ML19320C957: Difference between revisions

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* U. S. NUCLEAR REGULATCRY COMMIS$10N
* U. S. NUCLEAR REGULATCRY COMMIS$10N
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) ERC (f.77)PORM 364 LICENSEE EVENT REPORT CONTROL BLOCK: l i
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                                                                                    .
(PLEASE PRINT CR TYPE alt REQUIREO INFORMATIONI o i        l9,P l LICENSEE A l B CODE    l V l S l 1ISl@l 0 l 0 l-LICENSE                l 0 lNUMSER 0 l 0 l 0 l 0 l- Dl0 l 260 l@l        LICENSE4 l1TYPE l
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EVENTYEAR                                    REPCRT NO.                          CCOE                  TYPE                            No.
EVENTYEAR                                    REPCRT NO.                          CCOE                  TYPE                            No.
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NAME OF PnEPAR8R N* S* LOOUY                                              PHONE.                                                      $
NAME OF PnEPAR8R N* S* LOOUY                                              PHONE.                                                      $
800718032.1                                                                                                              -              . -
800718032.1                                                                                                              -              . -
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            *
, .
                                                    .
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.
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.
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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Latest revision as of 03:47, 1 February 2020

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

) ERC (f.77)PORM 364 LICENSEE EVENT REPORT CONTROL BLOCK: l i

l l l l l lh (PLEASE PRINT CR TYPE alt REQUIREO INFORMATIONI o i l9,P l LICENSEE A l B CODE l V l S l 1ISl@l 0 l 0 l-LICENSE l 0 lNUMSER 0 l 0 l 0 l 0 l- Dl0 l 260 l@l LICENSE4 l1TYPE l

l1JGl1 l $11 CAl@l l@

T $d I S le CON'T I

o i S

c'7R$ l L @l 0 lDOCK 60 el 5 lET0NUMsER l 0 l 0 l ea3 l 69314EVENT @lC 0ATEl 6 l 3 l 0 74 4 l 8REPORT l 0 DATE@l0 l780 11l1l810l@

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

. SE QUENTI At.

EVENTYEAR REPCRT NO. CCOE TYPE No.

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. l21 81 0l 22 23 24 26 27 28 29 30 31 32 C PL T ME 5 8 IT FCR 1 0 SLP* LIE MAN F CTLRER TAE N AC 0 MCURS h lz l@l zi@

33 34 l35z l@ lzl@

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g4 47 CIUSE OESCRIPTION ANO CORRECTIVE ACTIONS h ,

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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ISSU DESCRIPTION 1.2 L.J LdE @l N/A i tiliittistiill F S 3 to 69 69 60 5

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NAME OF PnEPAR8R N* S* LOOUY PHONE. $

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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