ML17263A285
| ML17263A285 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/07/1993 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9305170162 | |
| Download: ML17263A285 (4) | |
Text
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ACCEI ERAT DOCUMENT DISTRIBUTIONSYSTEM REGULATO INFORMATION DISTRIBUTIONOISTEM (RIDE)
ACCESSION NBA:9305170162 DOC.DATE: 93/05/07 NOTARIZED:
NO DOCKET FACIL:50-'244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3
SUBJECT:
Provides addi info in support of 930420 Relief Request 23 re hydrostatic pressure test alternatives for AFW sys recirculation check valve V-4023.Operability test performed during 1993 refueling outage post-installation testing.
DISTRIBUTION CODE:
A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code D
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 A
RECIPIENT ID CODE/NAME PD1-3 LA JOHNSONFA INTERNAL: NRR/DE/EMEB C/r-rMB E~L~E 01 RES/DSIR/EIB EXTERNAL: EG&G BROWN,B NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME PD1-3 PD NUDOCS-ABSTRACT OGC/HDS1 RES MILLMAN,G EGSG RANSOME,C NSIC COPIES LTTR ENCL D
D D
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED:
LTTR 15 ENCL ~a~
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,/ ggiI" ROCHESTER GAS AND ELECTRIC CORPORATION 8Z.::
o 89 EAST AVENUE, ROCHESTER N.Y. 14649-0001 ROBERT C MECREDY Vlcc PreHdent Cinna Nuclear Production May 7, 1993 TELEPHONE ArtErtcooE7 le 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project Directorate I-3 Washington, D.C.
20555
Subject:
Ginna Nuclear Power Plant Inservice Inspection Quality Assurance Manual, Appendix B
ASME Section XI Required Examinations Relief Request f23 R.E.
Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):
Letter from R. C. Mecredy (RGGE), to A. R. Johnson (NRC),
Subject:
Ginna Nuclear Power Plant, Quality Assurance
- Manual, Appendix B,
ASME Section XI Required Examinations, dated April 20, 1993
Dear Mr. Johnson:
This letter provides additional information in support of the hydrostatic pressure test. alternatives for the Auxiliary Feedwater System recirculation check valve V-4023 welds described in Relief Request No.
23 as referenced-above.
Although the pump shutoff head from the head-capacity curve is about 1620 psi, the maximum running pressure that the check valve is subjected to in service is approximately 1425 psig.
This occurs during quarterly operability testing of the downstream minimum flow recirculation valve 4291 (see P&ID 33013-1237, UFSAR Figure 10.5-1).
During post installation testing for the V-4023 replacement during the 1993 refueling
- outage, this operability test was performed.
The test included performing an ASME Section XI VT-2 examination as documented in the installation work package for SM.
We believe that this information is consistent with the information exchanged during the telecons between RGGE and Allen Johnson and Don Naujock of the NRC on April 29, 1993 and May 3, 1993.
Very truly yours, 2 goy ~
,."9305170162 930507 PDR
'*DOCK 05000244
',,'P';;
PDR Robert C. Mecredy
(,O'I q)4 o@
REJ/283 Attachment 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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