ML20141D855

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Revising TS Tables 3.7-1 & 3.7-2 by Changing MSSVs Orifice Size from 26 Inches to 28.27 Inches & Relocating Orifice Size from TS to TS Bases
ML20141D855
Person / Time
Site: Waterford Entergy icon.png
Issue date: 06/26/1997
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20141D854 List:
References
NUDOCS 9706300041
Download: ML20141D855 (7)
v • d • e


Text

.. _ _ . - _ _ _ =_, . . . _ _ _ . _ . . . _ _ _ . . _ - . . . _ _ . .__. . _ _ . . _ _ . . _ _ _ _ _ _ .

i l

TABLE 3.7-1 i

STEAM LINE SAFETY VALVES PER LOOP VALVE NUMBER LIFT SETTING f 3%)* ORIFICE SIZE -

Line No. I Line No. 2  !

a. 2MS-R613A 2NS-R6198 1070 psig 26 in*

(MS-106A) (MS-lG68)  ;

i

b. 2MS-R614A 2MS-R6208 1085 psig 26 in*  !

(MS-108A) (MS-1088)

c. 2MS-R615A 2MS-R6218 1100 psig 26 in a (MS-Il0A) (MS-Il08) 1
d. 2MS-R616A 2MS-R6228 1115 psig 26 in a (MS-Il2A) (MS-Il28)
e. 2M5-R617A 2MS-R6238 1125 psig 26 in* i (MS-Il3A) (MS-ll38)
f. 2MS-R618A 2MS-R6248 1135 psig 26 in* i (MS-Il4A) (MS-Il48)
  • The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

I WATERFORD - UNIT 3 3/4 7-2 Amendment No.111 9706300041 970626 r PDR ADOCK 05000382  ;

P PDR

~

. _ . .- - _ . -. = _ . _ - _ = _ _

. . . ~ . ~ - . - . - - - - - - - - - - _ - _ - - - - - - - - _ _ - - - - - - - - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - _ _ _ _ _ _ _ _ _ - - - - _ -

i

~

TABLE 3.7-2 ,

I MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE .

STEAM LINE SAFETY VALVES DURING OPERMION WITH BOTH STEAM GENERATORS MAXIMUM ALLOWABLE LINEAR POWER t i

MAXIMUM NUMBER OF INOPERABLE SAFETY LEVEL-HIGH TRIP SETPOINT VALVES ON ANY OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER) l 86.8 f

2 69.4 i 3 52.1 WATERFORD - UNIT 3 3/4 7-3 Amendment No. III e _ - _ - - - - _-_ _____ - _ _ -__---______- _ ______ _ _ -__ __________

l .

. I i

1 l 3/4.7 PLANT SYSTEMS i l I

j BASES i 4 ,

4 l

4 3]4.7.1 TURBINE CYCLE 315.7.1.1 SAFETY VALVES j j The OPERA 8ILITY of the main steam line code safety valves ensures that l 4

the secondary system pressure will be limited to within 110% (1210 psia) of its design pressure of 1100 psia during the most severe anticipated system i' 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 c;ndenser).
The specified valve lift settings and relieving capacities are in i

accordance with the requirements of Section III of the ASME Boiler and Pressure Vessel Code, 1974 Edition. The total relieving capacity for all- valves on all 4

of the steam lines is 16.267 x 10' lb/hr (at 1210 psia design pressure less 50 psi i pressure drop to the inlet of the valves) which is 104.2% of the total secondary steam flow plus 2% uncertainties of 15.61 x 10' lb/hr at 100% RATED THERMAL POWER.

{ A minimum of 2 OPERA 8LE safety valves per steam generator ensures that sufficient l relieving capacity is available for removing decay heat.

! STARTUP and/or POWER OPERATION is allowable with safety valves inoperable l within the limitations of the ACTION requirements on the basis of the reduction ,

! in secondary system steam flow and THERMAL POWER required by the reduced l r

reactor trip settings of the Power Level-High channels. The reactor trip '

l .setpoi nt reduct iont ar,e derived on the following bases:

1 For two-loop 4 pump operation SP = 6-"

6 x 104.2%

where:  !

SP = reduced reactor trip setpoint in percent of RATED THERMAL POWER N = maximum number of inoperable safety valves per steam line 104.2 = the ratio of the total relieving capacity of all 12 main steam safety valves divided by the secondary steam flow at 100% Rated Thermal Load, plus 2% uncertainty.

WATERFORD - UNIT 3 8 3/4 7-1

.t

I I

l l

l I

l . ,

I l

l l \

i l l I 1

i

! \

l l

NPF-38-199 1

l ATTACHMENT B l 1

1 l

l I

l i

I I

I

[

J

_ -- - ---- - - -- - - - ---- - --- - - - - . = - - - - -

TABLE 3.7-1 ,

STEAM LINE SAFETY VALVES PER LOOP VALVE NUMBER LIFT SETTING (i 3%)*-OR4FICE-SIZE l Line No.1 Line No. 2

a. 2MS-R613A 2MS-R619B 1070 psig 264n2 l  ;

(MS-106A) (MS-106B)

b. 2MS-R614A 2MS-R620B 1085 psig 26-in2 l (MS-108A) (MS-1088)
c. 2MS-R615A 2MS-R621B 1100 psig 2&in2 l (MS-110A) (MS-110B) ,
d. 2MS-R616A 2MS-R622B 1115 psig 26-in2 l '

(MS-112A) (MS-1128)

e. 2MS-R617A 2MS-R623B 1125 psig 2&4n2 l (MS-113A) (MS-113B) ,
f. 2MS-R618A 2MS-R624B 1135 psig 264n2 l (MS-114A) (MS-114B) i i
  • The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure. ,

l WATERFORD - UNIT 3 3/4 7-2 AMENDMENT No. 444 l

-?'

_ _ _ _ _ _ _ _ _ _ - _ _ - ~ - _ _ _ - - - . _ . - _ - _ _

e TABLE 3.7-2  ;

MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE  ;

STEAM LINE SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS i i

MAXIMUM ALLOWABLE LINEAR POWER MAXIMUM NUMBER OF INOPERABLE SAFETY LEVEL-HIGH TRIP SETPOINT  ;

VALVES ON ANY OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER) -!

i 1 86.8 -

l 2 69.4 _i

? - 52M l ,

i i

f i

5

~

s

WATERFORD - UNIT 3 3/4 7-3 AMENDMENT No. 411 l f

3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE

, 3/4.7.1.1 SAFETY VALVES l

l The OPERABILIW of the main steam line code safety valves ensures that the secondary system l pressure will be limited to within 110% (1210 psla) of its design pressure of 1100 psla during the most severe l anticSated system operational transient. The maximum relieving capacity is associated with a turbine trip l

l from 100% 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 i Section til of the ASME Boiler and Pressure Vessel Code,1974 Edition. The4et.*Lt:!!:v!~g cepecity for !! '

v !ve: On !! Of the deem "ne !: 19.297 x 106 !h?'(et 1210 p ! d=!;;n pr==re !c= 50 pe! p'e=ure-4 rop l to the h!et Of the vc!ve ) 7t10" !: 104.2% Of the tete! cecendcrj Steer Scw p!= 2% unce:*eirtics Of 15.S1 x l 406!h'br et 100% PATED THER. L POWER:MSSVs rated capacity passes the full steam flow at 102%

l RATED THERMAL POWER (100% + 2% for instrument error) with valves open. A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for removing decay heat. All the MSSVs have an orifice size of 28.27 in2, l l 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 system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Level-High channels. The l reactor trip setpoint reductions are derived on the following bases: An analysis of a loss of condenser l vacuum event initiated at the reduced power levels listed in Table 3.7-2 that shows peak steam generator j pressures are maintained below 1210 psia.

For twc400p 4 pumpeperation BP = X 104.-2%

6 1

l l

whers l

SP- =-reduc-d reader tdp retpc!rt !n percent 4-RATED-THERMAL-POWER I l

N =-maximum +uneraf inoperab!e safety-valves-per steam 4ine 404.2 - the4at40-of the total re!! vingM>ty Of 2!! 12 main stecasafety+alves-diwded by the seconderj steam Scw at 100% Rated Therma 0Loadrplus44 uncertainty, I

i r

v'. t : tERFORD - UNIT 3 8 3/4 7.1 AMENDMENT NoA44 l

Retrieved from "https://kanterella.com/w/index.php?title=ML20141D855&oldid=2857724"