ML20058F766
| ML20058F766 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/02/1993 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20058F734 | List: |
| References | |
| NUDOCS 9312080273 | |
| Download: ML20058F766 (3) | |
Text
'.
TABLE OF CONTENTS Section Pace 2
SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 2.1 Safety Limits. Reactor Core 2-1 2.2 Safety Limits. Reactor System Pressure 2-4 2.3 Limitina Safety System Settinos. Protection Instrumentation 2-5 3
LIMITING CONDITIONS FOR OPERATION 3-1 3.0 General Action Reauirements 3-1 3.1 Reactor Coolant System 3-la 3.1.1 Operational Components 3-la 3.1.2 Pressurization, Heatup and Cooldown Limitations 3-3 3.1.3 Minimum Conditions for Criticality 3-6 3.1.4 Reactor Coolant System Activity 3-8 3.1.5 Chemistry 3-10 3.1.6 Leakage 3-12 3.1.7 Moderator Temperature Coefficient of Reactivity 3-16 3.1.8 Single Loop Restrictions 3-17 3.1.9 Low Power Physics Testing Restrictions 3-18 3.1.10 Control Rod Operation 3-18a 3.1.11 Reactor Internal Vent Valves 3-18c 3.1.12 Pressurizer Power Operated Relief Valve (PORV) and Block Valve 3-18d 3.1.13 Reactor Coolant System Vents 3-18f 3.2 Makeup and Purification & Chemical Addition Systems 3-19 3.3 Emeroency Core Coolina. Reactor Buildina Emeroency Coolina and Reactor Buildina Spray Systems 3-21 3.4 Decay Heat Removal Capability 3-25 3.4.1 Reactor Coolant System Temperature Greater than 250 F 3-25 3.4.2 Reactor Coolant System Temperature 250"F or less 3-26 3.5 Instrumentation Systems 3-27 3.5.1 Operational Safety Instrumentation 3-27 3.5.2 Control Rod Group and Power Distribution Limits 3-33 3.5.3 Engineered Safeguards Protection System Actuation Setpoints3-37 3.5.4 Incore Instrumentation 3-38 3.5.5 Accident Monitoring Instrumentation 3-40a 3,5.6 Deleted 3-40f 3.6 Reactor Buildina 3-41 3.7 Unit Electrical Power System 3-42 3.8 fuel loadina and Refuelina 3-44 3.9 Deleted 3-46 3.10 Miscellaneous _ Radioactive Materials Sources 3-46 3.11 Handlina of Irradiated Fuel 3-55 3.12 Reactor Buildina Polar Croae 3-57 3,13 Secondary System Activity 3-58 3.14 Flood 3-59 3.14.1 Periodic Inspection of the Dikes Around TMI 3-59 3.14.2 Flood Condition for Placing the Unit in Hot Standby 3-60 3.15 Air Treatment Systems 3-61 3.15.1 Emergency Control Room Air Treatment System 3-61 3.15.2 Reactor Building Purge Air Treatment System 3-62a 3.15.3 Auxiliary and Fuel Handling Building Air Treatment System 3-62c 3.15.4 Fuel Handling Building ESF Air Treatment System 3-62e ii Amendment No. ES, 72, 7E, S/, SE, JJS, J27, JJE, JfS, 167 9312000273 931202 ADOCK 0500 gDR
t t
3.5.6-Deleted 1
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l TABLE 4.1-1 (Continued) t CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS
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- 49. Saturation Margin Monitor S(l)
M(1)
R (1)When T is greater than 525"F.
m 50.
Emergency Feedwater Flow NA M(1)
F (1)When T is greater than 250"F.
m j
Instrumentation a
- 51. Heat Sink Protection System 2
a.
EFW Auto Initiation (1) Includes logic test only.
P Instrument Channels w
- 1. Loss of Both Feedwater NA
-Q(1)
F Pumps
' 2. Loss of All RC Pumps NA Q(1)
R
~3?
- 3. Reactor Building NA Q
F
- y Pressure g
- 4. OTSG Low Level W
Q R
b.
R
~
M Pressure O
c.
EFW Control Valve Control
?
System
- 1. OTSG Level loops W
Q R
~
O
- 2. Controllers W
NA R
4 g
d.
HSPS Train Actuation Logic NA Q(1)
R
- 52. Backup Incore Thermocouple M(1)
NA R
(1)When T is greater than 250 F.
m Display
- 53. Deleted i
54.
RCS Inventory Trending System a.
Level NA NA F
b.
Void Fraction W
NA F
.