ML18025B691
| ML18025B691 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/09/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18025B692 | List: |
| References | |
| TVA-BFNP-TS-170, NUDOCS 8112230431 | |
| Download: ML18025B691 (8) | |
Text
ENCLOSURE 1
BROWNS FERRY NUCLEAR PLANT UNIT 3 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS (DOCKET NO.
50-296)
REQUEST NO. TVA BFNP TS 170
Section 3 ~ 4/4 ~ 4
- 3. 5/4. 5 3 ~ 6/4. 6 C.,
Scram Insertion Times D.
Reactivity Anomalies E.
Reactivity Control Standby Liquid Control System A.
Normal System Availability B.
Operation with Inoperable Components C..
Sodium Pentaborate Solution Core and Containment Cooling Syste'ms A.
Core Spray System B.
Residual Heat Removal System (RHRS)
(LPCI and Containment Cooling)
C.
RHR Service Mater System and Emergency Equipment Cooling Water System (EECMS)
D.
Equipment Area Coolers E.
High Pressure Coolant Infection System (HPCIS)
I Fi Reactor Core Isolation Cooling System (RCICS)
Automatic Depiessurization System (ADS)
,'G J.
Linear Heat Generation Rate K.
Minimum Critical Power Ratio
'(MCPR)
P L.
Reporting Requirements Primary System Boundary A.
- Thermal and Pressurization'Limitations H.
Maintenance of Filled Discharge Pipe
<<I.
Avexage Planar Linear Heat Generation Rate Page No..
128 129 129 137 137 139 139 146 149 155 158 159 160 161 163 165 166 167 167 a 184 184
~Set%on B.
Coolant Chemistry C.
Coolant Leakage D.
Safety and Relier'alves E.
Jet Pumps Parcae Ho.
187 191 192 193 Gi Recirculation Pump Operation Structural Integrity 195 196
- 3. 7f'4. 7.
H.
Shock Suppressors (Snubbers)
Containment Systems A.
Standby Gas Treatment System C.
Primary Containment Isolation Valves
'I E.
Control Room Emergency Ventilation F.
Primary Containment Purge System 198 231 231 247 251 254 256 258 G.
H ~
Containment Atmosphere Dilution System (CAD)
Containment Atmosphere Monitoring (CAM)
System H~ and Oz Analyzer 260 261 3.8/4 '
Radioactive Materials A.
Liquid Effluents B.
Airborne Effluents
- 299 299 302 3.9/4. 9 C.
Mechanical Vacuum Pump D.
Miscellaneous Radioactive Materials sources Auxiliary Electrical System A.
Auxiliary Electrical Equipment t
B.
Operation with Inoperable Equipment 307 308
~
316 316 322
(
4 ~ 2.E
'.2. F 4.2.G Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation Ninimum Test and Calibration Frequency for Surveillance Instrumentation Surveillance R;.quire.,i~nts for Control Room Isolation Instrumentation 101 102 103 4 ~ 2 ~ H Hinimum Test and Calibration Frequency for Flood Protection Instrumentation 104 4.2.J
- 4. 6.A 3.5 I
.'3. 6. H 3 ~ 7 ~ A 3 ~ 7.B 3 ~ 7.C 3.7.F Seismic Honitorinq Instrument Surveillance Requirements Reactor Coolant System Inservice Inspection Schedule MAPLHGR vs. Average Planar Exposure Shock Suppressors (Snulihers)
Primary Containment Isolation Valves Testable Penetrations with Double 0-Ring Seals Testable Penetrations with Testable Bellows Primary Containment Testable Isolation Valves Suppression Chamber Influent Lines Stop-Check Globe Valve Leakage Bates Check Valves on, Suppression Chamber Influent Lines 105 le,'16c, l82n 209 262 268 269 279 280
- 3. 7.G 3.7~ H 4 ~ 8. A 4 ~.8. B 6.3.A 6.8.A Check Valves on Drywell Influent Lines Testable Electrical Penetrations Radioactive Liquid Waste Sampling and Analysis Radioactive Gaseous Waste Sampling and Analysis I
Protection Factors for Respirators Hinimum Shift Crew Requirements 281'83 310 311 373 390 vii
LIST OF ILLUSTRATIONS Figure
- 2. 1-1 2 ~ 1-2 4 ~ 1 1
4 ~ 2-1
- 3. 4" 1
- 3. 4-2 Title APRH Flow Reference Scram and APRH Rod Block Settings APRM Flow Bias Scram Relationship to Normal Operating Conditions Graphic Aid in the Selection of an Adequate Interval Between Tests System Unavailability Sodium Pentaborate Solution Volume Concentration Requirements Sodium Pentaborate Solution Temperature Requirements
~ae 25 48 117 141 142 MCPR Limits 182b 3.5.2 3.6-1 3,6" 2 6.1-1
- 6. 1-2
- 6. 2-1 6 ~ 3" 1 Kg Factor vs. Percent Core Flow Temperature-Pressure Limitations Change in Charpy V Temperature vs.
Neutron Exposure TVA Office of Power Organization for Operation of Nuclear Power Plants Functional Organization
, Revie~
and Audit Function In-Plant Fire Program Organization 183 201 202 391 392 393 394
i.