ML18101A254

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


Text

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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 Table 4.3-1 Table 4.3-1 Table 4.3-1 94 :!. 0040060 94-0920

- ~\\

PDR ADOCK 05000272 p

PDR 3/4 3-11 3/4 3-12 3/4 3-13 3/4 3-13a

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r =

I = ",

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS FUNCTIONAL UNIT

  • 1.

Manual Reactor Trip Switch

2.

Power Range, Neutron Flux

3.

Power Range, Neutron Flux, High Positive Rate

4.

Power Range, Neutron Flux, High Negative Rate

5.

Intermediate Range, Neutron Flux

6.

Source Range, Neutron Flux

7.

overtemperature 4T

8.

overpower 4T CHANNEL CHECK N.A.

s N.A.

N.A.

s S(7) s s

9.

Pr***uriz*r Pre**uro--Low s

10.

Pr***urizer Pr***ure--High s

11.

Pre**urizer Water Level--High s

12. Lo** of Flow - Single Loop S

CALIBRATION N.A.

0(2), M(J) and Q(6)

R(6)

R(6)

R(6)

R(6)

R R

R R

R R

CHANNEL HODES IN WHICH FUNCTIONAL SURVEILLANCE REQUIRED 1,2 1,2 1,2 S/U(l) 1,2 and

  • Q and S/U(l) 2,3,4,5 and
  • 1,2 1,2 1,2 1,2 1,2 Q

1

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't' -

N TABLE 4.3-1 <<Continued)

REACTOR TRIP SYSTEM INSTRUHENIATION SURVEILLANCE REQUIREMENTS FUNCTIONAL UNIT

13.

Losa of Flow - Two Loop*

14.

Steam Generator Water Level--

Low-Low

15.

Steam/Feedwater Flow Mismatch ~

Low Steam Generator Water Level

16. Undervoltage - Reactor coolant Pump*
17. Underfrequency - Reactor Coolant Pumps
18. Turbine Trip A.

Low Autoatop Oil Pressure B.

Turbine Stop Valve Closure

19. safety Injection Input from ESF
20. Reactor Coolant Pump Breaker Po*ition Trip
21. Reactor Trip Breaker
22. Automatic Trip Logic CHANNEL CHECK s

s s

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

CALIBBATION R

R R

R R

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

CHANNEL FUNCTIONAL TEST N.A.

Q Q

Q S/U(l)

S/U(l)

H(4)(5)

MODES IN WHICH SURVEILLANCE REQUIRED 1

1,2 1,2 1

1 1,2 1,2 1,2 R

N.A.

S ---==::!{_Y ( 19),

~"' 1, 2 and

  • M'('ll, 13) I

~A(l2, 13) ~

and R(l4)

H(S) 1,2 and

  • ATTACHMENT B REVISED NOTATION FOR TABLE 4.3-1 NLR-N94003 LCR 93-06 INSERT (9)

(10) -

(11) -

(12) -

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.

DELETED The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the Reactor Trip Breaker Undervoltage and Shunt Trip mechanisms.

DELETED

( l ).

( 2)

( 3)

( 4)

( 5)

(6)

( 7)

(8)

  • TABLE 4.3-1 <Continued\\

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

If not performed in previous 31 days.

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

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

Manual SSPS functional input check every 18 months.

Each train or logic channel shall be tested at lea*t 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) setpoint.

Deleted teat Trip SALEM - UNIT 1 3/4 3-13 Amendment No. 142

(13) -

( 14) -

TABLE 4.3-1 (Continued)

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

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

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I

I I
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z 0

TABLE 4.3-1 RIACTQR TRIP SXSTEM INSTRUHINTATION SURVEILLANCE REOUIBEMENTS FUNctIQNAL UNIT

1.

Manual Reactor Trlp Switch

2.

Power Range, **utron Flux

3.

Power Range, Neutron Flux, High Poaitlve Rat*

4.

~ower Range, Neutron Flux, High Negative Rate

s.

Intermediate Range, Neutron Flux

6.

source Range, Neutron Flux

8.

overpower 4T

9.

Pre**url&er Preaaure--Low

10.

Pre**url&er Preaaure--Hlgh

11.

Pr***url&er Water Level--High

12. Lo** of Plow - Single Loop CHAHNEL CHECK N.A.

s N.A.

N.A.

s S(7) s.

s s

s s

s CALIBRATION N.A.

0(2), M(J) and Q(6)

R(6)

R(6)

R(6)

R(6)

R R

R R

R R

CHANNEL FUNCTIONAL TEST R

_,.-.sftrt 9 )

Q S/U(l)

Q and S/U(l)

HODES IN WHICH SURVEILLANCE REQUIRED 1,2 1,2 1,2 1,2 and

  • 2,J,4,5 and
  • 1,2 1,2 1,2 1,2 1,2 1

I c * -

-t N

w w

I....

N I

I I
I "

z 0.

TABLE 4.3-1 <<Continued*

RIACTQR TRIP SYSTEM INSTRUffENTATION SURVEILLANCE REOUIR£MENTS FUNCTIONAL UNIT

13. Lo** of flow - Two Loop*
14. Steam Gener*tor Water Level--

Low-Low

15. Steam/feedwater Plow Mi*match ~

Low steam Generator water Level

16. Uodervoltage - Reactor COolant Pump*
17. Underfrequency - Reactor Coolant Pwap*
18. Turbin* Trip
a. Low Auto*top Oil Pr***ure
b. Turbin* Stop Valve Clo*ure
19. Safety Injection Input from SSF
20. Reactor Coolant PWlp Breaker Po*ition Trip
21. Reactor Trip Breaker
22. Automatic Trip Logic CHANNEL CHECK s

s s

N.A.

N.A.

N.A.

N.A.

N.A.

M.A.

M.A.

N.A.

CALIBRATION R

R R

R R

M.A.

N.A.

N.A.

N.A.

N.A.

N.A.

CHANNEL FUNCTIONAL TEST N.A.

Q S/Up)

S/U(l)

M(4) (5)

R 5 ~Y.1:14.,f 1~91J-1)1-:,:--.J-M f'll, 13),

SAC1~1 H) and 8(14)

M(S)

MODES IN WHICH SURVEILLANCI REQUIRED 1

1,2 1,2 1

1 N.A.

N.A.

1,2 N.A.

1,2 and

  • 1,2 and
  • ATTACHMENT C REVISED NOTATION FOR TABLE 4.3-1 NLR-N94003 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.

(10) -

(11) -

(12) -

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

DELETED The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the Reactor Trip Breaker Undervoltage and Shunt Trip mechanisms.

DELETED

( l)

(2)

(3)

(4)

( 5)

(6)

(7)

(8)

( 9)

TABLE 4.3-l !Continued)

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

If not performed in previous 31 days.

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

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

Manual SSPS functional input check every 18 months.

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

Neutron detectors may be excluded from CHANNEL CALIBRATION.

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

Deleted SALEM -

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

(13) -

(14) -

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

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

SALEH - UNIT 2 3/4 3-13&

Amendment No. 74

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