ML20065F896

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Proposed Tech Spec 3/4.7.1.1 Re Max Allowed Reactor Thermal Power Operation W/Inoperable Main Steam Safety Valves
ML20065F896
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 03/31/1994
From:
GEORGIA POWER CO.
To:
Shared Package
ML20065F869 List:
References
NUDOCS 9404120063
Download: ML20065F896 (4)


Text

_ _ _ _

ENCLOSURE 3 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS INOPERABLE MAIN STEAM SAFETY VALVES ,

1 JNTi.TRUCTIONS FOR INCORPORATION AND PROPOSED CHANGES TO THE l TECHNICAL SPECIFICATIONS  !

The proposed change to the Vogtle Electric Generating Plant Technical Specification would be incorporated as follows:

Removed Page Insert Page 3/4 7-l* and 3/4 7-2 3/4 7-l* and 3/4 7-2 B 3/4 7-1 and B 3/4 7-2* B 3/4 7-1 and B 3/4 7-2*

  • Overleaf page containing no change E3-1 9404120063 940331 PDR ADOCK 05000424 '

P PDR .

TABLE 3.7-1  !

MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH j INOPERABLE STEAM LINE SAFETY VALVE 5 MAXIMUM NUMBER OF INOPERABLE MAXIMUM ALLOWABLE POWER RANGE SAFETY VALVES ON ANY NEUTRON FLUX HIGH SETPOINT OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER) 1

  • 71 2 .
  • 51 3
  • 31 I

i l

1 l

V0GTLE UNITS - 1 & 2 3/4 7-2 I _ _ _ . . _ _____ - _ _ _ - , _ .- ._____

1

. [ 3/4.7 PLANT SYSTEMS

~

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 ths.t

the Secondary System pressure will be limited to within 110% (1304 psig) of j its der.ign 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 nssumed loss of condenser heat sink (i.e., no steam bypass to the condenser).

J The specified valve lift settings and relieving capacities are in accordance with the requirements 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,is 18,607,220 lbs/h which is 117% of the total secondary steam flow l l

of 15.92x10 lbs/h at 100% RATED THERMAL POWER. A minimum of two OPERABLE 4

safety valves per steam generator ensures that sufficient relieving capacity is ,

j available for the allowable THERMAL POWER restriction in Table 3.7-1. l I

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 l reduced Reactor trip settings of the Power Range Neutron Flux channels. The Reactor Trip Setpoint reductions are derived on the following basis:

J For four loop operation i SP - (X) - (Y)(V) x 09) x REPLACE NNITH INSENT I

Where:

SP - Redu Reactor Trip Setpoint in ercent of RATED THERMAL P0 R, V - Maximum number of inoper e safety valves per steam ne, 109 Power Range Neutron ux-Hig' ,ip Setpoint for our loop 4

operation,

'X - Total reliev g capacity of all safety ves per steam line in 1 / hour, and Y - Maxi m relieving capacity of an one safety valve in 1 hour.

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

Amendment No.39(Unit 2)

! l

1. <

i .i

- j INSERT FOR BASES 3/4.7.1.1 Hi $ = (100/Q)(Wg htgN)

K where:

Hi $ = Safety Analysis power range high neutron flux setpoint, percent

.Q = Nominal NSSS power rating of the plant (including reactor coolant pump.

heat), MWt K = Conversion factor,947.82 (Btu /s)

MWt ws = Minimum total steam flow rate capability of the operable MSSVs on any l one steam generator at the highest MSSV opening pressure including .

tolerance and accumulation, as appropriate, in Ib/s. For example, if the maximum number ofinoperable MSSVs on any one steam generator is one, then washould be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating pressure, excluding the highest capacity MSSV. If the maximum number ofinoperable MSSVs

- per steam generator is three then wg should be a summation of the capacity of the operable MSSVs at the highest operable MSSV operating l pressure, excluding the three highest capacity MSSVs.

=

hrg Heat of vaporization for steam at the highest MSSV opening pressure l including tolerance and accumulation, as appropriate, Btu /lbm.

l N = Number ofloops in the plant.

l The values calculated must be reduced to acmunt for instrument and channel uncertainties (typically 9 percent power). Therefore, the maximum plam operating power level would then be lower than the reactor protection system setpoint by an appropriate operating margin.

l l

. -. . .,