ML17309A507

Advises That QA Manual,App B Program Being Modified to Incorporate Code Cases N-460 & N-498 Re Alternative Exam Coverage for Class 1 & 2 Welds & Alternate Rules for 10-yr Hydrostatic Pressure Testing,Respectively

ML17309A507
Person / Time
Site:	Ginna
Issue date:	01/05/1993
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9301110097
Download: ML17309A507 (8)

Text

ACCEI E DOCUMENT DIS TION SYSTEM REGUL NFORMATION DISTRIBUT TEM (RIDS)

"C ACCT>S>/ON'NBR:9301110097 DOC.DATE: 93/01/05 NOTARIZED: NO DOCKET FACIL:;50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Advises that QA manual,App B program being modified to incorporate Code Cases N-460 !t N-498 re alternative exam coverage for Class 1 6 2 welds 6 alternate rules for 10-yr D hydrostatic pressure testing, respectively.

DISTRIBUTION CODE: Q004D TITLE:

COPIES RECEIVED:LTR QA Topical Report, Amendment, or Correspondence 3 ENCL 2 SIZE:

(Docket/Ut lity Speci S

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NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 JOHNSONPA 1 1 D

INTERNAL: NRURQDLPQ/LPEB10 1 1 OC/LFMB 1 1 REG -

kH Ol 2 2 RGNl FILE 1 1 EXTERNAL: IHS 1 1 NRC PDR 1 1

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D NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9

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IlrzrzrrrfEI Irsutrrr ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST'AVENUE, ROCHESTER N.K 14649-0001 ROBERT C MECREDY TELEPHONE Vice Prerldent AttEa COOE 7 t 6 546-2700 anna Nuclear Production January 5, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Quality Assurance Manual Revision, Appendix B Ginna Nuclear Power Plant Inservice Inspection ASME Section XI Required Examinations R. E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a): Code Case N-460, "Alternative Examination Coverage for Class 162 Welds, Section XI, Division 1" (b): Code Case N-498, "Alternate Rules for 10 Year Hydrostatic Pressure Testing for Class 162 Systems"

Dear Mr. Johnson:

The purpose of this letter is to notify your office that the Rochester Gas and Electric Quality Assurance Manual, Appendix B Program is being modified to incorporate Code Cases N-460 and N-498 (References a and b above). Both Code Cases have been approved for use as specified in Regulatory Guide 1.147, Revision 9, dated April 1992. Also, RGGE requests relief from a provision of Code Case N-460, as described in Attachment 1.

Code Case N-460 states that if the 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 reduction in coverage is less than 10'. Code Case N-498 states that alternative rules may be used in lieu of those required by Section XI, Division 1, Table IWB-2500-1, Category B-P, and Table IWC-2500-1, Category C-H, for the 10 year hydrostatic pressure test.

The Relief Request, No. 19, described in Attachment 1 is required because, due to the closeness of three (3) nozzles and the pulsation dampener vessel support locations, interferences exist which pr'event obtaining the required 904 volume coverage.

Ver truly yours, Robert C. Mecr y GALK233 I'301110097.=,93010S pDR P 'DR i,'oocn;.i onooo24rr l~l

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Attachment xc: Mr. Allen R. Johnson (Mail Stop 14Dl)

Project Directorate I-3 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

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ATTACHMENT I RELIEF REQUEST NO. 19 I. Component for Which Relief is Requested:

Charging System, Class 2 Pulsation Dampener nozzle inside radius and nozzle welds examination volumes per Category C-B, Items C2.21 and C2.22.

II. ASME Requirement for Which Relief is Requested:

Within Table IWC-2500-1, Category C-B provides examination requirements for Class 2 pressure retaining nozzle welds in vessels. The Pulsation Dampener contains three (3) nozzles, in line, located at the bottom of the unit. These nozzles require both surface and volumetric examinations as specified by Item C2.21 for nozzle-to-shell welds. The same three (3) nozzles also require volumetric examination as identifi'ed by Item C2.22 for the nozzle inside radius sections. ASME Section XI requires "essentially 100~o of the weld length" as specified within the notes within the IWC-2500-1 tables. ASME Section XI Code Case N-460, approved 27 July 1988, provides clarification for Class 1 and 2 examination volume of welds due to interference by another component or part geometry.

Code Case N-460 states that if the 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 reduction is less than 10%.

The R. E. Ginna Nuclear Power Plant was constructed to B31.1, 1955 edition. This Code did not contain requirements to ensure that, items be accessible for future examinations. The Pulsation Dampener was constructed and installed in the early 1970's, and the construction code did not provide provisions for accessibility for ISI NDE.

I The three (3) nozzles that require examination are identified as CF-N1, CF-N2 and CF-N3. The outboard nozzle is identified as CF-N1. Between this nozzle and the middle nozzle (identi-fied as CF-N2) is a support that covers the edge of one nozzle weld heat affected zone to the edge of the other nozzle weld heat. affected zone. From the middle nozzle to the third nozzle (identified as CF-N3) is a space of only 7/8" from the edge of the other .nozzle heat affected zone. Due to the identified interferences of the nozzles and the vessel support, the associated volumetric and surface volume coverage acceptance criteria is below the stated value within Code Case N-460. The following table summarizes the maximum coverage obtained when using the indicated examination methods.

Nozzle Weld NDE Method 4 of Covera e CF-N1 PT 66%

UT 65%

CF-N2 PT 664 UT 65~o CF-N3 PT >90~o UT 8,0~o Since the original construction code did not specify accessi-bility requirements for future ISI NDE, the identified volume coverage should be considered acceptable in meeting code requirements. The proposed alternate method is described below.

III. Proposed Alternate Method:

Rochester Gas and Electric (RG&E) proposes that the NDE volume coverage identified within the table above be acceptable in fulfilling the Code required examinations. The actual physical configuration on the component being examined is not conducive to meeting the requirements specified within Code Case N-460.

In addition, RG&E proposes to perform a VT-2 visual examina-tion on the entire Pulsation Dampener during a leakage test and hydrostatic pressure test in accordance with IWA-5000 and Table IWC-2500-1.

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