05000280/LER-1980-018-01, /01T-0:on 800219,pipe Stress Reanalysis on IE Bulletin 79-14 Lines Revealed Overstressed Condition on Piping Penetrations Would Exist During Dbe.Addl Constraints Designed & Will Be Installed

/01T-0:on 800219,pipe Stress Reanalysis on IE Bulletin 79-14 Lines Revealed Overstressed Condition on Piping Penetrations Would Exist During Dbe.Addl Constraints Designed & Will Be Installed

ML18139A023
Person / Time
Site:	Surry
Issue date:	03/03/1980
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18138A067	List: 05000280/LER-1980-018, Forwards LER 80-018/01T-0 05000280/LER-1980-018-01, /01T-0:on 800219,pipe Stress Reanalysis on IE Bulletin 79-14 Lines Revealed Overstressed Condition on Piping Penetrations Would Exist During Dbe.Addl Constraints Designed & Will Be Installed
References
IEB-79-14, LER-80-018-01T-01, LER-80-18-1T-1, NUDOCS 8003040650
Download: ML18139A023 (2)

LER-1980-018, /01T-0:on 800219,pipe Stress Reanalysis on IE Bulletin 79-14 Lines Revealed Overstressed Condition on Piping Penetrations Would Exist During Dbe.Addl Constraints Designed & Will Be Installed

Event date:
Report date:
2801980018R01 - NRC Website

text

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REPCflTO-"TE SO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

!Pipe-stress reanalysis on IE Bulletin 79-14 lines (reactor c.;witv on:dficatinn and se::i~

[2J]J feturn) inside containment has revealed an overstressed condition on the piping pene-I

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frations would exist in the event of a Design Basis Earthquake.

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44 47 OJ)) ftress calculations on the affected lines indicate that the supports attached would rioJ [ill] frevent an overstressed condition on the containment penetrations should a DBE occur.

[III] tdditional constraints have been designed and will be installed to relieve the overstr3ss DJI] ~isclosed.

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Attachment, Page 1 of 1 Surry Power Station, Unit 1 Docket No. 50-280 Report ~o. 80-018/0lT-0 Event Date: 02/19/80 Title of Report:

Excessive Stress on I.E.Bulletin 79-14 Lines Inside Cont_ainment

1.

Description of Event

During the pipe stress reanalysis it was determined that an overstressed condition would be imposed upon the containment piping penetrations for lines 3"-RL-6-152, 3"-CH-99-152, should a Design Basis Earthquake be experienced.

This event is reportable in accordance with T.S. 6.6.2.ct.9.

2.

Probable Consequences & Status of Redundant Systems:

Left uncorrected, the problem could have led to a loss of containment integrity.

3.

Cause

The overstress condition was identified by the architect engineer in his reanalysis effort required by I.E.Bulletin 79-14, as an initial design inadequacy in the provision of constraints on the affected lines.

4.

Immediate Corrective Action

The unit was brought to a cold shutdown condition prior to the occurrence of a DBE so the health and safety of the public were not affected.

5.

Subsequent Corrective Action:

The required constraints have been designed and will be installed prior to future reactor operation.

6.

Future Corrective Action:

7.

Further inadequacies, if any, in design features will be addressed in a similar fashion.

Generic Implications:

The reanalysis continues on all lines covered by I.E.Bulletin 79-14 and appropriate corrective actions will be taken if other ove~stressed conditions are identified.