ML20206U148

Final Deficiency Rept (CDR 81-00-10) Re Inconsistency in Electrical Cable Tray Support Bolts Design.Initially Reported on 810727.Required Mods to Conduit & Cable Tray Support Connections Installed & Inspected

ML20206U148
Person / Time
Site:	Seabrook
Issue date:	08/21/1986
From:	Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
(CDR-81--10), (CDR-81-00-10), SBN-1179, NUDOCS 8610070328
Download: ML20206U148 (4)

Text

Ck) K. hl-os-to F ,N SFABROOK STATION Engin;; ring Offic:

August 21, 1986 NEW HAMPSHIRE YANKEE DIVISION SBN- 1179 T.F. Q2.2.2 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Fk . Richard W. Starostecki, Director Division of Project and Resident Programs

References:

(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) Telecon of July 27, 1981 between Mr. W. Lazarus (NRC) and II. E. Wingate (YAEC)

(c) PSNil letter (SBN-619), dated February 1,1984, " Interim 10CFR50.55(e) Report: Electrical Cable Tray Support Bolts", J. DeVincentis to R. W. Starostecki (d) Franklin Institute Strut Nut Connection Test Results, United Engineers and Constructors Documents 9763-SQ-00121-3Z006 and 3Z014 (e) New llampshire Yankee Document, " Cable Tray Qualification Program", dated March 7,1986 (f) " Performance Testing of Typical Cable Tray Configurations and Strength Testing of Selected Connection Details, Seabrook Station Test Cases A, B, and C", Test Report No. 1053.43B, Document No. A00161, ANCO Engineers, Inc. ,

Volumes I through V

Subject:

Final 10CFR50.55(e) Report; Electrical Cable Tray Support Bolts (CDR 81-00-10)

Dear Sir:

In Reference (b), we reported a 10CFR50.55(e) deficiency regarding an inconsistency in design information between test data, catalog data, and design allowables for Cable Tray Support Systems. Specifically, the Strut Support Systems used for certain bolted strut fittings, could be subjected to slippage at loads less than the published a]Iowable loads.

8610070328 860821 PDR ADOCK 05000443 8 PDR If0 Seabrook Station Construction Held Office

• P O. Box 700 . Seabrook. NH 03874

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United States Nuclear Regulatory Commission SBN- 1179 Attention: Mr. R. W. Starostecki Page 2 To resolve these inconsistancies, a test program was developed to establish allowable loads for strut nut connections. Test results were utilized to revise the connection design criteria.

Testing of the various strut nut connections used for cable tray and conduit supports has been completed. The testing was com-prised of two separate programs.

Program One -

Static testing of typical strut nut connections used for both cable tray and conduit supports was performed at the Franklin Institute Laboratories in Philadelphia, PA [ Reference (d)].

This testing served as the basis for developing reduced allow-able loads which were incorporated into the connection design criteria.

Program Two -

Full scale dynamic testing of representative Seabrook cable tray support configurations was performed at ANCO Laboratories in Culver City, Calif. This testing program serves as design input for a modified cable tray support qualification program [ Reference (e)].

This testing program demonstrated the integrity of typical cable tray support hardware and connection details under severe seismic loading [ Reference (f)]. Any installed cable tray support connection detail which is represented by the tested configurations is considered to be seismically qualified for the design basis earthquakes. Those connections not qualified directly by the testing program were evaluated using the connection design criteria developed in Program One.

As a result of the Engineering evaluation, modifications to cable tray and conduit support connections were required. The design change documents for these modifications were issued to Construction. The required modifications to conduit and cable tray support connections located in all Category I buildings have been installed and inspected.

As such, this is considered our final report on this item.

Very truly yours, aAtwd John Devincentis Director of Engineering cc: Atomic Safety and Licensing Board Service List Director, Of fice of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555

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