ML17340A888

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Affidavit Re Contention 6(d).Probability of through-wall Corrosion Crack Is So Small as to Be Insignificant.Seal Welds Required to Be Coated W/Varnish to Assure No Ingress of Oxygen Through Seal Weld.Prof Qualifications Encl
ML17340A888
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 03/09/1981
From: Turovlin B
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17340A884 List:
References
ISSUANCES-SP, NUDOCS 8103240526
Download: ML17340A888 (8)


Text

'UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING.BOARD In the Matter of

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FLORIDA POWER 8( LIGHT COMPANY

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(Turkey Point Nuclear Generating

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Uni ts 3 and 4)

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Docket Nos.

50-250-SP 50-251-SP (Proposed Amendments to Facility Operating License to Permit Steam Generator Repairs)

AFFIDAVIT OF BERNARD TUROVLIN ON CONTENTION 6 d

I, Bernard Turovlin, being duly sworn, state as follows:

1.

I am employed'y the U.S.

Nuclear Regulatory Commission as a

Senior Materials Engineer in the Division of Engineering, Office of Nuclear Reactor Regulation.

Contention 6 states, in part:

There are likely to occur radioactive releases from one or more stored assemblies

.to unrestricted areas which violate 10 CFR Part 20 or are not as low as is reasonably achievable within the meaning of 10 CFR Part 50, as a result of:

d.

corrosion resulting from moisture, sea water, or salt spray; I have reviewed materials and processes to be used'n the storage of the shells of the Turkey Point 3 and 4 steam generators.

During my review of that information I examined the possibility that through-wall corrosion of the steam generator may release radioactivity.

First, the

'steam generator will be gravity drained of water.

This along with evaporation will remove most of the water.

The steam generator will then

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In addition, the applicant has performed an oxygen depletion study for the atmosphere within the sealed steam generator shell.

The oxygen analysis of the atmosphere in the sealed steam generator showed that there would be insufficient oxygen to support through-wall corrosion.

Based upon my review of this study, I conclude that the probability of a through-wall corrosion crack is so small as to be insignificant.

To assure that there would be no ingress of oxygen through the seal

weld, we have required that all seal welds be coated with a heavy-bodied varnish such as Glyptol.

I have also examined the possibility of through-wall corrosion from the outside of the sealed steam generator.

Although I do not believe it is necessary for that purpose, the heavy-bodied varnish coating of the seal weld will also retard the corrosion from the outside.

I have examined reports of corrosion testing of low alloy steel, such as the Turkey Point steam generator assemblies, at Kure Beach, N.C.

Like I/

Turkey Point, this is a seacoast marine atmosphere.

The data showed that low alloy steel had lost only 0.003 inches of thickness after 7.5 years of exposure.

I would expect comparable experience from the Turkey Point steam generator storage.

Based upon the above, I conclude that there will not be through-wall corrosion, either from within or from without, during the storage period of the generators which could be as long as 30 years.

At that time the radioactivity will have decayed to less than 15 of the amount present at the time of SG removal (See Safety Evaluation Report (NUREG-0756),

dated

December, 1980, 5 2.8.2).

I further conclude, therefore, that 1/

C.P.

Larrabee, 9 Corrosion 259 (1953).

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radioactive material will not be released from the steam generators due

.to.corrosion to unrestricted areas in quantities which violate the, radiation protection standards of 10 CFR Part 20 or the dose guidelines of 10 CFR Part 50, Appendix I.

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Bernar Tu ovlin Subscribed and sworn to.before me this 9~'ay of~7+u'rl'-'981.

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u'<r'tary Public ICjf~

My Commission expires:

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BERNARD TUROVLIN PROFESSIONAL'NGINEER - CALIFORNIA 89180 MAY 1949 I

am a Materials Engineer in the Chemical Engineering Branch of the Office Of Nuclear Reactor Regulation, Nuclear Regulatory Commission.

I am responsible for safety review and evaluation of the corrosion and compatibility of materials used in the construction and operation of nuclear power plants.

I have been associated with nuclear energy development and construction as an engineer or metallurgist since 1942.

I have been employed in these capaci-ties by numerous organizations beginning with the Metallurgical Laboratory of the University of Chicago transferring to Los Alamos Laboratory, Brookhaven National Laboratory, Combustion Engineering Inc., General Atomic, General Dynamics/Convair, U. S.

Army Nuclear Power Group.

I have spent a minimum of 4 years at each location I.have been responsible for the development of basic fabrication techniques, non-destructive examination, and fai lure analysis.

I have done engineering design and component testing for various components used in the nuclear energy field.

I have done safety review and corrosion and compatibility evaluation.

I have more than 15 patents for various components and techniques used in nuclear energy technology.

I have published more than a dozen papers related to nuclear energy technology.

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