ML17262A810
| ML17262A810 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/01/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9204130006 | |
| Download: ML17262A810 (6) | |
Text
ACCELERATED D TRIBUTION DEMONS TION SYSTEM REGULATORY XNFORMATION DISTRIBUTION SYSTEM (RIDS )
ACCESSION NBR: 9204130006 DOC. DATE: 92/04/01 NOTARIZED:
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
Project Directorate I-3 DOCKET 05000244 R
/
05000244 A
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
COPIES RECIPIENT LTTR ENCL ID CODE/NAME RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A COPIES LTTR ENCL D
PD1-3 PD D
SUBJECT:
Advises that util investigating possibility of using BGW explosive-welded tubesheet sleeves as repair technique during 1992 refueling outage,per NRC 860130 ltr.Sleeves will use Inconel Alloy 690 thermally-treated matl.
DISTRIBUTION CODE:
A054D COPIES RECEIVED:LTR
(
ENCL ~
SIZE:
TITLE: OR Submittal:
Steam Generator Sleeving Review for PWR's INTERNAL: AEOD NRR/DOEA/OGCB11 NRR/PMAS/ILRB12 OC B
EG FILE 01 EXTERNAL: NRC PDR p1 y 49 7S~ ~~
NRR/DET/ECMB 9H NRR/DST/SPLB 8D NUDOCS-ABSTRACT OGC/HDS 1 RES/DS IR/EIB NSIC 1
1 1
1 4 1
D NOTE TO ALL"RIDS" RECIPIENTS:
D D
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 16 ENCL
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~,t 7z'ru,zzzirn ROCHESTER GAS AND ROBERT C. MECREDY Vice President Cinne Nudeer Production 3K::
ELECTRIC CORPORATION o
89 EAST AVENUE, ROCHESTER N. K 14649-0001 April 1, 1992 TELEPHONE AREACODE 716 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Allen R. Johnson Project, Directorate I-3 Washington, D.C.
20555
Subject:
B&W Explosive Welded Tube Sleeves Reference 1)
NRC Letter from G. Lear to R.W. Kober (RG&E),
"Steam Generator Tubesheet Sleeving",
1-30-86
Dear Mr. Johnson:
This letter is to inform the NRC that Rochester Gas
& Electric (RG&E) is investigating the possibility of using B&W explosive welded tubesheet sleeves as one of our repair techniques during the 1992 Refueling Outage.
These sleeves may be used either in combination with Combustion Engineering (CE) welded sleeves or in place of CE welded sleeves.
Although RG&E has used CE welded sleeves exclusively over the past six Refueling Outages, B&W sleeves have been used prior to 1986 at Ginna.
By Reference 1, the NRC granted RG&E permission in 1986 for unrestricted use of the B&W tubesheet sleeve.
The tubesheet sleeves being considered by RG&E are similar to the sleeve design approved by the NRC in 1986 except for a material change.
Sleeves which may be installed in 1992 and the future will use Inconel Alloy 690 thermally treated material in place of the nickel coated Inconel Alloy 600 thermally treated material used in the past.
The primary reason for the change-out in sleeve material is the improvement in sleeve/tube inspectability relative to that obtainable with the original bi-metallic sleeves.
Since this modification results in an improved sleeve repair, RG&E considers that this change can be accommodated using the 10CFR50.59 process.
Prior to any installation of-these sleeves at Ginna, qualification testing of the new sleeve material for weld integrity and tube/sleeve inspectability will be performed.
The results of this testing will be an integral part of the RG&E 10CRF50.59 review process.
As with the installation of bi-metallic sleeves in the mid-1980's, RG&E is considering manual installation of these sleeves in 1992.
Although this manual installation increases the tube repair dose, there will be a
comparable offsetting dose effect for other SG activities as a
result of being able to keep the SG water-filled during the repair.
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'T1204130006 92040 PDR, ADOCK,05000244L P'DR
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RGGE will inform the NRC of its final decision on the tube repair option to be used during the 1992 Refueling Outage as soon as that decision has been made.
Please contact us, if you have any questions concerning this issue.
Very ruly yours, JFD~222 Robert C. Mecr dy 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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