ML17208A527

Requests Technical Basis,Analysis & Experimental Data Re Use of Ameron Nukem 750 Caulk as Expansion Joint Filler Inside Containment.Info Should Be Provided by 800530 or NRC Should Be Informed in Seven Days If Unable to Meet Schedule

ML17208A527
Person / Time
Site:	Saint Lucie
Issue date:	04/10/1980
From:	Baer R Office of Nuclear Reactor Regulation
To:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
References
NUDOCS 8004250038
Download: ML17208A527 (3)

Text

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Docket No. 50-389 We request that you provide a technical basis, supported by analysis or experi-mental data, for the use of Ameron NUKEM 750 as a qualified caulk to withstand DBA conditions in the Unit 2 containment design.

This information should be provided no later than May 30, 1980.

P'tease inform us within seven days of receipt of this letter if you cannot meet this schedule.

~'incerely,,

Ortgtnal Signed R(f, Distribution NRC PDR ELD

'ocal-PDR IE(3) eR10 i889 Docket Fi 1 e RHVollmer LWR ¹2 File VBenaroya DFRoss FSchauer DBVassallo WSHazelton SAYarga BDLiaw FOWilliams NCMosely RLBaer HDThornburg RABirkel 'HGrier JLee JO'Reilly RJMattson VSNoonan Dr. Robert E, Uhrig SHanauer JGKeppl er Vice President of Nuclear J Knight KVSeyfr'it and General Engineering RTedesco RHEngelken Florida Power and Light Company RDeYoung CMurphy P. 0.

Box 529100 VAMcore JLenahan Miami, Florida 33152 hlKreger

.JHalapatz MLErnst NSIC

Dear Dr. Uhrig:

RPDenise TIC ACRS(16)

SUBJECT:

USE OF NUKEM 750 AS EXPANSION JOINT FILLER INSIDE CONTAINMENT (St. Luc)e Plant, Unit 2)

We understand that.you are using Ameron NUKEM 750 caulk for the circumferential expansion joint between the steel containment and the concrete floor inside the St, Lucie Plant, Unit 2 containment at elevation 23'-0".

We are unaware of the performance characteristics of NUKEM 750 in a DBA environment nor if the material has been so qualified.

There is evidence of degradation in materials similar to NUKEM 750 in a DBA environment.

Given such evidence we are unable to deter-mine that NUKEM 750 will survive a DBA without becoming dislodged and entering the containment sump as debris with the potential of impairing the effective-ness of engineered safety features, the emergency core cooling system and the containment spray system, as addressed in Regulatory Guide 1.82, "Sumps for Emergency Core Cooling and Containment Spray Systems" and Standard Review P'fan

6. 2.2, "Containment Heat Removal Systems."

ccs:

See next page Robert L. Baer, Chief Light Water Reactors Branch No.

2 Division of Project Management OFFICE SURNAME DATEf

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Or. Robert E. Uhrig

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Vice President of Nuclear and General Engineering Florida Power 5 Light Company P. 0.

Box 529100-Miami, Florida 33152 ApR 1018 CC:

Jack,R.

Newman, Esq.

Lowenstein,

Newman, Rei,s 8 Axelrad 1025 Connecticut

Avenue, N.

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Washington, D. C.

20036

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Norman'. Coll, Esq.

McCarthy, Steel, Hectory 8 Davis

,14th Floor, First National Bank Building Miami, Florida, 33131 Mr. Martin H. Kodder 1131 N. E. 86 Street

Miami, F 1 or ida 33138 Ch

<< ~ 4 Edward Luton, Esq.,

Chairman Atomic Safety and Licensing Board U.

S'. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. David L. Hetrick Professor of Nuclear Engineering The University of Arizona Tucson, Arizona 85721 S<<

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Dr. Frank F. Hooper School of Natural Resources University of Michigan Ann Arbor, Michigan 48104 C

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