ML19262C695
| ML19262C695 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/06/1980 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19262C672 | List: |
| References | |
| NUDOCS 8002150424 | |
| Download: ML19262C695 (4) | |
Text
/7 ATTACHMENT 4
REFERENCE:
ITEM 6 C7l 8002150 4-l 1
3.0 LIMITING CONDITIONS FOR OPERATION 3.1 REACTOR COOLANT SYSTEM Aoplicability Applies to the operating status of the reactor coolant system.
Objective To specify those limiting conditions for operation of the reactor coolant system which must be met to ensure safe reactor operations.
3.1.i Operational Components Speciication 3.1.1.1 Reactor Coolant Pumps A.
Pump combinations permissible for given power levels shall be as shown in Table 2.3-1.
B.
The boron concentration in the reactor coolant system shall not be reduced unless at least one reactor coolant pump or one decay heat renoval pump is circulating reactor coolant.
3.1.1.2 Steam Generator One steam generator shall be operable whenever the reactor coolant average temperature is above 280F.
3.1.1.3 Pressurizer Safety Valves A.
The reactor shall not remain critical unic s both pressurizer code safety valves are operable.
B.
When the reactor is subcritical, at least one pressurizer code safety vaive shall be operable, if all reactor coolant system openings are closed, except for hydrostatic tests in accord-ance with ASME Boiler and Pressure Vessel Code,Section III.
3.1.1.4 Reactor Internals Vent Valves 21 The structural integrity and operability of the reactor internals vent valves shall be maintained at level consistent with the acceptance criteria in Specification 4.1.
Amendment 21 16
3.1.1.5 Pressurizer Electromatic Relief Valve A.
The pressurizer electromatic relief valve (ERV) should be oper-ational and unisolated when the reactor coolant system pressure is above the low reactor coolant system pressure trip setpoint specified in Table 2.3-1.
C.
If the requirements of Specification 3.1.1.5.A are not met for more than a 24-hour period, a special report on the status of tha ERV shall be submitted in the same manner as those events in Specification 6.12.3.1.
Amendment iga
Ba s e_s_
A restor coolant pump or decay heat removal pump is required to be in opera-tion before the boron concentration is reduced by dilution with makeup water.
Either pump will provide mixing which will prevent sudden positive reactivity changes caused by dilute coolant reaching the reactor. One decay heat removal pump will circulate the eauivalent of the reactor coolant system volume in one half hour or less.
(l)
The decay heat removal system suction piping is designed for 300F thus, the system can remove decay heat when the reactor coolant system is below this temperature. (2,3)
One pressurizer code safety valve is ca;.
le of preventing overpressurization when the reactor is not critical since its relieving capacity is greater than that required by the sum of the available heat sources which are pump energy pressurizer heaters, and reactor decay heat.
(4) Both pressurizer code safety valves are required to be in service prior to criticality to ccnform to the The) code safety valves prevent everpres-system design relief capabilities.
(5 The pressurizer code safety valve sure for a rod withdrawal accident.
lif t set point shall be set at 2500 psig + 1 percent allowance for error and each valve shall be capable of relieving 300,000 lb/h of saturated steam at a pressure not greater than 3 percent above the set pressure.
26 The internals vent valves are provided to relieve the pressure generated by steaming in the core following a LOCA so that the core remains sufficiently covered.
Inspection and manual actuation of the internals vent valves (l) ensure operabiljty, (2) ensure that the valves are not open during normal operation, and (3) demonstrate that the valves begin to open and are fully open at the forces equivalent to the differential pressures assumed in the safety analysis.
The electromatic relief valve (ERV) is provided as overpressure protection for the reactor coolant system, but no credit is taken for its operation in the safety analysis.
However, failure of the ERV in the open position can be a major contributor to loss of inventory in the primary coolant.
REFERENCES (1)
FSAR, Tables 9-10 and 4-3 through 4-7.
(2)
FSAR, Section 4.2.5.1 and 9.5.2.3.
(3)
FSAR, Section 4.2.5.4.
(4)
FSAR, Section 4.3.10.4 and 4.2.4.
(5)
FSAR, Section 4.3.7.
Amendment No. 21, 2 17