ML021510294
| ML021510294 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/30/2002 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| TAC MB3478 | |
| Download: ML021510294 (5) | |
Text
NPF-73 INDEX LIMITING CONDITION FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3.3.5 Remote Shutdown Instrumentation .............. 3/4 3-52 3/4.3.3.8 Accident Monitoring Instrumentation .......... 3/4 3-57 3/4.3.3.11 Explosive Gas Monitoring Instrumentation ..... 3/4 3-61 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION 3/4.4.1.1 Normal Operation ............................. 3/4 4-1 3/4.4.1.2 Hot Standby .................................. 3/4 4-2 3/4.4.1.3 Shutdown ..................................... 3/4 4-3 3/4.4.1.4.1 Loop Isolation Valves - Operating ............ 3/4 4-5 3/4.4.1.5 Isolated Loop Startup ........................ 3/4 4-6 3/4.4.3 SAFETY VALVES ................................ 3/4 4-9 3/4.4.4 PRESSURIZER .................................. 3/4 4-10 3/4.4.5 STEAM GENERATORS ............................. 3/4 4-11 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 Leakage Detection Instrumentation ............ 3/4 4-17 3/4.4.6.2 Operational Leakage .......................... 3/4 4-19 3/4.4.6.3 Pressure Isolation Valves .................... 3/4 4-21 3/4.4.8 SPECIFIC ACTIVITY ............................ 3/4 4-27 3/4.4.9 PRESSURE/TEMPERATURE LIMITS 3/4.4.9.1 Reactor Coolant System ....................... 3/4 4-30 BEAVER VALLEY - UNIT 2 V Amendment No. 131
REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 a. At least two reactor coolant loops and associated steam generators and reactor coolant pumps# shall be in operation* when the rod control system is capable of control bank rod withdrawal.
- b. At least two reactor coolant loops and associated steam generators and reactor coolant pumps# shall be OPERABLE and one reactor coolant loop shall be in operation* when the rod control system is incapable of control bank rod withdrawal.
APPLICABILITY: MODE 3**
ACTION:
- a. With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- b. With less than two reactor coolant loops in operation, immediately deenergize all control rod drive mechanisms, or align the rod control system so that it is incapable of control bank rod withdrawal.
- c. With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiatL corrective action to return the required reactor coolant loop to operation.
- All reactor coolant pumps may be deenergized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration and (2) core outlet temperature is maintained at least 10'F below saturation temperature. This does not preclude natural circulation cooldown under abnormal cooldown conditions.
- See Special Test Exception 3.10.4.
- No reactor coolant pump in a non-isolated loop shall be started with one or more non-isolated RCS cold leg temperatures less than or equal to the enable temperature set forth in Specification 3.4.9.3, unless the secondary side water temperature of each steam generator in a non-isolated loop is less than 50'F above each of the non-isolated RCS cold leg temperatures.
BEAVER VALLEY - UNIT 2 3/4 4-2 Amendment No. 131
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.1.2.1 With the rod control system capable of rod withdrawal, at least two cooling loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.4.1.2.2 With the rod control system incapable of rod withdrawal, at least two cooling loops, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.
4.4.1.2.3 With the rod control system incapable of rod withdrawal, at least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
BEAVER VALLEY - UNIT 2 3/4 4-2a Amendment No. 131
REACTOR COOLANT SYSTEM SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.3 a. At least two of the coolant loops listed below shall be OPERABLE.
- 1. Reactor Coolant Loop (A) and its associated steam generator and reactor coolant pump,#
- 2. Reactor Coolant Loop (B) and its associated steam generator and reactor coolant pump,#
- 3. Reactor Coolant Loop (C) and its associated steam generator and reactor coolant pump,#
- 4. Residual Heat Removal Pump (A) and the (A) RHR heat exchanger,**
- 5. Residual Heat Removal Pump (B) and the (B) RHR heat exchanger.**
- b. At least one of the above coolant loops shall be in operation.***
APPLICABILITY: MODES 4 and 5.
ACTION:
- a. With less than the above required loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible; be in COLD SHUTDOWN within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
- b. With Lio coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.
- The normal or emergency power source may be inoperable in MODE 5.
- All reactor coolant pumps and Residual Heat Removal pumps may be deenergized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided: 1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and 2) core outlet temperature is maintained at least 10°F below saturation temperature.
- No reactor coolant pump in a non-isolated loop shall be started with one or more non-isolated RCS cold leg temperatures less than or equal to the enable temperature set forth in Specification 3.4.9.3, unless the secondary side water temperature of each steam generator in a non-isolated loop is less than 50'F above each of the non-isolated RCS cold leg temperatures.
BEAVER VALLEY - UNIT 2 3/4 4-3 Amendment No. 131
REACTOR COOLANT SYSTEM 3.4.1.6 (This Specification number is not used.)
BEAVER VALLEY - UNIT 2 3/4 4-7 Amendment No. 131