ML20065E068

Proposed Tech Specs Involving Change in Pool Coolant Sys Description from Two HX Legs to One HX Leg & Change in Pool Coolant Flow Scram Setpoint to Indicate Measurement of Total Pool Flow Instead of Measurement of Half Pool Flow

ML20065E068
Person / Time
Site:	University of Missouri-Columbia
Issue date:	03/28/1994
From:	MISSOURI, UNIV. OF, COLUMBIA, MO
To:
Shared Package
ML20065E065	List: ML20065E059 ML20065E068
References
NUDOCS 9404070340
Download: ML20065E068 (3)

Text

y g -

J ' ik$ TECHNICAL SPECIFICATION L y'Lds] i _

rn - M[t; F . UNIVERSITY OF MISSOURI

._' N RESEARCH REACTOR FACILITY rp)i = ?

Number 3.3 Page 2 of- 5

.Date '

m

SUBJECT:

Reactor Safety System (continued)

Pool Coolant Flow 2 1 0 425(4) gpm (Min) for each 50% . 7

- capacity heat exchanger leg -

850(4) gpm (Min) for one 100%

capacity heat exchanger -

Differential Pressure Across 2.52 psi (Min)

Reflector 1 0 0 8.00 psi (Max)

Differential Pressure Across 0.63 psi (Min)

Reflector 0 1 0 2.00 psi (Max)

Differential Pressure Across Core 1 0 0 3200(5) gpm (Min) .

Differential Pressure Across Core 0 1 1(2) 1600(5) gpm (Min)

Pressurizer High Pressure 1 1 1(2) 95 psia (Max)

Pressurizer Low Level 1 1 1(2) 16 inches below centerline'(Min) '

Pool Level 0 0 '1- 23 feet (Min)

Primary Coolant Isolation Valves 507A/B Off Open Either valve Position 1 1 1(2) Off Open Position Pool Coolant Isolation

. Valve 509 Off Open Valve 509 Off Open -

Position 1 1 0 Position t .-

Power Level Interlock 1 1 1- Scram as a result ofincorrect .

selection of operating mode.

Facility Evacuation 1 1 1 Scram as a result of actuating-facility evacuation system Reactor Isolation '1 1 1 Scram as a result of actuating reactor isolation system 9404070340 940320 PDR -ADOCK'05000186 P- PDR- ,_

a

w -.

"^

gz TECHNICAL SPECIFICATION; p< 7 g; 8 e x

• Q l#

(k UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY

• Q,/

l Number 3.3 i Page 3 of 5 Date

SUBJECT:

Reactor Safety System (continued)

Manual Scram 1 1 1 Push Button at Control Consolo (1) Flow orifice or heat exchanger AP (psi)in each operating heat exchanger leg corresponding to the flow value in the table.

(2) Not required below 50 KW operation if natural convection flange and pressure vessel cover are removed or in operation with the reactor suberitical by a margin of at least 0.015 AK.

(3) Trip pressure is that which corresponds to the pressurizer pressure indicated

l. in the table with normal primary coolant flow.

(4) Flow orifice AP (psi) corresponding to the flow value in the table.

(5) Core AP (psi) corresponding to the core flow value in the table.

Bases

a. The specifications on high power, primary coolant flow, primary coolant pressure, and reactor inlet temperature provide for the safety system settings outlined in specifications 2.2.a,2.2.b, and 2.2.c. In Mode I and II operation the core differential temperature is approximately 17 F d

me

+ '

s R:;.t .. TECHNICAL SPECIFICATION es 'l rf( *NTt; #j UNIVERSITY OF MIS.SOURI

' '4 RESEARCH REACTOR FACILITY p y D Number 4.4 Page 1- of 3 Date v

SUBJECT:

Reactor Coolant System N Annlicability f

This specification shall apply to the reactor coolant systems.

Obiective It is the objective of this specification to assure proper coolant for safe operation.

Specification

a. The reactor coolant system shall consist of not less than a reactor pressure vessel, two primary system pumps, primary pressurizer, two primary heat exchangers, two pool system pumps, one 100% capacity or two 50% capacity.

pool system heat exchanger (s), and one pool system hold-up tank plus all associated piping and valves.

b. The reactor coolant system shall have one secondary coolant system capable of-continuous discharge of heat generated at the operating power of the reactor,

c. The pumps and heat exchangers in the primary system shall constitute two parallel systems separately instrumented to permit safe operation at five megawatts on either system or ten megawatts with both systems operating

? simultaneously. .3 J

aY