ML17263A206: Difference between revisions

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| issue date = 04/05/1993
| issue date = 04/05/1993
| title = Forwards Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR
| title = Forwards Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR
| author name = MECREDY R C
| author name = Mecredy R
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| author affiliation = ROCHESTER GAS & ELECTRIC CORP.
| addressee name = JOHNSON A R
| addressee name = Johnson A
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000244
| docket = 05000244

Revision as of 03:43, 19 June 2019

Forwards Application for Amend to License DPR-18,revising TS to Remove Containment Isolation Valve Table 3.6-1 & Maintain Required Listing in Updated FSAR
ML17263A206
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/05/1993
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Andrea Johnson
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML17263A207 List:
References
NUDOCS 9304090207
Download: ML17263A206 (5)


Text

ACCELERA D DOCUMENT DIST UTION SYSTEM REGULARLY INFORMATION DISTRIBUTI SYSTEM (RIDS)ACCESSION NBR:9304090207 DOC.DATE: 93/04/05 NOTARIZED:

YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

Project Directorate I-3

SUBJECT:

Forwards application for amend to License DPR-18,revising TS to remove containment isolation valve Table 3.6-1&maintain required listing in updated FSAR.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:

General Distribution D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244/RECIPIENT ID CODE/NAME PD1-3 LA JOHNSONgA INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS1 COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 0 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DORS/OTSB NRR/DSSA/SCSB NRR/DSSA/SRXB OC EG FILE 01 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 A D NSIC 1 1 EXTERNAL: NRC PDR~>p2~aeqg)qg 1 1 A NOTE TO ALL"RIDS" RECIPIENTS:

I'LEASE HELP US TO REDUCE WASTE!CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!D TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14

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ROCHESTER GAS AND ELECTRIC CORPORATION rst1 il rO IA4 o 89 EAST AVENUE, ROCHESTER N.K 14649-0001 ROBERT C MECREDY Vice President Oinne Nucleer Production April 5, 1993 TELEPHONE AREA CODE 716 546.2700 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555

Subject:

Application for Amendment to Facility Operating License Rochester Gas and Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244

Reference:

(a)Letter from R.C.Mecredy, RG&E, to A.R.Johnson, NRC,

Subject:

Removal of the Table of Containment Isolation Val ves from Technical Specifications, dated November 30, 1992.

Dear Mr.Johnson:

Rochester Gas and Electric (RG&E)has proposed (Reference a)to revise the Ginna Station Technical Specifications to remove Containment Isolation Valve Table 3.6-1 and maintain the required listing in the UFSAR.However, this request, affecting many containment isolation and testing issues, has not yet been approved.Therefore, RG&E requests that a limited number of specific changes be made to Technical Specification Table 3.6-1 to support the Integrated Leak Rate Test (ILRT)which is to be conducted during the 1993 Refueling Outage.NRC approval of these changes is required prior to filling and venting the reactor coolant system which is currently scheduled for April 14, 1993.The proposed Amendment should be considered effective within 30 days after RG&E receipt of NRC approval.Very truly yours, Robert C.Mecr dy MDFtt518 08003~-'8040'7t0207-930405 PDR"ADOCK 05000244 P PDR' e l's'i xc: Mr.Allen R.Johnson (Mail Stop 14Dl)Project Directorate I-3 Washington, D.C.20555 Ms.Donna Ross New York State Energy Office U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector