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)

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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

• • 01ago C 7o

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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

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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

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1. Manual Reactor Trip N.A. -

N.A. S/U(1) N.A.

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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 flux and Rate S R(7) 1. 2 and*

11. Source Range, Neutron Flux S/U(S)(1) 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**

a n

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