NUREG-1537, Part 2 - NRC

Page
4 REACTOR DESCRIPTION ............................... 4-1
4.1 Summary Description .............................. 4-1
4.2 Reactor Core ............................... 4-1
4.2.1 Reactor Fuel .............................. 4-2
4.2.2 Control Rods ............................... 4-5
4.2.3 Neutron Moderator and Reflector ............................ 4-7
4.2.4 Neutron Startup Source .................................... 4-9
4.2.5 Core Support Structure ............................... 4-12
4.3 Reactor Tank or Pool ................................ 4-14
4.4 Biological Shield ........... ................... 4-17
4.5 Nuclear Design ........................................ . 4-19
4.5.1 Normal Operating Conditions .............................. 4-19
4.5.2 Reactor Core Physics Parameters ..... .... .................. 4-22
4.5.3 Operating Limits ................. I ............ .... 4-24
4.6 Thermal-Hydraulic Design .............................. 4-26
5 REACTOR COOLANT SYSTEMS ............................. 5-1
5.1 Summary Description .............. ................. 5-2
5.2 Primary Coolant System ................ .............. 5-2
5.3 Secondary Coolant System . .............................. 5-7
5.4 Primary Coolant Cleanup System ............................. 5-10
5.5 Primary Coolant Makeup Water System ............. ........... 5-12
5.6 Nitrogen-16 Control System . ............................... 5-14
5.7 Auxdiary Systems Using Primary Coolant ....................... 5-16
5.8 Reference ............................... 5-18
6 ENGINEERED SAFETY FEATURES ........................... 6-1
6.1 Summary Description ................ .............. 6-4
6.2 Detailed Descriptions . ............................... -4
6.2.1 Confinement .............................. 6-4
6.2.2 Containment .............................. 6-7
6.2.3 Emergency Core Cooling System ............................ 6-11
6.3 References ............................... 6-13
7 INSTRUMETATION AND CONTROL SYSTEMS ...... ......... 7-1
7.1 Summary Description ..................................... 7-2
7.2 Design of Instrumentation and Control Systems ....... ............ 7-3
7.3 Reactor Control System ..................................... 7-3
7.4 Reactor Protection System ................................... 7-9
7.5 Engineered Safety Features Actuation Systems ....... ............ 7-14
7.6 Control Console and Display Instruments ........ ............... 7-16
7.7 Radiation Monitoring Systems ............... ................ 7-20
7.8 References . ....................................... 7-22
VI
REV. O,2J96
NUREG-1537PART2
NUREG-1537,PART2 vi REV. 0,2/96
)