ML18143A968
| ML18143A968 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/22/1976 |
| From: | White L Rochester Gas & Electric Corp |
| To: | Purple R Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18143A968 (2) | |
Text
I:RC FCQM 195 I2 70I U.S. NUCLEAR REGULATORV C~ 'hIISSION DOC~ET NUMBER NRC DISTRIBUTION FQR PART 50 DOCKET MATERIAL FILE NUMBER TO:
MR R A'URPLE FROM:ROCHEST R GAS & ELEC CORP ROCHESTER, NY L D WHITE, JR DATE OF DOCUMENT
.3-Ll-ll DATE RECEIVED Q ay ETTE R ORIGINAL QCOPV DES C RIP T ION QNOTORI2ED UNC LASS IF I E D PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED L Sqn~~
LTR FURN REVIEW OF INSERVICE INSPECTION IN VIEW'OF PROJECTED FUEL STORAGE(
CAPABILITY..~....'
L
. PLANT NAME: QX.nba 4 <
SAFETY FOR ACTION/INFORMATION ENVIRO
~
4 ASSIGNED AD:
BRANCH CHIEF:
PROJECT MANAGER:
LIC~
SST a 4C.
ASSIGNED AD:
BRANCH CHIEF
~
PROJECT MANAGER:
LIC~ ASST REG FILE NRC PDR I &E GOSSICK & STAFF ENG NEER KNIGHT SIHWEIL PAVLICKI INTERNALDISTRI BUTION BENAROYA IPPOLITO OPERATING REACTORS STELLO OPERATING TECH E NST ALLARD SPANGLER SITE TECH GAMMILL STEPP HULMAN PROJECT MANAGEMENT BOYD P
COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT Lfbg'PDR0 TIC NS P
ASLB REACTOR SAFETY ROSS NOVAK ROSZTOCZY CHECK AT & I SALTZMAN RUTBFRG EXTERNAL ISTRIBUTION NATL LAB REG, V"IE LA PDR CONSULTANTS EISENHUT SHAO BAER SCHWENCER GRIMES SITE SAFETY & E R
ANALYSIS DENTON & MULLER BROOKHAVEN NATL LAB ULRIKSON(ORNL)
SITE ANALYSIS VOLIIIER BUNCH J,
COLLINS KREGER CONTROL NUMBER NRC FORM 195 I2 76)
I
~
ir/ ///I//III// g////I/ll/EiZ!/.
Ilrimz/Ill //II!izzzusu ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR.
VICE PRESIDENT a@eh-lg 1976 TELEPHONE ARE* CODE TIS 546T2700
,P'sr (9
DOET~O, gO u~T'" '
+ucP~~c,b+
Ig u.s "EO S,ch~
r Office of Nuclear Reactor Regulatio ATTN: Mr. Robert A. Purple, Chic Operating Reactors Branch Division of Operating React r
Washington, D. C., 20555
'4 in view of projected
Subject:
Review of inservice inspection fuel storage capability.
R. E. Ginna Nuclear Power Plant Unit No.
1 Docket No. 50-244
Dear Mr. Purple:
This letter is in response to your letter of February 9, 1976, regard-ing the effect of fuel storage capability on inservice inspection capabilities.
Rochester Gas and Electric Corporation has reviewed the inservice inspection requirements which would involve full core discharge and has determined that Technical Specifications would require full core discharge during the Spring 1979 outage.
The present spent fuel pit capacity is insufficient to accommodate such a discharge; however, in view of the shortage of spent fuel storage capa-bilityRG6E has submitted a proposed spent fuel pit modification to the NRC which would relieve the shortage at Ginna and would permit the 1979 inspection.
Very truly yours, r
L. D. White, 7r.