ML18092A878

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Proposed Tech Specs Adding Specs Per Generic Ltr 83-28,Item 4.3, Reactor Trip Breaker Automatic Shunt Trip
ML18092A878
Person / Time
Site: Salem  PSEG icon.png
Issue date: 10/17/1985
From:
Public Service Enterprise Group
To:
Shared Package
ML18092A877 List:
References
GL-83-28, NUDOCS 8510250092
Download: ML18092A878 (8)
v • d • e


Text

*-*-*--~------ **--------*~~---*-:_ ____. ______ ----------- *-*-*------ *- ---~-- --- ---* ~---*..

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e e

CHANGED PAGES FOR SALEM UNIT NO. 1 8510250092 851017 PDR ADOCK 05000272 P

PDR

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r-rr1 TABLE 4.3-1 (Continued) 3 c:

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQJIREMENTS

z

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CHANNEL f()DES IN ~ICH CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK

  • CALI BRA TI ON.

TEST REQJIRED

13. Loss of Flow - T\\\\O Loops s

R N.A*.

1 e

14. Steam Generator Leter Level-- Low-Low s

R M

1, 2

15. Steam/Feedwater Flow Mismatch & Low Steam Generator Water Level s

R M

1, ~

w

16. Undervoltage '.""'React.or Coolant Purrps N.A.

R M

1

~

17. *underfrequen~y - Reactor Coolant Purrps w

N.A.

R M

1 I.....

N

18. Turbine Trip a~ Low Autost.op Oil* Pressure.

N.A

  • N.A
  • S/U(l) 1, 2
b. Turbine Stop Valve Closure N.A.

N.A.

S/U(l) 1, 2

19. Safety Injection. Input from SSPS N.A.

N.A *.

M(4) 1, 2

20. Reactor Coolant Purrp Breaker Position e

Trip.

N.A.

N.A.

R N.A.

21. React.or Trip Breaker N.A.

N.A.

S/U(lO), M(ll,13),

SA(l2, 13)

& R(l4) 1, 2 and *

22. Automatic Trip Logic N~A.

N.A.

  • M(5) 1, 2 and *
  • e TABLE 4.3-1 (Continued)

NOTATION With the. reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.**

(1) _-

If mt performed in previous 7 days.

(2) * -

Heat balance only, above 15J. of RAT~D _THERMAL PO~R.

(3)

ComJ)are incore to excore axial offset above 15J. of RATED THERMAL PO\\tER *

. Recalibrate if absolute difference.?_ 3 percent.

(4)

Manual SSPS functional input check every 18 nnnths.

(5)

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION *

. (7)

Below P-6 (Block of Source Range Reactor* Trip) setpoint.

(8)

Logic only,. if not performed in previous 92 days.

(9)

If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of th.e Manual Reactor Trip Switches tO verify the Manual Reactor Trip Switch and the indeperident 6peration of the U.V. and shunt trip wi~ing. *

(10)

If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of:

.* Reactor Trip Breaker Shunt Tri_p (via manual pushbutton controls)

( 11)

Perform a functional test of:

  • Reactor Trip Breaker independent operation of u.v. Trip and Shunt Trip.(via*SSPS) and conduct response time testing of u.v. and Shunt Trip/Breakers (event recorders)

(12}

-. Perform periodic maintenance on. Reactor Trip Breakers and Reactor Trip

  • Bypass ~reakers semiannually as fallows:.
  • a... response time testing, (3 times) (visicorder) trend data
b. *trip bar 1 i ft force measurements
c. U.v. output force neasurement
d. *dropout voltage check
e. servicing/lubrication/adjustments (See Table 3.3-1 llbtation ###)
f. repeat tes~ing steps (a-d) following any necessary actions at step (e)

SALEM - UN IT 1 3/4 3-13

TABLE 4.3-1 (Continued)

(13) -

Verify operation of Bypass Breakers Shunt Trip function from local pushbutton while breaker is in the test position prior to placing. breaker in service.

(14)

Perform a.functional test of the Bypass Breakers U.V. Attachment via the SSPS.

SALEM - UN IT 1 3/4 3-13a

CHANGED PAGES FOR UNIT NO. 2

~

SI:!

TABLE 4.3-1 (Continued)

I I

I c

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQ.JIREfiENTS

z

-I

~

CHANNEL r4JDES IN WUCH I

CHANNEL FUNCTIONAL SURVEILLANCE.

I i FUNCTIONAL UNIT CHECK CAJ_IBRATION TEST RE9JIRED I

13. Loss of Flow - T\\'tO Loops s

R N.A.

1 9

1

14. Steam Generator W:lter Level-- Low-Low s

R M

1, 2

.. 11 11

15.

~team/Feedwater Flow Mi smatch & Low Steam Generator W:lter Level s

R M

1, 2 I Ii w

16. Underwltage - Reactor Coolant Pull{ls N.A*

R

  • M 1

~

w

17. Underfreqµency - Reactor Cool ant PuD{ls N.A.

R M

1 I.._.

N

18. Turbine Trip
a. Low Autostop Oil Pressure N.A.

N.A.

S/U(l)

N.A.

b. Turbine Stop Valve Closure N.A.

N.A.

S/U(l)

N.A.

r*

19. Safety Injection Input from SS PS N.A.

N.A.

M(4)

. 1, 2

20. Reactor Coolant PuD{l Breaker Fbsition 9*

Trip N.A.

R.

S/U(8) 1

21. Reactor Trip Breaker N.A
  • N.A.

S/U(lO), M(ll,13),

SA(l2, 13)

& R(l4) 1, 2 and *

22. Automatic Trip Logic N.A.

N.A*

M(5) 1, 2 and *

==--..:=--=--=-:::-:

-==--~---~--~---~--~--=---::-::--=--=-::-... :-:::

... ::-::.. =--=--::::::--=-==-=~-=--:--:-...

-:.:-::_-=-:-;-::~~-~~--~

TABLE 4.3-1 {Continued'._

NOTATION

{ 1)

(2)

(3)

{4)

{S)

{6}

(7) w;th the reactor trip system breakers closed and the control rod drive system capable of rod withdraw~l

  • If not performed in previous 7 days.

.Heat balance only, above 151of RATED THERMAL Rl\\.ER.

Compare incore to excore axial offset above 15% of RATED THERMAL Rl\\tER.

Recalibrate if absolute difference > 3 percent.

M.anual SSPS functional input check every 18 nnnths.

Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

Neutron detectors may be excluded from CHANNEL CALIBRATION.

Below P-6 {Block of Source Range Reactor-Trip) setpo int.

(8)

Logic only, if not performed in previous 92 days.

(9)

If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of the Manual Reactor Trip Switches to verify the Manual Reactor Trip Switch and the independent operation of the U.v. and *shunt trip wiring *

. (10)

If not performed in the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, conduct a functional test of:

(11)

-. Perform a functional test of:

{12)

  • Reactor Trip Breaker independent operation of u.v. Trip and Shunt Trip (vja SSPS) and conduct response time testing of u.v. and Shunt Trip/Breakers (event recorders)

-. Perform per1odic maintenance on_ Reactor Trip Breakers and Reactor Trip

  • Bypass Breakers semi annually as follows:
a. response time testing, (3 times)- (visicorder) trend data
b. trip bar lift force measurements
c. U.v. output force nEasurement
d. dropout voltage check e *. servi ci ng/l ubri cation/adjustments (See Table 3.3-1 l'btation -***)
f. repeat testing steps {a-d) following any necessary actions at step.(e)

SALEM - UN IT 2 3/4 3-13

TABLE 4.3-1 (Continued)

(13)

Verify operation of Bypass Breakers Shunt Trip function from local pushbutton while breaker is in the test position prior to placing breaker in service.

(14)

Perform a functional test of the Bypass Breakers U.V. Attachment via the SSPS.

SALEM -

UN IT 2 3/4 3-13a r

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