Text

Forwards Thermal & Radiation Aging Degradation of Selected Matls. Requests Review & Addition of Info by 791031
	ML19291B439
Person / Time
Issue date:	10/17/1979
From:	Lainas G; Office of Nuclear Reactor Regulation
To:	Bennett G; NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
References
	NUDOCS 7911080219
	Download: ML19291B439 (8)
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'o, UNITED STATES 8 j

,3., (h NUCLEAR REGULATORY COMMISSION N' ' "'/ ' '

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E WASHINGTON, D. C. 20555 OCT 171979 MEMORANDUM FOR: Gary Bennett, Chief, Research Support Branch, RSR FROM:

G. Lainar., Chief, Plant Systems Branch, D0R

SUBJECT:

QUALIFICATION TESTING EVALUATION PROGRAM - MATERIALS AGING The enclosed document entitled, "Themal and Radiation Aging Degradation of Selected Materials", is a part of DOR's proposed guidelines for evaluating qualification of Class IE electrical equipment in operating reactors. The infomation in this document and the subject of materials aging in general was reviewed at a meeting between Ron Feit, from your branch, Ken Gillen, from Sandia Laboratories, and Ed Butcher, from DOR, on September 18, 1979.

We believe that the work that RES is doing in the field of aging testing methodology is directly relevant to DOR's practical problem of identifying equipment where aging is a significant safety consideration. The purpose of this memorandum is to request that RES perform a review of the infor-mation contained in the enclosure and supplement the enclosure with any additional information that you have developed or that you are aware of which was developed by others working in the field.

We would appreciate it if you could complete your coments by the end of October 1979.

This short schedule is based on commitments to the Commission in connection with the staff reviews of licensee responses to IE Bulletin 79-01, Environment Qualification of Class IE Electrical Equipment.

I

/

Ql../

G. Lainas, Chief Plant Systems Branch Division of Operating Reactors

Enclosure:

As stated

Contact:

E. Butcher

,.li0 281 X-27900 cc:

See page 2 N

7911080 e nL

, cc w/ enclosure:

B. Grimes G. Lainas D. Tondi R. Feit E. Butcher

?010 282

APPENDIX C

, THERMAL AND RADIATION AGING DEGRADATION OF SELECTED MATERIALS Table C-1 is a partial list of materials which may be found in a nuclear power plant along with an indication of the material susceptibility to radiation and themal aging.

0 Susceptibility to significant themal aging in a 45 C environment and normal atmosphere for 10 or 40 years is indicated by an (*) in the appro-priate column.

Significant aging degradation is defined as that amount of degradation that would place in substantial doubt the ability c#

typical equipment using these materials to function in a hostile envi ronment.

Susceptibility to radiation damage is indicated by the dose level and the observed effect identified in the column headed BASIS. The meaning of the tems used to characterize the dose effect is as follows:

e Threshold - Refers to damage threshold, which is the radiation exposure required to change at least one physical property of the material.

Percent Change of Property - Refers to the radiation exposure e

required to change the physical property noted by the percent.

e Allowable - Refers to the radiation which can be abscrbed before serious degradation occurs.

The infomation in this appendix is based on a literature search of sources Scluding the National Technical Infor ation Service (NTIS), the National eronautics and Space Administra:icn's Scientific and Technical Aercspace a

Rapor: (STAR), NTIS Government Recor: Announcements and Incex (GRA), and

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s

_ 2 various manufacturers data reports.

The materials '.ist is not to be considered all inclusive neither is it to be used as a basis for specifying materials to be used for specific applications within a nuclear plant.

The list is solely intended for use by the NRC staff in making judgements as to the possibility of a particular material in a particular application being susceptible to significant degradation due to radiation or thermal aging.

The data base for thermal and radiation aging in engineering materials is rapidly expanding at this time. As additional infornation becomes available Table C-1 will be updated accordingly.

7oi 0 2134 O

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TABLE C-1

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ML19291B439

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