ML17352A732
| ML17352A732 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 07/19/1994 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17352A731 | List: |
| References | |
| NUDOCS 9407210341 | |
| Download: ML17352A732 (7) | |
Text
ATTACHMENT 3 PROPOSED TECHNZCAL SPECZFZCATZONS Marked-up Technical Specification Pages:
3/4 7-1 3/4 7-2 B 3/4 7-1 Xnsert "A" to page 3/4 7-1 940721 OCK 05000250 10541 940719 PDR ADO
. P.
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 I, 2, and S.+
ACTION:
With (3) 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 in-operable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7"1; otherwise, 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 SHUTDOWN within the following 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> s.
SURVEILLANCE RE UIREMENTS 4.7.1.1 No additional requirements other than those required by Specification
- 4. 0. 5.
l:n Mode 3, when the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.
TURKEY POINT - UNITS 3 8
4 3/4 7-1 AMENDMENT NOS.137 AND 132
h
~5 WQL~/$
I lpga /~
P
TABLE 3. 7" 1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAN LIN SAFETY VALVES DURING HREE LOOP OP RA ION HAXIMUH NUMBER OF INOPERABLE SAFETY VALVES ON ANY OPERATING STEAM GENERATOR MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT PERCENT OF RATED THERHAL POWER VALVE NUMBER TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP LIFT SETTING ilX "
ORIFICE SIZE S
UARE INCHES
~Loo A
~Loo B
~Loo C
1.
RV1400 RV1405 RV1410 2.,
RV1401 RV1406 RV1411 3.
RV1402 RV1407 RY1412 4.
RV14D3 RV140B RV1413 1085 psig 1100 psig 1115 psig 1130 psig 16 16 16 "The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
TURKEY POINT - UNITS 3 & 4 3/4 7"2
.A'-)ENDHENT NOS.I37 AND 132
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 that the Secondary System pressure will be limited to within 110'1193.5 psig) of its design pressure of 1085 psig during the most.severe anticipated system opera-tional transient.
The maximum relieving capacity is associated with a Turbine trip from 100K RATED THERMAL POWER coincident with an assumed loss of condenser heat sink {i.e.,
no steam bypass to the condenser).
The specified valve lift settings and relieving capacities are in accordance with the requirements of Section VIII of the ASME Boiler and Pressure
'Code, 1971 Edition.
The total relieving capacity for all valves on all of the steam lines is 10,670,000 lbs/h which is 111K of the total secondary steam flow of 9,600,000 lbs/h at 100K RATED THERMAL POWER.
A minimum of one, OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Table 3. 7-2.
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 following bases:
Where:
).
.. x {109)
RFPt AeC
~t~H t~
sCav'P Reduced Reac r Trip Setpoint in percent of RATED THE AL POWE 09 Maximum nu er of inoperabl safety valv per ste
- line, Power R
ge Neutron Flux-gh Trip Set
- int, Total elieving capacit of all safe valves p r steam line in lbs/hour, and M
imum relieving ca acity of any one safety valve in bs/hour 3/4. 7. 1. 2 AUXILIARYFEEDWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 3504F from normal operating conditions in the event of a total loss-of-offsite power.
Steam can be TURKEY POINT " UNITS 3 8 4 B 3/4 7-1 AMENDMENT NOS.137 AND 132
L-94-176 Attachment 3
INSERT FOR BASES 3 4.7.1.1 Hi $ = (100/Q) s fg K
where:
Hi g Safety Analysis power range high neutron flux
- setpoint, percent Nominal Nuclear Steam Supply System (NSSS) power rating of the plant (including reactor coolant pump heat),
MWt K
Conversion factor; 947.82 (Btu/sec)/MWt ws Minimum total steam flow rate capability of the operable MSSVs on any one steam generator at the highest MSSV opening pressure (including tolerance and accumulation)
(Lbm/sec).
For example, if the maximum number of inoperable MSSVs on any one steam generator is one, then ws should 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 of inoperable MSSVs per steam generator is three, then ws should be a summation of the capacity of the operable MSSV at the highest operable MSSV operating pressure, excluding the three highest capacity MSSVs.
hfg Heat of vaporization for steam at the highest MSSV opening pressure (including tolerance and accumulation)
(Btu/ibm)
N Number of loops in plant The values calculated from this algorithm must then be adjusted lower for use in TS 3.7.1.1 to account for instrument and channel uncertainties.
The maximum plant operating power level would then be lower than the reactor protection system setpoint by an appropriate operating margin.
V S4