ML17264A949
| ML17264A949 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/08/1997 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned) |
| References | |
| TAC-M98377, NUDOCS 9707170056 | |
| Download: ML17264A949 (6) | |
Text
CATEGORY j.
REGULATO INFORMATION DISTRIBUTION TEM (RIDS) i t ACCESSION NBR:9707170056 DOC;DATE: 97/07/08 NOTARIZED:
NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C;- 'ochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
SUBJECT:
Provides response to 970603 RAI re third,lO-year interval ISI program relief request 17 for plant.
DISTRIBUTION CODE:
A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code GL-9-04 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 T
E RECIPIENT ID CODE/NAME PD1-1 LA VISSINGiG.
INTERNAL: AEOD/SPD/RAB NRR/DE/EMEB OGC/HDS3 RES/DET/EMMEB EXTERNAL: LITCO ANDERSON NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
0 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD1-1 PD ILE CENTER NUDOCS-ABSTRACT RES/DET/EIB NOAC COPIES LTTR ENCL 1
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NOTE TO ALL "RIDS" RECXPXENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2'083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LXSTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 13 ENCL 12
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ROCHESlER MSANMIECIICCORPORA71ON
~ 89 EASl'VENUE, ROCHESTER, N. Y 146r194001 AREA COOE716 54'6-2700 July 8, 1997 ROBERT C. MECREDY Vice President Nuctear Operations U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-1 Washington, D.C.
20555
Subject:
Response
to Request for Additional Information, Re:
Third 10-year Interval Inservice Inspection Program (ISI) Relief Request No.
17 (TAC No. M98377)
R.
E. Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a):
Letter from Guy S. Vissing, NRC, to Robert C. Mecredy, RG&E, "Request for Additional Information Regarding the R.E.
Ginna Nuclear Power Plant Third 10-Year Interval Inservice Inspection Program Plan Request for Relief Request 17 (TAC No. M98377)," dated June 3,
1997
Dear Mr. Vissing:
The purpose of this letter is to provide the Rochester Gas and Electric (RG&E) response to the referenced letter.
The RG&E discussion is provided as attached.
Your action on this by July 31, 1997 would be greatly appreciated.
Subject to your evaluation of this transmittal, a revision to our relief request No.
17 may be appropriate to delete these six weld examinations.
Should you have any further questions please contact George Wrobel at (716) 724-8070.
Very truly yours, REJ4472 Robert C. Mecredy xc:
Mr. Guy S. Vissing (Mail Stop 14B2)
Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 US NRC Ginna Senior Resident Inspector 9707i70056 970708
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June 20, 1997
SUBJECT:
Relief Request NO.
17, Request for additional information.
Relief Request Number 17 was developed to address concerns when performing ultrasonic examinations on welds connecting cast stainless base metal and/or obtaining Code coverage on Category B-J weld examinations.
The six (6) welds identified within Section I, Item Number 2, are no longer applicable and should be removed from your consideration.
These welds were identified as potential problems in meeting Code. coverage in connection with the Steam Generator replacement effort at Ginna Station.
Preservice examinations were performed and Code coverage obtained.
Relief Request Number 17 should only apply to the four (4) welds identified in Section I, Item number 1.
It was requested that RGGE describe the "optimized ultrasonic techniques" that is referenced within the Relief Request.
The "optimized ultrasonic techniques" refers to the refracted "L"
wave that is applied to these welds.
Table 1 attached will identify each of the four (4) welds, the refracted examination technique and the Code required coverage that is expected to be obtained.
page 1 of 2
TABLE 1 Weld ID Exam Technique Coverage PL-FN-XII-LR(XIII) Longitudinal 45 RL Assuming 90% based on scanning parameters.
Not certain that the sound is penetrating the weld or following the weld fusion line to the ID surface.
PL-FW-XI-LR(XV)
Longitudinal 45 RL Assuming 90% based on scanning parameters.
Not certain that the sound is penetrating the weld or following the weld fusion line to t:he ID surface.
PL-FN-XV Elbow-to-Pump "B" 45 RL One sided exam.
50% Axial, 75%
Circumferential.
Could not verify calibration between 3/8
& 4/8 nodal points on calibration standard.
Not certain that the sound is penetrating the weld or following the weld fusion line to the ID surface.
PL-FW-XIII Elbow-to-Pump "A" 45 RL To be performed in 1997.
Coverage similar to that obtained on weld PL-FN-XV above.
page 2 of 2
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