ML20009E475

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Interim Rept Re Potential Deficiency Involving Pipe Support Welds,Initially Reported on 810608.Assessment of Safety Impact & Corrective Action Will Be Provided by 810901.Also Reported Under Part 21
ML20009E475
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 07/14/1981
From: Curtis N
PENNSYLVANIA POWER & LIGHT CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
10CFR-050.55E, 10CFR-50.55E, PLA-877, NUDOCS 8107280239
Download: ML20009E475 (2)


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@ Pennsylvania Power & Light Company 5b_ -y Two North Ninth Street

  • Allentown, PA 18101 + 215 I 770'5151 5>sn Norman W. Curtis Vice President-Engineering & Construction-Nuclear 215/ 770-5381 July 14, 198',

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b A Mr. Boyce H. Crier /f Director, Region I $

U. S. Nuclear Regulatory Comission ] Nl 2 7 gN b &w 631 Park Avenue pMEa, King of Prussia, Pennsylvania 19406 ,%

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SUSQUEHANNA STEAM ELECTRIC STATION j, INTERIM REPORT OF A POTEN".'IAL DEFICIENCY f, -

IINOLVING PIPE SUPPORT MELDS EPs 100450/100508 FILE 821-10/900-10

,FLA- 877

Dear Mr. Grier:

This letter serves to confirm information provided by telephone to NRC Region I Inspector Mr. L. Narrow by Mr. A. Sabol of PP&L on June 8,1981.

During that conversation, Mr. Narrow was advised that the subject condition was under evaluation for reportability under the provisions of 10CFR50.55(e) .

The deficiency involves various discrepancies both on pipe supports and on their associated welds. These discrepancies include are strikes, slag and weld splatter; undercut, undersized and missing alds; poor weld profiles and lack of weld symbols on design drawings. Bechtel NCR #7723 has been written to track and correct the discrepancies.

PP&L has concluded that these discrepancies have the potential to adversely affect safe plant operations and thus considers them to be potentially reportable under 10CFR50.55(e) .

Since the details of this report provide information relevant to the reporting requirements of 10CFR21, this correspondence is considered to also discharge any final respnsiblity PP&L may have for reporting in compliance thereto.

A full assessment of the discrepancies' safety impact and necessary corrective action will be provided by September 1,1981 when investigations, necessary to fully define the nature, extent and cause of these discrepancies, have been accomplished.

SC7 .f 8107280239 810714 PDR ADOCK 05000387 g

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Mr. B7yce H. Grier July 14, 1991 1

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Very truly yours,

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rs . . ,

N l N. W. Lurtis Vice President-Engineering & Construction-Nuclear

RAS /FLW jmk >

cc: Mr. Victor Stello (15)

Director-Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. G. Mcdonald, Director (1) 2 Office of Management Information & Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 i

! Mr. Gary Rhoads l U. S. Nuclear Regulatory Commission

P.O. Box 52 j Shickshinny, PA 18655 i

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