ML17265A764

Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel

ML17265A764
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 9910150185
Download: ML17265A764 (10)

Text

REGULA Y INFORMATION DISTRIBUTIO~ SYSTEM (RIDS) iy

<'a ACCESSION NBR.'9910150185 DOC.DATE: 99/10/05 NOTARIZED: NO FACIL:50-2'44 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

AUTH.k>ME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSXNG,G.S.

SUBJECT:

Requests approval for use of relief request number 42 to address volumetric examinations limitations (less than 90%)

associated with eight Class 1 identified. welds or areas of reactor pressure vessel.

DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

DOCKET 05000244 E

05000244 G

RECIPIENT ID CODE/NAME LITTLE,Q INTERNAL.~FILE CENTER03~

OGC/RP RES/DET/MEB COPIES LTTR ENCL 1

1 1

1 1

0 1

1 RECIPIENT ID CODE/NAME VISSING,G NUDOCS -ABSTRACT RES/DET/ERAB COPIES LTTR ENCL 1

1 1

1 1

1 EXTERNAL: LITCO ANDERSON NRC PDR 1

1 1

1 NOAC 1

1 D

t,llg$85)~K~

N NOTE TO ALL "RIDS" RECZPZENTS:

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 10 ENCL 9

AHD A Subsidiary of RGS Energy Group, Inc.

ROCHESTER GAS ANDEIECIICCORPORATION

~ 89EASTAVENUE, ROCHESTER, N.Y. 146494001

~ 7I6 546-2700 www.fge. corn ROBERT C. MECREDY Vice Presidenl Nuclear 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. 42 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 42 to address volumetric examination limitations (less than 90%) associated with eight (8) Class 1 identified welds or areas of the Reactor Pressure Vessel (RPV).

This Relief is requested for seven (7) welds or areas 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.

For one (1) weld an exemption is requested pursuant to the provisions of 10CFR50.55a (g)(6)(ii)(A)(5) for not meeting essentially 100% volumetric examination coverage.

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

.. ;n>

99iOi50i85 99i005 PDR ADQCK 05000244 8

PDR

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, FA 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 ReliefNo. 42 Reactor Pressure Vessel (RPV) Weld Examination Limitations System/Component(s) for Which Relief/Exemption is Requested:

This RelieflExemption Request pertains to eight (8) Reactor Pressure Vessel welds or Inner Radius Volumetric examinations. Ofthese eight welds or areas, seven are ASME Section XI required and one is required under 10 CFR 50.55a(g)(6)(ii)(A)(2). Volumetric examination ofthese items are limited as identified in Attachment Number 1 ~

II.

ASME Section XICode/10 CFR 50.55a Requirement:

ASME Section XICode and 10 CFR 50.55a(g)(6)(ii)(A)(2) requires essentially 100% ofthe weld length or area to obtain coverage.

ASME Section XICode Case N-460 and regulation 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/Exemption is Requested:

Relief/Exemption is requested from examining 100% ofthe weld length or areas for these eight (8) identified items. Examining 100% of the weld length or areas would be impractical due to original design interference. Attachment Number 1 identifies volumetric examination achievable coverage and associated limitations as well as identification as to the requirement (either ASME Section XIor 10 CFR 50.55a)

IV.

Basis for Relief/Exemption:

RelieflExemption is requested pursuant to the provisions of 10 CFR 50.55a(g)(5)(iii) and 10 CFR 50.55a(g)(6)(ii)(A)(5), the required examination coverage for the identified items are impractical and would require redesign to allow examination or to be replaced to enable inspection.

page 1 of3

Request for ReliefNo. 42 The Reactor Pressure Vessel (RPV) was designed and constructed to ASME Section III, 1965 Edition. This code did not contain requirements to ensure that items be accessible for future examinations.

The eight (8) items identified within Attachment Number 1 were installed utilizingthis construction code which did not provide for accessibility for future ISI NDE.

The Class 1 Reactor Pressure Vessel is part of the ASME Section XI VT-2 Leakage Examination boundary.

Class 1 Leakage Examinations are performed each refueling outage as required by 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 ofoperator walkdowns and the Class 1

leakage examination that is performed each refueling outage provide additional assurances in maintaining plant safety.

V.

Alternate Examinations:

R.E. Ginna Nuclear Power Plant proposes that the volumetric examination coverage identified within Attachment Number 1 be acceptable in fulfillingrequired volumetric examination coverage.

VI.

Justification for the Granting ofRelief/Exemption:

The Reactor Pressure Vessel was designed and constructed to ASME Section III, 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 or Regulation.

ASME Section XIClass 1 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 identi6ed volumetric examination coverage for these items should be acceptable in fulfillingcoverage requirements.

Previous examinations were performed on these items in conformance to the Code requirements in efFect for RG&E at those times. It should also be noted that ReliefRequest Number 42 is similar to RG&E's ReliefRequest Number 19, which was previously approved by the NRC.

page 2 of3

Request for ReliefNo. 42 VH.

Implementation Schedule:

These examinations have been performed, and code credit shall be taken for the Third 10-year Interval inspection, upon approval ofReliefRequest Number 42.

Page3 of3

Attachment Number 1 Rochester Gas 4 Electric Corporation, Relief Request Number 42 Reactor Pressure Vessel (RPV) Volumetric Examination Limitations Category HUHhK B-A B-A Item

~i B1.30 B1.11 Summate HEBE 000501 000502 000503 KcL4JD RPV-A RPV-D 0

I Vessel to Flange Circ. Weld Lower Shell to Ring Forging Circ. Weld.

e ui Obtained

~Cvc~e 54%

81%

Keyways 8h Irradiation Slots Guide Lugs A Incores B-D B-D B-D B-D D-B D-B B3.90 B3.90 B3.100 B3.100 B3.90 B3.90 001900 NlA 002500 N1B 002300 N2A-IRS 002900 N2B-IRS 003100 AC-1003 003400 AC-1002 Nozzle Vessel WD 028D-30M.

Nozzle Vessel WD 208D-30M.

'o e

Nozzle Inside Radius Section.

1 Nozzle Inside Radius Section.

,ec'o C

e e

Nozzle Vessel WD 108D-30M.

od e

Nozzle Vessel WD 288D-30M.

55%'P 55 7P 90%

90%

55%'2%~

55%'2%'ozzle Boss Nozzle Boss Inner Radius Inner Radius Nozzle Boss Nozzle Boss Volumetric Weld Examination Volumetric Near Surface Examination

CONTROL ROD DRIVE PENETRATIONS (18) 5-1. 2 RPV-HFW I)IIIIIII IIIIIIIIIf CLOSURE NUTS, WASHERS STUDS (4S)

VESSEL TO FLANGE WELD RPV-A (RRCOj)

TO INTERMEDIATE SHELL WELD RPV-8 INTERMEDIATE SHELL TO LOWER SHELL WELD RPV-C LOWER SHELL TO RING FORGING WELD RPV-D 4-1/8" LOWER HEAD PENETRATIONS (36)

RING FORGING TO LOWER HEAD WELD RPV-E LINE NO:

REACTOR PRESS.

VESSEL CALIBRATION BLOCK:

REF.

DRAWING:

33013-1260 W679J441 W679J440 DRAWN BY:

ABG DATE:

11/I/95 REVIEWED BY:

FAK DRAWING NUMBER A1 REV REACTOR PRESSURE VESSEL (RRC01)

FACILITYP g G J'P7P/g ROCHESTER Gas dc ELECTRIC CORP.

ROCHESTER.

NEW YORK

I

l WO N R

~t' N

~ g 0 co V) 0 w>

NO N ct 0 >-

Zl tII NNOZ ZO l

~O tttO g

'8 CO JR Ct) 4J N g) cv Og Z

Z ~

/ ~e O

00 tIt ZZ~i N Co N CV O~

Z o

0 I

O Cl cA 4J CC to Ctl N O V) Ct.

N~ l p 0

I coo ZOQ>

ZO O

z I

4J V)

I N'O

~

I n Oa Q. g ca ID CV lil (tl Vl Sl COO LINE NO:

REACTOR PRESSURE VESSEL CAUBRATION BLOCK:

REACTOR PRESSURE VESSEL FAQLITYP E

//PAL'Pfg ROCHESTER GAS 4 ~CTRIC CORP.

ROCHESTER.

NEW YORK REF.

DRAWING:

33013-1260 DRAWN BY:

ABG DATE:

11/1 /95 REVIEWED BY:

FAK DRAWING NUMBER A'I A REV