ML17262A326
| ML17262A326 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/22/1991 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9101310027 | |
| Download: ML17262A326 (4) | |
Text
I ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9101310027 DOC.DATE: 91/01/22 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATXON MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3 DOCKET 05000244 R
SUBJECT:
Responds to issue re testing of turbine driven auxiliary feedwater pump recirculation check valve 4023 at plant.
Relief Request VR-23 invoked in order to satisfy ASME Section XI testing requirements.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR J ENCL g SIZE: oF TITLE: OR Submittal: Inservice Inspection/Testing/Relief from ASME NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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Code 05000244 RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: AEOD/DSP/TPAB NRR/DET/EMEB 7E OC ~EN G NIL 01 EXTERNAL: EG&G BROWN,B NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD NRR/DET/ECMB 9H NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EG&G RANSOME i C NSIC COPIES LTTR ENCL D
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NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 16 ENCL A
D D
S
/////rm'il/IIII ROCHESTER GAS AND ELECTRIC CORPORATION o
89 EAST AVENUE; ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY Vice President Clnna Nuclear Producrion January 22, 1991 TELEPHONE AREACODE 7s6 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Nashington, D.C.
20555
Subject:
Inservice Test Program Relief Request No. VR-23 R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson:
This correspondence is in, response to the issue regarding the testing of the turbine driven auxiliary feedwater pump recirculation check valve,
- 4023, at Ginna Station.
Currently, relief request VR-23 is invoked in order to satisfy ASME Section XI testing requirements.
VR-23 states that since the recirculation line is not instrumented, forward flow exercising of 4023 is not practicable.
Partial stroke exercising each quarter and dis-assembly each refueling outage shall be performed. in its place.
A plant modification is presently underway to install an annubar flow instrument in the turbine driven auxiliary feedwater pump re-circulation line.
At this time, acceptance testing and engineering evaluation are required'o be completed before this new instrumen-tation is employed. to satisfy ASME Section XI testing.
Once the turbine driven auxiliary feedwater pump recirculation flow instrument is accepted, relief request VR-23 will be deleted from Ginna Stations's Inservice Test Program and. full flow exercising per ASME Section XI will be performed..
Our present target completion date for this change is the end of the 1991 Refueling Outage.
Very truly yours, Robert C.
Me edy KM/133 9102310027 910l22 PDR ADOCK 05000244 PDR
xc: Mr. Allen R. Johnson. (Mail Stop 14D1)
Project Directorate I-3 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
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