05000280/LER-1979-004, Update to LER 79-004/01X-2:on 790309,A/E Notified Util of Possible Nonconservatisms in Pipe Stress Code Used to Analyze Piping Sys & of Innaccurate Valve Weights Used by Error in Pipe Stress Analysis & Valve Weight

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Update to LER 79-004/01X-2:on 790309,A/E Notified Util of Possible Nonconservatisms in Pipe Stress Code Used to Analyze Piping Sys & of Innaccurate Valve Weights Used by Error in Pipe Stress Analysis & Valve Weight
ML18136A126
Person / Time
Site: Surry Dominion icon.png
Issue date: 10/29/1979
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18136A125 List:
References
LER-79-004-01X, LER-79-4-1X, NUDOCS 7910310352
Download: ML18136A126 (6)


LER-1979-004, Update to LER 79-004/01X-2:on 790309,A/E Notified Util of Possible Nonconservatisms in Pipe Stress Code Used to Analyze Piping Sys & of Innaccurate Valve Weights Used by Error in Pipe Stress Analysis & Valve Weight
Event date:
Report date:
2801979004R00 - NRC Website

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LICENSEE EVENT REPORT

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LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 REPORT I X I(';:\\ I o I 5 SOURCE L.::_j~ _

60 61 DOCKET NUMBER 68 69 I O I O I O I 2 I 8 I O 101 ° I 3 I O I 91 7 1 9 IG) 11 IO I 21 9 I 7 I 9 I 0 EVENT.DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

I The Architect-Engineer (AE) notified VEPCO of possible non-conservatisms in the pipe stress code used to analyze some piping systems at Surry.

Inaccurate valve weights [Q_fil were also identified in some instances.

The health and safety of the public was not [Q]}J affected.

This event is reported per Technical Specification 6.6.2.a.9.

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43 44 I In reviewing the Beaver ValJ-ey piping design, the AE discovered an error in the pipe stress analysis and the valve weight used to analyze stress in some piping systems.

I 1 12 I.I It was found that the discrepancy also applies to Surry. An evaluation of the problem 47

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Surry Power Docket Nos:

Report No.:

Event Date:

Station, Unit Nos.

50-280 & 50-281 79-004/0lX-2 03-09-79 UPDATED REPORT 1 & 2 e, page 1 Title of Report:

Pipe Stress Analysis Evaluation

1.

Description of Event

The Architect-Engineer (AE) notified VEPCO of possible non-conserv?tism in pipe stress code used to analyze some piping systems at Surry.

In-accurate valve weights were also identified in some instances.

The health and safety of the public were not affected.

This event is reported per Technical Specification 6.6.2.a.9.

2.

Probable Consequences and Status of Redundant Systems:

Possible non-conservatisms are being investigated by the Architect Engineer to determine their extent and magnitude.

3.

Cause

In reviewing the Beaver Valley piping design, the AE discovered an error in the pipe stress analysis and the valve weight used to analyze stress in some piping systems.

It was found that the discrepancy also applies to Surry.

Evaluations of the problem have identified the need for modifications to some of the supports installed, and the work to achieve the required safety factor on these supports has been accomplished to enable Unit No. J.

to return to power.

Continuing evaluation and modification are in progress to complete the.

work on Unit No. 1 as well as to detennine the extent of modifications which will be required for Unit No. 2.

4.

Immediate Corrective Action

The immediate corrective action*was to begin an investigation to determine if the significance of any non-conservatisms are of suffficient magnitude to require corrective action.

Unit 2 was already shutdown for steam genera-tor repairs.

Unit 1 was shutdown pending the investigation of the discrepancy.

5.

Subsequent Corrective Action:

Analysis of piping and supports within the containment has been completed, with a portion of the systems outside containment yet to be analyzed. gives basic details of modifications completed as of this time on Unit No. 1.

It should be noted that while some of the modifica-tions effected were required because of analysis results, many others were initiated to rectify as-built deficiencies.

lttt,i"ehrnent 2 Su1:ry Power Station, l'nit l & 2 Docket Nos: 50-2BO l, ?.Bl LER Rc,pot*t No: 79-00t,/OJ.X-2 Event Date:

03-09** 79 lll' DA'J'Ell lcEl'O!:T Page 1

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SHAY-STIWT C & RS 10"-RS-12-153 CONSTRAINT cc 18"-CC-17-121 COHSTRAINT cs 10"-CS-3-153 CONSTRAINT cc 18"-CC-17-121 CONSTRAINT cs 10"-CS-3-153 CONSTRAINT cc 18"-CC-17-121 CONSTP-AU!T RS 10"-RS-12-153 COllSTRAINT cc 18"-CC-229-121 CONSTRAINT RS 10"-RS-li-153 CONSTRAINT cc 18"-CC-228-121 CONSTRAI!!T cs 10".:..cs-4-153 CONSTMINT ----

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--~ I 6"-C~IOJ-151 CONSTRAINT cs 8"-CS-22-153 SWAY-STRUT CC 6"-CC-31-151 ANCHOR cs 8"-CS-22-153 SWAY STRUT cc 6"-CC-161-151 A!ICIIOR cs 8"-CS-34-153 ROD HANGER cc 6

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UPDATED REPORT, page 2

6.

Future Corrective Action:

Analysis will continue and modifications will be made to assure overstress conditions are relieved.

Upon completion of the entire program, a com-piled list of all modifications made will be submitted as a followup report.

7.

Generic Implications:

This event is applicable to Surry Units 1 and 2.

Att..ich1nent 2

  • e Surry Power Statiun, U~it 1 & 2 Docket llos: 50-280 & '.Wl LER Report No: 79-00!,/0J.X-*2 Event Date:

03-09-79 t;PD,\\TED REPORT

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