ML20053E402

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Responds to NRC Re Violations Noted in IE Insp Repts 50-440/82-03 & 50-441/82-03.Corrective Actions: Assembly OM-61-21X Weld B,Reradiographed W/Location Markers Placed in Correct Locations
ML20053E402
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 04/30/1982
From: Davidson D
CLEVELAND ELECTRIC ILLUMINATING CO.
To: Norelius C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20053E397 List:
References
NUDOCS 8206070877
Download: ML20053E402 (3)


Text

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O TJ E CLEVELaN D ELEC TRIC !LLUMIN ATiH G CO M P ANY P O. Box 5000 e CLEVELAND, oHlo 44101 e TELEPHONE (216) 622-9800 m ILLUM:NATING BLOG.

e 55 PUBLICSOUARE Serving The Best Location in the Nation Dalwyn R. Davidson VICE PRESIDENr April 30, 1982 SYSTEM ENGINEERING AND CONSTRUCTION Mr. C. E. Norelius, Director Division of Engineering and Technical Inspection U.S. Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE:

Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Response to I.E. Report

Dear Mr. Norelius:

This letter is to acknowledge receipt of Inspection Report Number 50-440/82-03; 50-441/82-03, attached to your letter dated April 6, 1982. This report identifies areas examined by Messrs. K. D. Ward and E. H. Nightingale during their inspection conducted February 23-26 and March 8-10, 1982.

Attached to this letter is our response to the one Severity Level V Violation described in Appendix A, Notice of Violation, dated March 31, 1982. This response is in accordance with the provisions of Section 2.201 of the NRC's

" Rules of Practice", Part 2, Title 10, Code of Federal Regulations.

Our response has been submitted to you within thirty days of the date of the Notice of Violation as you required, and the information submitted is true and correct to the best of my knowledge, information and belief.

If there are additional questions, please do not hesitate to call.

Very truly yours, o

1 R. Davidson

\\ ice President Systems Engineering and Construction DRD:pab Attachment cc:

USNRC - Site Mr. R. L. Spessard, Director Division of Resident and Project Inspection U.S. Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C.

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RESPONSE TO ENFORCEMENT ITEMS Below in our response to Appendix A, Notice of Violation, of United States Nuclear Regulatory Commission I.E. Report 50-440/82-03; 50-441/82-03:

I.

Noncompliance 440/82-03-03 A.

Severity Level V Violation 10CFR50, Appendix B, Criterion IX states in part that, " Measures shall be established to assure that special processes, including...

nondestructive testing, are controlled and accomplished by qualified personnel using qualified procedures in accordance with applicable codes, standards, specifications, criteria, and other special requirements."

The Ferry Nuclear Power Plant, Units 1 and 2, PSAR Section 17.1.9.2, states in part that "CEI requires contractors to establish and document measures that will assure that special processes will be accomplished...in accordance with the applicable codec..."

The specified code, American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code,Section V 1974 Edition, Summer 1975 Addenda, paragraph T-235.2 requires that the location markers locate the area of interest accurately and ASME Section III, 1974 Edition, Summer 1975 Addenda, paragraph NE-5321 states that incomplete fusion, excessive elongated indications (slag) and cracks are unacceptable.

Contrary to the above, lead location markers were in the area of interest, a repair area was not correctly identified by location markers, and lack of fusion, excessive slag and a crack were found in various welds.

B.

Response

Condition 1 - Assembly #0M-61-21X Weld B, area P-S-B was re-radio-graphed with the location markers placed in the correct locations, outside the area of interest, re-evaluated and found acceptable. No further action required.

Condition 2 - All radiographs of welds associated with NRs # 17-152,17-777, 17-195,17-254 and 17-268 has been re-reviewed by CEI NDE Element 100%. This second review consisted of 58 weld joints of which 36 were rejected. Based on this reject level, we are evaluating this problem for reportability pursuant to 10CFR50.55(e).

Because of the high reject rate of those containment welds identified above, the NDE element has committed to, and is in the process of per-forming a 100% re-review of all welds of Units I and II containments.

d RESPC1"E TO ENFORCEMENT ITEMS Page Two To date, 874 films have been re-reviewed representing 5% of the total for both containments.

Projected completion date for this rev'aw is August 31, 1982.