ML19320A163

Forwards Proposed Change to Tech Spec 3.5 Re Parameter Changes & Mods Required for Cycle 3 Operation & B&W Reload Rept as Suppl Info.Requests Approval of Proposal Prior to Second Week in Mar

ML19320A163
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/28/1977
From:	Rueter D ARKANSAS POWER & LIGHT CO.
To:	Desiree Davis Office of Nuclear Reactor Regulation
Shared Package
ML19320A164	List: ML19320A163 ML19320A167
References
1-127-19, NUDOCS 8004210466
Download: ML19320A163 (3)

Text

._ .- - _ _ _ _ _ __ _ _

bfSIKI3UTION Ab ISSUANCE OT "?E3AT'.NG LICENSE U.S. NuctzAn Raout. Atony con. -sai occxs?NuM14A

! NHC exw 196 f :2 789 k -

@- 3 /__3 l NRC DISTRIB0 TION aan PART 50 DCCKET MATERIAL l

.TO: FROM: =AT or cccuMaNT i Arkansas Power & Light Company 12/28/77 i Mr. D. K. Davis Little Rock, Arkansas ,,

, ,, gg,y , ,

Donald A. Rueter 12/29/76 .

, y- s n ONoToni:so ence iseurpopu wussa or c Pies anczivso l c3iGIN Al. Cd'NC LAS38 Fi t o I CCC / /$/M@

ssentPTicN 1 ENC:.OsuRE LJcense No. DPR-51 Appl for Amend: tech specs propcsed change concerning parameter -

changes and modifications required for Cycle l

. 3 operation..w/att supplementary info. in the

' f rm f a rePcrt entitled " Arkansas Nuc1, ear THIS DOCUMENT CONTAINS One, Unit 1 - Cycle 3 Reload Report " . . . . . . . .

POOR QUALITY PAGES na )

(18-P )+(1/ 4")

l PLANT NAME: Arkansas Unit No. 1 Af C RKl .

.RJL 1/3/78 s cp. B AtA> -t o 1 ,12e Przo b uct:_.

3R hs . '

' SAFETY FOR ACTION /INFORMATICN ,

, '3 RANCH C9IEF: (7) I ,Bh_S HEAD to H E@

l I

! l  !

I I I

I l l l I l . i  !

l ..---.J.. l l . l i r w ' % INTERNAL OtSTRIBUTION 1 J l i j i j M ?" - - . M A. CQ. . hi O hme enn f I i l l l le c. e in I I I iI L e rT 9 I I I I i b a Na t-ru l l  ! l l Puery i I 1 6 i  ;

i eve- ver- i f I  : 1 I

! cuan I l l 1 l l l

! 9 4 F7 I I I I I I

%t- T ru I I I l t I mmre l I I l l 1 i

'J. COLEINS I I l i l 1 ,

I 'I . MCC0t' Git i  ! t I  ! I i

! I I a i i s i i l i I i i  !

i  !  ? i i I f  !

i l i  ! I I i i t t i i i i I j

' i !  ! 6 i i i EXHRNAL OlST318UTICN CONTROL NUM3ER i t

L2}R: /t%Ksett wtl.e t/W/Y'.

• g i to .o

-II, 1 i 1 4 ,

! ACR5 le CYS SCC CAIIGCR*1_f/ 1 l j 3o04210 Igg

, 7") [ p ; . . - - . . .. , , .

.;f_y H ELPING BUILO ARKANSAS ARK ANS AS POWER S LIGHT COMPANY po. sox set Lef,L. AOCK. A A< A NS.. 72203 55013371-4000 December 28, 1977 1-127-19 ( ! f,?

Director of Nuclear Reactor Regulation I ATIN: Mr. D. K. Davis, Chief .l?-n ff i operating Reactor Branch #2

{s.f4 ,08cg8/,/p[ gg '

i U. S. Nuclear Regulatory Commission -

Washington, D.C. 20555 7 ,-

k f *'c er

Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 ,

g5{fl Proposed Technical Specifications (File: 1511.1)

Gentlemen:

Enclosed please find a proposed change to the Arkansas Nuclear One-Unit 1 Tec!'nical Specifications for your review and approval. This proposal was pre ,ared by-the Nuclear Power Generation Division of Babcock and Wilcox to incorporate those parameter changes and modifications required for Cycle 3 operation. Three copies of the Arkansas Nuclear One-Unit 1, Cycle 3 Reload Report as prepared by Babcock and Wilcox is attached as supplementary information.

Presently, the second refueling outage for Unit 1 is scheduled to begin January 28, 1978, and continue for approximately 8 weeks. Therefore, we are requesting that this proposal be approved and returned no later than the second week in March in order to allow time for implementation prior to Cycle 3 startup. '

If we may be of any further assistance in this regard, please contact us.

Very truly yours, Ad*

' onald A. Rueter

/ Director, Technical S Environmental Services DAR:JTE:nf Attachments

..-.. _ .. - _ .. ,z . -.-.. - .. - ..,...... .-

.. .. . n n.

Using a local quality limit of 22 percent at the point of minimum DNBR as a basis for curve 3 of Figure 2.1-3 is a conservative criterion even though the quality at the exit is higher than the quality at the point of minimum DNBR, The DNBR as calculated by the BAW-2 correlation continually increases from point of minimum DNBR, so that the exit DNBR is always higher and is a function of the pressure.

The maximum themal power for three pump operation is 85.6 percent due to a power level trip produced by the flux-flow ratio (74.7 percent flow x 1.060 79.1 percent power) plus the maximum calibration and instrumentation error.

The maximam themal power for other reactor coolant pump conditions is pro-duced in a similar manner.

For each curve of Figure 2.1-3, a pressure-temperature point above and to the left of the curve would result in a DNBR greater than 1.3 or a local quality at the point of minimum DNBR less than 22' percent for that particular reactor coolant pump situation. Curves 16 2 of Figure 2.1-3 are the most restrictive because any pressure / temperature point above and to the left of this curve will be above and to the left of the other curve.

PIFERENCES (1) Correlation of Critical Heat Flux in a Bundle Cooled by Pressurized Water, BAW-10000A, May, 1976. .

(2) FSAR, Sect ion 3. 2.3.1.1.c

@dwn Amendment No. 21