ML19319B956

Application for Amend to License NPR-3 Requesting That Surveillance Requirements on Table 4.3.1 for Intermediate Range Neutron Flux & Rate Instrumentation Be Modified to Not Require Channel Functional Test,If Performed within 7 Days

ML19319B956
Person / Time
Site:	Davis Besse
Issue date:	03/22/1978
From:	Roe L TOLEDO EDISON CO.
To:
Shared Package
ML19319B954	List: ML19319B952 ML19319B956
References
NUDOCS 8001290690
Download: ML19319B956 (3)

Text

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O APPLICATION FOR AMENDMENT TO LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (43) copies of the requested changes to the Davis-Besse Nuclear Power Station Ifnit No. 1 Technical Specifications, Appendix A to License No. NPF-3, together with the Safety Evaluation i

of the requested change.

By _

d Vice President,'Fa'cilities Development Sworn to and subscribed before me this twentieth day of March, 1978.

R M_w 3

Notary Public FRED W. GERMAIN Notary Pubi!c-State of Ohio ks e/13 My Commission Expires Oct. 30,1982

• • 01ag C 7 o

o

. ~.

DB-1 REQUESTED CHANGE TO THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 TECHNICAL SPECIFICATIONS (Appendix A to License No NPF-3)

The attached Table 4.3-1 has been modified by adding tP-Notation (1) for Functional Unit 10 under the Channel Functional Tet oolumn.

ks e/15 i

t

[

g TABLE 4.3-1 REACTOR PROTECT 10fl SYSTEH IllSTRilMErlTATI0tt SURVEILLANCE REQUIREMENTS y

m CllANNEL H0 DES IN WillCil

'E CHANNEL CilANNEL '

FUNCTIONAL SURVEILLANCE "i

FUNCTIONAL UNIT CllECK CAtlBRATI0tt TEST REQUIRED

~

1.

Manual Reactor Trip N.A.

N.A.

S/U(1)

N.A.

~

2.

liigh flux 5

0(2), and Q(7) ll

1. 2 3.

RC liigh Temperature S

R

'M

1. 2 4.

Flux - AFlux - Flow S(4)

M(3) and Q(7,8)

H

1. 2 5

.S.

RC Low Pressure S

R H

1. 2 6.

RC liigh Pressure S

R H

1. 2 g

7.

RC Pressure-Temperature S

R H

1. 2 8.

Illgh Flux /Numtier of Reactor

[

Coolant Pumps On S

R H

1. 2 9.

Contaisunent liigli Pressure S

R H

1. 2 10.

Intermediate Range, fleutron 3

S/U(S)(1) flux and Rate S

R(7)

1. 2 and*

11. Source Range, Neutron Flux and Rate S

R(7)

H and S/U(1)(S) 2, 3, 4 and S

'12. Control Rod Drive Trip Breakers N.A.

fl. A.

H and S/U(1) 1, 2 and*

13. Reactor Trip flodule Logic N.A.

N.A.

H

1. 2 and" p

14.

Sliutduwn Bypass liigli Pressure S

R H

2**.3**,4**,S**

an N

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