ML20053E635

Proposed Tech Spec Pages Allowing Operation W/Rcs Average Temp of 582.8 F as Apposed to Current Temp of 580.3 F

ML20053E635
Person / Time
Site:	North Anna
Issue date:	06/08/1982
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20053E618	List: ML20053E617 ML20053E626 ML20053E631 ML20053E635
References
NUDOCS 8206090097
Download: ML20053E635 (8)

Text

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ENCLOSURE 3 North Anna Technical Specifications Changes for Tavg of 582.8 F t

1 t

I i

l l

l t

i i

l 3

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! 8206090097 820608 l

PDR ADOCK 05000338 P PDR

[ - - - - _ .

TABLE 2.2-1 (Continuzd) ..

5 W REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS .

NOTATION Di z ~

1+tg S' g

NOTE 1: Overtemperature AT1T [K g-K2 1+t 8 (T-T')+K3 ~

}1 OI e . 2-Where: ATO " " "" *

• T = Average temperature. 'F T' = Indicated T at RATED THERMAL POWER 1 582.8 F P = Pressurizer pressure, psig P' = 2235 psig (indicated RCS nominal operating pressure)

N 1+t 1S = The function generated by the lead-lag controller for T,yg dynamic compensation f,

1+t 8 2

• 1 '2 = Time constantssatilized in the lead-lag controller for T**8 r = 25 sees, t

2

= 4 secs.

~

S =Laplacetransformoperator(sech

TABLE 2.2-1 (ContinuGd) z REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS O

NOTATION (Continued) .

E Operation with 2 Loops Operation with 2 Loops

> Operation with 3 Loops (1 loop isolated)*

8 (no loops isolated)*

6 Kg = ( ) Kg = ( )

Kg = 1.113 K " ( ) K "

( )

K = 0.0132 2 2

2 K = ( ) K = ( )

K = 0.000628 3 3

3 -

and f of the power-range nuclear ion chambers; with gains to be selected based on measu ,

instrument response during plant startup tests such that:

between - 35 percent and + 7 percent, f (AI) =0 g (1) for q -

9 b and qb arepercentRATEDTHERMALPOWERinthetopandbottom t

(where q

'f'o halvesofthecorerespectively,andq t

• Sb is total H E N M ER in percent of RATED THERMAL POWER).

for each percent that the magnitude of (q - qb) exceeds - 35 percent, (ii) the AT trip setpoint shall be automatically reduced by 1.21 percent of its value at RATED THERMAL POWER.

(iii) for each percent that the magnitude of (q -

qb) exceed 8 +7 Percent, theATtripsetpointshallbeautomaticalkyreducedby1.09percentof its value at RATED THERMAL POWER. ,

l

• Values dependent on NRC approval of ECCS evaluation for these operating conditions.

TABLE 2.2-1 (Continued) ,,

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS .

NOTATION (Continued) d

c ^

T 8

$ 3 T K

$ NOTE 2: Overpower AT1 AT,[K4-K5 6 (T-f )-f 2(0 }1 1+T 8

- 3 l

y Where: AT = Indicated AT st RATED THERMAL POWER i J o e-I

= Average temperature. *F

~ T T" = Indicated T at RATED THERMAL POWER 1582.8'F K = .088 4

K = 0.02r F for increasing average temperature 3

w = 0 for decreasing average temperatures K

.' 5 o

K 6

= 0.00119 for T > T"; K6 = 0 for T 1" T T S = The function generated by the rate lag controller for T,yg 3

dynamic compensation 1+T S 3

t - Time constant utilized in the rate lag controller for T **E T = 10 secs.

3 S = Laplace transform operator (see 1) z f 2(AI) = 0 for all Al Note 3: The channel's maximum trip point shall not exceed its computed trip point by more than 2 percent span.

TABLE 3.2-1 ,,

DNB PARAMETERS _

lb 4

m LIMITS z 2 Loops In Operation ** 2 Loops In Operation **

> & Loop Stop & Isolated Loop 3 Loops In 8

Valves Open Stop Valves Closed Operation E PARAMETER U

w <587'F ,

Reactor Coolant System T,y

>2205 psig*

Pressurizer Pressure

>278,400 gpa Reactor Coolant System Total Flow Rate Rs~

Y 0

• Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% RATED THERMAL POWER per minute or a THERMAL POWER step increase in excess of 10% RATED THERMAL POWER.

• • Values dependent on NRC approval of ECCS evaluation for these conditions.

1 i

l l

l

TABLE 2.2-1 (Continued)

$ REACTOR TRIP SYSTEM INSTRUltENT\ TION TRIP SETPOINTS g

• NOTATION g

g 1 ,-

'1+T gs NOTE 1: Overtemperature AT < 9T [Ky-K2 (T-T' )+K3 (P-P' )-f y(61) ]

g 1+T 8 g

e

_ 2_

N Where: ATO ~ " "" *

• T = Average temperature. *F T' = Indicated T avg at RATED THERMAL POWER < 582.8 F l

P = Pressurizer pressure, psig P' = 2235 psig (indicated RCS nominal operating pressure) ,

1+T S = The function generated by the lead-lag controller for T,yg dynamic compensation 1

"d, 1+T S 2

= Time constants utilized in the lead-lag controller for T **E T = 25 secs.

1 2 T a 4 secs.

2

~

S = Laplace transform operator (sec )

1 e

b w

s,

, TABI.E 2.2-1 (Continued) .

m REACTOR TRIP SYSTEM INSTRUMENTATION TRIP S6TPOINTS ' .

@y

~ i NOTATION (Continued)

E Operation-with 2 Loops Operation vie 2 Loops

> Operation with 3 Loops

' - (no loops isolated)* (1 loop isclated)*

E $ s

- ( ) Kg

( )

y Kg = 1.113 Kg w

K = 0.0132 .'

Kg

=

( m\ ' ) K 2

( ) -

2 ' '

K =

( ) - K "

( )

K = 0.000628 3 3 3  ?

and f g (AI) is a function of the indicated difference between top and bottom detectors -

of the power-range nuclear ion chambers; with gains to be selected based on measured -

s.

instrument response during plant startup te'ts such that: _

t (i) for q - 9 b between - 35 percent and + 7 percent, f (al) =0 t

(where q and qb arepercentRATEDTHERMALPOWERinthetopandbottom 7

• halvesofthecorerespectively,andq + qb is total THERMAL POWER in percent of RATED THERMAL POWER). .

t

, (ii) for each percent that the magnitude of (q - g ) exceeds - 35 percent, ,

b the AT trip setpoint shall be automatically reduced by 1.21 percent of -

its value at RATED THERMAL POWER. _

(iii) for each percent that the magnitude of (q -

qb) exceeds + 7 percent, the AT trip setpoint shall be automatica1Iy reduced by 1.09 percent of its value at RATED THERMAL POWER.

i

(

• Values dependent on NRC approval of ECCS evaluation for these operating conditions.

l

TABLE 3.2-1 DNB PARAMETERS

• 4 x LIMITS

$ 2 Loopa In Operation **

z 2 Loops In Operation **

& Loop Stop & Isolated Loop

' 3 Loops In Operation Valves Open Stop Valves Closed

@ PARAMETER 5

N Reactor Coolant System T avg <587'F l

>2205 psig*

Pressurizer Pressure Reactor Coolant System

>278,400 gpm Total Flow Rate M

• ~

Y 5

• Limit not applicable during either a THERMAL POWER ramp -increase in excess of 5% RATED TilERMAL POWER per minute or a THERMAL POWER step therease . in excess of 10% RATED TilERMAL POWER.

• • Values dependent on NRC approval of ECJS evaluation for these conditions.

- _.