ML20012G571

Proposed TS Re Limiting Safety Sys Settings for Neutron Flux,Control Rod Block & Reactor High Pressure Safety Valve Initiation

ML20012G571
Person / Time
Site:	Oyster Creek
Issue date:	03/03/1993
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20012G567	List: ML20012G566 ML20012G570 ML20012G571
References
NUDOCS 9303090268
Download: ML20012G571 (2)

Text

. _ - _.

l FUNCTION LIMITING SAFETY SYSTEM SETTINGS  :

B. Neutron Flux, Control Rod Block The Rod Block setting shall be .!

FRP S 5 [(0.90 x 10~') W + 53.1] [MFLPD]

with a maximum setpoint of 108% for core flow equal to 61 x 10' lb/hr and greater.

The definitions of S. W, FRP and MFLPD used above'for'the APRM scram trip apply. l .

I The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than 1.0, in which case  ;

the actual operating value will be used. i This adjustment may be accomplished by increasing the APRM gain and thus reducing the flow referenced-APRM rod' block  ;

curve by the rec.iprocal of the APRM gain change.  ;

C. Reactor High, 51060 psig Pressure, Scram j D. Reactor High Pressure, 2 0 5 1070 psig Relief Valves Initiation 3 @ 5 1090 psig E. Reactor High Pressure, 51060 psig with time delay-Isolation Condenser <3 seconds 1 Initiation i F. Reactor High Pressure, 4 0 1212 psig 112 psi l Sai~ety Valve Initiation 5 @ 1221 psig 112 psi -l i G. Low Pressure Main Steam 1825 psig (initiated in IRM Line, i MSIV Closure range 10) l 1

H. Main Steam Line Isolation 510% Valve Closure from

. Valve Closure, Scram full open I. Reactor Low Water Level, 211'5" above the top of the Scram active fuel as indicated.under  ;

normal operating conditions J. Reactor Low-Low Water 17'2" above the top of the ,

Level, Main Steam Line active fuel as indicated under -!

Isolation Valve Closure normal operating conditions- l t

OYSTER CREEK 2.3-2 Amendment No. 73, 75, 111, 150 9303090268-930303 PDR- ADOCK 05000219  ;

p -PDR l

p

, i

}

-4.3 REACTOR COOLANT l J

Apolicability: Applies to the surveillance requirements for the reactor l coolant system. .j Ob.iective: To determine the condition of the reactor. coolant system and the operation of the safety-devices related to it.

Specification: A. Materials surveillance specimens and neutron flux monitors shall be installed in the reactor vessel adjacent to the wall at the midplane of the active .

core. Specimens and monitors shall be periodically I removed, tested, and evaluated to determine the effects ,

of neutron fluence on the fracture toughness of the

• vessel shell materials. The results of these ,

evaluations shall be used to assess the adequacy of the  !

P-T curves (a),(b) and (c) in Figure 3.3.1. New curves  ;

shall be generated as required.

B. Inservice inspection of ASME Code Class 1, Class 2 and Class 3 systems and components shall be performed in accordance with Section XI of the ASME Boiler and  !'

Pressure Vessel Code and applicable Addenda as required by 10 CFR, Section 50.55a(g), except where specific  !

written relief has been granted by the NRC pursuant to i 10 CFR, Section 50.55a(g)(6)(i).  ;

C. Inservice testing.of ASME Code Class 1, Class 2 and' Class 3 pumps and valves shall be performed in l accordance with Section XI of the ASME Boiler and ,

Pressure Vessel Code'and applicable Addenda as. required by 10 CFR, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to "

10 CFR, Section 50.55a(g)(6)(i).

D. A visual examination-for leaks shall be made with the~ -;

reactor coolant system at pressure during each i scheduled refueling outage or after major repairs have been made to the reactor coolant system in accordance with Article 5000,Section XI. The requirements of ,

specification 3.3.A shall be met during the test.

E. Each replacement safety valve or valve that has been  !

repaired shall be tested in accordance with subsection IWV-3510 of Section XI of the ASME Boiler and Pressure Vessel Code. Setpoints shall be as follows: [ .

Number of Valves let Points (osio)-

4 1212 f 12 i 5 1221 12 l F. A sample of reactor coolant shall be analyzed _at least  !

every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the purpose of determining the  !

content of chloride ion and to check the conductivity. -l OYSTER CREEK 4.3-1 Amendment No.: 82,_90, 120, 150, 151 i

t

- - - - - , , , , , . . , u