ML20072F378

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Re Setpoint Tolerance for Main Steam Safety Valves
ML20072F378
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 08/16/1994
From:
GEORGIA POWER CO.
To:
Shared Package
ML20072F218 List:
References
NUDOCS 9408230317
Download: ML20072F378 (4)


Text

_____ _ __ _ __-___ _____-_____ __-_________________ _______ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _

3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line Code safety valves associated with each steam-generator shall be OPERABLE with lift settings *as specified in Table 3.7-2.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With four reactor coolant loops and associated steam generators in operation and with one or more main steam line Code safety valves inoperable, operation in MODES 1, 2, and 3 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 is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint (NI-0041B&C, NI-0042B&C, NI-0043B&C, NI-0044B&C) is reduced per Table 3.7-1; otherwisa, be in at least 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 in COLD SHDTD0WN within the following 30 Nurs.
b. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional requirements other than those required by Specification 4.0.5.

See Insert A 9408230317 940816 POR ADOCN 05000424 j P PDH l V0GTLE UNITS - 1 & 2 3/4 7-1 l

TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP LIFT SETTING VALVE NUMBER (*-45)*- ORIFICE SIZE SG-1 SG-2 SG-3 SG-4  ! )~ 0

1. PSV 3001 PSV 3011 PSV 3021 PSV 3031 1185 psig 16.0 in z
2. PSV 3002 PSV 3012 PSV 3022 PSV 3032 1200 psig 16.0 in8
3. PSV'3003 PSV 3013 PSV 3023 PSV 3033 1210 psig 16.0 in8
4. PSV 3004 PSV 3014 PSV 3024 PSV 3034 1220 psig 16.0 in8
5. PSV 3005 PSV 3015 PSV 3025 PSV 3035 1235 psig 16.0 in t A

N

  • The lift setting pressure shall correspond to ambient conditions of the valve at ' nominal operating temperature and pressure.

V0GTLE UNITS - 1 & 2 3/4 7-3

3/4.7 PLANT SYSTEMS l BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line Code safety valves ensures that the. Secondary System pressure will be limited to within 110% (1304 psig) of its design pressure of 1185 psig during the most severe anticipated system-operational transient. The maximum relieving capacity is associated with a Turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., no steam bypass to the condenser).

I See Insmet 8 The specified val e lift settings and relieving capacities are in accordance with the uirements of Section III of the ASME Boiler and Pressure Code, 1974 Edition. The total relieving capacity for all valves on all of-the steam lines lbs/h which is 117% of. the total secondary steam: flow of 15.92x10'is 18,607,220lbs/h at 1005 RATED THERMAL POWER. A minimum of t '

safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Table 3.7-1.

STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in Secondary Coolant System steam flow and THERMAL POWER required by the reduced Reactor trip settings of the Power Range Neutron Flux channels. The Reactor Trip Setpoint reductions are derived on the followi.1g basis:

i For four loop operation j

SP - (X) - (Y)(V) x (109)

X l

Where:

SP - Reduced Reactor Trip Setpoint in percent of RATED THERMAL-POWER, V - Maximum number of inoperable safety valves per steam line, 109 - Power Range Neutron Flux-High Trip Setpoint for four loop operation, X - Total relieving capacity of all safety valves per steam line in 1bs/ hour, and Y - Maximum relieving capacity of any one safety valve in 1bs/ hour.

t V0GTLE UNITS - 1 & 2 B 3/4 7-1 Amendment No.60(Unit 1)

Amendment No.39(Unit 2)

INSERT A

  • All valves tested must have "as-leR" lift setpoints that are within 11% of the lia setting values in Table 3.7-2.

INSERTB The safety valves are tested in accordance with the requirements of Section XI of the ASME Code. The lift setting allowable values are consistent with the safety analysis. In the event a safety valve lifts outside of the tolerances specified in Table 3.7-2, the Section XI provisions of adjusting the setpoint and testing additional valves applies. When tested, the as-left setting will be within il% of the specified set pressure.

I l

l l