IR 05000244/1997201

Forwards Copy of Leak-Before-Break Evaluation of Portions of RHR Sys at Re Ginna Nuclear Power Station, as Follow Up to Insp Rept 50-244/97-201,for Review & Approval

ML17264B099
Person / Time
Site:	Ginna
Issue date:	11/11/1997
From:	MECREDY R C ROCHESTER GAS & ELECTRIC CORP.
To:	VISSING G S NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17264B100	List: IR 05000244/1997201 ML17264B099 ML17264B101
References
50-244-97-201, NUDOCS 9711190067
Download: ML17264B099 (2)

Text

CATEGORY 1 REGULATOR..INFORMATION DISTRIBUTION STEM (RIDS)ACCESSION NBR:9711190067 DOC.DATE: 97/11/11 NOTARIZED:

NO FACXL:50-244 Robert Emmet Ginna'uclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION'ECREDY,R.C.

Rochester Gas&.Electric Corp.RECIP.NAME RECIPIENT AFFXLIATION VXSSING,G.S,.

DOCKET 0 05000244 SUBJECT: Forwards copy of"Leak-Before-Break Evaluation of Portions of RHR Sys at RE Ginna Nuclear Power Station," as'follow up to insp rept 50-244/97-201,for review 8 approval.~i/DISTRIBUTION CODE: XEOID COPIES RECEIVED:LTR I ENCL 1 SIZE: TITLE: General (50 Dkt)-'Xnsp Rept(Notice of Violation Response NOTES:License Exp'date'n accordan'ce with 10CFR2,2.109(9/19/72).

05000244 g RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD/SPD/RAB DEDRO NRR/DISP/PXPB NRR/DRPM/PECB NUDOCS-ABSTRACT OGC/HDS3 EXTERNALs LITCO BRYCE,iT H NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1'1 1 1 1 1 1 1 1 RECIPIENT.;, ID CODE/NAME VXSSXNG,G.

FXLE CENTE~DR HHFB NRR/DRPM/PERB OE DIR RGN1 FILE 01 NOAC NUDOCS FULLTEXT COPIES LTTR ENCL 1 1 1 1 1 1~1 1 1 1 1 1 1 1 1 1 1 1 0 R 0 E N NOTE TO ALL"RZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 18 AND ROCHESTER GAS AND ELECTRIC CORPORATION

~89 EAST AVENUE, ROCHESTER, M Y IrIbf9-0001 AREA CODE 716 546-27M ROBERT C.MECREDY Vice President Nuclear Operations November 11, 1997 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555 Subject: Rochester Gas&Electric Corporation's 50-244/97-201-03 Inspection Report R.E.Ginna Nuclear Power Plant Docket No.50-244

Dear Mr.Vissing:

During the subject inspection, the A/E Inspection team identified Inspector Follow-up Item 50-244/97-201-03, wherein NRC approval is required of the fracture mechanics evaluation performed for the 10-inch Residual Heat Removal RHR)piping to qualify for a leak-before-break exclusion in accordance with 10CFR50, App.A., Criterion 4.Attached for the NRC's review and approval is a copy of the"Leak-Before-Break Evaluation of Portions of the RHR System at R.E.Ginna Nuclear Power Station." Very Truly yours,/km Enclosure Robert C.Mec dy xc: Mr.Guy S.Vissing Project Directorate I-1 U.S.Nuclear Regulatory Commission Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector 9711190067

%711%1 PDR ADOCK 05000244 8 PDR IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII