ML20212R203

Proposed Tech Spec Table 3.3-1, Reactor Trip Sys Instrumentation

ML20212R203
Person / Time
Site:	Sequoyah
Issue date:	04/16/1987
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20212R194	List: ML20212R192 ML20212R203
References
NUDOCS 8704240345
Download: ML20212R203 (6)

Text

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TABLE 3.3-1 (Continued)

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y REACTOR TRIP SYSTEM INSTRUMENTATION h MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE c FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 5

H 19. Safety Injection Input N

from ESF 2 1 2 1, 2 12 l 20. Reactor Trip Breakers '

?  ? 1, ? , H

• 12,25 A. Startup and Power Operation 2 2 1,1 31,15

8. Shutdown 2 #l #1 3* 4* and 5* 16

21. Automatic Trip Logic  ? I  : 1,2,x2* 12 A. Startup and Power Operation 1 1 2. 1, 1 at B. Shutdown 2 #1 # 2, 3* 4* and 5* 16

$ 22. Reactor Trip System Interlocks

, A. Intermediate Range Neutron Flux, P-6 2 1 2 2, and* 8a B. Power Range Neutron Flux, P-7 4 2 3 1 8b C. Power Range Neutron Flux, P-8 4 2 3 1 8c D. Power Range Neutron Flux, P-10 4 2 3 1, 2 8d E. Turbine Impulse Chamber

, Pressure, P-13 2 1 2 1 8b F. Reactor Trip, P-4 2 1 2 1, 2, and

• 14 s

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TABLE 3.3-1 (Continued) .

g REACTOR TRIP SYSTEM INSTRUMENTATION' 8

MINIMUM

. TOTAL NO. CHANNELS CHANNELS g FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE APPLICABLE

~ MODES ACTION

~*

" 19. Safety Injection Input from ESF 2 1 2 1, 2 12

20. Reactor Trip Breakers 2 1 2 ', ', - ' * . '"-

A. Startup and Power Operation 1 B.

l 1 la 1 lij l5 Shutdown 2

.9* ] 4*1 3*, 4* and 5* 16

21. Automatic Trip Logic  ?  ? 2 1, 2, _.~

• 12 -

w A. Startup and Power Operation 1 2- #1 3 B. Shutdown 2 1

is 1

.@*l .4* 2 3*, 4* and 5* 16

- 22. Reactor Trip System Interlocks A. Intermediate Range Neutron Flux P-6 2 1 2 B. Power Range Neutron 2, and* 8a Flux - P-7 4 2 3 C. Power Range Neutron 1 8b Flux - P-8 4 2 3 1

0. Power Range Neutron 1 8c -

Flux - P-10 4 2 3 I E. Turbine Impulse Chamber 1, 2 8d

i Pressure - P-13 2 1 2 b F. Power Range Neutron 1 8b Flux - P-9 4 2 3 1 8e G. Reactor Trip - P-4 2 1 2 1, 2, and* 14 n

3- n _m ,m.:

9 9 9 $

ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANCES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-21)

DESCRIPTION AND JUSTIFICATION FOR PROPOSED CHANGE TO CORRECT REACTOR TRIP SYSTEN INSTRUMENTATION REQUIREMENTS 9

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i Description of change The proposed change will correct the line items alignment for functional units 20, reactor trip breakers, and 21, automatic trip logic, of Table 3.3-1, " Reactor Trip System Instrumentation." Additionally, the channels to trip, minimum channels operable, and applicable mode requirements for the same functional units will be revised to be consistent with the Westinghouse Standard Technical Specifications (STS).

Reason for Change The line item requirements of table 3.3-1 for functional units 20 and 21 do not correctly reflect the intended requirements. The proposed change 1 will more clearly define each requirement and remove any questions as to j which line requirement belongs to which functional unit.

The applicable modes for startup and power operation under functional units 20 and 21 do not need to include the "*" table note since this condition is covered by the shutdown modes. The numbers required for channels to trip and minimum channels operable to shutdown under functional units 20 and 21 are not correct. The proposed change will place the correct requirements in the table, i Justification for Change l

Functional unit requirements for the reactor trip breakers and automatic trip logic have been separated into two subsections because of the need t for two different action statements. The present line items are

incorrectly aligned. Since the functional unit has been split into two

! subsections, there is no need for line requirements for the functional i unit itself. Additionally, startup and power operation requirements have I been left blank. The proposed chan5e will make the proper alignment.

I The applicable modes for startup and power operation include the "*"

mode. This condition exists when the reactor trip breakers are in the

) closed position, when the control rod drive system is capable of rod withdrawal, and when fuel is in the reactor vessel. The purpose of this requirement is to ensure the "*" condition is covered during modes 3, 4, and 5. The way the functional unit requirements have been restructured, I the "*" mode is covered by the shutdown subsection and does not need to be

included with the startup and power operation subsection.

l The numbor requirements under the shutdown subsection for channels to trip and minimum channels operable are zero and one, respectively. These numbers are incorrect and should be revised to be consistent with the same numbers as required for the startup and power operation subsection. The capability to trip must still exist in the shutdown modes when the trip breakers are closed. Since the trip logic is 1 of 2, the minimum channels operable must be 2.

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l ENCLOSURE 3

', PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 j DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-21)

DETERMINATION OF NO SIGNIFICANT HAZARD CONSIDERATIONS FOR PROPOSED CHANGES TO CORRECT REACTOR TRIP SYSTEM ,

! INSTRUMENTATION REQUIREMENTS I

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ENCLOSURE 3 j

SIGNIFICANT HAZARDS CONSIDERATIONS

} 1. Is the probability of an occurrence or the consequences of an accident previously evaluated in the safety analysis report

significantly increased?

! No. The proposed change to correct line item alignment is strictly an administrative change. The removal of the "*" mode for startup j and power operation is also an administrative change because the change only involves removing a redundant entry. The proposed changes to correct number requirements for channels to trip and 1 minimum channels operable must be made to reflect trip capabilities in the shutdown modes. The proposed amendment involves no

! modifications or changes to the way in which plant operation is conducted.

2. Is the possibility for an accident of a new or different type than j evaluated previously in the safety analysis report created?

No. The proposed amendment is administrative in nature and does not create any new situations to those previously analyzed. The purpose j of the line requirements for the reactor trip breakers and automatic l trip logic has not been changed, i

f 3. Is the margin of safety significantly reduced?

No. The margin of safety has not been affected. The proposed i changes are administrative in nature and will not require any j modifications or alter any testing, action, or operating requirement j of the plant.

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