ML20155D699

Proposed Tech Specs,Revising Table 3.3-1, Reactor Coolant Protective Instrumentation, to Allow Plant Operators to Bypass Reactor Coolant flow-low Trip Below 10(-4)% of Rated Thermal Power

ML20155D699
Person / Time
Site:	Waterford
Issue date:	06/07/1988
From:	LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML20155D693	List: ML20155D699 W3P88-0995, Application for Amend to License NPF-38,consisting of Tech Spec Change Request NPF-38-82.Amend Would Revise Table 3.3-1, Reactor Protective Instrumentation, Allowing Plant Operators to Bypass Reactor Coolant flow-low Trip.Fee Paid
References
NUDOCS 8806150381
Download: ML20155D699 (4)

Text

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ATTACmiENT A C806150381 880607 PDR ADOCK 05000382 p

n r. n

TABLE 3.3-1 ac 23 REACTOR PROTECTIVE INSTRUNENTATION E

o MINIMUM E3 TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION C

25 1.

Manual Reactor Trip 2 sets of 2 1 set of 2 2 sets of 2 1, 2 1

-d 2 sets of 2 1 set of 2 2 sets of 2 3*, 4*, 5*

8 w

2.

Linear Power Level - High 4

2 3

1, 2 2#, 3#

3.

Logarithmic Power Level-High a.

Startup and Operating 4

2(a)(d) 3 1 2 2#, 3#

I 4

2 3

3, 4*, 5*

8 b.

Shutdown 4

0 2

3, 4, 5 4

4.

Pressurizer Pressure - High 4

2 3

1, 2 2#, 3#

5.

Pressurizer Pressure - Low 4

2(b) 3 1, 2 2#, 3#

u, f

6.

Containment Pressure - High 4

2 3

1, 2 2#, 3#

J, 7.

Steam Generator Pressure - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

8.

Steam Generator Level - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

9.

Local Power Density - High 4

2(c)(d) 3 1, 2 2#, 3#

10. DNBR - Low 4

2(c)(d) 3 1, 2 2#, 3#

11. Steam Generator Level - High 4/SG 2/SG(g) 3/SG 1, 2 2#, 3#

12. Reactor Protection System Logic 4

2 3

1 2 5

I 3, 4*, 5*

8 I

13. Reactor Trip Breakers 4

2(f) 4 1, 2 5

3*, 4*, 5*

8 x

EE

14. Core Protection Calculators,

4 2(c)(d) 3 1, 2 2#, 3# and 7

15. CEA Calculators 2

1 2(e) 1, 2 6 and 7 is

16. Reactor. Coolant Flow - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

• I

TABLE 3.3-1 (Continued)

TABLE NOTATION 3

l With the protective system trip breakers in the closed position, the CEA l

drive system capable of CEA withdrawal, and fuel in the reactor vessel.

1. The provisions of Specification 3.0.4 are not applicable.

(a) Trip may be manually bypassed above 10 k of RATED THERMAL POWER; bypass shal]4be automatically removed when THERMAL POWER is less than or equal to 10 % of RATED THERMAL POWER.

(b) Trip may be manually bypassed below 400 psia; bypass shall be auto-matically removed whenever pressurizer pressure is greater than or equal to 500 psia.

-4 (c) Trip may be manually bypassed below 10 % of RATED THERMAL POWER; bypass shall bg automatically removed when THERMAL POWER is greater than or equal to 10 of RATED THERMAL POWER.

During testing pursuant to Special Test Exception 3.10.3, trip may be manually bypassed below 5%

of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is. greater than or equal to 5% of RATED THERMAL POWER.

(d) Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.

(e) See Special Test Exception 3.10.2.

(f) Each channel shall be comprised of two trip breakers; actual trip logic shall be one-out-of-two taken twice.

(g) High steam generator level trip may be manually bypassed in Modes 1 and 2, at 20% power and below.

ACTION STATEMENTS ACTION 1 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or 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/or open the protective system trip breakers.

ACTION 2 With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance witt Specification 6.5.1.6k.

The channel shall be returned to OPERABLE status prior to STARTUP following the next COLD SHUT 00WN.

WATERFORD - UNIT 3 3/4 3-4 AMENDMENT NO. 14

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TABLE 3.3-1 k

REACTOR PROTECTIVE INSTRUMENTATION E

'o MINIMUM E

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP _

OPERABLE.

MODES ACTION 4

l c-5 1.

Manual Reactor Trip 2 sets of 2 1 set of 2 2 sets of'2 1 2 1

I 2 sets of 2 1 set of 2 2 sets of 2 3, 4*, 5*

8 w

2.

Linear Power Level - High 4

2 3

1, 2 2#, 3#

3.

Logarithmic Power Level-High a.

Startup and Operating 4

2(a)(d) 3 1 2 2#, 3#

4 I

4 2

3 3, 4*, 5*

8 b.

Shutdown 4

0 2

3, 4, 5 4

4.

Pressurizer Pressure - High 4

2 3

1, 2 2#, 3#

5.

Pressurizer Pressure - Low 4

2(b) 3 1, 2 2#, 3#

g

[

6.

Containment Pressure - High 4

2 3

1, 2 2#, 3#

J, 7.

Steam Generator Pressure -- Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

8.

Steam Generator Level - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

t 9.

Local Power Density - High 4

2(c)(d) 3 1, 2 2#, 3#

10. DNBR - Low 4

2(c)(d) 3 1, 2 2#, 3#

l

11. Steam Generator Level - High 4/SG 2/SG(g) 3/SG 1, 2 2#, 3#

4

12. Reactor Protection System Logic 4

2 3

1 2 5

3, 4*, 5*

8 1

1

13. Reactor Trip Breakers 4

2(f) 4 1, 2 5

k 3*, 4*, 5*

8 xg

14. Core Protection Calculators,

4 2(c)(d) 3 1, 2 2#, 3# and 7 k

15. CEA Calculators 2

1 2(e) 1, 2 6 and 7

,5

16. Reactor Coolant Flow - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

b-Add