ML20094Q170

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Proposed Tech Specs,Modifying TS 3/4.7.1 & Associated Bases to Increase Setpoint Tolerance of MSSV from +1% to +3% to Incorporate Requirement to Reset MSSV Lift Settings to within +1% Following Surveillance Testing
ML20094Q170
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 11/15/1995
From:
DUKE POWER CO.
To:
Shared Package
ML20094Q165 List:
References
NUDOCS 9512010071
Download: ML20094Q170 (13)
v • d • e


Text

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

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3/4.7 PLANT SYSTEMS I

'3/4.7.1' TURBINE CYCLE-SAFETY VALVES i

LIMITING CONDITION FOR OPERATION ,

i

} ~ 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.

i 1 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 Ccde safety valves inoperable, operation in MODES , 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 inopi able 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, g b. The provisions of Specification 3.0.4 are not applicable.

9 SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional requirement's other than those required by Specification 4.0.5. )veing guev4 Wae .tes&y, gg_.l.pt.jp se.ftAp g g ( g J,f,*4 2 l 9e .

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9512010071 951115 DR ADOCK 0500r4 3 gA,,g yo, (wgg) g

TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERATION MAXIMUM NUMBER'0F INOPERABLE MAXIMUM ALLOWABLE. POWER RANGE SAFETY VALVES ON ANY NEUTRON FLUX HIGH SETPOINT OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER) 1 87  ;

2 65 3 43 4 or 5 2/

k s

e l

  • Unit operation shall be res er than Mode 3. This is appli-cable for one time ering Mode . ~~ the first refueling outa CATAWBA - UNITS 1 & 2 3/4 7-2 Amendment No. Unit 1)

Amendment No. (Unit 2) l

l l

c, .

D TA8LE 3.7-2 5

2 STEAM LINE SAFETY VALVES PER LOOP e

l e VALVE NUMBER ($ J )

25 LIFT SETTING *(= 1.0")** ORIFICE SIZE l St Loop A Loop B Loop C Loop D

e. 1. SV-20 SV-14 SV-8 SV-2
  1. 1175 psig 14.18 in.2
2. SV-21 SV-15 SV-9 SV-3 1190 psig 14.18 in.2
3. SV-22 SV-16 SV-10 SV-4 1205 psig 14.18 in.2
4. SV-23 SV-17 SV-11 SV-S 1220 psig 14.18 in.2
5. SV-24 SV-18 SV-12 M SV-6 1230 psig a 14.18 in.2 N

O

  • The lift setting pressure shall correspond to ambient operating temperature and pressure. conditions of the valve at nominal "C;m. 3s orplies te Unit 2 .11 . 0;. ease vulese. only esplie5 -atil first fereed eetese, seeeter trip, er .efeelias El $' h' 0 3:

2!-rsaatat we 3:

50 4

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

3/4.7 PLANT SYSTEMS '

1 BASES  !

l -

i 3/4.7.1 TURBINE CYCLE Tolk.

eda 3.~7-w 6it.in; alIwt

%% aAi 3% Wm h.boint m e +cle.cuce.

% !.1% -

3/4.7.1.1 SAFETY VALVES duri$ rurve&aca. te rt/n3 ts allow Ar Jr*rR 8

y the Secondary System pressure will be limited to with e

i 110% (1304 psig) of '

j

. P., its designtransient.

operational pressure of 1185 psig during the most severeemanticip Turbine trip from valve wide-open condition coincident of condenser heat sink (f.e., no steam bypass to the condenser).

1 i The specified valve lift settings and relieving capacities are in i Code,1971 Edition.) The total relieving capacity 1

  • steam lines is 16.85 x los 1bs/h which is 105% of the total secondary lsi i

flow of 16.05 x 10' lbs/h at 100% RATED THERMAL A minimumPOWER.

of two OPERA 8LE safety valves per steam generator ensures that su capacity is available for the allowable THERMAL POWER restriction in

' Table 3.7-1.

' STARTUP and/or POWER OPERATION is allowable with safety v a

within the limitations of the ACTION requirements on the basis of the

reduced Reactor trip settings of the Power Range The
  • Reactor Trip Setpoint reductions are derived on the following bases:  !

i

! For four loop operation i

s

SP = (X) - (Y)(V) x (109) j l Where:  :

i SP = POWER, Reduced Reactor Trip Setpoint in percent of RATED THERMAL i

j V \

i = Maximum number of inoperable safety valves per steam line, i 109 =

j . Power Range Neutron Flux-High Trip Setpoint for four loop operation; i

2 X =

] Total relieving capacity of all safety valves per steam 4

i line in 1bs/ hour, and

~

Y=

Maximum lbs/ hour relieving capacity of any one safety valve in i I

1 k l j

CATAWBA - UNITS 1 & 2 l i

8 3/i 7-1

[g pM6 koe 4

/ w J e + No. (Uni + N ,

i )

i

Reprinted Technical Specification Pages i

1 5

4 9

$1 1

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t i

i J

a I

t 4

4 e

l 4

4 5

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 ino)erable, operation in MODES 1, 2, and 3 may proceed provided, that witiin 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 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
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. During surveillance testing, as-left lift settings shall be within

  • 1%.

1 l .

I

, l i

i CATAWBA - UNIT 1 3/4 7-1 Amendment No.

l TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY val.VES DURING FOUR LOOP OPERATION l

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 87 2 65 3 43 4 or 5 2 l t

l i

i 4

CATAWBA - UNIT 1 3/4 7-2 Amendment No.

TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP-VALVE NUMBER LIFT SETTING * (* 3%) ORIFICE SIZE LooD A M9_R LooD C L0oD D

1. SV-20 SV-14 SV-8 SV-2 1175 psig 14.18 in.2
2. SV-21 SV-15 SV-9 SV-3 1190 psig 14.18 in.2
3. SV-22 SV-16 SV-10 SV-4 1205 psig 14.18 in.2
4. SV-23 SV-17 SV-11 SV-5 1220 psig 1,4.18 in.2
5. SV-24 SV-18 SV-12 SV-6 1230 psig 14.18 in.2
  • The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

CATAWBA - UNIT 1 3/4 7-3 Amendment No.

t

3/4.7 PLANT SYSTEMS ggSrs I

3/4.7.1 TURBINE CYCLE j 3/4.7.1.1 SAFETY VALyfJ 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 valve wide-open condition 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 III of the ASME Boiler and Pres-sure Code, 1971 Edition. Table 3.7-2 allows a 3% setpoint tolerance for OPERABILITY; however, the valves are reset to i 1% during surveillance testing

~

to allow for drift. Thegotalrelievingcapacityforallvalvesonallofthe steamlinesis16.g5x10 lbs/h which is 105% of the total secondary steam flow of 16.05 x 10 lbs/h at 100% RATED THERMAL POWER. A minimum of two l OPERABLE safety valves per steam generator ensures that sufficient relieving i capacity is available for the allowable THERMAL POWER restriction in Table l 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 reduc- l tion 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:

For four loop operation

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

SP = X l

Where:

l SP = Reduced Reactor Trip Setpoint in percent of RATED THERMAL

POWER,

! l

V = Maximum number of inoperable safety valves per steam line, 1

l 109 = Power Range Neutron Flux-High Trip Setpoint for four loop

operation, l X = Total relieving capacity of all safety valves per steam line in Ibs/ hour, and l

1 l

Y = Maximum relieving capacity of any one safety valve in l

lbs/ hour l

l i CATAWBA - UNIT 1 B 3/4 7-1 l

)

i .

\__-__-___- - _ _ - ___- -_ . . . -, - - -

a 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 ino)erable, operation in MODES 1, 2, and 3 may proceed provided, that wit 11n 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 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS i

4.7.1.1 No additional requirements other than those required by Specification 4.0.5. During surveillance testing, as-left lift settings shall be within

! 1%.

i 1

l 1

  • l
l CATAWBA - UNIT 2 3/4 7-1 Amendment No.

i

m - -

TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH IN0PERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERATION MAXIMUM NUMBER OF INOPERABLE MAXIMUN ALLOWABLE POWER RANGE SAFETY VALVES ON ANY NEUTRON FLUX HIGH SETPOINT OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER) 1 87 2 65 3 43 4 or 5 2 i-I CATAWBA - UNIT 2 3/4 7-2 Amendment No.

TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP -

VALVE NUMBER . LIFT SETTING * (* 3%) ORIFICE SIZE Loon A Loon B LooD C LooD D

1. SV-20 'SV-14 SV-8 SV-2 1175 psig. 14.18 in.2

'2. SV-21 SV-15 SV-9 SV-3 1190 psig 14.18 in.2

3. SV SV-16 SV-10 SV-4 1205 psig 14.18 in.2
4. SV-23 SV-17 SV-11 SV-5 1220 psig 14.18~in.2
5. SV SV-18 SV-12 SV-6 1230 psig 14.18 in.2
  • The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

l CATAWBA - UNIT 2 -3/4 7-3 Amendment No.

i 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% (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 valve wide-open condition 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 III of the ASME Boiler and Pres- .

sure Code, 1971 Edition. Table 3.7-2 allows a

  • 3% setpoint tolerance for .

OPERABILITY; however, the valves are reset to

  • 1% during surveillance testing  !

to allow for drift. The gotal relieving capacity for all valves on all of the steamlinesis16.g5x10 lbs/h which is 105% of the total secondary steam flow of 16.05 x 10 lbs/h at 100% RATED THERMAL POWER. A minimum of two.

OPERABLE safety valves per steam generator ensures that sufficient relieving capacity is available for the allowable THERMAL POWER restriction in Table 3.7-1. i STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduc-tion 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:

i For four loop operation (X) - (Y)(V) x (109) l SP = X l

Where:

l SP = Reduced Reactor Trip Setpoint in percent of RATED THERMAL

! POWER,

.V = Maximum number of inoperable safety valves per steam line, l l

109 = Power Range Neutron Flux-High Trip Setpoint for four loop l operation, 4

l X = Total relieving capacity of all safety valves pe'r steam line in 1bs/ hour, and Y = Maximum relieving capacity of any one safety valve in 1bs/ hour 4

j CATAWBA - UNIT 2 B 3/4 7-1

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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