ML20212B091
| ML20212B091 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/24/1987 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20212B018 | List: |
| References | |
| NUDOCS 8703030474 | |
| Download: ML20212B091 (3) | |
Text
TABLE OF CONTENTS Section Page 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 Limiting Safety System Settings. Protection Instrumentation 2-5 3
LIMITING CONDITIONS FOR OPERATION 3-1 3.0 General Action Requirements 3-1 3.1 Reactor Coolant System 3-l a 3.1.1 Operational Components 3-l a 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 Tenperature Coefficient of Reactivity 3-16 3.1.8 Single Loop Restrictions 3-17 3.l.9 Low Power Physics Testing Restrictions 3-18 3.1.10 Control Rod Operation 3-18a 3.1.11 Reactor Internal Vent Valves 3-18b 3.1.12 Pressurizer Power Operated Relief Yalve (PORV) 3-18c and Block Valve 3.1.13 Reactor Coolant System Vents 3-18f 3.2 Makeup and Purification and Chemical Addition Systems 3-19 3.3 Emergency Core Cooling, Reactor Building Emergency Cooling, 3-21 and Reactor Building Spray Systems 3.4 Decay Heat Removal Capability 3-25 3.4.1 Reactor Coolant System Terrperature Greater Than 250*F 3-25 3.4.2 Reactor Coolant System Tenperature 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 Setpoints 3-37 3.5.4 Incore Instrumentation 3-38 3.5.5 Accident Monitoring Instrumentation 3-40a 3.5.6 Chlorine Detection Systems 3-40f l
l 3.6 Reactor Building 3-41 3.7 Unit Electrical Power System 3-42 3.8 Fuel Loading and Refueling 3-44 3.9 Radioactive Materials 3-46 3.10 Miscellaneous Radioactive Materials Source 3-46 3.11 Handling of Irradiated Fuel 3-55 3.12 Reactor Building Polar Crane 3-57 3.13 Secondary System Activity 3-58 3.14 Flood 3-59 l
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 11 Amendment No. $$, 77, 7S, 97, $3, 119, 122 Q 3]$$h $$$$$s9 PDR p
r 3.5.6 CHLORINE DETECTION SYSTEMS Applicability All modes of operation, when chlorine containers exceeding 150 pounds are located onsite.
Objective To ensure that the Chlorine Detection Systems (CDS) located at the River Water Pucp House Chlorinator House and at the Air Intake Structure are capable of providing alarm in the control room and isolating the control room in the event of an onsite chlorine gas release.
Specification 3.5.6.1 Two independent chlorine detection system channels at each of the above locations, shall be Operable.
Each channel shall be capable of initiating isolation of the control building ventilation system and providing alarms which allow operators 2 minutes to don emergency breathing apparatus.
Action 3.5.6.2 a.
With one chlorine detection system channel at either location inoperable, restore the inoperable channel to OPERABLE status within 7 days.
If not restored to OPERABLE status within 7 days, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and maintain operation of the control building ventilation system in the emergency recirculation mode of operation.
b.
With both chlorine detection system channels at any one location inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control building ventilation system in the emergency recirculation mode of operation.
Bases The Operability of the chlorine detection system ensures that sufficient capability is available to pronptly detect and initiate protective action in the event of an accidental chlorine release. This capability is required to protect control room personnel (and satisfies the intent of Regulatory I
Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," Revision 1, January 1977.)
The Chlorine Detection System is designed so that the human toxicity limits of 15 ppm by volume (45 mg/m3) is not exceeded in the control room within 2 minutes after the operators are made aware of the presence of chlorine.
3-40f l
F g
TABLE 4.1-1 (Centinund) g.
3e E
CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS 5
((
49.
Saturation Margin Monitor S(l)
M(1)
R (1) When Tave is greater than 525*F.
50.
Emergency Feedwater Flow NA M(1)
R (1) When Tave is greater than 250*F.
Instrunentation 51.
Emergency Feedwater Initiation a.
Loss of RCPs NA Q(1)(2)
R (1) When Tave is greater than 250*F.
b.
Loss of Both Feedwater Purps NA Q(1)(2)
R (2) Includes logic test only.
52.
Backup Incore Thermocouple M(1)
NA R
(1) When Tave is greater than 250*F.
Display
- 53. Chlorine Detection System W
M R(1)
(1) Calibration is a one concentration Instrumentation point check (need not be traceable to NBS standards)
?U S - Each Shift T/W - Twice per week R - Each Refueling Period D - Daily B/M - Every 2 months HA - Not Applicable W - Weekly Q - Quarterly B/W - Every two weeks M - Monthly P - Prior to each startup if not done previous week