ML20127A395
| ML20127A395 | |
| Person / Time | |
|---|---|
| Issue date: | 12/22/1982 |
| From: | Arndt E NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Jeffrey Mitchell Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20126E434 | List: |
| References | |
| FOIA-85-143 NUDOCS 8301040169 | |
| Download: ML20127A395 (4) | |
Text
.*
- lf UNITED STATES
, (gn ato, 'o g NUCLEAR REGULATORY COMMisslON g WASHINGTON, D. C. 20555 3
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\*****/ DEC 2 21982 MEMORANDUM FOR: Attendees FROM: E. G. Arndt MSEB, DET, RES
SUBJECT:
ORNL CONTAINMENT LEAK TEST SENSITIVITY STUDY In a meeting between NRC and ORNL staff on November 16, 1982, the objectives and limitations of this study were discussed and clarified.
The following points were made.
- 1. The two underlying' objectives behind this effort, as well as any other efforts on containment leakage, are to detennine:
- a. Adequacy of NRC regulations on leakage.
- b. Adequacy of containment leaktight integrity.
- 2. Tasks A - D in the FY 83 Program Brief were summarized as seeking the changes to risk contribution by the containment system as the leak rate changes. Analysis items (1) and (2) were summarized as an effort to estimate actual leakage between tests when combining test and operating data.
- 3. Primary study effort will be directed toward defining changes in risk relative to changes in containment leak rate, with enough effort devoted to estimating actual leakage between tests to establish an initial approach.
- 4. The judgements requested in (1) and (2) of the program scope will require time expenditures proportional to the amount of test and operational data to be analyzed. As a result, it was agreed that if the time needed to reduce and analyze the available data becomes excessive it would be acceptable to furnish a method for comparing the test and operational data to estimate actual leakage probabilities at times between tests, and to use only a limited data set to check the workability of the method.
- 5. Due to the complexity of issues involved and limited funding, it is recognized that this effort will involve simplifying assumptions that will generalize the results. The study will be useful in focusing on some significant questions of great current interest to the NRC staff, the public, and the nuclear industry. It will also be useful in detennining the amount of effort involved in pursuing any of the MI OlW L
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Att;nd:es .
' issues irt greater detail. Consideration of too many " realistic"
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variables would just guarantee that no product (s) would result from this limited effort. One of the simplifying assumptions will be that the affected person (s) will be assumed to be in place and exposed for the duration of the event, without evacuation.
- 6. ORNL will use NRC:DRA available material and will not perform any additional detailed computer runs.
- 7. Task C will not include consideration of the transient state as a containment changes from an "open" state, such as operating with purge valves open, to a " closed" state complying with 10 CFR 50, Appendix J requirements for post-accident isolation.
- 8. Task D is clarified to request ORNL opinions on improved method (s) for reporting containment leakage values that would be applicable to all containment types - without quantifying the value(s) to be used.
- 9. Direct comunicatiori between ORNL and NRC staff for exchange of information is appropriate, but conveying of instructions, inter-pretations or modifications will be through G. Arndt.
E . G .V dt Mechanical Structural Engineering Branch Division of Engineering Technology Office of Nuclear Regulatory Research l
,/ 7 Attendees: . -
George Flanagan, ORNL Thomas Burns. ORNL Karl Seyfrit. AE00/NRC Jocelyn Mitchell, NRR/NRC John Huang, NRR/NRC Joseph Murphy, RES/NRC Gunter Arndt, RES/NRC O
s 1
1 O
! Attendees '
. issues in greater detail. Consideration of too many " realistic" variables would just guarantee that no product (s) would result 1 from this limited effort. One of the simplifying assumptions will be that the affected person (s) will be assumed to be in place and exposed for the duration of the event, without evacuation.
- 6. ORNL will use NRC:DRA available material and will not perform any additional detailed computer runs. i
- 7. Task C will not include consideration of the transient state as a containment changes from an "open" state, such as operating with purge valves open, to a " closed" state complying with 10 CFR 50 Appendix J requirements for post-accident isolation.
- 8. Task D is clarified to request ORNL opinions on improved method (s)
- for reporting containment leakage values that would be applicable to all containment types - without quantifying the value(s) to be used.
- 9. Direct communicatio'n between ORNL and NRC staff for exchange of infonnation is appropriate, but conveying of instructions inter-pretations or modifications will be through G. Arndt.
E. G. Arndt Mechanical Structural Engineering Branch Division of Engineering Technology Office of Nuclear Regulatory Research i
DISTRIBUTION bec: R. Blond, RES RES Files W. Butler, NRR MSEB Files J. Shapaker, NRR E. Imbro, AE0D l G. Arndt i W. F. Anderson J. Barns l J. Richardson G. Arlotto L. Shao 1
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