ML20126F970
| ML20126F970 | |
| Person / Time | |
|---|---|
| Issue date: | 01/15/1985 |
| From: | Arndt G NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Richardson J NRC |
| Shared Package | |
| ML20126E434 | List: |
| References | |
| CON-FIN-B-0489, CON-FIN-B-489, FOIA-85-143 NUDOCS 8506180028 | |
| Download: ML20126F970 (8) | |
Text
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I ARNDT 1/15/85 O
NOTE T0: J. Richardson THRU: J. Burns I
FROM: G. Arndt
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i
SUBJECT:
STATUS OF ORNL-HELD FUNDS REMAINING FROM FIN B0489, CONTAINMENT LEAK RATE TESTING The $150,000 effort on Appendix J has been completed, with $3,105 left over.
The $50,000 supplementary effort on leak rate versus risk for DRA has been completed with $7,933 left over.
I The $7,933 has been transferred within ORNL and consolidated with Dan Naus'
$3.105, leaving a balance of $11,038.
This balance is being held in' reserve by Dan Naus, ORNL, to provide consulting expertise, if needed, in the area of containment leak rate testing. Some of these funds - about half - gy be used to have a potential subcontractor, Quadrex, answer some questions for NRR:CSB on the effects of diurnal temperature changes on leak rate tests. To date, however, Quadrex has not submitted the necessary material to ORNL to subcontract this review of test data.
ter Arndt hanical/ Structural Engineering Branch Division of Engineering Technology, RES 8506180028 850325 Q$ Jf'ID TB -143 PDR D
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FY 1983 PROGRAM ASSUMPT~ON DIVISION: DET 1
FIN NO.: B0489 TITLE: CONTAINMENT LEAK TEST SENSITIVITY STUDY CONTRACTOR: ORNL SITE: OAK RIDGE STATE: TN NRC TECHNICAL MONITOR: E. G. ARNDT PRINCIPAL INVESTIGATOR: G. FLANNIGAN FY 83 OBLIG: $50K BUDGET ACTIVITY:
FY 1983 WORK PERIOD: 11/1/82 - 2/1/83 OBJECTIVE:
DETERMINE WHETHER CURRENTLY SPECIFIED CONTAINMENT ALLOWABLE BE REVISED, AND, IF S0, HOW MUCH AND ON WHAT BASIS.
EVALUATE THE DESIRABILITY AND PRACTICALITY OF ESTABLISilING, EXPLICITLY IN APPENDIX J, A SINGLE LEAKAGE LIMITING CRITERION FOR ALL CONTAINMENT TYPES.
SCOPE:
DESIGN AND SITING PERSPECTIVES,"
DRAFT NUREG-0773, " REACTOR ACCIDENT SOURCE TERMS:
DATED MARCH 1982, PRESENTS CURRENT INFORMATION ON REACTOR ACCIDENTS THAT BEEN ANALYZED FOR VARIOUS REACTOR DESIGNS, AND DEVELOPS A SET OF RADI0 ACTIV RELEASES (SOURCE TERMS) IN CATEGORIES 1 THROUGH 5 WHICH RE OF ACCIDENTS.
USING RELEASE FRACTIONS TO THE CONTAINMENT WHIC!! CORRESPON 4 TERMS IN CATEGORIES 1 THROUGH 5:
A. PERFORM A SENSITIVITY ANALYSIS (INCLUDE ALSO TEST COST IN WHICH THE CONTAINMENT DESIGN LEAK RATE IS ASSUMED TO BE 0.1%, 0.5%, 1 5.0%,10%,25%,50%,and100%(WT.%/ DAY).
B. DETERMINE THE OFFSITE RISK IN TERMS OF DOSE TO THE PUBLIC F THESE POTENTIAL CONTAINMENT SOURCE TERMS, i
C. COMPARE RISK REDUCTION OF A SIMPLE GROSS CONTAINMENT IN THESE APPENDIX J LEAK RATE TESTS, AND D. EVALUATE THE DESIRABILITY AND PRACTICALITY OF ESTABLISHING, EXPLICITLY IN APPENDIX J, A SINGLE LEAKAGE LIMITING CRITERION FOR CONTAINMENT SYSTEM THAT WOULD APPLY EQUALLY WELL TO:
a) LARGE, DRY PWR CONTAINMENTS, b) TYPE I, II, AND III BWR CONTAINMENTS, c) ICE CONDENSER CONTAINMENTS, AND d) NEGATIVE PRESSURE CONTAINMENTS.
[ THIS ANALYSIS WILL PROVIDE A BASIS FOR JUDGING WHETHER THE P CONTAINMENT INTEGRATED LEAK RATE TEST CRITERIA ARE REALISTIC EFFECT ON PUBLIC RISK AND OPERATIONAL COSTS, AND SHOULD INCLUDE THE FOLLOWIN
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- 1) WHETHER THERE IS A CORRELATION BETWEEN LEAKAGE TEST VALUES / TEST INTERVALS AND ESTIMATED ACTUAL LEAKAGE DURING INTERVALS BETWEEN TESTS (BASED ON LERS, AS-FOUND TESTS, ETC.).
- 2) REVIEW THE CURRENT 0.25L3 SAFETY MARGIN TO SEE WHETHER IT PROVIDES REASONABLE ASSURANCE THAT ACTUAL LEAKAGE DOES NOT EXCEED DESIGN VALUE.
OTHER REFERENCES NUREG - 0771, (FOR COMMENT) REGULATORY IMPACT OF NUCLEAR REACTOR ACCIDENT SOURCE TERM ASSUMPTIONS, JUNE 1981.
- NUREG - 0772, TECHNICAL BASIS FOR ESTIMATING FISSION PRODUCT BEHAVIOR DURING LWR ACCIDENTS, JUNE 1981.
NUREG/CR - 2239 (DRAFT), TECHNICAL GUIDANCE FOR SITING CRITERIA DEVELOPMENT (2.3).
DESCRIBES, IN PART, ACCIDENT SOURCE TERMS, RELEASE CHARACTERISTICS, AND UNCERTAINTIES IN SOURCE TERM MAGNITUDES.
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WORK STATEMENT ADDENDUM Appendix J Requirements / Site Source Terms Draft NUREG - 0773, " Reactor Accident Source Terms: Design and iting Perspectives", dette-March 1982, presents current inf ormation reactor accidents that have been analyzed for various reactor design , and develops e a set of radioactive releases (source terms) in categories though 5
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^11$ Using release fractions to the containment which corre ond to these source terms, 4xcept-for thosc c ispu.RNng to an assumea c coinmeni. failuredi.e., .
. t%T-Q , in categories 1 through 5: ,.,eI. y p ,f c, , p. e s,d hu._ d p . r4 A. Perform a sensitivity analysis in which the containment design leak rate is assumed to be 0.1%, 0.5%, 1.0%,a w 5.0 a(wt.%/ day). 7 s
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B. Determine the of f-site risk, in terms- l ose, i.v Lhe pdBTI from each of these potential containment source erms, and C. Evaluate the desirability and pract cality of establishing, explicitly in Appendix J, a single leakage 11 iting criterion for containment systems that would apply equally well to-a) Large, dry PWR contain ents, b) Type I, II, and III B R containments, c) Ice condenser conta ments, and d) Negative pressure ntainments.
This analysis will provide a b sis for judging whether the present Appendix J containment integrated leak r te test criteria are realistic in terms of their effect on public risk and op rational costs, and should include the following:
- 1) Whether there is a rrelation between leakage test values / test intervals and estimated actu leakage during intervals beween tests (based on LERs, as-found tests, e .).
- 2) Review the curre t 0.25L., safety margin to see whether it provides reasonable assu<rance that actual leakage does not exceed design value.
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