ML20217M266
| ML20217M266 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 04/02/1998 |
| From: | MICHIGAN, UNIV. OF, ANN ARBOR, MI |
| To: | |
| Shared Package | |
| ML20217M258 | List: |
| References | |
| NUDOCS 9804080055 | |
| Download: ML20217M266 (4) | |
Text
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OPERATISG' LICENSE AND TECHNICAL lipECIFICATIONS
- Ford Nuclear Reactor
,* Docket 50-2. License R-28 Amendment 44: proposed i
l 2.1.2 Safety Limits in the Natural Convection Mode Applicability: I This specification applies to the interrelated variables associated with core thermal and hydraulic performance in the natural convection mode of operation. These variables are:
Reactor Thermal power, p 1 l
Reactor Coolant Inlet Temperature, Ti l
t Height of Water Above the Top of the Core, H l
' Objective:
l' To assure that the integrity of the fuel clad is maintained.
l l Specification:
- 1. The true value of the reactor thermal power (p) shall not exceed 380 kw.
- 2. The true value of the reactor coolant inlet temperature (Ti.) shall not exceed 131 oF.
- 3. The height of pool water above the core (H) shall not be less than 18 feet.
Bases:
The basis for natural convection safety limits is that the calculated maximum cladding temperature in the hot channel of the most .
compact FNR c~ ore (25 elements) will not reach the boiling point of the water coolant at a ,
depth of 18 feet.
l 2.2 Limiting Safety System Settings (LSSS) '
i 2.2.1 Limiting Safety System Setting in the Forced Convection Mode
-Applicability:
This specification applies to the set points i for the safety channels monitoring reactor l thermal power ( p), primary coolant flow (m), ;
height of water above the top of the core (H), l44 core exit temperature-(Te) and core inlet
{
i temperature (T1).
l l
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9804000055 900402 2 PDR ADOCK 050 l P
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1 GPERATING LICENSE AND TECHNICAL SPECIFICATIONS
, Ford Nuclear Reactor
.- Docket 50-2, License R-28 Amendment 44: Proposed Objective:
To assure that automatic protective action is i initiated to prevent a safety limit from being exceeded.
Specification:
- 1. The limiting safety syster settings for reactor thermal power (p), primary coolant flow through the core (m), height of water above the top of the core (H), and reactor coolant exit temperature ( T. ) shall be as follows:
Variablg LSSS '
P (Max) 2.60 Mw (39 m (Min) 900 gpm H (Min) 19 ft ;
T.(Max) 129 0F
- 2. The limiting safety system setting for l44 reactor coolant inlet temperature at thermal power levels above 1.6 Mw shall be:
Ti (max) = 114 oF
[44 Bases:
l The limiting safety system settings for forced convection assure that automatic protective action will correct the most severe abnormal situation anticipated before a safety limit is exceeded.
2.2.2 Limiting Safety System Settings in the Natural l Convection Flow Mode i Applicability:
These specifications apply to the setpoint for the safety channels monitoring reactor thermal power (P), pool water level (H), and pool water ,
temperature (T).
Objective:
To assure that automatic protective action is '
initiated to prevent a safety' limit from being exceeded. ;
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OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2 License R-28 Amendment 44: Proposed i
, , Table 3.1 REQUIRED SAFETY CHANNELS Minimum Number Channel Setpoint Heauirea Function Log Count Rate 2 cps 1 Rod Withdrawal Interlock Log N Period 1 Wide range power level, power level l44 interlocks, and input l for period scram Period Safety 5 see 1 Scram Level Safety 122.5% (2.45 Mw) 2 Scram l39
! High Power /No (a) 900 gpm 1 Scram 2100 kw Water Flow (b) holdup tank isolation valve not fully open (c) holdup tank static pressure l 1 psig below full power value High Power /
Header Down 1 Scram 1100 kw Header Up/ 900 gpm 1 Scram No Water Flow i Building Exhaust I mrem /hr 1 Scram Radiation Level
! Buildihg Alarm 1 Scram L Manual Switch Manual Scram Switch- 1 Scram
! Magnet Power Keyswitch 1 Scram Reactor Coolant l44 Inlet Temp. 114 *F 1 Auto Rundown 2 1.6-MW l Reactor Coolant Exit' Temp. 129 'F 1 Auto Rundown Reactor pool 44 Temperature 129 0F 1 Auto Rundown Page 13
. OPERATING LICENSE AND TECHNICAL SPECIFICATIONS Ford Nuclear Reactor Docket 50-2, License R-28 Amendment 44: Proposed
, , Power-flow coincident scrams provide redundant channels to assure that an automatic loss of flow scram will I occur in the event of a loss of flow when the reactor i is operating at power levels above 100 kw. i 1
The rod withdrawal interlock on the Log Count Rate channel assures that the operator has a measuring i channel operating and indicating neutron flux levels l during the approach to criticality. i The reactor coolant inlet temperature, reactor coolant (44 ;
exit temperature, reactor pool temperature auto I runcown functions and the pool level auto rundown assure that the reactor w111 not be operated above the safety limit for core inlet temperature and below the i salety limit for pool level in either natural or 44 I forced connection mode.
The manual scram button and the magnet power keyswitch provide two methods for the reactor operator to j manually shutdown the reactor if an unsafe or abnormal condition should occur and the automatic reactor protection does not function.
The use of the area radiation monitor system assures that areas of the facility in which a high radiation l area could exist are monitored.
Specifications 3.2.2 and 3.2.3 assure that the safety system response will be appropriate.
Mechanical holddown devices specified in 3.2.4 ensure l38 that a fuel element cannot be lifted from the core by withdrawal of a control rod and be released back into the core resulting in a sudden positive reactivity l insertion.
3.3 FNR Confinement Building Applicability:
This specification applies to the Ford Nuclear Reactor confinement building requirements. '
Objective:
To assure that the Ford Nuclear Reactor Building l38 confinement integrity is maintained during reactor operation and to minimize the release of airborne radioactive materials from the reactor building.
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