Text

Proposed Tech Specs Re Reactor Trip Sys Surveillance Requirements
	ML18101A254
Person / Time
Site:	Salem
Issue date:	09/20/1994
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18101A253	List: ML18101A252; ML18101A254;
References
	NLR-N94003, NUDOCS 9410040060
	Download: ML18101A254 (12)
	v • d • e

I---- --

ATTACHMENT B NLR-N94003 LCR 93-06 REACTOR TRIP SYSTEM SURVEILLANCE REQUIREMENTS REVISIONS SALEM GENERATING STATION UNIT 1 FACILITY OPERATING LICENSE DPR-70 DOCKET NO. 50-272 The following Technical Specifications have been revised (pen and ink) to reflect the proposed changes:

Technical Specification Table 4.3-1 3/4 3-11 Table 4.3-1 3/4 3-12 Table 4.3-1 3/4 3-13 Table 4.3-1 3/4 3-13a 94 :!. 0040060 94-0920 - ~\

PDR ADOCK 05000272 p PDR

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS c:

z

-t CHANNEL CHANNEL HODES IN WHICH FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION REQUIRED

1. Manual Reactor Trip Switch N.A. N.A.

2. Power Range, Neutron Flux s 0(2), M(J) 1,2 and Q(6)

3. Power Range, Neutron Flux, N.A. R(6) 1,2 High Positive Rate

4. Power Range, Neutron Flux, N.A. R(6) 1,2

~ High Negative Rate

-w I 5. Intermediate Range, Neutron Flux s R(6) S/U(l) 1,2 and *

6. Source Range, Neutron Flux S(7) R(6) Q and S/U(l) 2,3,4,5 and *

7. overtemperature 4T s R 1,2

8. overpower 4T s R 1,2

9. Pr***uriz*r Pre**uro--Low s R 1,2 r=

I= 10. Pr***urizer Pr***ure--High s R 1,2

,." 11. Pre**urizer Water Level--High s R 1,2

12. Lo** of Flow - Single Loop S R Q 1

TABLE 4.3-1 <<Continued)

REACTOR TRIP SYSTEM INSTRUHENIATION SURVEILLANCE REQUIREMENTS c:

z

-4 CHANNEL CHANNEL FUNCTIONAL MODES IN WHICH SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBBATION TEST REQUIRED

13. Losa of Flow - Two Loop* s R N.A. 1

14. Steam Generator Water Level-- s R Q 1,2 Low-Low

15. Steam/Feedwater Flow Mismatch ~ s R Q 1,2 Low Steam Generator Water Level

16. Undervoltage - Reactor coolant N.A. R Q 1 w Pump*

't' N

17. Underfrequency - Reactor Coolant Pumps N.A. R 1

18. Turbine Trip A. Low Autoatop 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 ESF N.A. N.A. H(4)(5) 1,2

20. Reactor Coolant Pump Breaker N.A. N.A. R N.A.

Po*ition Trip

21. Reactor Trip Breaker N.A. N.A. S ---==::!{_Y ( 19) , ~"' 1, 2 and

M'('ll, 13) I

~A(l2, 13) ~

and R(l4)

N.A. N.A. H(S) 1,2 and *

22. Automatic Trip Logic

ATTACHMENT B REVISED NOTATION FOR NLR-N94003 TABLE 4.3-1 LCR 93-06 INSERT (9) The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the Undervoltage and Shunt Trip mechanism for the Manual Reactor Trip Function.

The test shall also verify OPERABILITY of the Bypass Breaker Trip circuits.

(10) - DELETED (11) - The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the Reactor Trip Breaker Undervoltage and Shunt Trip mechanisms.

(12) - DELETED

TABLE 4.3-1 <Continued\

NOTATION

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

( l ). If not performed in previous 31 days.

( 2) Heat balance only, above 15\ of RATED THERMAL POWER.

( 3) Compare incore to excore axial offset above 15\ of RATED THERMAL POWER. Recalibrate if absolute difference C!: 3 percent.

( 4) Manual SSPS functional input check every 18 months.

( 5) Each train or logic channel shall be tested at lea*t 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) Deleted teat Trip SALEM - UNIT 1 3/4 3-13 Amendment No. 142

TABLE 4.3-1 (Continued)

NOTATION (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 - UNIT 1 3/4 3-l3a Amendment No. 97

ATTACHMENT C NLR-N94003 LCR 93-06 REACTOR TRIP SYSTEM SURVEILLANCE REQUIREMENTS REVISIONS SALEM GENERATING STATION UNIT 2 FACILITY OPERATING LICENSE DPR-75 DOCKET NO. 50-311 The following Technical Specifications have been revised (pen and ink) to reflect the proposed changes:

Technical Specification Table 4.3-1 3/4 3-11 Table 4.3-1 3/4 3-12 Table 4.3-1 3/4 3-13 Table 4.3-1 3/4 3-13a

TABLE 4.3-1 RIACTQR TRIP SXSTEM INSTRUHINTATION SURVEILLANCE REOUIBEMENTS c:

....-4

z CHANNEL HODES IN WHICH N CHAHNEL FUNCTIONAL SURVEILLANCE FUNctIQNAL UNIT CHECK CALIBRATION TEST REQUIRED

1. Manual Reactor Trlp Switch R

N.A. N.A. _,.-.sftrt 9 )

2. Power Range, **utron Flux s 0(2), M(J) Q 1,2 and Q(6)

3. Power Range, Neutron Flux, N.A. R(6) 1,2 High Poaitlve Rat*

w 4. ~ower Range, Neutron Flux, N.A. R(6) 1,2 High Negative Rate

-w I

s. Intermediate Range, Neutron Flux s R(6)

R(6)

S/U(l)

Q and S/U(l) 1,2 and

2,J,4,5 and *

6. source Range, Neutron Flux S(7) s R 1,2

8. overpower 4T s R 1,2

9. Pre**url&er Preaaure--Low s R 1,2 s R 1,2

10. Pre**url&er Preaaure--Hlgh s 1,2 I:I

11. Pr***url&er Water Level--High R I

I z

0

12. Lo** of Plow - Single Loop s R 1

TABLE 4.3-1 <<Continued*

RIACTQR TRIP SYSTEM INSTRUffENTATION SURVEILLANCE REOUIR£MENTS

-c

- t N

FUNCTIONAL UNIT CHANNEL CHECK CALIBRATION CHANNEL FUNCTIONAL TEST MODES IN WHICH SURVEILLANCI REQUIRED

13. Lo** of flow - Two Loop* s R N.A. 1

14. Steam Gener*tor Water Level-- s R 1,2 Low-Low

15. Steam/feedwater Plow Mi*match ~ s R Q 1,2 Low steam Generator water Level w 16. Uodervoltage - Reactor COolant N.A. R 1

Pump*

w N

I

17. Underfrequency - Reactor Coolant N.A. R 1 Pwap*

18. Turbin* Trip

a. Low Auto*top Oil Pr***ure N.A. M.A. S/Up) N.A.

b. Turbin* Stop Valve Clo*ure N.A. N.A. S/U(l) N.A.

19. Safety Injection Input from SSF N.A. N.A. M(4) (5) 1,2 M.A. N.A. R N.A.

20. Reactor Coolant PWlp Breaker Po*ition Trip I

I 5 ~Y.1:14.,f1~91J-1)1-:,:--.J- 1,2 and

M.A. N.A.

I

21. Reactor Trip Breaker Mf'll, 13),

" SAC1~1 H)

.z 0 and 8(14)

N.A. N.A. M(S) 1,2 and *

22. Automatic Trip Logic I

ATTACHMENT C REVISED NOTATION FOR NLR-N94003 TABLE 4.3-1 LCR 93-06 INSERT (9) The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the Undervoltage and Shunt Trip mechanism for the Manual Reactor Trip Function.

The test shall also verify OPERABILITY of the Bypass Breaker Trip circuits.

(10) - DELETED (11) - The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the Reactor Trip Breaker Undervoltage and Shunt Trip mechanisms.

(12) - DELETED

TABLE 4.3-l !Continued)

NOTATION

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

( l) If not performed in previous 31 days.

(2) Heat balance only, above 15\ of RATED THERMAL POWER.

(3) Compare incore to excore axial offset above 15\ of RATED THERMAL POWER. Recalibrate if absolute difference ~ 3 percent.

(4) Manual SSPS functional input check every 18 months.

( 5) Each train or logic channel shall be tested at least every 62 daya 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) Deleted

( 9)

SALEM - UNIT 2 3/4 3-13 Amendment No. 121

(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.

-- I I

SALEH - UNIT 2 3/4 3-13& Amendment No. 74

ML18101A254

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