ML20126E831

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Requests Authorization for ORNL to Execute Program Described in Encl NRC Order 60-82-248
ML20126E831
Person / Time
Issue date: 04/09/1982
From: Arlotto G
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To: Hart R
ENERGY, DEPT. OF
Shared Package
ML20126E434 List: ... further results
References
CON-FIN-B-0489-2, CON-FIN-B-489-2, FOIA-85-143 NUDOCS 8506170235
Download: ML20126E831 (7)
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Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.

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f APR v;m Mr. R. J. Hart, Manager Oak Ridge Operations Office U. S. Department of Energy P. O. Box E Oak Ridge, Tennessee 37830

Dear Mr. Hart:

FY 1982 NUCLEAR REGULATORY RESEARCH ORDER N0. 60-82-248 FOR OAK RIDGE NATIONAL LABORATORY Please authorize Oak Ridge National Laboratory to execute the program described in the enclosed NRC Order.

If this meets with your approval, it is requested thait acceptance be indicated on the enclosed form and the original be returned to the NRC Controller and a copy to this office.

Sincerely.

W.0 Afhtt-f' OHginal staned by eensmahete Guy A. Arlotto Director Division of Engineering Technology Office of Nuclear Regulatory Research

Enclosure:

NRC Order cc DIST cc w/ enclosure:

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4 NRC ecaw 173 us hwcLaaocacv6Aton,Csw stic%

onota=wwero 12 78' 60-82-248 i.

i DATE STANDARD ORDER FOR DOE WORK APR D 1982 l

lBEUL D TO IDGE Of f.cel itEUED BY INRC O' lice)

ACCOUNTING Cif AT40N Oak Ridge Operations Office Division of Engineering 31X0200.602 Technology, RES m a nww.t.

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P RFoRMiNG ORGANIZATION ANo toCATios P i~ ~uv et.

i Oak Ridge National Laboratory 80489-2 WORK PERIOD THis ORDE R i

FIN TITLE Flato O EsTiM ATED D Containment Leak Rate Testing enOv To 1 0/1/81 9/30/82 OBLIG ATION AVAIL ABILITY PROVIDED BY:

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150,000 A THIS ORDe m 8.

TOT AL 08 ORDi'*5 PL act D PRIOR TO TMis 047 6 mTM TMt PE R5 0RMING ORG ANa2 AttoN

' " ^N THE "*ST ' va D'G'T5 ' THE 5

41,281.000 TN "N5 e"cisio'"s 7v',' N 5Y"'

C. TOTAL ORDERS TO DATE rTOTAL A a el 8

41,431,000 D AMOUNT INCLUCED IN "C" APPLICABLE TO THE " FIN NUMBE R" CITED IN THIS ORDER.

S 150,000 el FIN ANCI AL F LEXIOILITY:

I C FUNDS WILL NOT BE REPROGRAMMED BETWEEN FINS. LINE D CONSTITUTES A LIMITATION ON OsLIGATIONS AUTHORIZED.

FUNDS M AY BE REPROGR AMMEO NOT TO EXCEED 210% OF FIN LEVEL UP TO S60K. LINE C CONSTITUTES A LIMITATION

@ ON OeLIGATiONS AUTMomi2ED

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STANDARD TERMS AND CONDITIONS PROVIDED t OE ARE CONSIDERED PART OF THis ORDER i I UNLESS OTHERWISE NOTED, ATTACHMENTS; THE FOLLOWING ATTACHMENTS ARE MEMEBY SECURITY:

MADE A PART OF THIS ORDER:

QWORK ON THis ORDER ll NOT CLAS$1FIED.

5 STATEMENT OF WORK Q WORK ON THIS ORDER INVOLVES CLAf$lklED D ADDITIONALTERMS AND CONDITIONS INFORMATION NRC FORM 187 is ATTACHED.

O OTHER REMARKS:

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/ ISSUIM k) THOR /T Y ACCEPTING ORG ANIZ ATION SIONATURL

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$iGNAfymg Guy Intto. DireedoF Division Of Engineertng Technology TiTLa l

TiTLs Office of Nuclear Regulatory Research ATs NRCFORM 173 12 78)

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I 1982 PROGRAM BRIEF I

PROGRAM: DET

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CONT: FIN NO.:

B0489 TITLE: Containment Leak Rate Testing CONTRACTOR: ORNL f

SITE:

Dak Ridge

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f NRC TECHNICAL MONITOR: E. G. Arndt f*

PRINCIPAL INVESTIGATOR: D.[aus t

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08JECTIVE:

i Evaluate the practicality of the containment leak testing program, and i

compatibility of regulatory requirements and industry testing standards.

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BUDGET ACTIVITY:

i 08LIG:

$150,000 i

l FY 1982 SCOPE:

(10/01/81-09/30/82) j A. Review existing containment leak rate testing regulatory requirements, and the programs conducted in compliance with these requirements, using field

,i and licensing experience.

i

8. Review the proposed Appendix J revision. Provide recommendations and bases for specific proposed Appendix J revisions, and comment on the remainder of l

l the proposed revision as appropriate.

f 56.8-1981, " Containment System Leakage Testing Requirements",

C. Review ANSI /ANS for compatibility with the proposed Appendix J revision.

I D. Provide a value-impact analysis for the entire proposed Appendtx J revision.

f as prepared for public comment issue, addressing the value and impact on the licensees, the licensing process, and the public. Revise the value-impact

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analysis as necessary following the pubite comment period, reflecting any chang l

made for the final rule.

i REPORTS:

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Monthly progress reports One draft report One final report l

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Fin # B0489 f

WORK STATEMENT ADDENDUM i

4 Appendix J Requirements / Site Source Terms Draf t NUREG - 0773, " Reactor Accident Source Terms: Design and Siting Perspectives", dated March 1982, presents current information on reactor t

accidents that have been analyzed for various reactor designs, and develops a set of radioactive releases (source terms) in categories 1 though 5 which represent the spectrum of accidents.

i' Using release fractions to the containment which correspond to these source terms, except for those corresponding to an assumed containment f ailure (i.e.,

SST-1), in categories 1 through 5:

l A. Perform a sensitivity analysis in which the containment design leak rate is assumed to be 0.1%, 0.5%,1.0%,and 5.0% (wt.%/ day).

B. Determine the off-site risk, in terms of dose, to the public from each of these potential containment source terms, and C. Evaluate the desirability and practicality of establishing, expitettly in Appendix J, a single leakage limiting criterion for containment systems l

that would apply equally well to:

a Large, dry PWR containments, b Type I, II, and !!! BWR containments, c Ice condenser containments, and d Negative pressure containments, j

This analysis will provide a basis for judging whether the present Appendix J containment integrated leak rate test criteria are realistic in terms of their i

effect on public risk and operational costs, and should include the following:

1) Whether there is a correlation between leakage test values / test intervals j

and estimated actual leakage during intervals beween tests (based on LERs, j

as-foundtests,etc.).

i

2) Review the current 0.25L., safety margin to see whether it provides reasonable assurance that actual leakage does not exceed design value.

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UNITE D STATES 5

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20$55 May 5 1982

Dan, Here is a copy of the missing material that should have been in the package delivered to you.

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7 o <N.m..... v ime ORNL Contract W odus - Luk Totinn _

W. Pasedag. AEB J. Glynn, RRBR Aftmy 4terationn between RRBRtRES & AEBtNRR.

7 o (N.m..ng.nM) ggggg ggs aggg T nian to discunn with ORNL on May 7.

1982 8"'8 the enata nchedule and content of the addendu!

me metsched. P l e n en e let in e know an early as 70 (Name.ad.ast) perm,s os.. ass cc: J.

Burns, SISEE possible if this addendum should not be G. Burdick, RRBR negotiated in its current form. Contributions to pay for this addendum are also solicited r aou <=.m..a..aro from your organizations to make sure that this work will get funded and done.

35860 4/27/82

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y Fin i 80489 WORK ST*TEMENT ADDENDUM Appendix J Requirements / Site Source Terms Draft NUREG - 0773, " Reactor Accident Source Terms: Design and Siting Perspectives", dated March 1982, presents current information on reactor accidents that have been analyzed for various reactor designs, and develops a set of radioactive releases (source terms) in categories 1 though 5 which represent the spectrum of accidents.

Using release fractions to the containment which correspond to these source terms, except for those corresponding to an assumed containment failure (i.e.,

SST-1), in categories 1 through 5:

A. Perform a sensitivity analysis in which the containment design leak rate is assumed to be 0.1%, 0.5%,1.0%,and 5.0% (wt.5/ day).

B. Determine the of f-site risk, in terms of dose, to the public from each of these potential containment source terms, and C. Evaluate the desirability and practicality of establishing, explicitly in Appendix J, a single leakage limiting criterion for containment systems that.would apply equally well to:

a Large, dry PWR containments, b Type I, II, and !!! BWR containments, c Ice condenser containments, and d Negative pressure containments.

This analysis will provide a basis for judging whether the present Appendix J containment integrated leak rate test criteria are realistic in terms of their effect on public risk and operational costs, and should include the following:

1) Whether ther'e is a correlation between leakage test values / test intervals and estimated actual leakage during intervals beween tests (based on LERs, as-foundtests,etc.).
2) Review the current 0.25L safety margin to see whether it provides reasonable assurance that actual leakage does not exceed design value.
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