", the clean copy of the TS page has the letter "s" in "shift" capitalized. The staff considers this change, including the change between the mark-up and clean TS pages, editorial, not significant to safety, and does not alter any technical requirements. The staff finds the proposed change acceptable.

3.32 Page 6.5 TABLE 6.2-1: change Superintendent to "Manager" (four places) and the acronym SS to "SM" (three places) to correct titles.

3.33 Page 6-6 Section 6.2.4.1: change Superintendent to "Manager" to correct title.

The proposed changes involve corrections to titles and do not alter any technical requirements, intent of these specifications, or interpretation of these specifications. Therefore, the NRC staff finds the proposed changes acceptable.

3.34 Page 6.8: change 6-12 to read "6-13" in the middle of the page and 6-13 to "6-14" at the bottom of the page to reflect the deletion of page 6-13 as proposed in the next item below.

3.35 Page 6-13 and 6-14: delete TSs 6.6 and 6.7, and delete page 6-13 in its entirety.

TS 6.6.1 discusses the actions taken for REPORTABLE EVENTS (LERs) and as set forth in 10 CFR 50.73. Because Waterford 3 is still required to meet this regulation, repetition of the regulatory requirements in the TS is not needed. Also, in view of the explanation provided for 3.17, the staff finds the changes in 3.34 and 3.35 acceptable.

3.36 Page 6-14: insert "6.6 NOT USED" and "6.7 NOT USED" above 6.8 and change PORC in NOTES: (1) to "On-Site Safety Review Committee".

TSs 6.6 and 6.7 were deleted in 3.35, and 3.36 clarifies the deletion by the explanation "6.6 NOT USED" and "6.7 NOT USED." The staff accepts this change. Changing PORC to "On-Site Safety Review Committee" in NOTES: (1) involves correction to a title and does not alter any technical requirements, intent of these specifications, or interpretation of these specifications. Therefore, the NRC staff finds the proposed change acceptable.

3.37 Page 6-17: revise TS 6.9.1 to read, "The following reports shall be submitted in accordance with 10 CFR 50.4."

3.38 Page 6-18: revise TS 6.9.1.6 by deleting "to the Director, Office of Resource Management, U. S. Nuclear Regulatory Commission, Washington, DC 20555, with a copy to the Regional Administrator of the regional office of the NRC."

3.39 Page 6-20a: revise TS 6.9.2 to read "Special Reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report."

On November 6, 1986, the NRC amended its regulation (51 FR 40303) to establish procedures for submitting correspondence, reports, applications, or other written communications pertaining to the domestic licensing of production and utilization facilities. The rule superseded all existing requirements and guidance with respect to the number of copies and mailing procedures. Licensees whose TSs contained conflicting submittal directions were authorized by the rule to delete conflicting directions by pen-and-ink changes to their TSs. The Commission did not require formal applications for amendments to effect these changes. The changes proposed to TS 6.9.1, TS 6.9.1.6, and TS 6.9.2 formally conform the current Waterford 3 TSs to this rule change by deleting superceded information and directing that the reports be submitted in accordance with 10 CFR 50.4 within the time period specified for each report. The staff finds this change to be acceptable.

3.40 The licensee also provided changes to the TS Bases pages B 3/4 2-2, B 3/4 3-3, B 314 7-4a, and B 3/4 7-5 for information.

Since the changes are related to Bases changes and are provided to the NRC for information only, the new Bases page will be prepared using the marked-up page in Attachment 3 under 50.59 once the overall change is approved by the NRC. The staff finds this approach acceptable.

4.0

SUMMARY

The NRC staff reviewed the proposed changes to TS 3.1 through 3.39, discussed above. The proposed changes do not alter any technical requirements, intent of these specifications, or interpretation of these specifications. Therefore, the NRC staff finds the proposed changes acceptable.

5.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Louisiana State official was notified of the proposed issuance of the amendment. The State official had no comments.

6.0 ENVIRONMENTAL CONSIDERATION

The amendment changes record keeping, reporting, or administrative procedures or requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (68 FR 5673 dated February 4, 2003). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 0). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

7.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: N. Kalyanam Date: April 3, 2003

Waterford Generating Station 3 cc:

Mr. Michael E. Henry, Administrator and State Liaison Officer Department of Environmental Quality P.O. Box 82135 Baton Rouge, LA 70884-2135 Vice President, Operations Support Entergy Operations, Inc.

P.O. Box 31995 Jackson, MS 39286-1995 Director Nuclear Safety Assurance Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751 Wise, Carter, Child & Caraway P. 0. Box 651 Jackson, MS 39205 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Parish President Council St. Charles Parish P.O. Box 302 Hahnville, LA 70057 Executive Vice President

& Chief Operating Officer Entergy Operations, Inc.

P. O. Box 31995 Jackson, MS 39286-1995 Chairman Louisiana Public Services Commission P.O. Box 91154 Baton Rouge, LA 70825-1697 General Manager Plant Operations Waterford 3 SES Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751 Licensing Manager Entergy Operations, Inc.

17265 River Road Killona, LA 70066-0751 Winston & Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 Resident Inspector/Waterford NPS P.O. Box 822 Killona, LA 70066-0751

v t e Letter Sequence Other
TAC:MB7150, TSTF-5 (Approved, Closed)
Initiation Acceptance... Administration Questions Answers Results Approval Other: ML030940420
MONTHYEAR2003-04-03 [Table View]

ML030940420

Text

SUBJECT:

Dear Mr. Venable:

Enclosures:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

SUMMARY

5.0 STATE CONSULTATION

6.0 ENVIRONMENTAL CONSIDERATION

7.0 CONCLUSION

Navigation menu

Search