ML20128L527

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Summary of 930115 Meeting W/Util in Rockville,Md Re Containment Penetration Bellows Tests in Response to NRC Info Notice 92-20
ML20128L527
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 02/12/1993
From: Hopkins J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
IEIN-92-020, IEIN-92-20, NUDOCS 9302190281
Download: ML20128L527 (17)


Text

_

4 Docket No. 50-346 February 12, 1993 LICENSEE:

10LEDG EDIS0N COMPANY FACILITY:

DAVIS-LESSE NUCLEAR POWER STATION, UNIT 1

SUBJECT:

SUtWiRY Of MEETING HELD ON JANUARY 15, 1993 TO DISCUSS CONTAINMENT PENETRATION BEtt0WS TESTS On January 15, 1993, NRC staff members met at Rockville, Maryland, with employees of Toledo Edison Company (TE) to discues containment penetration bellows tests at Davis-Besse in respons>1 to NRC Informaticn Notice 92-20. A list of attendees is included as enclosure 1.

The handout used at the meeting is included as enclosure 2.

The licensee discussed background information, its proposed testing program, and a proposed exemption request.

Following the licensee's presentation, the NRC staff stated that it would like TE to perform some measurement testa that would confirm the need for an exemption.

The NRC staff also requested TE to provide a description of their crack measurement leakage determination method including a discussion of uncertainties with any exemption request that is submitted. TE stated that they would consider the NRC requests for additional information, and would be submitting an exemption request fairly soor.,

original signed by Jon B. Hopkins, Sr. Project Manager Project Directorate 111-3 Olvision of Reactor Projects III/IV/V Ofrice of Nuclear Reactor Regulation QlSTRIBRUOB

Enclosures:

Docket File OGC As stated NRC & Local PDRs EJordan PD3-3 Reading SStasek cc w/ enclosure:

THurley/FMiraglia RLanksbury See next page JPartlow ACRS(10)

JRoe GGrant, EDO JZwolinski Region 111, URP JHannon RBarrett PKreutzer JKudrick JHopkins JPulsipher

_L OFFICE PDill-3:tA:DRPW PDill 3._:PM:DRPW PDill 9,: dD.:..D.RPW NAME PKreutzerAM JBHonkins/Jbh/et JHannon w.TE a //2 /93

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ATTENDEES January 15, 1993 UAME DEGANIZAT10t(

J, Hopkins NRC E. Caba 1E J. Cunnings IE J. Hannon NRC R. Barrett NRC R. Schrauder TE P. Smith IE i

M. Schreitier 1E J. Kudrick NRC J. Pulsipher NRC t

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Toledo Edison 1

Meeting 1witTKRC on-Davis-Besse: Response L

to InformationLNo: ice 92220 Containment Penetration

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Present Activities Since November 19,1992-Meeting Summarize Relevant Information Present Basis for Planned Exemption Recuest h"

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BACKGROUND IN 92-20 identifies containment bellows LLRT problems at Quad Cities (March !992);

Bellows plies may be in contact restricting flow Davis-Besse bellows from same manufacturer (different design than Quad Cities)

Similar LLRT test method LLRT required during 8RFO (non-ILRT outage)-

No bellows integrity problem based on five past lLRTs and LLRTS h

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BACKGROUND Davis-Besse Orientation l

Large steel containment with Shield Building Emergency Ventilation System No unfiltered leakage path from bellows 4 penetrations; 2 bellows-per penetration-Penetration location presents difficult access:

Limited access except during refueling outages High Pa (38 psig)

Consistent ILRT Performance No leakage detected by current test method

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J SLIM VIARY O.: ACTIVr~lES S hon N OV EV 3R ~ 9,1992 M EE~~ LNG 9

investigate 3 anned Va ication lDuririg 3 ant Oaera: ion Gain 3etter Uncerstariding of Quad:Ci"les!

o 3ro alem Conclusions o

Current - es: Viethod De::ects Lea < age;

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No Crecia e Vlechanisms to Caallenge La 3e": ween IL9TS t

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QUAD CITIES EXPERIENCE Excessive Bellows Leakage discovered during ILRT Modification Work during outage on attached valvo and adjacent penetration Pre-and Post-mod LLRTs indicated an-5 increase in Measured Leakage Special LLRT Flaws Mapped Bellows was replaced Metallurgical Exam of Bellows

  • Contaminants of indeterminant origin Crack Growth Evaluation
  • Critical Crack Size Comparison of estimated / measured leakage Special He and Air tests on Bellows at Dresden l

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M LEAKAGE DETECT!ON CAPABILITY CECO Helium Test

  • Two tests; one air, one helium
  • Indicates if air flow between plies to external leaks are obstructed
  • Results compare favorably with expect resuit:

for He Based on this test NRC concluded that current isst method can detect leakage Demonstrated that test can detect leakage

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CURR'ENT PLANS L

lecuest Exemotion " rom Appendix J
  • Tyoe B _ea< age Quaritification I

BAS.S FO9 2XEV PTLOh Uncer ying 3uraose of A3cencix J Satis"lec

  • Assure tlat La is not exceec ec
  • 3ericcio Survei ance icenti"les the need for Corrective Actions Puroose Satisfiec oy Current Test Vetloc
  • No crecib e meclanism.to exceed La
  • Detect significant lea:< age Y

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~O EXCEED La Large Margin between As-Found ILRTs and L~a Metallurgical Exams concluded TGSCC:was.

mechanism which initiated flaws t

Evidence suggests flaws were opened by refueling.

outage work J

TGSCC due to presence of contaminants of indeterminate origin Manifested as pits on inside bellows.

. Leakage first detected at Quad Cities at 5 years No leakage detected in 15 years at DBNPS-

  • Mechanism not active-or slow a
  • Leakage would be detected by current test Slow Crack growth rate Margin to Critical Flaw Size Margin to La could accommodate many flaws

JB N PS '3RO 3OS EJ TES N G 3ROGRAM

o Estaa is, tires 1old lea< rate "or current test of 0.5 sof, c;

" 0.5 sc"1 exceec ec.

repeat test wit 1 suitaa e trace gas-

  • sniff ae lows exterior f exterior ea< age cetectec a
  • sni" interior o" bel.ows If both interior / exterior ea< age.cetectec
  • 9emove arotective siroud Veasure anc maa crac<e Eva uate
  • Current anc arojectec. lea < rate
  • Structura. Assessment

.f aro.'ectec lea < rate exceeds 0.15Lc revisit witi N RC arier to restart 1

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SUMMAR'Y t-i Underlying Purpose satisfied ay current test

  • Progressive actions based on test resu ts
  • No credible mechanisms to cha ;enge La e

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