ML19326C134

Requests Amend to License DPR-51 to Allow Mod to Tech Specs Re Increase to Spent Fuel Rack Storage Capacity.Tech Specs 5.4 & 9,AP Pettit Affidavit,Fsar Page Revisions & Safety Analysis for Fuel Storage Rack Encl

ML19326C134
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/07/1976
From:	Pettit A ARKANSAS POWER & LIGHT CO.
To:	Ziemann D Office of Nuclear Reactor Regulation
Shared Package
ML19326C135	List: ML19326C134 ML19326C140 ML19326C144
References
NUDOCS 8004210632
Download: ML19326C134 (6)

Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

.[Cemu19,5 U.S. NUCLE AR REGULATo AY ( WSSl!N ooCKET NUMOER

'ad' .

- sn 111 NRC DISTR 10UTION roR PART 50 DOCKET MATERIAL To: Mr Ziemann FROM: Arkansas Pwr & Light do oATE oF OoCUMENT Little Rock, Ark 1n-7-76 A P Pettit oATE RECEIVED 1Q.8 76 OLcTTcR ONoroRizco PROP INPUT FORM NUMBER oF COPIES RECEIVED 1C oRiu'N AL QuNcL ASSIFIE D OcoPv one signed DESCRIPTION E N CLoSU R E Ltr notarized 10-I-76. . . .trans the following: Amdt to OL/ Change to Tech Specs: Consists of revised & addl pgs, tables, figs & info to 6ppendix A with regard to spent fuel rack modifications. . . .(40 cys enci rec'd)

THIS DOCUMENT CONTAINS P00R QUAUTY PAGES -

A. CKNOWLEDGEb PLANT NAME: Arkansas #

DONOT REMoyg a

SAFETY FOR ACTION /INFORMATION ENVTRO 10-12-76 ehf

'A33 mne.u au: L '

_f.SO'*,00 /.0:

/J_RANCit Cl[IEF: '2.1 e_ rri ot n e9 f.5) BEAUCH cHTEF.

f. PROJECT PANAGER: do no e,y s e PROJECT MANAGER?

/ LIC, ASST.: Si c g LIC. ASST.!

_j INTERNAL DISTRIBUTION r ' Kt.G JILE 7 ~

SYSTEMS SAFETY PTANT SYSTEifS SITE SAEETY &

Gt.jiu, run HEINEMAN - P.ne.sen ENVIRO ANALYSIS I

/ I & E ( 2,)

SCHROEDER BENAROYA DENTON & MUT T.FR l

/ OEl.D LAINAS ')

2 COSSICK & STAFF .

ENGUIEERING IPPOLI.TO ENVIRQ,TEC11. ___

_M EC MACCARRY Kl_IlKWOOD FRNST CA_SE KNICllT BALIARD ..

_JtANAUER SIINEIL OPERATING REACTORS SPANcf FR , _

ltARLESS PAWLICKI STELLO p CCOEury syry rycn

_JJ._01ECT MANACElfENT REACTOR SAFETY OPE _ RATING _TF,Sil. CMSITLL BOYD _R,0S.S / E I_SE_f[lLUT STEPP

_l. COI. LINS _NOVAK / SHA0 11ULMAN HOUSTON ROSZTOCZY / BAER /

PETERSON CllECK / BUTLER SITE _AFALYST S {'

_MELTZ / GR_lES VOLLMER 11ELTI'.MES AT & I BUUCll SKOV110LT SALTZMAN / .fmCOLLINS._

RIITRERG KRFcFR EX1 EllNAL UlSTH10U TION _ CONTHOL NUMUER 2I.PDR;fgy14,llut(fc.4,/C NAT LAB: BR00Klf4VER yATh ./

b04210[3)

TIC: HEC. VIE UI.RIKSON(OR'lL) Q( g

(( tt3Ic.

1.A PDR /

ASI.ll - C0!!SULTA!ITS

? ACRSMYS = . i. .t.7i EN f7J E b y

/6220

&,=:= ;;.= --

~

. REGm ou ~anqY DOCKET r(LE CO?Y H EL PIN G BUILO ARKANSAS A AK ANS AS POWER G LIGHT COMPANY p0 sox esi LsT*LE AOCK. A AK ANSAS 722O3 15011371 4000 October 1976 9 f Dr N

1-106-1 O go UtreAC f

Director of Nuclear Reactor Regulation P ATTN: Mr. Dennis L. Ziemann, Chief Operating Reactor Branch #2

6) @hl97

~

C cy, ,m i 13 U. S. Nuclear Regulatory Commission 9 * ,,%" '" * *  !

Washington, D. C. 20555

% ,s Subj ect: Arkansas Power 6 Light Compa Arkansas Nuclear One-Unit 1 O1)[f7 Docket No. 50-313 License No. DPR-51 Spent Fuel Rack Modification (File: 1511.1, C-42.1)

Gentlemen:

Our Ictter to you of September 9,1976, notified you of our intent to modify the spent fuel racks of Arkansas Nuclear One-Unit 1 (ANO-1) to provide increased storage capacity for spent fuel. Arkansas Power 6 Light Company thus requests an amendment to Operating License No. DPR-51 to allow such a change. This amendment will allow AP6L to replace the existing spent fuel racks consisting of 253 storage locations plus one failed fuel container location, with new racks consisting of 590 storage locations plus one failed fuel container location.

Submitted herewith as Attachment I to this letter are proposed changes '

to the Technical Specifications for ANO-1 to accommodate this modification.

In addition, changes will be required to the ANO-1 Final Safety Analysis Report (FSAR). These changes are presented in Attachment II to this letter as' information to aid in your review and approval of this license amend-ment. Actual replacement pages to the FSAR will be distributed when the license amendment is grr.nted.

Attachment III to this letter is a safety analysis of the proposed modifi-cation. This analyois addresses the safety and environmental matters associated with the change with the exception of a seismic analysis of the new racks. Tha: analysis will be submitted for review by the NRC Staff on October 18, 1976.

2%O T A x p Av4NG. INVESTOR OWNEO d MEMBER M400LE SOU TH U TILITIE S S YSTEM

Mr Dennis L. Ziemann Octobsr 7, 1976 1 106

• As we identified to you in our September 9, 1976 letter, the schedule for this modification is very tight in order for us to be prepared for the first refueling of ANO-1 which is currently scheduled to begin in mid-January 1977. Our schedule calls for us to begin removal of existing racks on November 1, 1976. For that reason, we request that a meeting be scheduled for October 27 or 28, 1976 to discuss any NRC Staff concerns on this matter.

.Your prompt review and approval of this change are requested.

t Very truly yours, bf$

A. P. Pettit President APP:ay

f, * . . . /- .

. ~

STATE OF ARKANSAS )

) SS COUNW OF PillASKI )

A. P. Pettit, being duly sworn, states that he is the President of Arkansas Power T Light Company; chat he is authori:cd on the part of said Company to sign and file with the Nucicar Regulatory Commission this Supplementary informatlon; that he has reviewed or caused to have reviewed all of the statements contained in such Information, av d that all such statements made and matters set forth therein are true and correct to the best of his knowledge, i n fo rma t i on and belief.

A. P. Pettit SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the County and State abo,vc named, this lb day of- k (id. % , 1976.

0% b. (sCo m a Notary Public My Commission Exprics:

March 1, 1978-

To-SIS "Lt t Oc bz) ' h 5 *htggk64.[

os j ATTACINENT I ARKANSAS NUCLEAR ONE-UNIT 1 I

PROPOSED AMENDMENT 1 To OPERATING LICENSE NO. DPR-51

~

l l

10:23

,~ ~~

,/ ' .

.S.4 NEW AND SPENT FUEL STORAGE FACILITIES Applicability Applies to storage facilities for new and spent fuel, assemblies.

Objective To assure that both new and spent fuel assemblies will be stored in such a manner that an inadvertent criticality could not occur.

Specification 5.4.1 New Fuel Storage

1. New fuel will normally be stored in the new fuel storage pool. The fuel assemblies are stored in racks in parallel rows, having a nominal center to center distance of 21 inches in both directions. This spacing is sufficient to

' maintain a Keff of less than .9 even if flooded with unborated water, based on fuel with an enrichment of 3.5 weight percent U235.

2. New fuel may also be stored in the spent fuel, pool or in their shipping containers.

5.4.2 Spent Fuel Storage

1. Irradiated fuel assemblics will be stored, prior to offsite shipment, in the stainless steel lined spent fuel pool, which is located in the auxiliary building. The pool is sized to accommodate a full core of irradiated fuel assemblies in addition to the concurrent storage of two and one-third cores of. spent fuel previously discharged. L

2. The spent fuel pool is filled with borated water with a minimum concentration of 1800 ppm boron during refueling.

3. One spent fuct storage rack position is designed to accommodate a special container for storage of a leaking fuel assembly.

4. The spent fuel pool and new fuel pool racks are designed as seismic Class 1 equipment.

References

'FSAR, Section 9.6 116

. -