ML17265A684
| ML17265A684 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/21/1999 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9906290269 | |
| Download: ML17265A684 (6) | |
Text
gl ACCESSION NBR FACIL:50-244 AUTE.NAME MECRgDY,R.C.
RECIP.NAME VISSING; G. S.
REGULA Y INFORMATION DISTRIBUTION YSTEM (RIDS)
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- 9906290269 DOC.DATE: 99/06/2X" NOTARIZED: NO DOCKET 0
.Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTHOR AFFILIATION Rochester Gas 8 Electric Corp.
RECIPIENT AFFILIATION
SUBJECT:
Informs util wishes to amend extent of alternate exams provided for relief request re ISI program ASME Section XI recpxire exams for first 10-Yr interval for containment.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code GL-09-04 NOTES:License Exp'date in accordance with 10CFR2,2.109(9/19/72).
05000244 E
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'E NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE."TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 12 ENCL 11
AND ROCHESTER GASANDELEClÃICCORPORAVON ~ 89EASTAYENUE, ROCHESrER N. Y Id6r19-0001 AREA CODE716 &f6-2700 ROBERT C. MECREDY Vice President Nuclear Operations June 21, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
Inservice Inspection Program ASME Section XI Required Examinations for First 10-Year Interval for Containment (IWE and IWL)
Request for Relief No. 40 R.E. Ginna Nuclear Power Plant Docket No. 50/244
Dear Mr. Vissing:
RG&E provided the NRC with the subject relief request on January 11, 1999. As a result of a telecon with NRC staff on June 16, 1999, RG&E wishes to amend the extent of the alternate examinations provided for in that relief request.
In addition to the testing to be conducted in accordance with 10CFR 50 Appendix J, RGB E will perform an IWE detailed visual examination of the repaired or replaced area (VT-1). A replacement page of the attachment to our January 11, 1999 relief request is provided.
Very truly yours, Robert C. Mecredy 9906290269 990b2'i POR ADQCK 0500024%i
xc:
Mr. Guy S. Vissing (Mail Stop 8C2)
Project Directorate I-1 Division of Reactor Projects
- I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S.
NRC Ginna Senior Resident Inspector
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Collection systems, as required during the conduct ofa system pressure test. In addition, personnel performing VT-2 examinations are required to be qualified in accordance with Subarticle IWA-2300 ofASME Section XI.
For repairs, replacements or modifications that are performed under ASME Section XI Code, applicable Construction Code (or Installation Code) non-destructive examinations (NDE) are performed and must meet the acceptance criteria ofthe Construction /
Installation Code. In addition to the Construction Code NDE, applicable ASME Section XINDE pre-service NDE are also performed.
These Construction Code and Section XI pre-service NDE requirements provide additional assurances that the repairs, replacements or modifications are sound and leak-tight.
Table IWE-2500-1, Examination Category E-P, identifies the examination method of 10 CFR 50, Appendix J and does not specifically identify a VT-2 visual examination.
10 CFR 50, Appendix J provides requirements for testing as well as acceptable leakage criteria. These tests are performed by Appendix J "Test" personnel and utilize calibrated equipment to determine acceptability. Additionally, 10 CFR 50.55a (b) (2) (x) (E) requires a general visual examination ofthe containment each period that would identify any structural degradation that may contribute to leakage. A"VT-2"visual examination willnot provide additional assurance ofsafety beyond that ofcurrent Appendix J practices.
Relief is requested in accordance with 10 CFR 50.55a (a) (3) (I). The proposed alternative (pressure testing in accordance with 10 CFR 50, Appendix J) willprovide and acceptable level ofquality and safety.
The reference to paragraph IWA-5240 has been removed in the 1997 Addenda ofASME Section XI. This addenda has been approved by the ASME Main Committee and should be published in 1998.
Alternate Examinations:
Testing shall be conducted in accordance with 10 CFR 50, Appendix J, in lieu of Paragraph IWE-5240 ofASME Section XI, as well as performing an IWE detailed visual examination ofthe repaired or replaced area (VT-l).
Request forReliefNo. 40 Attachment Page 2 of3
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