ML20072A767

Forwards Addl Request for Relief from Preservice Exam Requirements for Reactor Coolant Loop Piping Attachment Weld,Supplementing 821222 Relief Requests

ML20072A767
Person / Time
Site:	Mcguire
Issue date:	01/19/1983
From:	Tucker H DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8301240123
Download: ML20072A767 (7)

Text

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.e DUKE POWER GOMPANY P.O. HOX 33180 CHAMLOTTE. N.C. 23242

!: AL II. TUCKER TEI.EPHONE (704) 373-4531 vers rarement

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January 19, 1983 Mr. liarold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention:

Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station Docket Nos. 50-369, 50-370 Outstanding Information Responses

Dear Mr. Denton:

In response to Ms. Elinor G. Adensam's (NRC/ DOL) letter of November 24, 1982, my December 22, 1982 letter transmitted several outstanding information responses needed for the NRC to complete its review of the Unit 2 operating license appli-cation as well as Unit 1 close out matters. Among the items transmitted were four Unit 2 relief requests, serial numbers MC-2-001 through 004 (reference Attachments 2A through 2D of my December 22, 1982 letter), for preservice examination.

Picase find attached a fifth Unit 2 relief request, serial number MC-2-005.

This problem was discovered towards the end of the inspection and it is anticipated that this will be the final relief request. This matter has been previously discussed with your staff in a telecon between Mr. P. B. Nardoci, et.al. (DPC) and Mr. R. Birkel, et.al. (NRC/NRR) on January 18, 1982.

Should you have any questions with the attached information, please advise.

Very truly yours, J/a / 8 75cd/Ce6 Ital B. Tucker PBN:jfw Attachment cc:

Mr. James P. O'Reilly, Regional Administrator Senior Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuclear Station Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 EG G da o Idaho Falls, Idaho 83415 8301240'1Z3 830119

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MC-2-005 Page 1 of 2 OUKE POWER COMPANY Request For Relief From inservice inspection Requirement Station: McGuire Nuclear Station Unit: 2 Reference Code: ASME Boiler and Pressure Vessel Code,Section XI 1974 Edition through Summer 1975 1.

Component for which exemption is requested:

Name and identi ficat ion Number:

Reactor Coolant Loop Piping Attachment Veld NC2FW 83-H47 b.

Function:

Reactor '.colant Pressure Boundary c.

ASME Section 111 Code Class:

Class I d.

Valve Category: NA l

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11. Reference Code Requirement that has been determined to be impractical:

Table IW3-2600 i tem No. 84.9 reaui res volumetric ex' amination for integrally welded supports.

Ultrasonic examination is impractical due to configuration, and radiography cannot be performed for inservice inspection due to accessibility.

See Attachment 1&2 111. Basis for Reques ti ng Relief:

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Estimate of preservice examination performed - 0%

l Original fabrication examination - dye penetrant l

Measures which would be required to make the area accessible - Removal of Hanger 2MCR-NC-4203

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S: rial No.

MC-2-005 Page 2 of 2 111.

Basis for Requesting Relief (cont.)

Removal of hanger would not give a meaningful volumetric examination.

Construction examination provided adequate assurance of component reliability.

IV.

Alternate Examination:

lione Available V.

implemen tation Schedule: No inspection due to accessibility.

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