Text

Changes Made to the Technical Specifications Bases and Technical Requirements Manual
	ML022680131
Person / Time
Site:	Watts Bar
Issue date:	09/19/2002
From:	Pace P; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML022680131 (94)
	v • d • e

Tennessee Valley Authonty, Post Office Box 2000, Spnng City, Tennessee 37381-2000 SEP 1 9 2002 10 CFR 50.71(e)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket No. 50-390 Tennessee Valley Authority WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 - CHANGES MADE TO THE WBN TECHNICAL SPECIFICATION BASES AND TECHNICAL REQUIREMENTS MANUAL The purpose of this letter is to provide the NRC with copies of changes to the WBN Technical Specification Bases (TS Bases), through Revision 46, and WBN Technical Requirements Manual (TRM), through Revision 30, in accordance with WBN TS Section 5.6, "TS Bases Control Program," and WBN TRM Section 5.1, "Technical Requirements Control Program," respectively.

These changes have been implemented at WBN during the period since WBN's last update (March 27, 2001) and meet criteria described within the above control programs for which prior NRC approval is not required. Both control programs require such changes to be provided to the NRC on a frequency consistent with 10 CFR 50.71(e). WBN's FSAR update in accordance with 10 CFR 50.71(e) was provided under separate cover. In addition, this letter provides a replacement table of contents including an effective page listing for the WBN Technical Specifications (TS), the TS Bases, and the TRM. provides the WBN TS Table of Contents and List of Effective Pages. Enclosure 2 provides the Table of Contents and List of Effective Pages for the TS Bases and the changes mc Pnrted on recycled paper

U.S. Nuclear Regulatory Commission Page 2 SEP 1 9 2002 to the TS Bases addressed above. Note that changes made to the TS Bases under approved license amendments to the WBN TS are not included unless necessary for page integrity. provides the Table of Contents and List of Effective Pages for the WBN TRM and the changes to the TRM addressed above. Changes to the TS Bases and TRM made only to address pagination or format are not included in this transmittal.

If you have any questions, please contact me at (423) 365 1824.

Since~aY P. L. *ace, Manager Licensing and Industry Affairs Enclosure cc (Enclosure):

U.S. Nuclear Regulatory Commission Page 3 SEP 1 9 2002 cc (Enclosures):

NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr. L. Mark Padovan, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08G9 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303

ENCLOSURE 1 TABLE OF CONTENTS AND LIST OF EFFECTIVE PAGES WBN TECHNICAL SPECIFICATIONS

TABLE OF CONTENTS TABLE OF CONTENTS. ......................................... .i LIST OF TABLES. .............. ..... ..... ... ...... .. .v LIST OF FIGURES .............................................. .vi LIST OF ACRONYMS .............................................. .vii LIST OF EFFECTIVE PAGES........................................... .viii 1.0 USE AND APPLICATION ...................................

.1.1-1 1.1 Definitions ....................................... .1.1-1 1.2 Logical Connectors ................................. .1.2-1 1.3 Completion Times .................................. .1.3-1 1.4 Frequency .........................................

.1.4-1 2.0 SAFETY LIMITS (SLs) ...................................

.2.0-1 2 .1 SLs ............................................... .2.0-1 2.2 SL Violations ..................................... .2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.. ......... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ........... ......... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS .................. ............ 3.1-1 3.1.1 SHUTDOWN MARGIN (SDM) -Ta.,, > 200OF ...... ............ 3.1 -1 3.1.2 SHUTDOWN MARGIN (SDM) -Tav,

200OF ...... ............ 3.1-2 3.1.3 Core Reactivity ......................... ............ 3.1-3 3.1.4 Moderator Temperature Coefficient (MTC). ............ 3.1-5 3.1.5 Rod Group Alignment Limits .............. ............ 3.1-8 3.1.6 Shutdown Bank Insertion Limits .......... ............ 3.1-12 3.1.7 Control Bank Insertion Limits ........... ............ 3.1-14 3.1.8 Rod Position Indication ................. ............ 3.1-17 3.1.9 PHYSICS TESTS Exceptions-MODE 1 ........ ............ 3.1-20 3.1.10 PHYSICS TESTS Exceptions-MODE 2 ........ ............ 3.1-23 3.2 POWER DISTRIBUTION LIMITS ............................. .... 3.2-1 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) .............. .... 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot.Channel Factor (FNAH)... .... 3.2-6 3.2.3 AXIAL FLUX DIFFERENCE (AFD) ....................... .... 3.2-9 3.2.4 QUADRANT POWER TILT RATIO (QPTR) .................. .... 3.2-10 3.3 INSTRUMENTATION ........................................... 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation ............. 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation ................................... 3.3-24 3.3.3 Post Accident Monitoring (PAM) Instrumentation ........ 3.3-41 3.3.4 Remote Shutdown System .................................. 3.3-46 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation .................................... 3.3-49 3.3.6 Containment Vent Isolation Instrumentation ............ 3.3-52 3.3.7 Control Room Emergency Ventilation System (CREVS)

Actuation Instrumentation .......................... 3.3-57 3.3.8 Auxiliary Building Gas Treatment System (ABGTS)

Actuation Instrumentation ......................... 3.3-61 (continued)

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TABLE OF CONTENTS (continued) 3.4 REACTOR COOLANT SYSTEM (RCS) .............................. 3.4-1 3 4 1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ..................... 3.4-1 3.4.2 RCS Minimum Temperature for Criticality ................ 3.4-3 3.4.3 RCS Pressure and Temperature (P/T) Limits ............. 3.4-5 3.4.4 RCS Loops-MODES 1 and 2 .............................. 3.4-7 3.4.5 RCS Loops--MODE 3 ..................................... 3.4-B 3.4.6 RCS Loops-MODE 4 ..................................... 3.4-11 3.4.7 RCS Loops-MODE 5, Loops Filled ....................... 3.4-14 3.4.8 RCS Loops-MODE 5, Loops Not Filled ................... 3.4-16 3.4.9 Pressurizer ........................................... 3.4-18 3.4.10 Pressurizer Safety Valves ............................. 3.4-20 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ...... 3.4-22 3.4.12 Cold Overpressure Mitigation System (COMS) ............ 3.4-25 3.4.13 RCS Operational LEAKAGE ............................... 3.4-30 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ............ 3.4-32 3.4.15 RCS Leakage Detection Instrumentation ................. 3.4-36 3.4.16 RCS Specific Activity ................................. 3.4-39 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ..................... 3.5-1 3.5.1 Accumulators .......................................... 3.5-1 3.5.2 ECCS-Operating ....................................... 3.5-4 3.5.3 ECCS--Shutdown ........................................ 3.5-7 3.5.4 Refueling Water Storage Tank (RWST) ................... 3.5-9 3.5.5 Seal Injection Flow ................................... 3.5-11 3.6 CONTAINMENT SYSTEMS ....................................... 3.6-1 3.6.1 Containment ........................................... 3.6-1 3.6.2 Containment Air Locks ................................. 3.6-3 3.6.3 Containment Isolation Valves .......................... 3.6-8 3.6.4 Containment Pressure .................................. 3.6-15 3.6.5 Containment Air Temperature ............................ 3.6-16 3.6.6 Containment Spray System .............................. 3.6-18 3.6.7 Hydrogen Recombiners .................................. 3.6-20 3.6.8 Hydrogen Mitigation System (HMS) ...................... 3.6-22 3.6.9 Emergency Gas Treatment System (EGTS) ................. 3.6-24 3.6.10 Air Return System (ARS) ............................... 3.6-26 3.6.11 Ice Bed ............................................... 3.6-28 3.6.12 Ice Condenser Doors ................................... 3.6-31 3.6.13 Divider Barrier Integrity ............................. 3.6-35 3.6.14 Containment Recirculation Drains ...................... 3.6-38 3.6.15 Shield Building ....................................... 3.6-40 3.7 PLANT SYSTEMS ......................................... 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) ...................... 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) ................... 3.7-5 (continued)

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TABLE OF CONTENTS (continued)

-- 3.7 PLANT SYSTEMS (continued) 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves ................. ..... 3.7-7 3.7.4 Atmospheric Dump Valves (ADVs) ................... ..... 3.7-9 3.7.5 Auxiliary Feedwater (AFW),System ................. ..... 3.7-11 3.7.6 Condensate Storage Tank (CST) .................... ..... 3.7-15 3.7.7 Component Cooling System (CCS) ................... ..... 3.7-17 3.7.8 Essential Raw Cooling Water (ERCW) System ........ ..... 3.7-19 3.7.9 Ultimate Heat Sink (UHS) .................. ..... 3.7-21 3.7.10 Control Room Emergency Ventilation System (CREVS) ..... 3.7-22 3 .7.11 Control Room Emergency Air Temperature Control System (CREATCS) ............................... ..... 3.7-25 3 .7.12 Auxiliary Building Gas Treatment System (ABGTS).. ..... 3.7-27 3 .7.13 Fuel Storage Pool Water Level .................... ..... 3.7-29 3 .7.14 Secondary Specific Activity ...................... ..... 3.7-30 3.7.15 Spent Fuel Assembly Storage ...................... ..... 3.7-31 3.8 ELECTRICAL POWER SYSTEMS ........................... ........ 3.8-1 3.8.1 AC Sources--Operating .......................... ........ 3.8-1 3.8.2 AC Sources--Shutdown ........................... ........ 3.8-18 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air .... ........ 3.8-21 3.8.4 DC Sources--Operating .......................... ........ 3.8-24 3.8.5 DC Sources--Shutdown ........................... ........ 3.8-30 3.8.6 Battery Cell Parameters ........................ ........ 3.8-33 3.8.7 Inverters -Operating ............................ ........ 3.8-37 3.8.8 Inverters - Shutdown ............................ ........ 3.8-39 3.8.9 Distribution Systems--Operating ................ ........ 3.8-41 3 .8.10 Distribution Systems--Shutdown ................. ........ 3.8-43 3.9 REFUELING OPERATIONS ............................... ........ 3.9-1 3.9.1 Boron Concentration ............................ ........ 3.9-1 3.9.2 Unborated Water Source Isolation Valves ........ ........ 3.9-2 3.9.3 Nuclear Instrumentation ........................ ........ 3.9-4 3.9.4 Containment Penetrations ....................... ........ 3.9-6 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation-High Water Level ............... ........ 3.9-8 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level ................ ........ 3.9-10 3.9.7 Refueling Cavity Water Level ................... ........ 3.9-12 3.9.8 Reactor Building Purge Air Cleanup Units ....... ........ 3.9-14 3.9.9 Spent Fuel Pool Boron Concentration ............ ........ 3.9-16 4.0 DESIGN FEATURES ........................................... 4.0-1 4.1 Site .................................................. 4 .0-1 4.2 Reactor Core .......................................... 4.0-1 4.3 Fuel Storage .......................................... 4.0-2 (continued)

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TABLE OF CONTENTS (continued) 5.0 ADMINISTRATIVE CONTROLS ................................... 5.0-1 5.1 Responsibility ........................................ 5.0-1 5.2 Organization .......................................... 5.0-2 5.3 Unit Staff Qualifications ............................. 5.0-5 5.4 Training .............................................. 5.0-6 5.5 Reviews and Audits ..................................... 5.0-7 5.6 Technical Specifications (TS) Bases Control Program ... 5.0-8 5.7 Procedures, Programs, and Manuals ..................... 5.0-9 5.8 Safety Function Determination Program (SFDP) .......... 5.0-29 5.9 Reporting Requirements ................................. 5.0-30 5.10 Record Retention ....................................... 5.0-36 5.11 High Radiation Area .................................... 5.0-37 Watts Bar-Unit 1 IV

LIST OF TABLES N

Table No. Title Page Page 1.1-1 MODES ................................................ 1.1-7 3.3.1-1 Reactor Trip System Instrumentation .................. ...... 3.3-15 3.3.2-1 Engineered Safety Features Actuation System Instrumentation ................................... ...... 3.3-34 3.3.3-1 Post-Accident Monitoring Instrumentation ............. ...... 3.3-44 3.3.4-1 Remote Shutdown System Instrumentation and Controls ...... 3.3-48 3.3.5-1 LOP DG Start Instrumentation ......................... ...... 3.3-51 3.3.6-1 Containment Vent Isolation Instrumentation ........... ...... 3.3-56 3.3.7-1 CREVS Actuation Instrumentation ...................... ...... 3.3-60 3.3.8-1 ABGTS Actuation Instrumentation ............... *....... ...... 3.3-64 3.7.1-1 OPERABLE Main Steam Safety Valves versus Applicable Power in Percent of RATED THERMAL POWER ............................................. ...... 3.7-3 3.7.1-2 Main Steam Safety Valve Lift Settings ................ ...... 3.7-4 3.8.1-1 Diesel Generator Test Schedule ....................... ...... 3.8-17 3.8.6-1 Battery Cell Parameter Requirements .................. ...... 3.8-36 5.7.2.12-1 Steam Generator Tube Inspection Supplemental Sampling Requirements ............................. ...... 5.0-20 5.7.2.12-2 Minimum Number of Steam Generators to be Inspected During Inservice Inspection ....................... ...... 5.0-21 Watts Bar-Unit 1 V

LIST OF FIGURES Figure No. Title Page ................................................. Page 2.1.1-1 Reactor Core Safety Limits ................................ 2.0-2 3.4.16-1 Reactor Coolant DOSE EQUIVALENT 1-131 Specific Activity Limit Versus Percent Of RATED THERMAL POWER ..................................................... 3.4-42 3.7.15-1 Acceptable Burnup Domain - Watts Bar Spent Fuel Storage Racks ............................................. 3.7-32 4.1-1 Site and Exclusion Area Boundaries ........................ 4.0-4 4.1-2 Low Population Zone ....................................... 4.0-5 4.3-1 Spent Fuel Pool Plan ...................................... 4.0-7 4.3-2 New Fuel Storage Rack Loading Pattern ..................... 4.0-8 Watts Bar-Unit 1 V1 Revision 15

Acronym Title ABGTS Auxiliary Building Gas Treatment System ACRP Auxiliary Control Room Panel ASME American Society of Mechanical Engineers AFD Axial Flux Difference AFW Auxiliary Feedwater System ARO All Rods Out ARFS Air Return Fan System ARV Atmospheric Relief Valve BOC Beginning of Cycle CAOC Constant Axial Offset Control CCS Component Cooling Water System CFR Code of Federal Regulations COLR Core Operating Limits Report CREVS Control Room Emergency Ventilation System CSS Containment Spray System CST Condensate Storage Tank DNB Departure from Nucleate Boiling ECCS Emergency Core Cooling System EFPD Effective Full-Power Days EGTS Emergency Gas Treatment System EOC End of Cycle ERCW Essential Raw Cooling Water ESF Engineered Safety Feature ESFAS Engineered Safety Features Actuation System HEPA High Efficiency Particulate Air HVAC Heating, Ventilating, and Air-Conditioning LCO Limiting Condition For Operation MFIV Main Feedwater Isolation Valve MFRV Main Feedwater Regulation Valve MSIV Main Steam Line Isolation Valve MSSV Main Steam Safety Valve MTC Moderator Temperature Coefficient NMS Neutron Monitoring System ODCM Offsite Dose Calculation Manual PCP Process Control Program PIV Pressure Isolation Valve PORV Power-Operated Relief Valve PTLR Pressure and Temperature Limits Report QPTR Quadrant Power Tilt Ratio RAOC Relaxed Axial Offset Control RCCA Rod Cluster Control Assembly RCP Reactor Coolant Pump RCS Reactor Coolant System RHR Residual Heat Removal RTP Rated Thermal Power RTS Reactor Trip System RWST Refueling Water Storage Tank SG Steam Generator SI Safety Injection SL Safety Limit SR Surveillance Requirement UHS Ultimate Heat Sink Watts Bar-Unit 1 vii

TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES PAGE REVISION DATE*

i 0 Initial ii 0 Initial iii 6 07-28-97 iv 0 Initial v 0 Initial vi 15 12-01-98 vii 0 Initial viii 36 08-30-02 ix 28 01-22-01 x 19 03-22-00 xi 34 03-06-02 xii 33 03-01-02 xiii 30 01-31-02 I xiv 36 08-30-02 xv 31 02-12-02 xvi 35 03-08-02 xvii 15 12-01-98 xviii 28 01-22-01 I xix 36 08-30-02 xx 9 10-21-97 PAGE AMENDMENT DATE 1.1-1 0 Initial 1.1-2 0 Initial 1.1-3 24 06-13-00 1.1-4 0 Initial 1.1-5 31 01-22-01 1.1-6 0 Initial 1.1-7 0 Initial 1.2-1 0 Initial 1.2-2 0 Initial 1.2-3 0 Initial 1.3-1 0 Initial 1.3-2 0 Initial 1.3-3 0 Initial 1.3-4 0 Initial 1.3-5 0 Initial 1.3-6 0 Initial 1.3-7 0 Initial 1.3-8 0 Initial 1.3-9 0 Initial 1.3-10 0 Initial 1.3-11 0 Initial 1.3-12 0 Initial 1.3-13 0 Initial 1.4-1 0 Initial 1.4-2 0 Initial Initial is the effective date of the WBN 1 Full Power License. Initial Issue pages do not have a revision level, date, or amendment number.

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TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES PAGE AMENDMENT ,DATE 1.4-3 0 Initial 1.4-4 0 Initial 2.0-1 0 Initial 2.0-2 31 01-22-01 I 3.0-1 0 Initial 3.0-2 0 Initial 3.0-3 0 Initial 3.0-4 0 Initial Initiai 3.0-5 0 3.1-1 0 Initial 3.1-2 0 Initial 3.1-3 0 Initial 3.1-4 0 Initial 3.1--5 0 Initial 3.1-6 0 Initial 3.1-7 0 Initial 3.1-8 0 Initial 3.1-9 0 Initial 3.1-10 0 Initial 3.1-11 0 Initial 3.1-12 0 Initial 3.1-13 0 Initial 3.1-14 0 Initial 3.1-15 0 Initial 3.1-16 0 Initial 3.1-17 0 Initial 3.1-18 0 Initial 3.1-19 0 Initial 3.1-20 0 Initial 3.1-21 0 Initial 3.1-22 0 Initial 3.1-23 28 09-13-00 3.1-24 28 09-13-00 3.2-1 0 Initial 3.2-2 0 Initial 3.2-3 0 Initial 3.2-4 11 09-09-98 3.2-5 0 Initial 3.2-6 0 Initial 3.2-7 0 Initial 3.2-8 0 Initial 3.2-9 0 Initial 3.2-10 0 Initial 3.2-11 0 Initial 3.2-12 0 Initial Watts Bar-Unit 1 ix Revision 28

TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES PAGE AMENDMENT DATE 3.3-1 0 Initial 3.3-2 0 Initial 3.3-3 0 Initial 3.3-4 0 Initial 3.3-5 0 Initial 3.3-6 0 Initial 3.3-7 0 Initial 3.3-8 0 Initial 3.3-9 0 Initial 3.3-10 0 Initial 3.3-11 0 Initial 3.3-12 0 Initial 3.3-13 0 Initial 3.3-14 0 Initial 3.3-15 18 01-15-99 3.3-16 0 Initial 3.3-17 0 Initial 3.3-18 7 09-11-97 3.3-19 0 Initial 3.3-20 0 Initial 3.3-21 7 09-11-97 3.3-22 7 09-11-97 3.3-23 0 Initial 3.3-24 0 Initial 3.3-25 0 Initial 3.3-26 0 Initial 3.3-27 0 Initial 3.3-28 0 Initial 3.3-29 0 Initial 3.3-30 0 Initial 3.3-31 0 Initial 3.3-32 17 12-30-98 3.3-33 13 10-26-98 3.3-34 0 Initial 3.3-35 0 Initial 3.3-36 23 03-22-00 3.3-37 7 09-11-97 3.3-38 1 02-28-96 3.3-39 0 Initial 3.3-40 0 Initial 3.3-41 0 Initial 3.3-42 0 Initial 3.3-43 0 Initial 3.3-44 0 Initial Watts Bar-Unit 1 X Revision 19

TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES PAGE AMENDMENT DATE 3.3-45 0 Initial 3.3-46 0 Initial 3.3-47 0 Initial 3.3-48 0 Initial 3.3-49 0 Initial 3.3-50 0 Initial 3.3-51 36 03-06-02 I 3.3-52 35 02-12-02 3.3-53 0 Initial 3.3-54 35 02-12-02 3.3-55 17 12-30-98 3.3-56 0 Initial 3.3-57 0 Initial 3.3-58 35 02-12-02 3.3-59 0 Initial 3.3-60 0 Initial 3.3-61 0 Initial 3.3-62 0 Initial 3.3-63 0 Initial 3.3-64 0 Initial 3.4-1 7 09-11-97 3.4-2 7 09-11-97 3.4-3 0 Initial 3.4-4 0 Initial 3.4-5 0 Initial 3.4-6 0 Initial 3.4-7 0 Initial 3.4-8 0 Initial 3.4-9 0 Initial 3.4-10 0 Initial 3.4-11 0 Initial 3.4-12 0 Initial 3.4-13 0 Initial 3.4-14 0 Initial 3.4-15 0 Initial 3.4-16 0 Initial 3.4-17 0 Initial 3.4-18 0 Initial 3.4-19 0 Initial 3.4-20 0 Initial 3.4-21 0 Initial 3.4-22 0 Initial 3.4-23 0 Initial 3.4-24 0 Initial Watts Bar-Unit 1 xi Revision 34

TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES PAGE AMENDMENT DATE 3.4-25 14 11-10-98 3.4-26 0 Initial 3.4-27 0 Initial 3.4-28 0 Initial 3.4-29 0 Initial 3.4-30 38 03-01-02 3.4-31 0 Initial 3.4-32 0 Initial 3.4-33 0 Initial 3.4-34 0 Initial 3.4-35 0 Initial 3.4-36 0 Initial 3.4-37 0 Initial 3.4-38 0 Initial 3.4-39 0 Initial 3.4-40 0 Initial 3.4-41 0 Initial 3.4-42 0 Initial 3.5-1 0 Initial 3.5-2 21 03-17-00 3.5-3 0 Initial 3.5-4 0 Initial 3.5-5 0 Initial 3.5-6 0 Initial 3.5-7 0 Initial 3.5-8 0 Initial 3.5-9 0 Initial 3.5-10 7 09-11-97 3.5-11 0 Initial 3.5-12 0 Initial 3.6-1 0 Initial 3.6-2 5 05-27-97 3.6-3 0 Initial 3.6-4 0 Initial 3.6-5 0 Initial 3.6-6 0 Initial 3.6-7 5 05-27-97 3.6-8 0 Initial 3.6-9 0 Initial 3.6-10 0 Initial 3.6-11 0 Initial 3.6-12 0 Initial Watts Bar-Unit 1 x~i Revision 33

TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES PAGE AMENDMENT DATE 3.6-13 0 Initial 3.6-14 5 05-27-97 3.6-15 0 Initial 3.6-16 0 Initial 3.6-17 0 Initial 3.6-18 0 Initial 3.6-19 0 Initial 3.6-20 0 Initial 3.6-21 0 Initial 3.6-22 10 06-09-98 3.6-23 10 06-09-98 3.6-24 0 Initial 3.6-25 0 Initial 3.6-26 0 Initial 3.6-27 0 Initial 3.6-28 0 Initial 3.6-29 33 01-31-02 3.6-30 22 03-21-00 3.6-31 0 Initial 3.6-32 3 09-09-96 3.6-33 3 09-09-96 3.6-34 3 09-09-96

3. 6-34a 3 09-09-96 3.6-35 0 Initial 3.6-36 0 Initial 3.6-37 0 Initial 3.6-38 0 Initial 3.6-39 0 Initial 3.6-40 0 Initial 3.6-41 0 Initial 3.7-1 31 01-22-01 3.7-2 0 Initial 3.7-3 31 01-22-01 3.7-4 0 Initial 3.7-5 0 Initial 3.7-6 0 Initial 3.7-7 0 Initial 3.7-8 0 Initial 3.7-9 16 12-17-98 3.7-10 0 Initial 3.7-11 0 Initial 3.7-12 0 Initial 3.7-13 13 10-26-98 3.7-14 13 10-26-98 3.7-15 0 Initial 3.7-16 0 Initial 3.7-17 0 Initial I

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TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES PAGE AMENDMENT DATE 3.7-18 0 Initial 3.7-19 0 Initial 3.7-20 0 Initial 3.7-21 0 Initial 3.7-22 35 02-12-02 3.7-23 35 02-12-02 3.7-24 0 Initial 3.7-25 35 02-12-02 3.7-26 35 02-12-02 3.7-27 0 Initial 3.7-28 0 Initial 3.7-29 0 Initial 3.7-30 0 Initial 3.7-31 6 07-28-97 3.7-32 6 07-28-97 3.8-1 0 Initial 3.8-2 39 07-01-02

3. 8-2a 39 07-01-02 3.8-3 39 07-01-02 3.8-4 39 07-01-02 3.8-5 39 07-01-02 3.8-6 0 Initial 3.8-7 0 Initial 3.8-8 0 Initial 3.8-9 0 Initial 3.8-10 0 Initial 3.8-11 0 Initial 3.8-12 12 10-19-98 3.8-13 0 Initial 3.8-14 0 Initial 3.8-15 0 Initial 3.8-16 0 Initial 3.8-17 0 Initial 3.8-18 0 Initial 3.8-19 0 Initial 3.8-20 0 Initial 3.8-21 0 Initial 3.8-22 0 Initial 3.8-23 0 Initial 3.8-24 0 Initial 3.8-25 0 Initial 3.8-26 0 Initial 3.8-27 0 Initial 3.8-28 12 10-19-98 3.8-29 12 10-19-98 Watts Bar-Unit 1 xiv Revision 36

TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES PAGE AMENDMENT DATE 3.8-30 0 -Initial 3.8-31 0 Initial 3.8-32 0 Initial 3.8-33 0 Initial 3.8-34 0 Initial 3.8-35 0 Initial 3.8-36 0 Initial 3.8-37 0 Initial 3.8-38 0 Initial 3.8-39 0 Initial 3.8-40 0 Initial 3.8-41 0 Initial 3.8-42 0 Initial 3.8-43 0 Initial 3.8-44 0 Initial 3.9-1 0 Initial 3.9-2 0 Initial 3 .9-3 0 Initial 3.9-4 0 Initial 3.9-5 0 Initial 3.9-6 35 02-12-02 I 3.9-7 0 Initial 3.9-8 0 Initial 3.9-9 0 Initial 3.9-10 0 Initial 3.9-11 0 Initial 3.9-12 35 02-12-02 l 3.9-13 3.9-14 0 Initial J 35 02-12-02 3.9-15 0 Initial 3 .9-16 0 Initial 4.0-1 8 09-15-97 4.0-2 6 07-28-97 4.0-3 6 07-28-97 4.0-4 15 12-01-98 4.0-5 6 07-28-97 4.0-6 6 07-28-97 4 .0-7 6 07-28-97 4.0-8 15 12-01-98 5.0-1 0 Initial 5.0-2 0 Initial 5.0-3 0 Initial 5.0-4 4 10-15-96 5.0-5 0 Initial 5.0-6 0 Initial 5.0-7 0 Initial 5.0-8 32 06-15-01 Watts Bar-Unit 1 xv Revision 31

TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES PAGE AMENDMENT DATE 5.0-9 0 Initial 5.0-10 0 Initial I 5.0-11 34 03-08-02 5.0-12 0 Initial 5.0-13 0 Initial 5.0-14 0 Initial 5.0-15 38 03-01-02 5.0-16 38 03-01-02 5.0-17 38 03-01-02 5.0-18 38 03-01-02 5.0-19 38 03-01-02

5. 0-19a 38 03-01-02

5. 0-19b 38 03-01-02 5.0-20 0 Initial 5.0-21 0 Initial 5.0-22 0 Initial 5.0-23 0 Initial 5.0-24 0 Initial 5.0-25 0 Initial 5.0-26 0 Initial 5.0-27 0 Initial 5.0-28 5 05-27-97

5. 0-28a 5 05-27-97 5.0-29 0 Initial j 5.0-30 0 Initial 5.0-31 0 Initial 5.0-32 31 01-22-01 5.0-33 31 01-22-01 5.0-34 9 10-21-97 5.0-35 38 03-01-02 5.0-35a 38 03-01-02 5.0-36 0 Initial 5.0-37 0 Initial 5.0-38 0 Initial 5.0-39 0 Initial 5.0-40 0 Initial Watts Bar-Unit 1 XVI Revision 35

TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES AMENDMENT LISTING Amendments NPF-20 Low Power Issued 11-09-95 Sub ect Operating License NPF-90 Full Power Operating License 02-07-96 Amendment 1 02-28-96 Turbine Driven AFW Pump Suction requirement Amendment 2 06-13-96 Ice Bed Surveillance_£requency and weight.

Amendment 3 09-09-96 Ice Condenser Lower Inlet Door Surveillance.

Amendment 4 10-15-96 Operations Manager Requirements.

Amendment 5 05-27-97 Appendix J, Option B.

Amendment 6 07-28-97 Spent Fuel Pool Rerack.

Amendment 7 09-11-97 Cycle 2 Core Reload.

Amendment 8 09-15-97 Tritium Producing Burnable Poison Rods (TPBAR) Lead Test Assembly (LTA).

Amendment 9 10-21-97 PTLR Methodology.

Amendment 10 06-09-98 Hydrogen Mitigation System Temporary Specification.

Amendment 11 08-10-98 Relocation of F(Q) Penalty to COLR Amendment 12 10-19-98 Online testing of the diesel batteries and performance of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months diesel endurance run.

Amendment 13 10-26-98 Clarification of Surveillance Testing Requirements for TDAFW Pump Amendment 14 11-10-98 COMS - Four Hour Allowance to Make RHR Suction Relief Valve Operable after Mode 4 Entry Amendment 15 12-01-98 Increase of Enrichment Limit to Five Percent for New Fuel Storage Watts Bar Nuclear Plant Xvii Revision 15

TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES AMENDMENT LISTING Amendments Issued Subject Amendment 16 12-17-98 New action for Steam Generator ADVs due to Inoperable ACAS.

Amendment 17 12-30-98 Slave Relay Surveillance Extension to 18 Months Amendment 18 01-15-99 Deletion of Power Range Neutron Flux High Negative Rate Reactor Trip Function Amendment 19 03-07-00 Reset Power Range High Flux Reactor Trip Setpoints for Multiple Inoperable MSSVs.

Amendment 20 03-14-00 Change to a More Negative Moderator Temperature Coefficient (MTC)

Amendment 21 03-17-00 Best Estimate Large Break Loss-of-Coolant Accident Analysis Amendment 22 03-21-00 Ice Condenser sampling surveillance requirements, SR 3.6.11.5 and SR 3.6.11.7.

Amendment 23 03-22-00 For SR 3.3.2.10, Table 3.3.2-1, added

-I note h for one time relief from turbine trip response time testing.

Amendment 24 06-13-00 Elimination of Response Time Testing Amendment 25 07-17-00 Ice Condenser flow channel inspection requirements, SR 3.6.11.4 Amendment 26 08-24-00 Administrative Controls for Open Penetrations During Refueling Operations Amendment 27 09-08-00 Steam Generator Alternate Repair Criteria F-Star (F*) for Tube Sheet Region Amendment 28 09-13-00 Physics Tests Exceptions Amendment 29 12-05-00 Physical Security Plan amendment regarding testing frequency for tamper switch/line supervision alarms Amendment 30 12-08-00 One Time DG Action Completion Time extension from 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to 10 days for the lB-B DG generator replacement Watts Bar Nuclear Plant xv.1il Revision 28

TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES AMENDMENT LISTING Amendments Issued - Subject Amendment 31 01-19-01 "Power Uprate from 3411 MWt to 3459 MWt Using Leading Edge Flow Meter (LEFM)

Amendment 32 06-15-01 Revise Bases Control Program Pursuant to 10 CFR 50.59.

Amendment 33 11-29-01 Ice Weight Reduction Amendment 34 01-14-02 Post Accident Sampling System Elimination Amendment 35 01-22-02 Relaxation of CORE ALTERATIONS Restrictions Amendment 36 01-23-02 Increase Degraded Voltage Time Delay from 6 to 10 seconds Amendment 37 02-21-02 Spent Fuel Pool Cooling Analysis Methodology Change Amendment 38 02-26-02 RCS Operational LEAKAGE and SG Alternate Repair'Criteria for Axial Outside Diameter Stress Corrosion Cracking (ODSCC)

Amendment 39 07-01-02 Extension of the allowed outage time (AOT) for a single diesel generator from 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to 14 days.

Watts Bar Nuclear Plant xix Revision 36

TECHNICAL SPECIFICATIONS LIST OF APPROVED EXEMPTIONS

1. An exemption to 10 CFR 50 Appendix J, Section III.D.2(b) (ii) was granted with the operating license on November 9, 1995 for performing the overall air lock leak test at pressure Pa before establishing containment integrity if air lock maintenance had been performed that have could affected the air lock sealing capability. Justification for this exemption is in WBN Supplemental Safety Evaluation Report (SSER) 4.

This Exemption was deleted with the issuance of Amendment 5 on May 27, 1997.

2. An exemption to 10 CFR 70.24 was previously granted in the SSER 5 for the criticality monitoring requirements in the Special Nuclear Material (SNM) License SNM-1861. The exemption was carried forth into the WBN Unit 1 Operating License on November 9, 1995.

3. An exemption to 10 CFR 73.55(c) (10) for the surface vehicle bomb rule was granted from the implementing schedule of fuel load until February 27, 1996. Justification for this exemption is provided in SSER 15 an granted in the WBN Unit 1 Low Power Operating License on November 9, 1995. Implementation was certified by letter dated February 15, 1996 (T04 960215 292)

4. An exemption to certain requirements in 10 CFR 73.55(d) (5) was granted relating to the returning of picture badges upon exit from the protected areas such that individuals not employed by TVA who are authorized unescorted access into the protected areas can take their badges offsite. Justification for this exemption is discussed in SSER 15 and granted by letter dated December 15, 1994 (A0O 941219 003).

5. An exemption to 10 CFR 50, Appendix E was granted such that the State of Tennessee which is within the ingestion exposure pathway emergency planning zone, need not participate in the next full participation exercise. This exemption was granted in the Low Power Operating License dated November 9, 1995. Exemption is no longer valid after the full participation exercise which was held on November 15, 1995.

6. An exemption to 10 CFR 50.60 was granted to use the safety margins in ASME Code Case N-514, "Low Temperature Overpressure Protection," in lieu of the safety margins required by 10 CFR 50, Appendix G to establish fracture toughness requirements for the RCS pressure boundary pressure and temperature limits. This exemption was granted on September 29, 1997 (L44 971006 005).

Watts Bar Nuclear Plant XX Revision 9

ENCLOSURE 2 TABLE OF CONTENTS, LIST OF EFFECTIVE PAGES, AND CHANGED PAGES WBN TECHNICAL SPECIFICATIONS BASES

TABLE OF CONTENTS TABLE OF CONTENTS ....... .................................................. i LISTOFTABLES .........-....................... o .......................... iv LIST OF FIGURES ......................................................... v LIST OF ACRONYMS ................................ . ....... vi LIST OF EFFECTIVE PAGES . .v..................................................Viii B 2.0 SAFETY LIMITS (SLs) ............. B......B 2.0-1 B 2.1.1 Reactor Core SLs ..................................... B 2.0-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL ............. B 2.0-8 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .......... B 3.0-1 B 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .................... B 3.0-10 B 3.1 REACTIVITY CONTROL SYSTEMS; ............................. B 3.1-1 B 3.1.1 SHUTDOWN MARGIN (SDM) Tay > 200FF ...................... B 3.1-1 B 3.1.2 SHUTDOWN MARGIN 4(SDM) Tavg : 200F ....................... B 3.1-7 B 3.1.3 Core Reactivity ...................................... B 3.1-12 B 3.1.4 Moderator Temperature'Coefficient (MTC) .............. B 3.1-18 B 3.1.5 Rod Group Alignment Limits ........................... B 3.1-24 B 3.1.6 Shutdown Bank Insertion Limits ....................... B 3.1-35 B 3.1.7 Control Bank Insertion Limits ........................ B 3.1-40 B 3.1.8 Rod Position Indication .............................. B 3.1-48 B 3.1.9 PHYSICS TESTS Exceptions MODE 1 ....................... B 3.1-55 B 3.1.10 PHYSICS TESTS Exceptions MODE 2 ...................... B 3.1-63 B 3.2 POWER DISTRIBUTION LIMITS ..................... ............. B 3.2-1 B 3.2.1 Heat Flux Hot Channel Factor (FQ(Z)) ..... ............. B 3.2-1 B 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FAH) ............. ........... ............ B 3.2-12 B 3.2.3 AXIAL FLUX DIFFERENCE (AFD) .............. ......................................... B 3.2-19 B 3.2.4 QUADRANT POWER TILT RATIO (QPTR) ......... ......................................... B 3.2-24 B 3.3 INSTRUMENTATION ........................................... B 3.3-1 B 3.3.1 Reactor Trip System (RTS) Instrumentation ............ B 3.3-1 B 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation ... ................ B 3.3-64 B 3.3.3 Post Accident Monitoring (PAM) Instrumentation ....... B 3.3-121 B 3.3.4 Remote Shutdown System ............................... B 3.3-141 B 3.3.5 Loss of Power (LOP) Diesel Generator (DG)

Start Instrumentation ............................. B 3.3-147 B 3.3.6 Containment Vent.Isolation Instrumentation ........... B 3.3-154 B 3.3.7 Control Room Emergency Ventilation System (CREVS) Actuation Instrumentation ................. B 3.3-163 B 3.3.8 Auxiliary Building Gas Treatment System (ABGTS)

Actuation Instrumentation ......................... B 3.3-171 (continued)

Watts Bar-Unit 1 i

TAB3LE OF CONTENTS (continued)

B 3.4 REACTOR COOLANT SYSTEM (RCS) .............................. B 3.4-1 B 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ................ B 3.4-1 B 3.4.2 RCS Minimum Temperature for Criticality .............. B 3.4-6 B 3.4.3 RCS Pressure and Temperature (P/T) Limits ............ B 3.4-9 B 3.4.4 RCS Loops-MODES 1 and 2 .............................. B 3.4-17 B 3.4.5 RCS Loops-MODE 3 ..................................... B 3.4-21 B 3.4.6 RCS Loops-MODE 4 ..................................... B 3.4-27 B 3.4.7 RCS Loops-MODE 5, Loops Filled ....................... B 3.4-33 B 3.4.8 RCS Loops-MODE 5, Loops Not Filled .................... B 3.4-38 B 3.4.9 Pressurizer .......................................... B 3.4-41 B 3.4.10 Pressurizer Safety Valves ............................ B 3.4-46 B 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) .................................... B 3.4-51 B 3.4.12 Cold Overpressure Mitigation System (COMS) ........... B 3.4-58 B 3.4.13 RCS Operational LEAKAGE .............................. B 3.4-74 B 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ........... B 3.4-81 B 3.4.15 RCS Leakage Detection Instrumentation ................ B 3.4-87 B 3.4.16 RCS Specific Activity ................................ B 3.4-93 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ..................... B 3.5-1 B 3.5.1 Accumulators ......................................... B 3.5-1 B 3.5.2 ECCS-Operating ....................................... B 3.5-10 B 3.5.3 ECCS- Shutdown ........................................ B 3.5-20 B 3.5.4 Refueling Water Storage Tank (RWST) ................... B 3.5-24 B 3.5.5 Seal Injection Flow .................................. B 3.5-31 B 3.6 CONTAINMENT SYSTEMS ....................................... B 3.6-1 B 3.6.1 Containment .......................................... B 3.6-1 B 3.6.2 Containment Air Locks ................................ B 3.6-6 B 3.6.3 Containment Isolation Valves ......................... B 3.6-14 B 3.6.4 Containment Pressure ................................. B 3.6-28 B 3.6.5 Containment Air Temperature .......................... B 3.6-31 B 3.6.6 Containment Spray Systems ............................ B 3.6-35 B 3.6.7 Hydrogen Recombiners ................................. B 3.6-43 B 3.6.8 Hydrogen Mitigation System (HMS) ..................... B 3.6-49 B 3.6.9 Emergency Gas Treatment System (EGTS) ................. B 3.6-55 B 3.6.10 Air Return System (ARS) .............................. B 3.6-60 B 3.6.11 Ice Bed .............................................. B 3.6-65 B 3.6.12 Ice Condenser Doors .................................. B 3.6-74 B 3.6.13 Divider Barrier Integrity ............................ B 3.6-84 B 3.6.14 Containment Recirculation Drains ...................... B 3.6-90 B 3.6.15 Shield Building ...................................... B 3.6-95 (continued)

Watts Bar-Unit 1 ii

TABLE OF CONTENTS (continued)

B 3.7 PLANT SYSTEMS ............................................. B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) ...................... B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) .................. B 3.7-7 B 3.7.3 Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves ...................... B 3.7-13 B 3.7.4 Atmospheric Dump Valves (ADVs) ....................... B 3.7-20 B 3.7.5 Auxiliary Feedwater (AFW) System ..................... B 3.7-24 B 3.7.6 Condensate Storage Tank (CST) ......................... B 3.7-34 B 3.7.7 Component Cooling System (CCS) ....................... B 3.7-38 B 3.7.8 Essential Raw Cooling Water (ERCW) System ............ B 3.7-43 B 3.7.9 Ultimate Heat Sink (UHS) .............................. B 3.7-48 B 3.7.10 Control Room Emergency Ventilation System (CREVS) .... B 3.7-51 B 3.7.11 Control Room Emergency Air Temperature Control System (CREATCS) ......................... B 3.7-58 B 3.7.12 Auxiliary Building Gas Treatment System (ABGTS) ...... B 3.7-62 B 3.7.13 Fuel Storage Pool Water Level ........................ B 3.7-68 B 3.7.14 Secondary Specific Activity .......................... B 3.7-71 B 3.7-15 Spent Fuel Assembly Storage .......................... B 3.7-75 B 3.8 ELECTRICAL POWER SYSTEMS .................................. B 3.8-1 B 3.8.1 AC Sources--Operating .................................. B 3.8-1 B 3.8.2 AC Sources--Shutdown ................................... B 3.8-37 B 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air .......... B 3.8-43 B 3.8.4 DC Sources--Operating .................................. B 3.8-54 B 3.8.5 DC Sources--Shutdown ................................... B 3.8-70 B 3.8.6 Battery Cell Parameters ............................. B 3.8-74 B 3.8.7 Inverters--Operating ................................... B 3.8-81 B 3.8.8 Inverters--Shutdown ................................... B 3.8-85 B 3.8.9 Distribution Systems--Operating ........................ B 3.8-89 B 3.8.10 Distribution Systems--Shutdown ........................ B 3.8-99 B 3.9 REFUELING OPERATIONS ....................................... B 3.9-1 B 3.9.1 Boron Concentration ................................... B 3.9-1 B 3.9.2 Unborated Water Source Isolation Valves .............. B 3.9-5 B 3.9.3 Nuclear Instrumentation .............................. B 3.9-8 B 3.9.4 Containment Penetrations .............................. B 3.9-12 B 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation-High Water Level ....................... B 3.9-17 B 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level ........................ B 3.9-21 B 3.9.7 Refueling Cavity Water Level ......................... B 3.9-25 B 3.9.8 Reactor Building Purge Air Cleanup Units ............. B 3.9-29 B 3.9.9 Spent Fuel Pool Boron Concentration ................. B 3.9-33 Watts Bar-Unit 1 iii Revision 11

LIST OF TABLES

/

Table No. Title Page Page B 3.8.9-1 AC and DC Electrical Power Distribution Systems ........................................ B 3.8-98 Watts Bar-Unit 1 iv

LIST OF FIGURES Figure No. Title Page B 2.1.1-1 Reactor Core Safety Limits vs Boundary of Protection .............................. ............. B 2.0-7 B 3.1.7-1 Control Bank Insertion vs Percent RTP ......... ............ B 3.1-47 B 3.2.1-1 K(z) - Normalized FQ(z) as a Function of Core Height .. .............................................. B 3.2-11 B 3.2.3-1 AXIAL FLUX DIFFERENCE Acceptable Operation Limits as a Function of RATED THERMAL POWER ................. B 3.2-23 Watts Bar-Unit 1 V

LIST OF ACRONYMS Acronyma Title (Page 1 of 2)

ABGTS Auxiliary Building Gas Treatment System ACRP Auxiliary Control Room Panel ASME American Society of Mechanical Engineers AFD Axial Flux Difference AFW Auxiliary Feedwater System ARO All Rods Out ARFS Air Return Fan System ADV Atmospheric Dump Valve BOC Beginning of Cycle CAOC Constant Axial Offset Control CCS Component Cooling System CFR Code of Federal Regulations COLR Core Operating Limits Report CREVS Control Room Emergency Ventilation System CSS Containment Spray System CST Condensate Storage Tank DNB Departure from Nucleate Boiling ECCS Emergency Core Cooling System EFPD Effective Full-Power Days EGTS Emergency Gas Treatment System EOC End of Cycle ERCW Essential Raw Cooling Water ESF Engineered Safety Feature ESFAS Engineered Safety Features Actuation System HEPA High Efficiency Particulate Air HVAC Heating, Ventilating, and Air-Conditioning LCO Limiting Condition For Operation MFIV Main Feedwater Isolation Valve MFRV Main Feedwater Regulation Valve MSIV Main Steam Line Isolation Valve MSSV Main Steam Safety Valve MTC Moderator Temperature Coefficient NMS Neutron Monitoring System ODCM Offsite Dose Calculation Manual PCP Process Control Program PIV Pressure Isolation Valve PORV Power-Operated Relief Valve PTLR Pressure and Temperature Limits Report QPTR Quadrant Power Tilt Ratio RAOC Relaxed Axial Offset Control RCCA Rod Cluster Control Assembly RCP Reactor Coolant Pump RCS Reactor Coolant System RHR Residual Heat Removal RTP Rated Thermal Power Watts Bar-Unit 1 vi

LIST OF-ACRONYMS (Page 2 of 2)

Acronym Title RTS Reactor Trip System RWST Refueling Water Storage Tank SG - Steam Generator SI I Safety Injection SL Safety Limit SR Surveillance Requirement UHS Ultimate Heat Sink Watts Bar-Unit 1 vii

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE*

i 0 Initial ii 0 Initial iii 11 07-28-97 iv 0 Initial 0 Initial vi 0 Initial vii 0 Initial V

I viii 50 08-30-02 ix 32 04-13-00 x 40 09-13-00 xi 39 03-17-00 xii 34 07-07-00 xiii 13 09-11-97 49 03-08-02 xiv 45 02-12-02 xv xvi 42 03-07-01 47 03-01-02 xxii 44 01-31-02 44 01-31-02 xx 41 01-22-01 xxv xviii xxi 45 02-12-02 xxiii 50 08-30-02 xxiii 50 08-30-02 46 02-25-02 xxv xxvi 45 02-12-02 xxvi 16 06-09-98 xxvili 27 01-15-99 37 09-08-00 XX3X 48 03-06-02 xxx 50 08-30-02 PAGE REVISION DATE B 2.0-1 0 Initial B 2.0-2 0 Initial B 2.0-3 0 Initial B 2.0-4 13 09-11-97 B 2.0-5 13 09-11-97 B 2.0-6 13 09-11-97 B 2.0-7 0 Initial B 2.0-8 0 Initial B 2.0-9 0 Initial B 2.0-10 0 Initial B 2.0-11 0 Initial B 2.0-12 0 Initial B 3.0-1 0 Initial B 3.0-2 0 Initial B 3.0-3 0 Initial Initial is the effective date of the WBN 1 Full Power License. Initial Issue pages do not have a revision level, date, or amendment number.

Watts Bar-Unit 1 Villl Revision 50

TECHNICAL SPECIFICATIONS BASES LIST oF EFFECTI PAGES PAGE REVISION DATE B 3.0-4 0 Initial B 3.0-5 0 Initial B 3.0-6 0 Initial B 3.0-7 0 Initial B 3.0-8 0 Initial B 3.0-9 0 Initial.

B 3.0-10 0 Initial B 3.0-11 10 05-27-97 B 3.0-12 10 05-27-97 B 3.0-13 0 Initial B 3.0-14 0 Initial B 3.0-15 0 Initial B 3.1-1 0 Initial B 3.1-2 0 Initial B 3.1-3 0 Initial B 3.1-4 0 Initial B 3.1-5 0 Initial B 3.1-6 0 Initial B 3.1-7 0 Initial B 3.1-8 0 Initial B 3.1-9 0 Initial B 3.1-10 0 Initial B 3.1-11 0 Initial B 3.1-12 0 Initial B 3.1-13 32 04-13-00 I B 3.1-14 0 Initial B 3.1-15 0 Initial B 3.1-16 0 Initial B 3.1-17 0 Initial B 3.1--18 32 04-13-00 B 3.1-19 32 04-13-00 B 3.1-20 32 04-13-00 B 3.1-21 32 04-13-00 B 3.1-22 32 04-13-00 B 3.1-23 0 Initial B 3. 1-24 0 Initial B 3.1-25 0 Initial B 3.1-26 0 Initial B 3. 1-27 0 Initial B 3.1-28 0 Initial B 3.1-29 0 Initial B 3.1-30 0 Initial' B 3.1-31 0 Initial B 3.1-32 0 Initial B 3.1-33 0 Initial Watts Bar-Unit 1 ix Revision 32

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES 7)

PAGE REVISION DATE B 3.1-34 0 Initial B 3.1-35 0 Initial B 3.1-36 0 Initial B 3.1-37 0 Initial B 3.1-38 0 Initial B 3.1-39 0 Initial B 3.1-40 0 Initial B 3.1-41 0 Initial B 3.1-42 0 Initial B 3.1-43 0 Initial B 3.1-44 0 Initial B 3.1-45 0 Initial B 3.1-46 0 Initial B 3.1-47 0 Initial B 3.1-48 0 Initial B 3.1-49 0 Initial B 3.1-50 0 Initial B 3.1-51 0 Initial B 3.1-52 0 Initial B 3.1-53 0 Initial B 3.1-54 0 Initial B 3.1-55 0 Initial I B 3.1-56 B 3.1-57 B 3.1-58 40 40 0

09-28-00 09-28-00 Initial B 3.1-59 0 Initial B 3.1-60 0 Initial B 3.1-61 40 09-28-00 B 3.1-62 40 09-28-00 B 3.1-63 40 09-28-00 B 3.1-64 39 03-17-00 B 3.1-65 0 Initial B 3.1-66 39 03-17-00 I B 3.1-67 40 09-28-00 B 3.2-1 0 Initial B 3.2-2 39 03-17-00 B 3.2-3 0 Initial B 3.2-4 39 03-17-00 B 3.2-5 0 Initial B 3.2-6 0 Initial B 3.2-7 0 Initial Watts Bar-Unit 1 X Revision 40

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.2-8 38 09-17-00 B 3.2-9 18 09-09-98 B 3.2-10 0 Initial B 3.2-11 0 Initial B 3.2-12 0 Initial B 3.2-13 39 03-17-00 B 3.2-14 39 03-17-00 B 3.2-15 0 Initial B 3.2-16 0 Initial B 3.2-17 0 Initial B 3.2-18 0 Initial B 3.2-19 0 Initial B 3.2-20 0 Initial B 3.2-21 0 Initial B 3.2-22 0 Initial B 3.2-23 0 Initial B 3.2-24 0 Initial B 3.2-25 0 Initial B 3.2-26 0 Initial B 3.2-27 0 Initial B 3.2-28 0 Initial B 3.2-29 0 Initial B 3.2-30 0 Initial B 3.3-1 0 Initial B 3.3-2 0 Initial B 3.3-3 0 Initial B 3.3-4 0 Initial B 3.3-5 0 Initial B 3.3-6 0 Initial B 3.3-7 0 Initial B 3.3-8 0 Initial B 3.3-9 0 Initial B 3.3-10 0 Initial B 3.3-11 0 Initial B 3.3-12 27 01/15/99 B 3.3-13 27 01/15/99 B 3.3-14 0 Initial B 3.3-15 0 Initial B 3.3-16 17 07-31-98 B 3.3-17 13 09-11-97 B 3.3-18 13 09-11-97 B 3.3-19 13 09-11-97 B 3.3-20 0 Initial B 3:3-21 0 Initial B 3.3-22 0 Initial Watts Bar-Unit 1 xi Revision 39

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.3-23 0 Initial B 3.3-24 13 09-11-97 B 3.3-25 13 09-11-97 B 3.3-26 0 Initial B 3.3-27 0 Initial B 3.3-28 13 09-11-97 B 3.3-29 13 09-11-97 B 3.3-30 13 09-11-97 B 3.3-31 13 09-11-97 B 3.3-32 13 09-11-97 B 3.3-33 13 09-11-97 B 3.3-34 13 09-11-97 B 3.3-35 13 09-11-97 B 3.3-36 0 Initial B 3.3-37 0 Initial B 3.3-38 0 Initial B 3.3-39 0 Initial B 3.3-40 0 Initial B 3.3-41 0 Initial B 3.3-42 27 01/15/99 B 3.3-43 0 Initial B 3.3-44 0 Initial B 3.3-45 0 Initial B 3.3-46 0 Initial B 3.3-47 0 Initial B 3.3-48 0 Initial B 3.3-49 0 Initial B 3.3-50 0 Initial B 3.3-51 0 Initial B 3.3-52 0 Initial B 3.3-53 0 Initial B 3.3-54 0 Initial B 3.3-55 0 Initial B 3.3-56 0 Initial B 3.3-57 0 Initial B 3.3-58 0 Initial B 3.3-59 0 Initial B 3.3-60 0 Initial B 3.3-61 0 Initial B 3.3-62 34 07-07-00 B 3.3-62a 34 07-07-00 B 3.3-63 34 07-07-00 B 3.3-64 0 Initial B 3.3-65 0 Initial B 3.3-66 0 Initial B 3.3-67 0 Initial Watts Bar-Unit 1 xii Revision 34

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.3-68 0 Initial B 3.3-69 0 Initial B 3.3-70 0-1 Initial B 3.3-71 0 Initial B 3.3-72 0 Initial B 3.3-73 0 Initial B 3.3-74 0 Initial B 3.3-75 0 Initial B 3.3-76 0 Initial B 3.3-77 0 Initial B 3.3-78 0 Initial B 3.3-79 9 04-29-97 B 3.3-80 9 04-29-97 B 3.3-81 0 Initial B 3.3-82 0 Initial B 3.3-83 0 Initial B 3.3-84 0 Initial B 3.3-85 0 Initial B 3.3-86 0 Initial B 3.3-87 0 Initial B 3.3-88 0 Initial B 3.3-89 0 Initial B 3.3-90 0 Initial B 3.3-91 0 Initial B 3.3-92 13 09-11-97 I B 3.3-93 2 02-28-96 B 3.3-94 2 02-28-96 B 3.3-95 0 Initial B 3.3-96 0 Initial B 3.3-97 0 Initial B 3.3-98 0 Initial B 3.3-99 0 Initial B 3.3-100 0 Initial B 3.3-101 0 Initial B 3.3-102 0 Initial B 3.3-103 0 Initial B 3.3-104 0 Initial B 3.3-105 0 Initial B 3.3-106 0 Initial B 3.3-107 0 Initial B 3.3-108 0 Initial B 3.3-109 0 Initial B 3.3-110 0 Initial B 3.3-111 0 Initial B 3:3-112 0 Initial Watts Bar-Unit 1 xiii Revision 13

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PAGE REVISION DATE B 3.3-113 0 Initial B 3.3-114 0 Initial B 3.3-115 0 Initial B 3.3-116 26 12-30-98 B 3.3-117 1 02-07-96 B 3.3-118 34 07-07-00 B 3.3-118a 34 07-07-00 B 3.3-119 34 07-07-00 B 3.3-120 34 07-07-00 B 3.3-121 0 Initial B 3.3-122 0 Initial B 3.3-123 0 Initial B 3.3-124 0 Initial B 3.3-125 0 Initial B 3.3-126 0 Initial B 3.3-127 0 Initial B 3.3-128 0 Initial B 3.3-129 0 Initial B 3.3-130 0 Initial B 3.3-131 28 04-02-99 B 3.3-132 0 Initial B 3.3-133 0 Initial B 3.3-134 0 Initial

-4 B 3.3-135 0 Initial B 3.3-136 0 Initial B 3.3-137 49 03-08-02 B 3.3-138 0 Initial B 3.3-139 0 Initial B 3.3-140 0 Initial B 3.3-141 0 Initial B 3.3-142 0 Initial B 3.3-143 0 Initial B 3.3-144 0 Initial B 3.3-145 0 Initial B 3.3-146 0 Initial B 3.3-147 48 03-06-02 B 3.3-148 0 Initial B 3.3-149 0 Initial B 3.3-150 0 Initial B 3.3-151 0 Initial B 3.3-152 0 Initial B 3.3-153 0 Initial B 3.3-154 43 05-29-01 B 3.3-155 9 04-29-97 B 3.3-156 45 02-12-02 B 3.3-157 0 Initial Watts Bar-Unit 1 xiv Revision 49

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES N)

PAGE REVISION DATE B 3.3-158 -0 Initial B 3.3-159 45 02-12-02 B 3.3-160 0 Initial B 3.3-161 0 Initial B 3.3-162 26 12-30-98 B 3.3-163 0 Initial B 3.3-164 45 02-12-02 B 3.3-165 0 Initial I I B 3.3-166 0 Initial B 3.3-167 45 02-12-02 B 3.3-168 I 0 Initial B 3.3-169 0 Initial B 3.3-170 0 Initial B 3.3-171 0 Initial B 3.3-172 0 Initial B 3.3-173 0 Initial B 3.3-174 0 Initial B 3.3-175 0 Initial B 3.3-176 0 Initial B 3.3-177 0 Initial B 3.4-1 0 Initial B 3.4-2 13 09-11-97 B 3.4-3 0 Initial B 3.4-4 29 03-13-00 B 3.4-5 29 03-13-00 B 3.4-6 0 Initial B 3.4-7 0 Initial B 3.4-8 29 03-13-00 B 3.4-9 0 Initial B 3.4-10 0 Initial B 3.4-11 0 Initial B 3.4-12 0 Initial B 3.4-13 0 Initial B 3.4-14 0 Initial B 3.4-15 0 Initial B 3.4-16 0 Initial B 3.4-17 0 Initial B 3.4-'18 0 Initial B 3.4-19 0 Initial B 3.4-20 0 Initial B 3.4-21 0 Initial B 3.4-22 0 Initial B 3.4-23 0 Initial B 3.4-24 0 Initial B 3.4-25 29 03-13-00 Watts Bar-Unit 1 XV Revision 45

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.4-26 29 03-13-00 B 3.4-27 0 Initial B 3.4-28 0 Initial B 3.4-29 0 Initial B 3.4-30 0 Initial B 3.4-31 0 Initial B 3.4-32 29 03-13-00 B 3.4-33 0 Initial B 3.4-34 0 Initial B 3.4-35 0 Initial B 3.4-36 29 03-13-00 B 3.4-37 29 03-13-00 B 3.4-38 0 Initial B 3.4-39 0 Initial B 3.4-40 0 Initial B 3.4-41 0 Initial B 3.4-42 0 Initial B 3.4-43 0 Initial B 3.4-44 29 03-13-00 B 3.4-45 29 03-13-00 B 3.4-46 0 Initial B 3.4-47 0 Initial B 3.4-48 0 Initial B 3.4-49 0 Initial B 3.4-50 0 Initial B 3.4-51 0 Initial B 3.4-52 42 03-07-01 B 3.4-53 42 03-07-01 B 3.4-54 42 03-07-01 B 3.4-55 42 03-07-01 B 3.4-56 42 03-07-01 B 3.4-57 42 03-07-01 B 3.4-58 0 Initial B 3.4-59 0 Initial B 3.4-60 0 Initial B 3.4-61 0 Initial B 3.4-62 0 Initial B 3.4-63 0 Initial B 3.4-64 0 Initial B 3.4-65 0 Initial B 3.4-66 0 Initial B 3.4-67 22 11-10-98 B 3.4-68 0 Initial B 3.4-69 0 Initial B 3.4-70 0 Initial Watts Bar-Unit 1 xvi Revision 42

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.4-71 7 09/28/96 B 3.4-72 7 09/28/96 B 3.4-73 0 Initial B 3.4-74 0 Initial B 3.4-74a 47 03/01/02 b 3.4-74b 47 03/01/02 B 3.4-75 0 Initial B 3.4-76 47 03/01/02 B 3.4-77 47 03/01/02 B 3.4-78 0 Initial B 3.4-79 0 Initial B 3.4-80 0 Initial B 3.4-81 0 Initial B 3.4-82 0 Initial B 3.4-83 0 Initial B 3.4-84 0 Initial B 3.4-85 0 Initial B 3.4-86 0 Initial B 3.4-87 12 09-10-97 B 3.4-88 12 09-10-97 B 3.4-89 12 09-10-97 B 3.4-90 12 09-10-97 B 3.4-91 12 09-10-97 B 3.4-92 12 09-10-97 B 3.4-93 0 Initial B 3.4-94 0 Initial B 3.4-95 0 Initial B 3.4-96 0 Initial B 3.4-97 0 Initial B 3.4-98 0 Initial B 3.5-1 0 Initial B 3.5-2 39 03-17-00 B 3.5-3 39 03-17-00 B 3.5-4 39 03-17-00 B 3.5-5 0 Initial B 3.5-6 0 Initial B 3.5-7 29 03-13-00 B 3.5-8 0 Initial B 3.5-9 29 03-13-00 B 3.5-10 14 10-10-97 B 3.5-11 0 Initial B 3.5-12 39 03-17-00 B 3.5-13 39 03-17-00 B 3.5-14 0 Initial B 3.5-15 0 Initial B 3.5-16 0 Initial B 3.5-17 0 Initial Watts Bar-Unit 1 xvii Revision 47

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.5-18 0 Initial B 3.5-19 0 Initial B 3.5-20 0 Initial B 3.5-21 0 Initial B 3.5-22 0 Initial B 3.5-23 0 Initial B 3.5-24 0 Initial B 3.5-25 0 Initial B 3.5-26 13 09-11-97 B 3.5-27 0 Initial B 3.5-28 0 Initial B 3.5-29 29 03-13-00 B 3.5-30 29 03-13-00 B 3.5-31 0 Initial B 3.5-32 0 Initial B 3.5-33 0 Initial B 3.5-34 29 03-13-00 B 3.6-1 10 05-27-97 B 3.6-2 10 05-27-97 B 3.6-3 10 05-27-97 B 3.6-4 10 05-27-97 B 3.6-5 10 05-27-97 B 3.6-6 5 07-03-96 B 3.6-7 10 05-27-97 B 3.6-8 0 Initial B 3.6-9 0 Initial B 3.6-10 0 Initial B 3.6-11 0 Initial B 3.6-12 10 05-27-97 B 3.6-13 10 05-27-97 B 3.6-14 0 Initial B 3.6-15 0 Initial B 3.6-16 0 Initial B 3.6-17 8 11-21-96 B 3.6-18 8 11-21-96 B 3.6-19 0 Initial B 3.6-20 0 Initial B 3.6-21 0 Initial B 3.6-22 0 Initial B 3.6-23 0 Initial B 3.6-24 0 Initial B 3.6-25 10 05-27-97 B 3.6-26 10 05-27-97 B 3.6-27 10 05-27-97 B 3.6-28 44 01-31-02 Watts Bar-Unit 1 XVIll Revision 44

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.6-29 0 Initial B 3.6-30 29 03-13700 B 3.'6-31 0 Initial B 3.6-32 0 Initial B 3.6-33 29 03-13-00 B 3.6-34 29 03-13-00 B 3.6-35 0 Initial B 3;6-36 0 Initial B 3.6-37 44 01-31-02 I B 3.6-38 0 Initial B 3.6-39 0 Initial B 3.6-40 0 Initial B 3.6-41 0 Initial B 3.6-42 0 Initial B 3.6-43 0 Initial B 3.6-44 0 Initial B 3.6-45 0 Initial B 3.6-46 0 Initial B 3.6-47 0 Initial B 3.6-48 0 Initial B 3.6-49 0 Initial B 3.6-50 0 Initial B 3.6-51 0 Initial B 3.6-52 0 Initial B 3.6-53 0 Initial B 3.6-54 16 06-09-98 B 3.6-55 0 Initial B 3.6-56 0 Initial B 3.6-57 0 Initial B 3.6-58 29 03-13-00 B 3.6-59 29 03-13-00 B 3.6-60 0 Initial B 3.6-61 0 Initial B 3.6-62 0 Initial B 3.6-63 0 Initial B 3.6-64 0 Initial B 3.6-65 44 01-31-02 I B 3.6-66 0 Initial B 3.6-67 0 Initial B 3.6-68 0 Initial B 3.-6-69 29 03-13-00 B 3.6-70 44 01-31-02 I B 3.6-71 36 08-23-00 B 3.6-72 36 08-23-00 B 3.6-72a 36 08-23-00 Watts Bar-Unit 1 xix Revision 44

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.6-73 36 08-23-00 B 3.6-74 0 Initial B 3.6-75 0 Initial B 3.6-76 0 Initial B 3.6-77 0 Initial B 3.6-78 36 08-23-00 B 3.6-79 0 Initial B 3.6-80 6 09-09-96 B 3.6-81 6 09-09-96 B 3.6-82 21 11-30-98 B 3.6-83 6 09-09-96 B 3.6-84 0 Initial B 3.6-85 0 Initial B 3.6-86 0 Initial B 3.6-87 0 Initial B 3.6-88 0 Initial B 3.6-89 0 Initial B 3.6-90 0 Initial B 3.6-91 0 Initial B 3.6-92 0 Initial B 3.6-93 0 Initial B 3.6-94 0 I Initial B 3.6-95 0 Initial B 3.6-96 0 Initial B 3.6-97 29 03-13-00 B 3.6-98 29 03-13-00 B 3.7-1 31 04-06-00 B 3.7-2 31 04-06-00 I B 3.7-3 41 01-22-01 B 3.7-4 31 04-06-00 B 3.7-5 31 04-06-00 B 3.7-6 31 04-06-00 B 3.7-7 0 Initial B 3.7-8 0 Initial B 3.7-9 0 Initial B 3.7-10 0 Initial B 3.7-11 0 Initial B 3.7-12 0 Initial B 3.7-13 0 Initial B 3.7-14 0 Initial B 3.7-15 0 Initial B 3.7-16 0 Initial B 3.7-17 0 Initial B 3.7-18 0 Initial B 3.7-19 0 Initial Watts Bar-Unit 1 Revision 41

STECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.7-20 0 Initial B 3.7-21 0 Initial B 3.7-22 24 12-17-98 B 3.7-23 24 12-17-98 B 3.7-24 0 Initial B 3.7-25 0 Initial B_ 3.7-26 0 "Initial B 3.7-27 0 Initial B 3.7-28 0 Initial B 3.7-29 0 Initial B 3.7-30 0 Initial B 3.7-31 20 10-26-98 B 3.7-32 20 10-26-98 B 3.7-33 0 Initial B 3.7-34 0 Initial B 3.7-35 41 01-22-01 B 3.7-36 0 Initial B 3.7-37 29 03-13-00 B 3.7-38 0 Initial B 3.7-39 0 Initial B 3.7-40 0 Initial B 3.7-41 0 Initial B 3.7-42 0 Initial B 3.7-43 0 Initial B 3.7-44 0 Initial B 3.7-45 0 Initial B 3.7-46 0 Initial B 3.7-47 0 Initial B 3.7-48 0 Initial B 3.7-49 0 Initial B 3.7-50 29 03-13-00 B 3.7-51 0 Initial B 3.7-52 0 Initial B 3.7-53 45 02-12-02 B 3.7-54 45 02-12-02 B 3.7-55 45 02-12-02 B 3.7-56 0 Initial B 3.7-57 0 Initial B 3.7-58 0 Initial B 3.7-59 0 Initial B 3.7-60 45 02-12-02 B 3.7-61 0 Initial B 3.7-62 0 Initial B 3.7-63 0 Initial B 3.7-64 0 Initial Watts Bar-Unit 1 xxi Revision 45

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B 3.7-65 0 Initial B 3.7-66 35 08-14-00 B 3.7-67 29 03-13-00 B 3.7-68 0 Initial B 3.7-69 0 Initial B 3.7-70 0 Initial B 3.7-71 47 03-01-02 B 3.7-72 0 Initial B 3.7-73 0 Initial B 3.7-74 0 Initial B 3.7-75 11 07-28-97 B 3.7-76 11 07-28-97 B 3.7-77 11 07-28-97 B 3.8-1 0 Initial B 3.8-2 0 Initial B 3.8-3 0 Initial B 3.8-4 0 Initial B 3.8-5 0 Initial B 3.8-6 0 Initial B 3.8-7 0 Initial B 3.8-8 50 08-30-02 B 3.8-9 50 08-30-02 B 3.8-10 50 08-30-02 B 3.8-11 50 08-30-02 B 3.8-11a 50 08-30-02 _2 B 3.8-12 50 08-30-02 B 3.8-13 50 08-30-02 B 3.8-14 50 08-30-02 B 3.8-15 50 08-30-02 B 3.8-16 0 Initial B 3.8-17 0 Initial B 3.8-18 29 03-13-00 B 3.8-19 0 Initial B 3.8-20 0 Initial B 3.8-21 0 Initial B 3.8-22 0 Initial B 3.8-23 0 Initial B 3.8-24 0 Initial B 3.8-25 0 Initial B 3.8-26 0 Initial B 3.8-27 0 Initial B 3.8-28 19 10-19-98 B 3.8-29 50 08-30-02 B 3.8-29a 19 10-19-98 B 3.8-30 0 Initial B 3.8-31 0 Initial Watts Bar-Unit 1 xxil Revision 50

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.8-32 0 Initial B 3.8-33 0 Initial B 3.8-34 0 Initial B 3.8-35 0 Initial B 3.8-36 B 3.8-36a B 3.8-37 50 50 0

08-30-02 08-30-02 Initial I

B 3.8-38 0 Initial B 3.8-39 0 Initial, B 3.8-40 0 Initial B 3.8-41 0 Initial B 3.8-42 0 Initial B 3.8-43 0 Initial B 3.8744 0 Initial B 3.8-45 0 Initial B-3.8-46 0 Initial B 3.8-47 0 Initial B 3.8-48 29 03-13-00 B 3.8-49 0 Initial B 3.8-50 0 Initial B 3.8-51 29 03-13-00 B 3.8-52 0 Initial B 3.8-53 29 03-13-00 B 3.8-54 0 Initial B 3.8-55 0 Initial B 3.8-56 0 Initial B 3.8-57 0 Initial B 3.8-58 0 Initial B 3.8-59 0 Initial B 3.8-60 0 Initial B 3.8-61 0 Initial B 3.8-62 0 Initial B 3.8-63 0 Initial B 3.8-64 19 10-19-98 B 3.8-65 19 10-19-98 B 3.8-66 19 10-19-98 B 3.8-67 19 10-19-98 B 3.8-68 0 Initial B 3. 8-69 0 Initial B 3.8-70 0 Initial B 3.8-71 0 Initial B 3.8-72 0 Initial B 3.8-73 0 Initial B 3.8-74 0 Initial B 3.8-75 0 Initial B 3.8-76 0 Initial Watts Bar-Unit 1 xxiii Revision 50

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.8-77 0 Initial B 3.8-78 0 Initial B 3.8-79 0 Initial B 3.8-80 0 Initial B 3.8-81 0 Initial B 3.8-82 0 Initial B 3.8-83 0 Initial B 3.8-84 0 Initial B 3.8-85 0 Initial B 3.8-86 0 Initial B 3.8-87 0 Initial B 3.8-88 0 Initial B 3.8-89 0 Initial B 3.8-90 0 Initial B 3.8-91 0 Initial B 3.8-92 0 Initial B 3.8-93 0 Initial B 3.8-94 0 Initial B 3.8-95 0 Initial B 3.8-96 0 Initial B 3.8-97 0 Initial B 3.8-98 33 05-02-00 B 3.8-99 0 Initial B 3.8-100 0 Initial B 3.8-101 0 Initial B 3.8-102 0 Initial B 3.9-1 0 Initial B 3.9-2 0 Initial B 3.9-3 0 Initial B 3.9-4 0 Initial B 3.9-5 0 Initial B 3.9-6 0 Initial B 3.9-7 0 Initial B 3.9-8 0 Initial B 3.9-9 0 Initial B 3.9-10 0 Initial B 3.9-11 0 Initial B 3.9-12 45 02-12-02 B 3.9-13 46 02-25-02 B 3.9-14 45 02-12-02 B 3.9-15 45 02-12-02 B 3.9-16 37 09-08-00 B 3.9-17 0 Initial B 3.9-18 23 01-05-99 B 3.9-19 0 Initial Watts Bar-Unit 1 xxiv Revision 46

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.9-20 0 -- Initial B 3.9-21 0 Initial B 3.9-22 23 01-05-99 B 3.9-23 0 Initial B 3.9-24 0 Initial B 3.9-25 45 02-12-02 B 3.9-26 45 02-12-02 B 3.9-27 6 Initial B 3.9-28 45 02-12-02 B 3.9-29 0 Initial B 3.9-30 0 Initial B 3.9-31 45 02-12-02 B 3.9-32 0 Initial B 3.9-33 11 07-28-97 B 3.9-34 0 Initial Watts Bar-Unit 1 XXV Revision 45

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES REVISION LISTING REVISIONS ISSUED SUBJECT NPF-20 11-09-95 Low Power Operating License Revision 1 12-08-95 Slave Relay Testing NPF-90 02-07-96 Full Power Operating License Revision 2 (Amendment 1) 12-08-95 Turbine Driven AFW Pump Suction Requirement Revision 3 03-27-96 Remove Cold Leg Accumulator Alarm Setpoints Revision 4 (Amendment 2) 06-13-96 Ice Bed Surveillance Frequency And Weight Revision 5 07-03-96 Containment Airlock Door Indication Revision 6 (Amendment 3) 09-09-96 Ice Condenser Lower Inlet Door Surveillance Revision 7 09-28-96 Clarification of COT Frequency for COMS Revision 8 11-21-96 Admin Control of Containment Isol. Valves Revision 9 04-29-97 Switch Controls For Manual CI Phase A Revision 10 (Amendment 5) 05-27-97 Appendix-J, Option B Revision 11 (Amendment 6) 07-28-97 Spent Fuel Pool Rerack Revision 12 09-10-97 Heat Trace for Radiation Monitors Revision 13 (Amendment 7) 09-11-97 Cycle 2 Core Reload Revision 14 10-10-97 Hot Leg Recirculation Timeframe Revision 15 02-12-98 EGTS Logic Testing Hydrogen Mitigation System I Revision 16 (Amendment 10) 06-09-98 Temporary Specification Watts Bar-Unit 1 xxvi Revision 16

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES PEVISION LISTING REVISIONS ISSUED SUBJECT Revision 17 07-31-98 -SR Detectors (Visual/audible indication)

Revision 18 (Amendment 11) 09-09-98 Relocation of F(Q) Penalty to COLR Revision 19 (Amendment 12) 10-19-98 Online Testing of the Diesel Batteries and Performance of the 24 Hour Diesel Endurance Run Revision 20 (Amendment 13) 10-26-98 Clarification of Surveillance Testing Requirements for TDAFW Pump Revision 21 11-30-98 Clarification to Ice Condenser Door ACTIONS and door lift tests, and Ice Bed sampling and flow blockage SRs Revision 22 (Amendment 14) 11-10-98 COMS - Four Hour Allowance to Make RHR Suction Relief Valve Operable Revision 23 01-05-99 RHR Pump Alignment for Refueling Operations Revision 24 (Amendment 16) 12-17-98 New action for Steam Generator ADVs due to Inoperable ACAS.

Revision 25 02-08-99 Delete Reference to PORV Testing Not Performed in Lower Modes Revision 26 (Amendment 17) 12-30-98 Slave Relay Surveillance Frequency Extension to 18 Months Revision 27 (Amendment 18) 01-15-99 Deletion of Power Range Neutron Flux High.Negative Rate Reactor Trip Function Watts Bar-Unit 1 XXVIl Revision 27

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES REVISION LISTING REVISIONS ISSUED SUBJECT Revision 28 04-02-99 P2500 replacement with Integrated Computer System (ICS). Delete Reference to ERFDS as a redundant input signal.

Revision 29 03-13-00 Added notes to address instrument error in various parameters shown in the Bases.

Also corrected the applicable modes for TS 3.6.5 from 3 and 4 to 2, 3 and 4.

Revision 30 (Amendment 23) 03-22-00 For SR 3.3.2.10, Table 3.3.2-1, one time relief from turbine trip response time testing.

Also added Reference 14 to the Bases for LCO 3.3.2.

Revision 31 (Amendment 19) 03-07-00 Reset Power Range High Flux Reactor Trip Setpoints for Multiple Inoperable MSSVs.

Revision 32 04-13-00 Clarification to Reflect Core Reactivity and MTC Behavior.

Revision 33 05-02-00 Clarification identifying four distribution boards primarily used for operational convenience.

Revision 34 (Amendment 24) 07-07-00 Elimination of Response Time Testing Revision 35 08-14-00 Clarification of ABGTS Surveillance Testing Revision 36 (Amendments 22 08-23-00 Revision of Ice Condenser and 25) sampling and flow channel surveillance requirements Revision 37 (Amendment 26) 09-08-00 Administrative Controls for Open Penetrations During Refueling Operations Watts Bar-Unit 1 XXVilll Revision 37

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES Th REVISION LISTING REVISIONS ISSUED ,SUBJECT Revision 38 09-17-00 SR 3.-2.1.2 was revised to reflect the area of the core that will be flux mapped.

Revision 39 (Amendments 21 09-13-00 Amendment 21 - Implementation and 28) of Best Estimate LOCA analysis.

Amendment 28 - Revision of LCO 3.1.10, "Physics Tests Exceptions - Mode 2."

Revision 40 09-28-00 Clarifies WBN's compliance with ANSI/ANS-19.6.1 and deletes the detailed descriptions of Physics Tests.

Revision 41 (Amendment 31) 01-22-01 Power Uprate from 3411 MWt to 3459 MWt Using Leading Edge Flow Meter (LEFM)

Revision 42 03-07-01 Clarify Operability Requirements for Pressurizer PORVs Revision 43 05-29-01 Change CVI Response Time from 5 to 6 Seconds Revision 44 (Amendment 33) 01-31-02 Ice weight reduction from 1236 to 1110 lbs per basket and peak containment pressure revision from 11.21 to 10.46 psig.

Revision 45 (Amendment 35) 02-12-02 Relaxation of CORE ALTERATIONS Restrictions Revision 46 02-25-02 Clarify Equivalent Isolation Requirements in LCO 3.9.4 Revision 47 (Amendment 38) 03-01-02 RCS operational LEAKAGE and SG Alternate Repair Criteria for Axial Outside Diameter Stress Corrosion Cracking (ODSCC)

Revision 48 (Amendment 36) 03-06-02 Increase Degraded Voltage Time Delay from 6 to 10 seconds.

Watts Bar-Unit 1 xxix .Revision 48

TECHNICAL SPECIFICATIONS BASES LIST OF EFFECTIVE PAGES REVISION LISTING REVISIONS ISSUED SUBJECT Revision 49 (Amendment 34) 03-08-02 Deletion of the Post-Accident Sampling System (PASS) requirements from Section 5.7.2.6 of the Technical Specifications.

Revision 50 (Amendment 39) 08-30-02 Extension of the allowed outage time (AOT) for a single diesel generator from 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to 14 days.

Watts Bar-Unit 1 xxx Revision 50

Containment Vent Isolation Instrumentation B 3.3.6 B 3.3 INSTRUMENTATION B 3.3.6 Containment Vent Isolation Instrumentaticn -Th BASES BACKGROUND Containment Vent Isolation Instrumentation containment isolation valves in closes the the Containment Purge System. This action isolates the containment from the environment to minimize atmosphere releases of radioactivity in the event of an accident. The Reactor Building Purge System may be in use during reactor operation and with the reactor shutdown.

Containment vent isolation is initiated injection (SI) signal or by manual by a safety actuation. The Bases for LCO 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," discuss initiation of SI signals.

Redundant and independent gaseous radioactivity monitors measure the radioactivity lev'els of exhaust, each of which will initiate the containment purge its associated train of automatic Containment Vent Isolation upon detection of high gaseous radioactivity.

The Reactor Building Purge System has inner and outer containment isolation valves in its supply and exhaust J ducts. This system is described in the Bases for LCO 3.6.3, "Containment Isolation Valves."

APPLICABLE The containment isolation valves for SAFETY ANALYSES Purge System close within six seconds the Reactor Building following the DBA.

The containment vent isolation radiation backup to the SI signal to ensure monitors act as system supply and exhaust valves. closing of the purge air They are also the primary means for automatically isolating containment in the event of a fuel handling accident during shutdown. Containment isolation in turn ensures meeting the containment leakage rate assumptions of the safety analyses, the calculated accidental offsite and ensures that radiological doses are below 10 CFR 100 (Ref. 1) limits.

The Containment Vent Isolation instrumentation satisfies Criterion 3 of the NRC Policy Statement.

(continued)

Watts Bar-Unit 1 B 3.3-154 Revision 43

Containment Penetrations B 3.9.4 BAS ES BACKGROUND The Reactor Building Purge Ventilation System operates to (continued) supply outside air into the containment for ventilation cooling or heating, to equalize internal and external and pressures, and to reduce the concentration of noble gases within containment prior to and during personnel access. The supply and exhaust lines each contain two isolation valves.

Because of their large size, the 24-inch containment lower compartment purge valves are physically restricted to : 50 degrees open.

The Reactor Building Purge and Ventilation System valves opened in MODES 5 and 6, but are closed automatically can be by the Engineered Safety Features Actuation System (ESFAS).

In MODE 6, large air exchanges are necessary to conduct refueling operations. The normal 24-inch purge system is used for this purpose. The ventilation system must be either isolated or capable of being automatically isolated upon detection of high radiation levels within containment.

The other containment penetrations that provide direct from containment atmosphere to outside atmosphere must access isolated on at least one side. be Isolation may be achieved by an OPERABLE automatic isolation valve, or by a manual isolation valve, blind flange, or equivalent. Equivalent isolation methods must be approved and may include use of a material can provide a temporary, atmospheric pressure, ventilation that barrier for the other containment penetrations during movements (Ref. 1). fuel Closure by other valves or blind flanges may be used if they are similar in capability to those for containment isolation. provided These may be constructed of standard materials and may be justified on the basis of either analysis methods or reasonable engineering judgment normal (Ref. 4).

APPLICABLE During CORE ALTERATIONS or movement of irradiated fuel SAFETY ANALYSES assemblies within containment, the most severe radiological consequences result from a fuel handling accident.

The fuel handling accident is a postulated event that involves irradiated fuel (Ref. 2). damage to Fuel handling accidents, analyzed in Reference 3, include dropping a single irradiated fuel and handling tool or a heavy object onto other irradiated assembly assemblies. fuel The requirements of LCO 3.9.7, "Refueling Cavity Water Level," in conjunction with a minimum decay time of 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to irradiated fuel movement with containment closure capability ensures that the release of fission radioactivity, subsequent to a fuel handling accident, product in doses that are well within the guideline values specifiedresults 10 CFR 100. in Standard Review Plan, Section 15.7.4, Rev. 1 (Ref. 3), defines "well within" 10 CFR 100 to be 25%

the 10 CFR 100 values. or less of The acceptance limits for offsite radiation exposure will be 25% of 10 CFR 100 values or the NRC staff approved licensing basis (e.g., a specified fraction of 10 CFR 100 limits).

Containment penetrations satisfy Criterion 3 of the NRC Policy Statement.

(continued)

Watts Bar-Unit 1 B 3.9-13 Revision 37, 45, 46 Amendment 26, 35

ENCLOSURE 3 TABLE OF CONTENTS, LIST OF EFFECTIVE PAGES, AND CHANGED PAGES WBN TECHNICAL REQUIREMENTS MANUAL

TABLE OF CONTENTS TECHNICAL REQUIREMENTS TABLE OF CONTENTS .................................................

LIST OF TABLES .......................................................... v LIST OF FIGURES .......................................... ............ vi LIST OF ACRONYMS ........................................................ vii LIST OF EFFECTIVE PAGES ................................................. viii 1.0 USE AND APPLICATION ................................... i..1-1 1.1 Definitions .......................................... 1.1-1 1.2 Logical Connectors ................................ 1.2-1 1.3 Completion Times .................................. 1.3-1 1.4 - Frequency ......................................... 1.4-1 TR 3.0 APPLICABILITY ................................................. 3.0-1 TR 3.1 REACTIVITY CONTROL SYSTEMS ............................ 3.1-1 TR 3.1.1 Boration Systems Flow Paths, Shutdown ............. 3.1-1 TR 3.1.2 Boration Systems Flow Paths,.Operating.1 ........... 3.1-3 TR 3.1.3 Charging Pump, Shutdown .............. *............3.1-5 TR 3.1.4 Charging Pumps, Operating... ;..................... 3.1-6 TR 3.1.5 Borated Water Sources, Shutdown ................... . 3.1-8 TR 3.1.6 Borated Water Sources, Operating .................. 3.1-10 TR 3.1.7 Position Indication System, Shutdown .............. 3.1-13 TR 3.3 INSTRUMENTATION................. *............. 3.3-1 TR 3.3.1 Reactor Trip System (RTS) Instrumentation ......... 3.3-1 TR 3.3.2 Engineered Safety Features Actuation System (ESFAS) Instrumentation ........ 3.3-5 TR 3;3.3 Movable Incore Detectors .......................... 3.3-12 TR 3.3.4 Seismic Instrumentation ........................... 3.3-14 TR 3.3.5 Turbine Overspeed Protection ...................... 3.3-18 TR 3.3.6 Loose-Part Detection System ...................... 3.3-20 TR 3.3.7 Plant Calorimetric Measurement .................... 3.3-22 TR 3.4 REACTOR COOLANT SYSTEM (RCS) ............................ 3.4-1 TR 3.4.1 Safety Valves, Shutdown ........................... 3.4-1 TR 3.4.2 Pressurizer Temperature Limits .................... 3.4-3 TR 3.4.3 RCS Vents ............................................ 3.4-5 TR 3.4.4 Chemistry ............................................ 3.4-7 TR 3.4.5 Piping System Structural Integrity ................ 3.4-10 TR 3.6 CONTAINMENT SYSTEMS ..................................... 3.6-1 TR 3.6.1 Ice Bed Temperature Monitoring System ............. 3.6-1 TR 3.6.2 Inlet Door Position Monitoring System ............. 3.6-4 TR 3.6.3 Lower Compartment Cooling (LCC) System ............ 3.6-6 (continued)

Watts Bar-Unit 1 i 01/22/01 Teýhnical Requirements Revision 23

TABLE OF CONTENTS (continued)

TR 3.7 PLANT SYSTEMS ........................................ 3.7-1 TR 3.7.1 Steam Generator Pressure/

Temperature Limitations ........................... 3.7-1 TR 3.7.2 Flood Protection Plan ............................. 3.7-3 TR 3.7.3 Snubbers .......................................... 3.7-10 TR 3.7.4 Sealed Source Contamination ....................... 3.7-22 TR 3.7.5 Area Temperature Monitoring ....................... 3.7-26 TR 3.8 ELECTRICAL POWER SYSTEMS ............................. 3.8-1 TR 3.8.1 Isolation Devices ................................. 3.8-1 TR 3.8.2 Containment Penetration Conductor Overcurrent Protection Devices .............................. 3.8-5 TR 3.8.3 Motor-Operated Valves Thermal Overload Bypass Devices .................................. 3.8-10 TR 3.8.4 Submerged Component Circuit Protection ............ 3.8-17 TR 3.9 REFUELING OPERATIONS ................................. 3.9-1 TR 3.9.1 Decay Time ........................................ 3.9-1 TR 3.9.2 Conmunications .................................... 3.9-2 TR 3.9.3 Refueling Machine ................................. 3.9-3 TR 3.9.4 Crane Travel - Spent Fuel Storage Pool Building... 3.9-5 5.0 ADMINISTRATIVE CONTROLS ............................... 5.0-1 5.1 Technical Requirements (TR) Control Program ....... 5.0-1 (continued)

Watts Bar-Unit 1 ii 09/30/95 Technical Requirements

I TABLE OF CONTENTS (continued)

BASES B 3.0 TECHNICAL REQUIREMENTS (TR) AND TECHNICAL SURVEILLANCE REQUIREMENTS (TSR)

APPLICABILITY ...................................... B 3.0-1 B 3.1 REACTIVITY CONTROL SYSTEMS ............................ B 3.1-1 B 3.1.1 Boration Systems Flow Paths, Shutdown.. ............ B 3.1-1 B 3.1.2 Boration Systems Flow Paths, Operating ............. B 3.1-5 B 3.1.3 Charging Pump, Shutdown ............................ B 3.1-9 B 3.1.4 Charging Pumps, Operating .......................... B 3.1-11 B 3.1.5 Borated Water Sources, Shutdown... ................ B 3.1-14 B'3.1.6 Borated Water Sources, Operating ................... B 3.1-18 B 3.1.7 Position Indication System, Shutdown ............... B 3.1-23 B 3.3 INSTRUMENTATION .......................................... B 3.3-1 B 3.3.1 Reactor Trip System (RTS) Instrumentation ......... B 3.3-1 B 3.3.2 Engineered Safety Features Actuation System (ESFAS) Instrumentation ........ B 3.3-4 B 3.3.3 Movable Incore Detectors .......................... B 3.3-7 B 3.3.4 Seismic Instrumentation ........................... B 3.3-10 B 3.3.5 Turbine Overspeed Protection ...................... B 3.3-14 B 3.3.6 Loose-Part Detection System ....................... B 3.3-18 B.3.3.7 Plant Calorimetric Measurement ..................... B 3.3-21 B 3.4 REACTOR COOLANT SYSTEM (RCS) ............................ B 3.4-1 B 3.4.1 Safety Valves, Shutdown ........................... B 3.4-1 B 3.4.2 Pressurizer Temperature Limits .................... B 3.4-4 B 3.4.3 RCS Vents ............................................ B 3.4-7 B 3.4.4 Chemistry ............................................ B 3.4-10 B 3.4.5 Piping System Structural Integrity ............... B 3.4-14 B 3.6 CONTAINMENT SYSTEMS .................................. B 3.6-1 B 3.6.1 Ice Bed Temperature Monitoring System ............. B 3.6-1 B 3.6.2 Inlet Door Position Monitoring System ............. B 3.6-6 B 3.6.3 Lower Compartment Cooling (LCC) System ............ B 3.6-10 B 3.7 PLANT SYSTEMS ............................................ B 3.7-1 B 3.7.1 Steam Generator Pressure/Temperature Limitations.. B 3.7-1 B 3.7.2 Flood Protection Plan ............................. B 3.7-4 B 3.7.3 Snubbers ............................................. B 3.7-12 B 3.7.4 Sealed Source Contamination ....................... B 3.7-18 B 3.7.5 Area Temperature Monitoring ....................... B 3.7-22 (continued)

Watts Bar-Unit 1 iii 01/22/01 Technical Requirements Revision 23

TABLE OF CONTENTS (continued) ")

B 3.8 ELECTRICAL POWER SYSTEMS .............................. B 3.8-1 B 3.8.1 Isolation Devices ................................. B 3.8-1 B 3.8.2 Containment Penetration Conductor Overcurrent Protection Devices .................. B 3.8-7 B 3.8.3 Motor-Operated Valves Thermal Overload Bypass Devices ......................... B 3.8-15 B 3.8.4 Submerged Component Circuit Protection ............ B 3.8-19 B 3.9 REFUELING OPERATIONS .................................. B 3.9-1 B 3.9.1 Decay Time ........................................ B 3.9-1 B 3.9.2 Communications .................................... B 3.9-3 B 3.9.3 Refueling Machine ................................. B 3.9-5 B 3.9.4 Crane Travel - Spent Fuel Storage Pool Building ................................... B 3.9-8 Watts Bar-Unit 1 iv 09/30/95 Technical Requirements

I LIST OF TABLES Table No. TITLE PAGE Page MODES.............................................. 1.1-6 3.3.1-1 Reactor Trip System Instrumentation Response Times .... 3.3-3 3.3.2-1 Engineered Safety Features Actuation System Response Times .................... 3.3-7 3.3.4-1 Seismic Monitoring Information ........................ 3.3-17 3.7.3-1 Snubber Visual Inspection Acceptance Criteria ......... 3.7-14 3.7.3-2 Snubber Visual Inspection Surveillance Frequency ...... 3.7-15 3.7.3-3 Snubber Transient Event Inspection ................... 3.7-17 3.7.3-4 Snubber Functional Testing Plan ....................... 3.7-18 3.7.3-5 Snubber Functional Testing Acceptance Criteria ........ 3.7-20 3.7.5-1 Area Temperature Monitoring ........................... 3.7-29 3.8.3-1 Motor-Operated Valves Thermal Overload Devices Which Are Bypassed Under Accident Conditions ............ 3.8-12 3.8.4-1 Submerged Components With Automatic De-energization Under Accident Conditions ......................... 3.8-19 Watts Bar-Unit 1 V 09/30/95 Technical Requirements

LIST OF FIGURES Fioure No. Title Page Page 3.1.6 Boron Acid Tank Concentration - ppm Boron .............

3.1-12a 3.7.3-1 Sample Plan B For Snubber Functional Test .............

3.7-21 LIST OF MISCELLANEOUS REPORTS AND PROGRAMS I Core Operating Limits Report j

Watts Bar-Unit l vi 04/13/00 Technical Requirements Revision 21

LIST OF ACRONYMS Acronym Title ABGTS Auxiliary Building Gas Treatment System ACRP Auxiliary Control Room Panel ASME American Society of Mechanical Engineers AFD Axial Flux Difference AFW Auxiliary Feedwater System ARO All-Rods Out ARFS 2 Air Return Fan System' ARV -Atmospheric Relief Valve BOC Beginning of Cycle CCS Component Cooling Water System CFR Code of Federal Regulations COLR Core Operating Limits Report CREVS Control Room Emergency Ventilation System CSS Containment Spray System CST Condensate Storage Tank DNB Departure from Nucleate Boiling ECCS Emergency Core Cooling System EFPD Effective Full-Power Days EGTS Emergency Gas Treatment System EOC End of Cycle ERCW Essential Raw Cooling Water ESF Engineered Safety Feature ESFAS Engineered Safety Features Actuation System HEPA -High Efficiency Particulate Air HVAC Heating, Ventilating, and Air-Conditioning LCC Lower Compartment Cooler LCO Limiting Condition For Operation MFIV Main Feedwater Isolation Valve MFRV Main Feedwater Regulation Valve MSIV Main Steam Line Isolation Valve MSSV Main Steam Safety Valve MTC Moderator Temperature Coefficient NMS Neutron Monitoring System ODCM 'Offsite Dose Calculation Manual PCP Process Control Program PIV Pressure Isolation Valve PORV -Power-Operated Relief Valve PTLR Pressure and Temperature Limits Report QPTR Quadrant Power Tilt Ratio RAOC Relaxed Axial Offset Control RCCA Rod Cluster Control Assembly RCP Reactor Coolant Pump RCS .,Reactor Coolant System RHR Residual Heat Removal.

RTP Rated Thermal Power RTS Reactor Trip System RWST -Refueling Water Storage Tank SG Steam Generator SI Safety Injection SL Safety Limit SR Surveillance Requirement UHS Ultimate Heat Sink Watts Bar-Unit 1 vii 09/30/95 Technical Requirements

TECHNICAL REQUIREMENTS LIST OF EFFECTIVE PAGES PAGE REVISION DATE i 23 01/22/01 ii 0 09/30/95 iii 23 01/22/01 iv 0 09/30/95 0 09/30/95 vi 21 04/13/00 vii 0 09/30/95 V

viii 30 06/05/02 ix 30 06/05/02 x 29 02/26/02 xi 27 01/31/02 xii 30 06/05/02 xiii 29 02/26/02 xiv 26 05/29/01 xv 30 06/05/02 PAGE REVISION DATE 1.1-1 0 09/30/95 1.1-2 22 07/07/00 1.1-3 0 09/30/95 1.1-4 22 07/07/00 1.1-5 0 09/30/95 1.1-6 0 09/30/95 1.2-1 0 09/30/95 1.2-2 0 09/30/95 1.2-3 0 09/30/95 1.3-1 0 09/30/95 1.3-2 0 09/30/95 j

1.3-3 0 09/30/95 1.3-4 0 09/30/95 1.3-5 0 09/30/95 1.3-6 0 09/30/95 1.3-7 0 09/30/95 1.3-8 0 09/30/95 1.3-9 0 09/30/95 1.3-10 0 09/30/95 1.3-11 0 09/30/95 1.3-12 0 09/30/95 1.3-13 0 09/30/95 1.4-1 0 09/30/95 1.4-2 0 09/30/95 1.4-3 0 09/30/95 1.4-4 0 09/30/95 3.0-1 0 09/30/95 3.0-2 0 09/30/95 3.0-3 0 09/30/95 3.0-4 0 09/30/95 3.1-1 0 09/30/95 3.1-2 0 09/30/95 3.1-3 0 09/30/95 3.1-4 0 09/30/95 3.1-5 0 09/30/95 Watts Bar-Unit 1 Vill 06/05/02 Technical Requirements Revision 30

TECHNICAL REQUIREMENTS LIST OF EFFECTIVE PAGES PAGE REVISION DATE 3.1-6 "0 "09/30/95 3.1-7 0 09/30/95 3.1-8 0 09/30/95 3.1-9 9 10/10/97 3.1-10 0 09/30/95 3.1-11 9 -10/10/97

-3.'1-12 0 09/30/95 3.1-12a 9 10/10/97 3.1-13 8 09/22/97

ý3.3-1 0 09/30/95 3.3-2 0 09/30/95 3.3-3 13 03/30/99 3.3-4 0 09/30/95 3.3-5 0 09/30/95 "3.3-6 0 09/30/95 3.3-7 26 05/29/01 3.3-8 26 05/29/01 3.3-9 3 02/28/96 3.3-10 0 09/30/95 3.3-11 0 09/30/95 3.3-12 0 09/30/95 3.3-13 0 09/30/95 3.3-14 19 10/12/99 3.3-15 19 10/12/99 3.3-16 0 09/30/95 3.3-17 19 10/12/99 "3.3-18 6 09/08/97 3.3-19 3.3-20 30 0

06/05/02 09/30/95 I

3.3-21 0 09/30/95 3.3-22 23 01/22/01 3.3-23 23 01/22/01 3.4-1 0 09/30/95 3.4-2 0 09/30/95 3.4-3 0 09/30/95 3.4-4 0 09/30/95 3.4-5 0 09/30/95 3.4-6 0 09/30/95 3.4-7 0 09/30/95 3.4-8 0 09/30/95 3.4-9 0 "09/30/95 3.4-10 0 09/30/95 3.4-11 0 09/30/95 3.4-12 0 09/30/95 3.6-1 0 09/30/95 "3.6-2 0 09/30/95 3.6-3 0 09/30/95 3.6-4 0 09/30/95 3.6-5 0 09/30/95 3:6-6 0 09/30/95 3.6-7 0 .09/30/95 3.7-1 0 09/30/95 3.7-2 0 09/30/95 Watts Bar-Unit 1 ix 06/05/02 Technical Requirements Revision 30

TECHNICAL REQUIREMENTS LIST OF EFFECTIVE PAGES PAGE REVISION DATE 3.7-3 17 05/25/99 3.7-4 17 05/25/99 3.7-5 17 05/25/99 3.7-6 17 05/25/99 3.7-7 17 05/25/99 3.7-8 17 05/25/99 3.7-9 17 05/25/99 3.7-10 29 02/26/02 3.7-11 0 09/30/95 3.7-12 0 09/30/95 3.7-13 0 09/30/95 3.7-14 0 09/30/95 3.7-15 0 09/30/95 3.7-16 0 09/30/95 3.7-17 0 09/30/95 3.7-18 0 09/30/95 3.7-19 5 08/29/97 3.7-20 0 09/30/95 3.7-21 0 09/30/95 3.7-22 0 09/30/95 3.7-23 0 09/30/95 3.7-24 0 09/30/95 3.7-25 0 09/30/95 3.7-26 0 09/30/95 3.7-27 0 09/30/95 3.7-28 0 09/30/95 3.7-29 2 01/04/96 3.7-30 2 01/04/96 3.8-1 0 09/30/95 3.8-2 0 09/30/95 3.8-3 0 09/30/95 3.8-4 25 05/15/01 3.8-5 0 09/30/95 3.8-6 0 09/30/95 3.8-7 0 09/30/95 3.8-8 0 09/30/95 3.8-9 25 05/15/01 3.8-10 0 09/30/95 3.8-11 0 09/30/95 3.8-12 0 09/30/95 3.8-13 0 09/30/95 3.8-14 0 09/30/95 3.8-15 0 09/30/95 3.8-16 0 09/30/95 3.8-17 0 09/30/95 3.8-18 18 08/03/99 3.8-19 18 08/03/99 3.9-1 0 09/30/95 3.9-2 0 09/30/95 3.9-3 28 02/05/02 3.9-4 28 02/05/02 3.9-5 0 09/30/95 5.0-1 24 03/19/01 Watts Bar-Unit 1 x 02/26/02 Technical Requirements Revision 29

TECHNICALREQUIREMENTS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.0-1 0 09/30/95 B 3.0-2 0 09/30/95 B 3.0-3 0 09/30/95 B 3.0-4 0 09/30/95 B 3.0-5 0 09/30/95 B 3.0-6 0 09/30/95 B 3.0-7 0 09/30/95

-B 3.0-8 0 09/30/95 B 3.0-9 0 09/30/95 B 3.0-10 0 09/30/95 B 3.0-11 0 09/30/95 B 3.0-12 0 09/30/95 B 3.0-13 0 09/30/95 B 3.0-14 0 09/30/95 B 3.0-15 0 09/30/95 B 3.1-1 "0 09/30/95 B 3.1-2 0 09/30/95 B'3.1-3 20 03/13/00 B 3.1-4 0 09/30/95 B 3.1-5 0 09/30/95 B 3.1-6 0 09/30/95 B 3.1-7 20 03/13/00 B 3.1-8 20 03/13/00 B 3.1-9 0 09/30/95 B 3.1-10 0 09/30/95 B 3.1-11 0 09/30/95 B 3.1-12 0 09/30/95 B 3.1-13 0 09/30/95 B 3.1-14 0 09/30/95 B 3.1-15 20 03/13/00

_B 3.1-16 27 01/31/02 B 3.1-17 27 01/31/02 B 3.1-18 0 09/30/95 B 3.1-19 0 09/30/95 B 3.1-20 20 03/13/00 B 3.1-21 27 01/31/02 B 3.1-22 27 01/31/02

-B 3.1-23 0 09/30/95 B 3.1-24 0 09/30/95 B 3.1-25 8 09/22/97 B 3.3-1 0 09/30/95 B 3.3-2 0 09/30/95 B 3.3-3 0 109/30/95 B 3.3-4 22 07/07/00 B 3.3-5 22 07/07/00 B 3.3-6 0 09/30/95

" B 3.3-7 0 09/30/95 B 3.3-8 0 .09/30/95 B 3.3-9 0 09/30/95 B 3.3-10 19 10/12/99 Watts Bar-Unit 1 xi 01/31/02 Technical Requirements Revision 27

TECHNICAL REQUIREMENTS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.3-11 19 10/12/99 B 3.3-12 19 10/12/99 B 3.3-13 19 10/12/99 B 3.3-14 0 09/30/95 B 3.3-15 6 09/08/97 B 3.3-16 6 09/08/97 B 3.3-17 30 06/05/02 B 3.3-18 0 09/30/95 B 3.3-19 0 09/30/95 B 3.3-20 11 01/08/99 B 3.3-21 23 01/22/01 B 3.3-22 23 01/22/01 B 3.3-23 23 01/22/01 B 3.3-24 23 01/22/01 B 3.4-1 0 09/30/95 B 3.4-2 0 09/30/95 B 3.4-3 0 09/30/95 B 3.4-4 0 09/30/95 B 3.4-5 0 09/30/95 B 3.4-6 0 09/30/95 B 3.4-7 0 09/30/95 B 3.4-8 0 09/30/95 B 3.4-9 0 09/30/95 B 3.4-10 0 09/30/95 B 3.4-11 0 09/30/95 B 3.4-12 0 09/30/95 B 3.4-13 0 09/30/95 B 3.4-14 0 09/30/95 B 3.4-15 0 09/30/95 B 3.4-16 0 09/30/95 B 3.4-17 0 09/30/95 B 3.6-1 0 09/30/95 B 3.6-2 20 03/13/00 B 3.6-3 20 03/13/00 B 3.6-4 0 09/30/95 B 3.6-5 0 09/30/95 B 3.6-6 10 12/17/98 B 3.6-7 20 03/13/00 B 3.6-8 10 12/17/98 B 3.6-9 0 09/30/95 B 3.6-10 0 09/30/95 B 3.6-11 0 09/30/95 B 3.6-12 0 09/30/95 B 3.7-1 0 09/30/95 B 3.7-2 0 09/30/95 B 3.7-3 20 03/13/00 B 3.7-4 17 05/25/99 B 3.7-5 17 05/25/99 B 3.7-6 17 05/25/99 Watts Bar-Unit 1 xli 06/05/02 Technical Requirements Revision 30

TECHNICAL REQUIREMENTS BASES LIST OF EFFECTIVE PAGES PAGE REVISION DATE B 3.7-7 17 05/25/99 B 3.7-8 17 05/25/99 B 3.7-9 17 05/25/99 B 3.7-10 17 05/25/99 B 3.7-11 17 05/25/99 B 3.7-12 0 09/30/95 B 3.7-13 5 08/29/97 B 3.7-14 29 02/26/02 B 3.7-15 4 08/18/97 B 3.7-16 5 08/29/97 B 3.7-17 29 02/26/02 B 3.7-18 0 09/30/95 B 3.7-19 0 09/30/95 B 3.7-20 0 09/30/95 B 3.7-21 0 09/30/95 B 3.7-22 0 09/30/95 B 3.7-23 20 03/13/00 B 3.7-24 0 09/30/95 B 3.7-25 20 03/13/00 B 3.8-1 0 09/30/95 B 3.8-2 0 09/30/95 B 3.8-3 0 09/30/95 B 3.8-4 0 09/30/9S B 3.8-5 0 09/30/95 B 3.8-6 25 O5/lS/01 B 3.8-7 25 o5/1/01O B 3.8-8 0 09/30/95 B 3.8-9 0 09/30/95 B 3.8-10 0 09/30/95 B 3.8-11 0 09/30/95 B 3.8-12 0 09/30/95 B 3.8-13 25 B 3.8-14 05 / 15/01 25 05/15/01 B 3.8-15 0 09/30/95 B 3.8-16 0 09/30/95 B 3.8-17 0 09/30/95 B 3;8-18 0 09/30/95 B 3.8-19 0 09/30/95 B 3.8-20 0 09/30/95 B 3.8-21 0 09/30/95 B 3.8-22 18 08/03/99 B 3.9-1" 0 09/30/95 B 3.9-2 0 09/30/95 B 3.9-3 0 09/30/95 oB 3.9-4 0 09/30/95 B 3.9-5 28 02/05/02 B 3.9-6 0 09/30/95 B 3.9-7 28 02/05/02 B 3.9-8 0 09/30/95 B 3.9-9 0 09/30/95 Watts Bar-Unit 1 xiii Technical Requirements 02/26/02 Revision 29

TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES REVISION LISTING Revisions Issued SUBJECT Revision 0 09-30-95 Initial Issue

1' Revision 1 12-06-95 Submerged Component Circuit Protection Revision 2 01-04-96 Area Temperature Monitoring - Change in MSSV Limit Revision 3 02-28-96 Turbine Driven AFW Pump Suction Requirement Revision 4 08-18-97 Time-frame for Snubber Visual Exams Revision 5 08-29-97 Performance of Snubber Functional Tests at Power Revision 6 09-08-97 Revised Actions for Turbine Overspeed Protection Revision 7 09-12-97 Change OPAT/OTAT Response Time Revision 8 09-22-97 Clarification of Surveillance Frequency for Position Indication System Revision 9 10-10-97 Revised Boron Concentration for Borated Water Sources Revision 10 12-17-98 ICS Inlet Door Position Monitoring - Channel Check Revision 11 01-08-99 Computer-Based Analysis for Loose Parts Monitoring Revision 12 01-15-99 Removal of Process Control Program from TRM Revision 13 03-30-99 Deletion of Power Range Neutron Flux High Negative Rate Reactor Trip Function Revision 14 04-07-99 Submerged Component Circuit Protection Revision 15 04-07-99 Submerged Component Circuit Protection Revision 16 04-13-99 Submerged Component Circuit Protection Revision 17 05-25-99 Flood Protection Plan Revision 18 08-03-99 Submerged Component Circuit Protection Revision 19 10-12-99 Upgrade Seismic Monitoring Instruments Revision 20 03/13/00 Added Notes to Address Instrument Error for Various Parameters Revision 21 04/13/00 COLR, Cycle 3, Rev 2 Revision 22 07/07/00 Elimination of Response Time Testing Watts Bar-Unit 1 xiv Technical Requirements 05/29/01 Revision 26

TECHNICAL REQUIREMENTS MANUAL LIST OF EFFECTIVE PAGES REVISION LISTING Revisions Issued SUBJECT Revision 23 01/22/01 Plant Calorimetric (LEFM)

Revision 24 03/19/01 TRM Change Control Program per 50.59 Rule Revision 25 05/15/01 Change in Preventive Maintenance Frequency for Molded Case Circuit Breakers Revision 26 05/29/01 Change CVI Response Time from 5 to 6 Seconds Revision 27 01/31/02 Change pH value in the borated water sources due to TS change for ice weight reduction Revision 28 02/05/02 Refueling machine upgrade under DCN D-50991-A Revision 29 02/26/02 Added an additional action to TR 3.7.4 to perform an engineering evaluation of inoperable snubber's impact on the operability of a supported system.

Revision 30 06/05/02 Updated TR 3.3.5.1 to reflect implementation of the TIPTOP program in a Technical Instruction (TI).

Watts Bar-Unit 1 xv 06/05/02 Technical Requirements Revision 30

ESFAS TR 3.3.2 Table 3.3.2-1 (Page 1 of 5)

Engineered Safety Features Actuation System Response Times INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

1. Manual Initiation

a. Safety Injection (ECCS)

N.A.

b. Containment Spray N.A.

c. Phase "A" Isolation N.A.

d. Phase "B" Isolation

e. Containment Ventilation Isolation N.A.

N.A.

f. Steam Line Isolation N.A.

g. Feedwater Isolation N.A.

h. Auxiliary Feedwater

i. Essential Raw Cooling Water N.A.

N.A.

j. CREVS Actuation

k. Containment Air Return Fan N.A.

1. Component Cooling System N.A.

m. Start Diesel Generators N.A.

N.A.

n. Reactor Trip N.A.

2. Containment Pressure-High

a. Safety Injection (ECCS) < 27(4)/32 (14)1/37(5)

1) Reactor Trip <2

2) Feedwater Isolation < 03)

3) Containment Isolation-Phase "A"(6)

< 12(2)/22"l

4) Containment Ventilation Isolation < . (2) 11) 6 0

5) Auxiliary Feedwater Pumps <60 10)

6) Essential Raw Cooling Water < 47(2)/57(1)

7) CREVS Actuation N.A.

8) Component Cooling System < 51(2)/60(l)

9) Start Diesel Generators < 12 (12)

3. Pressurizer Pressure-Low

a. Safety Injection (ECCS) < 27 (4)132(14)137(5)

1) Reactor Trip <2

2) Feedwater Isolation < 80)

3) Containment Isolation-Phase "A"(6) <12(z)/22(l)

4) Containment Ventilation Isolation

5) Auxiliary Feedwater Pumps

< 6.0o((11)

< 60(10)

I (continued)

Watts Bar-Unit 1 3.3-7 05/29/01

- Technical Requirements Revision 26

ESFAS TR 3.3.2 Table 3.3.2-1 (Page 2 of 5)

Engineered Safety Features Actuation System Response Times INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

3. Pressurizer Pressure-Low (continued)

6) Essential Raw Cooling Water

< 47(2)/57(1)

7) CREVS Actuation

8) N.A.

Component Cooling System

< 50(23/60(1)

9) Start Diesel Generators

< 12('

4. Steam Line Pressure Negative Rate-High

a. Steam Line Isolation

< 8

5. Steam Line Pressure - Low

a. Safety Injection (ECCS) < 27(4'/32(14)1/37(5)

1) Reactor Trip (from SI)

< 2

2) Feedwater Isolation s 80)

3) Containment Isolation-Phase "A",,6) 12(2)/22(1)

4) Containment Ventilation Isolation < 6.0(2)(113

5) Auxiliary Feedwater Pumps

< 60(1°)

6) Essential Raw Cooling Water S 47(2)/57(l)

7) CREVS Actuation

8) Component Cooling System N.A.

< 50(2)/60(1)

9) Start Diesel Generators

< 12(12)

b. Steam Line Isolation

< 8

6. Containment Pressure - High - High

a. Containment Spray

< 221(13)

b. Containment Isolation-Phase "B"

< 68 (2/78(1)

c. Steam Line Isolation

d. < 8 Containment Air Return Fans 480 < RT < 600

7. Steam Generator Water Level - High - High

a. Turbine Trip

< 2.5

b. Feedwater Isolation < 8 ()

(continued)

Watts Bar-Unit 1 3.3-8 Technical Requirements 05/29/01 Revision 26

Turbine Overspeed Protection TR 3.3.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One reheat stop B.1 Restore inoperable 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months valve or one reheat valve(s) to OPERABLE "

intercept valve per status.

low pressure turbine steam line inoperable., OR B.2 Close at least one 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months valve in the affected steam line(s).

OR B.3 Isolate the turbine 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months from the steam supply.

C. Turbine Overspeed C.1 Isolate the turbine 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Protection System from the steam inoperable for supply system.

causes other than Condition A or Condition B.

TECHNICAL SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TR 3.3.5.1 ---------------- NOTE ------------------

TSR 3.0.4 is not applicable.

Verify the Turbine Overspeed In accordance Protection System is OPERABLE in with TIPTOP.

accordance with the Turbine Integrity Program With Turbine I Overspeed Protection (TIPTOP).

Watts Bar-Unit 1 3.3-19 Revision 30 Technical Requirements 06/05/02

Snubbers TR 3.7.3 TR 3.7 PLANT SYSTEMS TR 3.7.3 Snubbers TR 3.7.3 All snubbers utilized on safety related systems shall be OPERABLE. For those snubbers utilized on non-safety related systems, each snubber shall be OPERABLE if a failure of that snubber or the failure of the non-safety related system would have an adverse effect on any safety related system.

APPLICABILITY:

MODES 1, 2, 3, and 4.

MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1.1 Restore snubber(s) to snubber(s) 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

inoperable.

I OR A.1.2 Replace snubber(s). 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months I AND A.2 Perform an engineering 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months evaluation per Table 3.7.3-5 on the attached component.

OR A.3 Perform an engineering 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months evaluation demonstrating OPERABILITY of the supported system.

(continued)

Watts Bar-Unit I Technical Requirements 3.7-10 02/26/02 Revision 29

Isolation Devices TR 3.8.1 TECHNICAL SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE T FREQUENCY FREQUENCY I.

TSR 3.8.1.4 ------------------ NOTE For each circuit breaker found inoperable during functional tests, an additional representative sample of 10%

of the defective type shall be functionally tested until no more failures are found or all of that type have been functionally tested.

Perform an integrated system functional 18 months test on each medium voltage (6.9 kV) breaker which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed.

TSR 3.8.1.5 Inspect each circuit breaker and I 72 months perform preventive maintenance in accordance with procedures prepared in conjunction with the manufacturer's and EPRI NP-7410-V3, Rev. 1 recommendations

)

for electrically operated breakers and Class 1E MCCB.

Watts Bar-Unit 1 3.8-4 Technical Requirements 05/15/01 Revision 25

Containment Penetration Conductor Overcurrent Protection Devices TR 3.8.2 TECHNICAL SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY FRQEC TSR 3.8.2.4 NOTES --

1. Electrically-operated circuit breakers selected for functional testing shall be selected on a rotating basis.

2. The functional test shall be conducted by simulating a fault current with an approved test set and verifying that each electrically-operated circuit breaker functions as designed.

3. For each electrically-operated circuit breaker found inoperable during functional tests, an additional representative sample of 10% of the defective type shall be functionally tested until no more failures are found or all of that type have been functionally tested.

Perform functional test on representative sample of ; 10% of each 18 months type of electrically-operated circuit breaker.

TSR 3.8.2.5 Inspect each circuit breaker and perform preventive maintenance in accordance with procedures prepared in conjunction with the manufacturer's and EPRI NP-7410-V3, Rev. 1 recommendations:

1. For electrically operated breakers 72 months and Class 1E MCCB.

2. For non-Class 1E MCCB.

96 months J._____________________________

Watts Bar-Unit 1 3.8-9 Technical Requirements 05/15/01 Revision 25

Refueling Machine TR 3.9.3 TR 3.9 REFUELING OPERATIONS TR 3.9.3 -Refueling Machine TR 3.9.3 The Refueling Machine and Auxiliary Hoist shall be used for movement of fuel assemblies or drive shafts and shall be OPERABLE as follows:

a. The Refueling Machine shall have a capacity of Ž 3150 pounds, and two electrical overload cutoff limits of 5 2650 pounds and 5 2800 pounds, respectively.

b. The Auxiliary Hoist shall have a capacity of ; 1200 pounds and a load indicator shall be used to indicate the lifting of loads > 1190 pounds.

APPLICABILITY: During movement of fuel assemblies or drive shafts within the reactor pressure vessel.

ACTIONS rýr%?'?

1j.L I LUIIJ REQUIRED ACTION COMPLETION TIME A. Refueling Machine A. 1 Suspend use of Immediately inoperable. Refueling Machine from operations involving the movement of fuel assemblies within the reactor pressure vessel.

i i B. Auxiliary Hoist B. 1 Suspend use of Immediately inoperable. Auxiliary Hoist from operations involving the movement of drive shafts within the reactor pressure vessel.

I..

______________ I________

Watts Bar-Unit 1 3.9-3 Technical Requirements 02/05/02 Revision 28

Refueling Machine TR 3.9.3 TECHNICAL SURVEILLANCE REQUIREMENTS )

SURVEILLANCE FREQUENCY TSR 3.9.3.1 For each required Refueling Machine, 18 months perform a load test of ; 3150 pounds and demonstrate an automatic electrical load cutoff before the crane load is

> 2650 pounds. Demonstrate a second automatic electrical load cutoff before the crane load is > 2800 pounds.

TSR 3.9.3.2 For each required Auxiliary Hoist and Within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months associated load indicator, perform a prior to start load test of ; 1200 pounds. of drive shafts movement within the reactor pressure vessel.

)

Watts Bar-Unit 1 3.9-4 Technical Requirements 02/05/02 Revision 28

Borated Water Sources, Shutdown B 3.1.5 BASES TECHNICAL TSR 3.1.5.1 (continued)

SURVEILLANCE REQUIREMENTS is greater than or equal to 60°F. With ambient air temperature greater than 60"F, should not decrease below this the RWST solution temperature limit, therefore, monitoring is not required.

TSR 3.1.5.2 This surveillance requires verification every 7 days that the boron concentration of the RWST is k 2,500 ppm.

boron concentration is sufficient This to provide an adequate SDM and also ensure a pH value between 7.5 and 10.0. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic mechanical systems and components. stress corrosion on Since the RWST volume is normally stable, a 7 -day Frequency concentration is appropriate to verify boron and has been shown to be acceptable through operating experience.

TSR 3.1.5.3 This surveillance requires verification every 7 days the RWST borated water volume that does not account for instrumentis k 62,900 gallons (value volume is sufficient to provide error). This borated water an adequate SDM and also ensure a pH value between 7.5 and 10.0. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress systems and components. corrosion on mechanical Since the RWST volume is normally stable, a 7 -day Frequency to verify borated water volume appropriate and has been shown is operating experience. to be acceptable through The 62,900 gallon volume requirement includes 11,100 gallons for shutdown margin, adjustments minimum safety limit level for in the RWST, and adjustments instrument error. for TSR 3.1.5.4 This surveillance requires verification every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the Boric Acid Tank (BAT) solution that (value does not account for temperature is k 63°F instrument error). This ensures that the concentration of boric allowed to precipitate due acid in the BAT is not to cooling. The Frequency of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for performance of the surveillance is frequent enough to identify a temperature change that would approach the 63°F temperature limit.

(continued)

Watts Bar-Unit 1 B 3.1-16 Technical Requirements Revision 20, 27

Borated Water Sources, Shutdown B 3.1.5 BASES TECHNICAL TSR 3.1.5.5 SURVEILLANCE REQUIREMENTS This surveillance requires verification every 7 days that (continued) the boron concentration of the BAT is between 6,120 ppm and 6,990 ppm. This boron concentration is sufficient to provide an adequate SDM and also ensure a pH value between 7.5 and 10.0. This pH band minimizes the evolution bf "

iodine an ýminimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

Since the BAT volume is normally stable, a 7-day Frequency to verify boron concentration is appropriate and has been shown to be acceptable through operating experience.

TSR 3.1.5.6 This surveillance requires verification every 7 days that the BAT borated water volume is Ž 3,800 gallons (value does not account for instrument error). This borated water volume is sufficient to provide an adequate SDM and also ensure a pH value between 7.5 and 10.0. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. Since the BAT volume is normally stable, a 7-day Frequency to verify borated water volume is appropriate and has been shown to be acceptable through operating experience.

REFERENCES 1. WCAP-11618, "MERITS Program-Phase II, Task 5, Criteria Application," including Addendum 1 dated April, 1989.

2. CEN-603, "Boric Acid Concentration Reduction Effort, Technical Bases and Operational Analysis for Watts Bar, Unit l," Revision 00, April 1993.

3. TVA Calculation, EPM-PDM-071197, Revision 0, "Boric Acid Concentration Analysis for BAT and RWST."

4. Westinghouse Letter, WAT-D-10940, Revision 1, "Watts Bar Unit One TRM & FSAR Markups - Post LOCA Sump pH."

Watts Bar-Unit 1 B 3.1-17 Revision 20, Technical Requirements 27

Borated Water Sources, Operating B 3.1.6 BASES TECHNICAL TSR 3.1.6.2 (continued)

SURVEILLANCE REQUIREMENTS boron precipitation in the core will not occur and the effect of chloride and caustic stress corrosion on mechanical systems and components will be minimized.

Since the RWST volume is normally stable, a 7-day Frequency to verify boron concentration is appropriate and has been shown to be acceptable through operating experience.

TSR 3.1.6.3 This surveillance requires verification every the RWST borated water volume is within the 7 days that required limit of ; 370,000 gallons (value does not account for instrument error). This will ensure that a sufficient initial supply is available for injection and to support continued Containment Spray System pump operation on ECCS and recirculation.

Since the RWST volume is normally stable, a 7-day Frequency to verify borated water volume is appropriate and has been shown to be acceptable through operating experience.

TSR 3.1.6.4 This surveillance requires verification every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that the Boric Acid Tank (BAT) solution temperature (value does not account for instrument is : 63°F error). This ensures that the concentration of boric acid in the BAT is not allowed to precipitate due to cooling. The Frequency of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for performance of the surveillance is frequent enough to identify a temperature change that would 63 °F temperature limit and has been approach the through operating experience. shown to be acceptable This surveillance has been modified by a NOTE stating that the surveillance is only required if the BAT is used as one of the required borated water sources for TR 3.1.2.

TSR 3.1.6.5 This surveillance requires verification every 7 days that the boron concentration of the BAT is in accordance Figure 3.1.6 of TR 3.1.6. with This boron concentration is sufficient to provide an adequate SDM and also ensure a pH value between 7.5 and 10.0. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. Since the BAT volume is normally stable, a (continued)

Watts Bar-Unit 1 B 3.1-21 Revision 20, 27 Technical Requirements

- -* Borated Water Sources, Operating B 3.1.6 BASES TECHNICAL TSR 3.1.6.5 (continued)

SURVEILLANCE REQUIREMENTS 7-day sampling Frequency to verify boron concentration is appropriate and has been shown to be acceptable through operating experience.

This surveillance has been modified by'a the surveillance is only required if the NOTE stating that BAT is used as one of the required borated water sources for TR 3.1.2.

TSR 3.1.6.6 This surveillance requires verification every the BAT borated water volume is in accordance 7 days that with Figure 3.1.6 (the values listed on the figure do not account for instrument error). This borated water volume at the boron concentration specified in TSR 3.1.6.5 is sufficient to provide an adequate SDM. Since the BAT volume is normally stable, a 7-day Frequency to verify borated water volume is appropriate and has been shown to be acceptable through operating experience.

This surveillance has been modified by a NOTE stating that the surveillance is only required if the BAT is used as one of the required borated water sources for TR 3.1.2.

The maximum expected boration capability requirement occurs near EOL from full power peak xenon conditions and requires borated water from a boric acid tank in accordance with Figure 3.1.6, and additional makeup from either (1) the common boric acid tank and/or batching tank, or (2) a maximum of 23,000 gallons of 2,500 ppm borated the refueling water storage tank. water from With the refueling water storage tank as the only borated water source, a maximum of 61,000 gallons of 2,500 ppm borated water is required.

REFERENCES 1. WCAP-11618, "MERITS Program-Phase II, Task 5, Criteria Application," including Addendum 1 dated April, 1989.

2. CEN-603, "Boric Acid Concentration Reduction Effort, Technical Bases and Operational Analysis for Watts Bar Nuclear Plant, Unit 1," Revision 00, April 1993.

3. TVA Calculation, EPM-PDM-071197, Revision 0, "Boric Acid Concentration Analysis For BAT and RWST."

4. Westinghouse Letter, WAT-D-10940, Revision 1, "Watts Bar Unit One TRM and FSAR Markups - Post LOCA Sump pH."

Watts Bar-Unit 1 B 3.1-22 Revision 20, 27 Technical Requirements

Turbine Overspeed Protection B 3.3.5 BASES ACTIONS B.1 (continued) taking into account the redundant capabilities afforded by the OPERABLE valve in the same steam line(s) and reasonable time for repairs.

B.2 A first alternative to Required Action B.1 is to close at least one valve in the affected steam line(s). This places the low pressure steam line(s) with the inoperable valve(s) in a no flow condition. This ensures total steam isolation to the low pressure turbine(s) in the event of an overspeed condition, even with a single failure of another reheat stop valve or reheat intercept valve. An additional 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (total of 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months ) are allowed for a power reduction, if necessary, in an orderly manner and without challenging plant systems.

B.3 A second alternative is to isolate the turbine from the steam supply. This places the turbine in a condition where overspeed protection is not required. Again, an additional 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (total of 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months ) are allowed for a power reduction, if necessary, in an orderly manner and without challenging plant systems.

C.1 If the Turbine Overspeed Protection System is inoperable for causes other than Condition A or Condition B, the turbine must be placed in a condition where overspeed protection is not required. This is accomplished by isolating the turbine from the steam supply system. A Completion Time of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is allowed to shutdown the turbine in an orderly manner and without challenging plant systems.

TECHNICAL TSR 3.3.5.1 SURVEILLANCE REQUIREMENTS The Turbine Overspeed Protection System testing requirements and frequencies are provided in Reference

3. In addition, the Surveillance is modified by a Note stating that TSR 3.0.4 is not applicable.

REFERENCES 1. Watts Bar FSAR, Section 10.2, "Turbine Generator."

2. WCAP-11618, "MERITS Program-Phase II, Task 5, Criteria Application," including Addendum 1 dated April, 1989.

3. Turbine Integrity Program With Turbine Overspeed Protection (TIPTOP). I Watts Bar-Unit 1 B 3.3-17 Revision 30 Technical Requirements 06/05/02

Snubbers B 3.7.3 BASES ACTIONS A.1. A.1.2, and A.2 (continued) b) Determine the impact on the suported component This evaluation shall determine if inoperable snubber has adversely affected the the attached component.

The 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is based on engineering experiences and is reasonable, considering the time identify the problem and take the it will take to proper corrective actions. This requirement is considered met snubbers rendered inoperable by for those removal for functional testing by the generic engineering evaluation included in Reference 9.

A.3 Another alternative is to perform evaluation to demonstrate inoperable an engineering snubber(s) do not impact the OPERABILITY of the supported system for the existing plant condition. (Reference 10)

B.l If Required Actions under Condition within the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the supported A are not met system or component is immediately declared inoperable.

TECHNICAL The TSRs are preceded by three Notes.

SURVEILLANCE Note 1 states that the snubber inservice inspection REQUIREMENTS program shall be carried out in accordance with the requirements Tables 3.7.3-1, 2 and 3. in This represents an enhanced snubber inservice inspection program compared Inservice Inspection Program which stipulates to the inservice inspection in accordance with ASME section XI. The snubber inservice inspection program the requirements of Generic Letter 90-09, includes "Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions." ASME Section XI, 1989 Edition, Subsection IWF-5300(a) and (b) require that inservice examinations of snubbers, using the VT-3 visual examination method described in IWA-2213, and inservice tests of snubbers be performed in accordance with the first Addenda to ASME/ANSI OM-1987, Part 4.

Note 2 requires repair or replacement of snubbers which fail inspection, and testing of repaired snubbers before installation. Note 3 indicates that a "snubber type," as used in this TR, is determined by the design and manufacturer, but not by size.

(continued)

Watts Bar-Unit I B 3.7-14 Revision 29 Technical Requirements 02/26/02

Snubbers B 3.7,3 BASES TSR 3.7.3.4 SURVEILLAN~CE K' REQUIREMENTS The TSR is preceded by three Notes which (continued) need for considering service life underline the of sub-components and to replace these sub-components before the end of the respective service lives. The replacement of sub components must be documented and the retained for further reference. documentation TSR 3.7.3.4 addresses the monitoring of the service life of The requirement to monitor the snubber the snubbers.

service life included to ensure that the snubbers periodically is undergo a performance evaluation in view and operating conditions. of their age The expected service life is established by the manufacturer and is operating experience with critical snubber based on as seals and springs in a radiation environment.parts such every refueling outage Frequency is based The engineering experience and is reasonable on verification service life. for the REFERENCES 1. ASME Boiler and Pressure Vessel Code, Section III and XI.

2. Regulatory Guide 1.124, "Design Limits and Loading Combinations for Class 1 Linear-Type Component Supports".

3. Regulatory Guide 1.130, "Design Limits and Loading Combinations for Class 1 Plate-and Shell-Type Component Supports".

4. "Zion Probabilistic Safety Study", Commonwealth Edison Company, September 1981.

5. "Millstone Unit 3 Probabilistic Safety Study,"

North-east Utilities Company, August 1983.

6. NRC Staff Review of Nuclear Steam Supply System Vendor Owners Groups' Application of The Commission's Interim Policy Statement Criteria to Standard Technical Specifications, Attachment to letter dated May, 1988 from T.E. Murley, NRC to W.S. Wilgus, Chairman The B&W Owners Group.

7. Regulatory Guide 8.8, "Information Relevant Maintaining Occupational Radiation Exposure to Low as Practicable.", as

8. Regulatory Guide 8.10, "Operating Philosophy Maintaining Occupational Radiation Exposure for Low as Practicable."$ as

9. SA/SE WBPLCE-97-028-0, RIMS T28970829803.

10. Screening Review WBPLCE-02-003-0.

I Watts Bar-Unit 1 B 3.7-17 Revision 29 Technical Requirements 02/26/02

Isolation Devices B 3.8.1 BASES TECHNICAL SURVEILLANCE TSR 3.8.1.3 2)

REQUIREMENTS This surveillance requires that the performance of a CHANNEL (continued) CALIBRATION of all protective relays associated with medium voltage (6.9 kV) isolation overcurrent devices. A CHANNEL CALIBRATION assures that the relays will be able to detect overcurrent conditions on the non-Class 1E loads. The Frequency of 18 months is consistent with the typical industry refueling cycle.

TSR 3.8.1.4 This surveillance requires the performance of an integrated system functional test which verifies that the relays and associated medium voltage (6.9 kV) circuit breakers function as designed to isolate fault currents. An integrated test assures that the individual elements of the protection scheme, the relays, breakers and other control circuits, interact as designed.

The surveillance has been modified by a Note stating that if a failure is discovered in the integrated functional test, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be tested to assure that there is no common cause failure mechanism that could systematically affect all breakers of a given type.

The Frequency of 18 months coincides with the typical industry refueling cycle.

TSR 3.8.1.5 This surveillance requires the inspection of each circuit breaker and the performance of procedures prepared in conjunction with the manufacturer's recommendations. By performance of recommended maintenance, the likelihood for the circuit breakers to become inoperable can be minimized.

The 72 months periodicity for Class 1E circuit breaker, (Ref. 5), takes into consideration the low frequency of operation of the circuit breakers and the low likelihood that operation and maintenance activities at the plant could adversely affect the OPERABILITY of the circuit breaker.

(continued)

Watts Bar-Unit 1 B 3.8-6 05/15/01 Technical Requirements Revision 25

Isolation Devices B 3.8.1 BASES (continued)

REFERENCES 1. Watts Bar FSAR, Section 6.0, "Engineered Safety Feature," and Section 15.0, "Accident Analyses."

2. WCAP-13470, "Watts Bar Unit 1 Technical Specifications Criteria Application Report," dated August, 1992.

3. Watts Bar Wiring Diagram Series 45A710, "Periodic Breaker Test."

4. NUREG-0847, "Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Units 1 and 2" including Supplements thereto.

5. EPRI NP-7410-V3, "Molded Case Circuit Breaker Application and Maintenance Guide," Revision 1.

Watts Bar-Unit 1 B 3.8-7 05/15/01 Technical Requirements Revision 25

Containment Penetration Condgctor Overcurrent Protection Devices B 3.8.2 BASES TECHNICAL TSR 3.8.2.4 SURVEILLANCE REQUIREMENTS This surveillance requires the performance of a functional (continued) test on a representative sample of ; 10% of each type electrically-operated circuit breaker used as penetration of protection. This sample size is sufficiently large to represent the actual failure distribution within the whole population of circuit breakers of a given type used in the plant. If there are any failure mechanisms that could affect the OPERABILITY of the circuit breaker(s),

they are likely to have occurred in the sample tested. The 18 month Frequency takes into consideration the infrequent operation of the breakers and their correspondingly low failure rate.

The Surveillance is augmented by three Notes. The first Note states that the breakers shall be selected for testing on a rotating basis. This ensures that all of the breakers will eventually be tested and those failures that may not have been discovered in the initial 10% samples will eventually be discovered. The second Note describes the functional test procedure and the response to be verified to ensure OPERABILITY.

The third Note states that for each electrically-operated circuit breaker found inoperable during functional tests an additional representative sample of 10% of the defective type shall be functionally tested until no more failures are found or all of that type have been functionally tested. This helps to ensure that a failure discovered in the representative sample was not caused by a failure mechanism that could systematically affect other breakers in the overall population of breakers of the same type.

TSR 3.8.2.5 This surveillance requires the inspection of each circuit breaker and the performance of preventive maintenance in accordance with procedures prepared in conjunction with the manufacturers recommendation. Performance of recommended preventive maintenance helps ensure the operability of the circuit breakers. The 72 months periodicity for Class 1E and 96 months for non-Class 1E circuit breakers, (Ref. 4), takes into consideration known failure rates for the circuit breakers and operating experience.

(continued)-

Watts Bar-Unit 1 B 3.8-13 05/15/01 Technical Requirements Revision 25

Containment Penetration Conductor Overcurrent Protection Devices B 3.8.2 BASES (continued)

REFERENCES 1. Regulatory Guide 1.63 "Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants" Revision 3.

2. WCAP-11618, "MERITS Program-Phase II, Task 5, Criteria Application," including Addendum 1 dated April, 1989.

3. Watts Bar Wiring Diagram Series 45A710, "Periodic Breaker Test."

4. EPRI NP-7410-V3, "Molded Case Circuit Breaker Application and Maintenance Guide," Revision 1.

Watts Bar-Unit 1 B 3.8-14 05/15/01 Technical Requirements Revision 25

Refueling Machine B 3.9.3 B 3.9 REFUELING'OPERATIONS B 3.9.3 Refueling Machine BASES R

BACKGROUND The refueling machine is used during CORE ALTERATIONS to either move fuel assemblies to new'positions in the core, load new fuel assemblies, or unload spent fuel assemblies.

The refueling machine consists of a rectilinear bridge and trolley crane with a vertical mast extending down into the refueling water. The bridge and trolley motions position the vertical mast over are used to a fuel assembly in the core.

A long tube with a pneumatic gripper on the end is lowered down out of the mast to grip the fuel assembly and manipulate it so that it can be transported to its new position.

The refueling machine has two auxiliary monorail which are located on each side hoists of the bridge. The auxiliary hoists are used for the movement of control rod drive shafts in order to facilitate the refueling the hoist, the drive shafts must process. Before using be disconnected from their respective control rods and, with the upper internals, removed from the vessel (Ref.

1).

APPLICABLE This requirement ensures that SAFETY ANALYSES the refueling machine and auxiliary hoists have sufficient load capacity to lift a fuel assembly or a drive shaft, respectively.

prevent a load from being accidentally This is to refueling process. dropped during the The requirement also ensures that limiting devices are available load to prevent damage to a fuel assembly during fuel movement.

These requirements have not been identified as a significant risk contributor (Ref. 2).

TR TR 3.9.3 requires that the refueling machine and auxiliary hoist shall be used for the movement drive shafts and that they shall of fuel assemblies or be OPERABLE with certain requirements as discussed below.

The refueling machine shall have a capacity of at least electrical overload cutoff limits 3150 pounds, with two of 2650 pounds, and 2800 pounds, respectively.

(continued)

Watts Bar-Unit 1

"-' Technical Requirements B 3.9-5 02/05/02 Revision 28

Refueling Machine B 3.9.3 BASES (continued)

TECHNICAL TSR 3.9.3.1 SURVEILLANCE REQUIREMENTS TSR 3.9.3.1 requires the performance of three tests on the refueling machine. A 1oad test of 3150 pounds must be performed on the refueling machine to verify its capacity.

A test must be performed to demonstrate an automatic electrical load cutoff before the crane load .

is greater than 2650 pounds. A test must also be performed to demonstrate second automatic electrical load cutoff before a the crane load is greater than 2800 pounds. These tests verify that the capacity and the load limits are still within the Technical Requirements. The Surveillance Frequency of 18 months is based upon engineering judgement, manufacturer recommendation, the fact that the refueling machine is an infrequently used and highly reliable piece of equipment, and consistency with the typical industry refueling cycle.

TSR 3.9.3.2 TSR 3.9.3.2 requires a load test of at least 1200 pounds be performed on each required auxiliary hoist and its associated load indicator. This test verifies that the capacity is within the technical requirement and that the load indicator is functional. This surveillance is to be performed within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to starting the movement of the drive shafts within the reactor pressure vessel. The surveillance frequency is based on engineering judgement and the fact that the auxiliary hoist is an infrequently used and reliable piece of equipment.

REFERENCES 1. Watts Bar FSAR, Section 9.1.4, "Fuel Handling System."

2. WCAP-11618, "MERITS Program-Phase II, Task 5, Criteria Application," including Addendum 1 dated April, 1989.

Watts Bar-Unit 1 B 3.9-7 Technical Requirements 02/05/02 Revision 28

ML022680131

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