ML17333A422

Revised Proposed Ts,Moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1

ML17333A422
Person / Time
Site:	Cook
Issue date:	04/08/1996
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17333A421	List: ML17333A420 ML17333A422
References
NUDOCS 9604150254
Download: ML17333A422 (2)

Text

"4 3/4 LIMFllNGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITINGCONDITION FOR OPERATION 3.7.1.1 Allmain steam line code safety valves associated with each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODES 1 & 2: With 4 reactor coolant loops and associated steam generators in operation, and with one or more main steam line code safety valves inoperable, operation may proceed provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve(s) are restored to OPERABLE status, or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and comply with action statement b.

MODE 3: With a minimum of 3 reactor coolant loops and associated steam generators in operation, and with one or more main steam line code safety valves associated with an operating loop inoperable, operation may proceed provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve(s) are restored to OPERABLE status, or the reactor trip breakers are opened; otherwise, be in HOT SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

I The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE in accordance with Specification 4.0.5 and with liftsettings as shown in Table 4.7-1. The safety valve shall be reset to the nominal value J1% whenever found outside the +1% tolerance. 'he provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

9604150254 960408 PDR ADOCK 05000315 P PDR COOK NUCLEAR PLANT-UNIT 1 Page 3/4 7-1 AMENDMENT420, 444, QQ

e 1

~ gl>

'I 3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITINGCONDITION FOR OPERATION 3.7.1.1 Allmain steam line code safety valves associated with each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODES 1 & 2: With 4 reactor coolant loops and associated steam generators in olieration, and with one or more main steam line code safety valves inoperable, operation may proceed provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve(s) are restored to OPERABLE status, or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and comply with action statement b.

b. MODE 3: With a minimum of 3 reactor coolant loops and associated steam generators in operation, and with one or more main steam line code safety valves associated with an operating loop inoperable, operation may proceed provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve(s) are restored to OPERABLE status, or the reactor trip breakers, are opened; otherwise, be in HOT SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.7.1.1 Each main steam line code safety valve shall be demonstrated OPERABLE in accordance with Specification 4.0.5 and with liftsettings as shown in Table 4.7-1. The safety valve shall be reset to the nominal value +1% whenever found outside the ~1% tolreance. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 7-1 AMENDMENT82, ~