ML20213E705
| ML20213E705 | |
| Person / Time | |
|---|---|
| Issue date: | 12/27/1983 |
| From: | Bernero R NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Mattson R, Ross D, Speis T NRC |
| Shared Package | |
| ML20213E209 | List:
|
| References | |
| FOIA-87-113, FOIA-87-60 NUDOCS 8401230133 | |
| Download: ML20213E705 (6) | |
Text
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December 27, 1983 MEMORANDUM FOR: SARP Management Group FROM:
Robert M. Bernero, Director Accident Source Tem Program Office Office of Nuclear Regulatory Research
SUBJECT:
REVISIDNS TO KEY MEETING SCHEDULE IN INE WINTER 1983-1984 In my, memorandum of November 25, 1983 I outlined a schedule of key severe accident and source tem meetings over the next 6 months. Since that time I have received word from IDCOR that they are experiencing delays in completing their reports.
Attached for your infomation is a proposed revised meeting schedule.
If the new meeting dates pose problems, please let me know.
Robert M. Bernero Director Accident Source Tem Program Office Office of Nuclear Regulatory Research
Attachment:
As Stated cc:
M. Ernst J. Larkins M. Cunningham A. Wang, ACRS
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Addressees - Memorandum dated December 27, 1983 D. Ross R. Mattson T. Speis
~ R. Vollmer E. Jordan G. Arlotto
- 0. Bassett A. Bernero 9
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12/19/83 l
1 SCHEDULE OF KEY MEETINGS.
ON SEVERE ACCIDENT WORK Meeting No. ~1, NRC/IDCOR - Phenomena November 29-December 1 Agenda:
Phenomena basis for modeling of:
1.1 Progression of core melt in the reactor coolant system 1.1.1 Calculation of reactor coolant system thermal and hydraulic behavior 1.1.2 Rite and magnitude of hydrogen production in-vessel 1.1.3 Interactions between fuel debris and structures surrounding a
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or supporting the fuel 1.1.4 Interactions between fuel debris and the reactor vessel or
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vessel penetrations i
Likelihood and magnitude of in-vessel steam explosions or 1.1. 5 spikes 1.1.6 Debris coolability in the vessel 1.2. Loading of the containment j,
1.2.1 Calculation of containment temperature and pressurc response 1.2.2 Rate and magnitude of combustible gas production ex-vessel 1.2.3 Distribution of combustible gases 1.2.4 Conditions leading to and resulting from diffusion flames 1.2.5 Conditions leading to and resulting from deflagration 1.2.6 Conditions leading to and resulting from detonation 1.2.7 Likelihood and magnitude of ex-vessel steam explosions or spik-l-
1.2.8 Debris coolability in ex-vessel locations 1.2.9 Debris dispersal following vessel failure
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Holten fuel - structural interactions:
1.2.10 Between fuel debris and containment shell 1.2.11 Between fuel debris and containment floor 1.2.12 Between fuel debris and internal containment structures 1.2.13 Generation of non-condensible gases 1.2.2 Generation of combustible gases 1.3.7 Extent of penetration of floor Remarks: This meeting covers the phenomena but will undoubtedly include some discussions of modeling.
It will be useful to identify potential areas of controversy in modeling for agenda planning of later meetings but the controversies should not be pursued in Meeting No. 1.
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American Physical Society Visit to ORNL December ' 2-3
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Agenda: The APS team studying the science of source term estimation will review the research and test data from ORNL programs.
Initial Meeting on Containment Capacity December 21 Agenda: Open dialogue on the known differences between IDCOR and NRC treatment of containment capacity.
Remarks: This is an introductory meeting and is not expected to produce firm statements of agreement or difference.
American Physical Society Review of BCL Work (Cambridge, MA)
January 16-17 Agenda: The APS team studying.the science of source term estimation will review the research test data, and analytical results from BCL programs. Agenda will also include selected comparisons with IDCOR data.
NRC-IDCOR Management Meetin,g (Washington,D.C.)
January 25 Final Source Term Experts Peer Review Meeting January 25-26 Agen'da: The source term experts who have been providing detailed peer review of source term work since January 1983 will meet for the final review of BMI-2104.
Remarks: All volumes of BMI-2104 (reference plant source term esti-mates for selected accident sequences) will be available by December 15.
NRC Containment Loads Group (Soeis)
February 1-3 Agenda: Continue development of NRC position on calculation of containment loads for the reference plants.
Remarks: Although some loose ends are expected. this meeting should help to set the basis for the interaction with IPUDR in this subject area during Meeting No. 3.
Meeting No. 2, NRC/IDCOR - F.P. Transport February 7-8 Agenda: This meeting covers:
1 1.4 Fission product release and transport 1.4.1 Rate and magnitude of release of fission products from fuel l
in-vessel 1.4.2 Deposition of fission products during in-vessel transport
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1.4.3 Rate and magnitude of release of radionuclides from fuel ex-vessel 1.4.4 Deposition of fission products in containment due to natural processes 1.4.5 Effect of engineered safety features on fission product retention 1.4.6 Deposition of fission products in other plant buildings 1.5 Ex-containment consequence analysis Remarks: Based on discussions with IDCOR (Bernero/Fontana) little discussion of ex-containment' consequence analysis is needed.
Discussion of the other elements of F.P. transport should have a solid basis since most of the NRC work is available already in source term work, etc.
Only 2 days are allocated for this meeting because major controversies are not expected in F.P. transport modeling but rather in the MAAP code or MARCH / MERGE calculated temperatures which drive the F.P. transport.
NRC Containment Capacity Group (Vollmer)
February ?
Agenda:
Review and agree on the technical basis for the leakage model as now addressed in Draft No. 3 of the "Bagchi Report."
Remarks _:
Some loose ends should be expected here too. The report completion is expected in March, but the technical positions which derive from this meeting are needed for IDCOR interaction in Meeting No. 3 and perhaps in a separate NRC/IDCOR meeting which is a followup to the December 21 meeting.
March 1-2 NRC Containment Loads Group (Speis)
Agenda: Complete development of NRC position on calculation of contain-ment loads for the reference plants.
March 12-13?
APS Meeting on Sandia Work Agenda: The APS team studying the science of source term estimation will review the research, test data, and analytical results from Sandia programs.
Meeting No. 3, NRC/IDCOR - Integrated Assessment _
April 10-13 Agenda _: This meeting will treat the integrated assessment of severe accidents, covering:
2.1 Identification of the important accident sequences 2.1.1 Plant categorization 2.1.2 Identification of accident sequences for deterministic and probabilistic analysis 2.1.3
.Quantification of sequence likelihood for probabilistic analysis
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1 1.3 Response of the containment and other essential equipment I'
1.3.8 Reliability of early containment isolation
' (Character and likelihood of early containment failures
- 1. 3.1 -1. 3. 6 (Character and likelihood of later containment failures 1.3.9 Equipment and instrumentation survivability 2.2 Integrated assessment of safety 2.2.1 Calculated response of typical (reference) plants to selected i
severe accidents 2.2.2 Qua'litative assessment of likelihood and capability for severe accidents 2.2.3 Integrated probabilistic risk assessments for reference plants 2.2.4-2.2.7
{Genericconclusionsindependentofdesign Conclusions applicable only to reference plants Residual uncertainty for other plants Analysis required to qualify other plants to the generic
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Remarks: This appears to be the most difficult meeting of the NRC/IDCOR above)ge of The covera set because of its scope; 3 to'4 days will be needed.
should identification of accident sequences (elements 2.1.1-2.1.3 not take more than about 1/2 to 3/4 of one day.
The response of contain-ment could be a separate meeting but, if separated, it would seriously detract from this meeting.
Note: When relatively firm NRC positions in key technical areas are made relatively fim by Meeting No. 3 and the two NRC meetings preceding it.
the revised source tem calculations by BCL and revised risk and risk reduction cost / benefit calculations by SNL can be started.
l Meeting No. 4, NRC/IDCOR - Design, Operations, and Risk May 30- 31 i
L A_genda:
l 2.3 Assessment of possible changes in design, operation and emergency preparedness
[ Operational reliability 2.2.8, 2.3.1 LDesign changes to better prevent accidents 2.3.2 Improvements in severe accident management capability 2.3.3 Design and emergency preparedness changes for severe accident consequence mitigation
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Selection of cost-benefit methods and criteria Note: The preceding schedule should permit completion of key source term calculations and initial detemination of NRC staff position on i
severe accidents by summer of 1984.
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