ML17265A763

Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000

ML17265A763
Person / Time
Site:	Ginna
Issue date:	10/05/1999
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9910150168
Download: ML17265A763 (8)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9910150168 DOC-DATE: 99/10/05 NOTARIZED: NO Ginna Nuclear Plant, Unit 1, Rochester DOCKET I

>AC$ ~,"'5(>-244 Robert Emmet G 05000244

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. AUTHOR AFFILIATION "94ECR06Y,R.C. Rochester Gas & Electric Corp.

RE@'IP.NAME RECIPIENT AFFILIATION VIS'SING,G.S.

SUBJECT:

Requests approval for use of Relief Request number 43 to address volumetric examination limitations (less than 90>)

associated with A & B RHR heat exchanger outlet nozzle to shell.welds.Approval is requeSted by Dec 31,2000.

DISTRIBUTION CODE( A047D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code E

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 G

RECIPIENT COPIES RECIPIENT COPIES 0 ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LITTLE,S 1 1 VISSING,G 1 R INTERNAL: ILE CENTER 01 1 1 NUDOCS -ABSTRACT 1 1 OGC RP 1 0 RES/DET/ERAB 1 RES/DET/MEB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC NRC PDR 1 1 E

N WASTETH NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE 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 10 ENCL 9

AND

~ A Subsidiary of RGS Energy Group, Inc.

ROCHESTER GAS AND ELECIIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. IrI6r19CNOI ~ 716 5d6-2700 www.rge.corn ROBERT C. MECREDY Vice President Nvdeor Operations October 5, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I Washington, D.C. 20555

Subject:

Inservice Inspection Program ASME Section XI Required Examinations Third 10-Year Interval Relief Request No. 43 R. E. Ginna Nuclear Power Plant

'Docket No. 50-244

Dear Mr. Vissing:

The purpose of this letter is to seek approval for the use of Relief Request Number 43 to address volumetric examination limitations (less than 90%) associated with the A and B Residual Heat Removal Heat Exchanger Outlet Nozzle to Shell Welds.

This Relief is requested for bvo (2) welds pursuant to the provisions of 10CFR50.55a (g)(5)(iii). The required examination coverage for the identified items are impractical and would require redesign to allow examination or to be replaced to enable inspection. Justification concerning limitations are included in the attachment to this letter.

Since this relief request is for our 3rd 10-year interval ISI program, which ends December 31, 1999, approval, is requested by December 31, 2000 in accordance with 10CFR50.55a (g)(5)(iv).

Very truly yours, Robert C. Mecredy Attachment 0

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xc: Mr. Guy S. Vissing (Mail Stop 8C2)

Project Directorate I Division of Licensing Project Management 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

ATTACHMENT Rochester Gas and Electric Corporation Ginna Station Docket No. 50/244 Third 10- Year Interval Request for Relief No. 43 Residual Heat Removal (RHR) Heat Exchanger Outlet Nozzle Welds Examination Limitations System/Component(s) for Which Relief/Exemption is Requested:

This Relief Request pertains to two (2) Residual Heat Removal (RHR) Heat Exchanger Outlet Nozzle to Shell Welds, ASME Class 2, Category C-B, Item C2.32. There is one nozzle of this type associated with each of the two identical RHR Heat Exchangers. The Code requires that the examination be performed when the component is opened. Both Heat Exchangers were opened and Volumetrically examined. Limited coverage is identified below.

Sum~arur II Weld ID a c 169253 ONSRHE-1B 79% due to internal welded separation plate 169053 ONSRHE-1A 79% due to internal welded separation plate II. ASME Section XI Code Requirement:

ASME Section XI Code requires essentially 100% of the weld length or area to obtain coverage. ASME Section XI Code Case N-460 states that ifthe entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in coverage is acceptable provided that the coverage (the lack of) is less than 10%.

III. Requirement from Which Relief is Requested:

Relief is requested from examining 100% of the weld length or areas for these two (2) identified items. Examining 100% of the weld length or areas would be impractical due to original design interference.

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'equest for Relief No. 43 IV. Basis for Relief/Exemption:

Relief is requested pursuant to the provisions of 10 CFR 50.55a(g)(5)(iii), the required examination coverage for the identified items are impractical and would require redesign to allow examination or to be replaced to enable inspection.

The two identical Residual Heat Removal (RHR) Heat Exchangers was designed and constructed to ASME Section VIII, 1965 Edition. This code did not contain requirements to ensure that items be accessible for future examinations. The two (2) ASME Class 2 items identified above were installed utilizing this construction code which did not provide for accessibility for future ISI NDE. The ISI ASME Section XI volumetric requirement is identified within Table IWC-2500-1, Category C-B, Item Number C2.32.

The Residual Heat Removal (RHR) Heat Exchangers is part of the ASME Section XI VT-2 Leakage Examination boundary. Leakage Examinations are performed each period as required by Category C-B, Item Number C2.33 of the Code to insure pressure boundary integrity. In addition to the ASME Section XI leakage examinations, Operator walkdowns as specified by Plant Operating Procedures are also performed. The combination of operator walkdowns and period leakage examinations that are performed provide additional assurances in maintaining plant safety.

V. Alternate Examinations:

R.E. Ginna Nuclear Power Plant proposes that the volumetric examination coverage identified above be acceptable in fulfillingrequired volumetric examination coverage.

VI. Justification for the Granting of Relief:

The Residual Heat Removal (RHR) Heat Exchangers were designed and constructed to ASME Section VIII, 1965 Edition construction code. This code did not contain requirements to ensure that items be made accessible for future NDE examinations. Due to the original limited design accessibility, examination coverage can not be obtained to the extent required by the current ASME Code.

ASME Section XI periodic leakage examinations are performed as well as Operator walkdowns as specified by Plant Operating Procedures. These operator walkdowns and periodic system leakage examinations provide additional assurances in maintaining plant safety. The identified volumetric examination coverage for these items should be acceptable in fulfillingcoverage requirements.

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Request for Relief No. 43 It should also be noted that Relief Request Number 43 is similar to RG&E's Relief Request Number 19 and 34, which were previously approved by the NRC.

VII. Implementation Schedule:

These examinations have been performed, and code credit shall be taken for the Third 10-year Interval inspection.

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1 10G-AC5-152 SUPPORT LEG 10F-AC5-152 LOCATION 3

SHELL TO UPPER HEAD WELD CCW 2

S II.75" A EAC02A 36.5 DIA.

OUTLET 0 0 C-6 101-AC5-152 INLET I OH AC5-152 a

I I I CCW I I I g FLANGE TO UPPER SHELL WELD 44 HOLES O

1,5" DIA. BOLTING 1A-BT 1B-BT CLASS 3 LOWER SHELL TO FLANGE WELD LSFWRHE CLASS 2 INLET NOZZLE TO SHELL OUTLET NOZZLE TO SHELL INSRHE ONSRHE 8E-AC-601 INLET BA-AC-601 8C-AC-601 Pu TLP T BX-AC-601 INLET REINFORCING PLATE WELD OUTLET REINFORCING PLATE WELD IRPRHE ORPRHE RHEA-2A-AC-601 RHEB-2A-AC-601 LOWER HEAD TO LOWER SHELL WELD LHLSWRHE RHEA-28-AC-601 RHEB-28-AC-601 A 8 C RHEA-2C-AC-601 SOCKET WELD RHEB-2C-AC-601 UPPER 4 LOWER VESSEL SHELL 304 STAINLESS: .75 THICK SUPPORT LEGS STAINLESS S..625 THICK LINE NO: CALIBRATION BLOCK:

RESIDUAL HEAT REMOVAL HT EXCHANGERS REF. DRAWING:

FACILITY P E ggP7gg ROCHESTER GAS,hc ELECTRIC CORP.

ROCHESTER. NEW YORK WESTINGHOUSE 4807-1 DRAWN BY: ABG DRAWING NUMBER REV.

33013-1247 DATE: 11/I/95 REVIEWED BY: FAK