ML19308B050
| ML19308B050 | |
| Person / Time | |
|---|---|
| Site: | Oconee |
| Issue date: | 07/27/1977 |
| From: | Parker W DUKE POWER CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912120802 | |
| Download: ML19308B050 (2) | |
Text
_ _ _
,e4 NRC romu 196 u.s. Nucts An gsautAToav coquiss4N oCCKsT NuM!sn (3 76)
NRC DISTRIBUTION con PART 50 DOCKET MATERIAL TO:
FROM:
oats cP ooCvMsNT Duke Power Company 7/27/77 Mr. Edson G. Case Charlotte, North Carolina o,7,,,c,,y, o William O. Parker, Jr.
8/1/77 l
I CLsTTsa CNoTomizso anon iNeur eeau Nuussa or copias,<sesivso ComiciN AL CuNcLAssiciso Ccopy essemeTios sNetosvas g-fh.. rt.
WAS /E'I'] S l' E /b Consists of information concerning the increase of the fuel cycle length for Cycle 3 to 312 EFPD.....
3m--,_.....,,..,
)
(y,p)
Av--+ ele'e<i.~.,y.gA)
~
PLANT NAME: Oconee Unit No.1 J'O' *
- - - - 4 :., f i,s RJL 8/2/77 cape-r FOR ACTION /INFORMATION ENVIPSNMENT3.~.
I AgqicNED AD, ASSIGNED ADt V. MOORE (LTR)
I unetcn tyTE?,
BRANCH CHIEFt
~
PROJECT MANAGER:
i PROJECT WANAGERr I
LICENSING ASSISTANT:
LICENSING ASSISTANT:
I i
B. MARLESS INTERNAL OlSTRIBUTION r an "'- '
l SYSTFMS SAFEIY PIRE SYSTEMS SITE SAFETf &
'i no r-pnp i HEINe' MAN TEDESCO
' ENVIRON ANALYSIS Iv
- e. e SCHROEDER 3ENAROYA DENTON & MULLER I met n T A T'73 g
< perer urver n I CO C C T /"< & STAF?
ENGINEERING
.IPPOLITO I vivwee
'rNTCMT IF. ROSA I ENVIRO TECH.
I vter-BOCNAK I
I ERNST
.! < sce r-j eingEtt iOPERATING REAC*0RS BALLARD I pnvr) i DA%1.It TT STET 10 YOUNGBLCOD 1
1 ETCfNutr I own Ter-- u a n Ac t w yeAC'TR CATIT'l CHA0 A*
I 5 : wunt ?
ROSS 3AER
! 'e
ilTN9 NOVAK 3UTLER I GAMMILL (2)
I untrR9'N I
ROSZTOC2Y GRI"ES l
i ve' T*
I CHEC~<
l SITli ANALYSIS Iverreves i
VOLLMER I CV AT&T 3UNCH I
SALT
- MAN I
J. COLLINS I
ipen3 ERG l
KREGER EXTERNAL DISTRIBUTICN CONTROL NUMBER M E'
- ')lt 5(
j p
,y 1NAT 'AE h
,,2140224
~p IREG IV IJ. HANCME"") I i i
16 CYS ACPS SENT CAT 3GCRY l a f
i t i i
- eLeeonw 19512 78)
DUKE POWER CO IPMY j
^*
Powra Dt:::.ntxo 422 SouTu Cat: wen Srner, CnAnt.oTTE, N. C. 2a24a
..wwo.. men.E July 27, 1977 (CF Pats.cgwr
'gst.=c%g: Anga 704 5'came paoovceow 373-4083 Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 RE: Oconee Unit 1 Docket No. 50-269
Dear Sir:
By letters dated December 1, 1975 and February 27, 1976, proposed amendments to the Oconee Nuclear Station Technical Specifications were requested to assure the operation of Oconee 1, Cycle 3 core within applicable fuel design and performance criteria. As stated in the accompanying report BAW-1427 "0conee Unit 1, Cycle 3 Reload Report" the design cycle length was 292 EFPD. NRC approval for operation of Oconee 1, Cycle 3 was granted on March 25, 1976.
As discussed with members of your staff, recent unscheduled outages on the Duke system have made it desirable to increase the fuel cycle length for Cycle 3 to 312 EFPD. The existing technical specification limits have been reviewed and it has been confirmed that they remain valid for this extended cycle length.
Very truly yours, w
, % - lD.
u
' William O. Parker, Jr. d MST:ge 772140214