ML19320C957

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LER 80-044/01T-0:on 800630,review Showed Existing Steam Generator Snubber Embedment Design Does Not Reflect as- Constructed Embedment Condition.Cause Not Yet Determined
ML19320C957
Person / Time
Site: Beaver Valley
Issue date: 07/11/1980
From: Lacey W
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19320C955 List:
References
LER-80-044-01T, LER-80-44-1T, NUDOCS 8007180322
Download: ML19320C957 (2)


Text

-. ..

  • U. S. NUCLEAR REGULATCRY COMMIS$10N

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EVENT OESCRIPTION AND PRO 8A8LE CCNSEQUENCES h FTTT1 IDuquesne Light Company has been informed by the BVPS Unit 1 Architect-Engineer that al pgy] l review showed that the existing steam generator snubber embedelent design does not l i o i .: l l reflect the "as constructed" condition of the embedment. The original Calculations j

[oisl l assumed that the load was applied normal to the embedment surface rather than skewed.l n5Ts'l IThe original calculations considered loads due to pipe break and seismic. However. l lo17l Ithe calculations were not updated to reflect the revised seismic loads and loads [

l o is t t associated with asymmetric pressure due to a break within the (continued on attached)l60 1 8 9 C OM P. V. . . e SYSTEM CAUSE CAUSE CODE - CODE SUSCODE COMPCNENT CODE SLBCODE SUSCC3E loisi 7 8 l9 z l z l@ [B_J@ l A l@ l S l U l P l 0 l R l T l@ l B l@ l20z l @

10 81 12 13 18 19 OCCURRENCE REPORT REVISION

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IiioJ [A review of the original load calculations revealed these deficiencies. We have I i i Ireceived revised load calculations from Westinghouse for two loadn whfch are believedi i,,23lco reflect the " worst case condition". As expected, the revised loads are below the [

iit31l design loading and the concrete at the embedments has been found to exceed the l

[TTTI le.esigned strencth by 2500 PSI. The skewed load calculation (continued on attached)l 3o 7 a s STA S *b POWER OTHER STATUS is O RY Otso 'Vte1Y DESCRIPfloN y W@ l0 !O l0 l@l Design l l D l@l Informed by Arc:.itect-Engineer 80 l

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800718032.1 - . -

Attachment To LER 80-44/0lT Beaver Valley Power Station Duquesne Light Company Docket No. 50-334 Event Description And Probable Consequences boundary of the neutron shield tank. The result was the establishment of non-conservative loads for the embedment anchors.

Cause Description And Corrective Actions study by the Architect-Engineer is still in progress but results are expected to be acceptable based on the reduced applied loads and superior concrete strength.

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