ML20004B090

Significant Deficiency Rept SD-370/81-03 Re Inappropriate Consideration of Effects of Concentrated Weights During Small Bore Piping Analysis Performed by Criteria.Affected Piping Analysis Models Shall Be Brought Into Compliance

ML20004B090
Person / Time
Site:	Mcguire
Issue date:	05/22/1981
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
10CFR-050.55E, 10CFR-50.55E, SD-370-81-03, SD-370-81-3, NUDOCS 8105270217
Download: ML20004B090 (3)

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DUKE POWER COMPM Powra Dtrtt.osxo c2 Sot:Tri Cut:ncu Srneur. CitAnt.orte. N. C. 20242 W l(LI A M Q. PAR K E R J R.

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s,c. ano.c e, May 22, 1981 2 ,.2PN

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f Mr. James P. O'Reilly, Director --

U.S. Nuclear Regulatory Commission y Region II 0, 1- IAN S g'QS M p .

101 Marietta Street, Suite 3100

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Atlanta, Georgia 30303 T' Re: 1 e Nuclear Station

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Docket No. 50-370

Dear Mr. O'Reilly:

Pursuant to 10 CFR 50.55e please find attached Significant Deficiency Report SD 370/81-03.

Very truly yours, ,

E' /tt w h 6* W, William 0. Parker, Jr. Il j

RWO:pw Attacinent cc: Director Ms. M. J. Graham.

Office of Inspection and Enforcement Resident Inspector-U.S. Nuclear Regulatory Commission McGuire Nuclear Station Washington, D. C. 20555 .

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FCGUIRE NUCLEAR STATION UNIT 2 REPORT NO: SD-370/81-03 REPORT DATE: May 22, 1981 DCILITY: McGlire Nuclear Staticn, Unit 2 IDEvrIFICATICN CF DEFICIFCI: Small Bore Piping Analysis Performed by Criteria Did Not Appropriately Consider Effects of Concentrated Weights DESCRIPTICM CF DEFIC E CI:

In the application of conse.rvative, s:rall bore piping analysis criteria, a deficiency occurred in the use and interpretation of that portion of the criteria concerning support layout for pipe spans centaining a single concen-trated m ight. As applied to McGuire Unit 2 Auxiliary Bui; ding ASME Class 2 and 3 7all bore piping, analyses of 16 of 229 math :mdels do not specify support / restraints in accordance with specified concentrated weight span cri-teria. As a result, it is possible that portions of piping and existing suoport/ restraints in tin vicinity of con ntrated wights, not appropriately considered, may be over stressed due to absence of sufficient support / restraints during a seisnic event.

ANALYSIS OF SAFETY IMPLICATICN:

Subsequent rigorous corruterized analysis for the .crst case situatien has shcwn that affected, installed piping and support / restraints are adecuate.

CORPEETIVE ACTION:

No corrective action is necessary to assure adequacy of the affected supports fro.r a safety stardpoint. However, to assure consistent application of the Duke analytical criteria, the folicwing actions will be taken.

(1) All affected piping analysis mcdels shall be revised to be brought into cenpliance with existing s:rall bore analysis criteria, and additional support / restrains shall be provided as required by that criteria.

(2) Current analysis checking criteria shall be reviewed and updated as deemed necessary. A formal checklist for review of analysis ccnpliance with governing criteria shall be developed and implemnted in the analysis process.

(3) Technical personnel currently assicned to perform this analysis shall receive a formal training urx! ate by the designated resparr-sible EDS Nuclear Inc. Project Ehgineer.

P00RORSWM

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l (4) A technical audit shall be p rformed to ensure the proper 4 application of the entire small bore analysis criteria.

SOEDUIE EDR Cumr.L;nVE ACTICNS:

All corrective actions are expectsi to be ccmplete'by 7/1/81 4

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