ML20125D479
| ML20125D479 | |
| Person / Time | |
|---|---|
| Issue date: | 09/27/1977 |
| From: | Richings H Office of Nuclear Reactor Regulation |
| To: | Minners W Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20125D471 | List: |
| References | |
| REF-GTECI-D-03, REF-GTECI-SY, TASK-D-03, TASK-D-3, TASK-OR NUDOCS 8001140325 | |
| Download: ML20125D479 (2) | |
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SEP 2 7 B77 MEMORANDUM FOR: W. Minners, Technical Assistant, DSS FROM: H. Richings, Reactor Physics Section, Core Performance Branch, DSS
SUBJECT:
ACRS GENERIC ITEMS - II A 1 In response to your memorandum of September 19, 1977, nothing has changed for II A 1, Control Red Drop Accident (BWRs), since the last report. The last status statement may 'be repeated, Control Rod Drop i.e., " Resolved and documented in staff report Accident (BWR)' submitted to the Committee on June 1, 1976."
As an aid to understanding the status of this item, the follow-ing is a brief reminder of the recent history of interaction with the ACRS.
- 1. The staff sent (above) report in June 1976 discussing various aspects of rod drop concerns including the original problem on reactivity insertion rates and later problem on 3D vs 2D analyses, and the resolu-tions of these problems. The report indicated we considered the problems resolved, but would continue in the future on 3D analyses when computer codes (MEKIN) reached the state of application.
- 2. The report was discussed with the ACRS (June 76 7) and no significant question or dissent was raised.
- 3. At a later (February 77 ?) ACRS meeting the subject of the German response to GE (analysis of original l German paper) was brought up and the ACRS (Dr. Okrent) requested to see it. Tne response was sent February 11, l
1977 along with a note with a brief discussion to assist the ACRS review and a statement that nothing in the response altered our view that the item is resolved.
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- 4. No new question or dissent since 'that time is known.
E' At this time there is no new information-from the staff (or BNL) on 3D' calculations. BNL has been working on getting.the code understood and operational.
A coarse-mesh version has been used for a.BWR scram reactivity study, but this version is not satisfactory for rod drop analysis. BNL is still working on the acquisition and operability of more suitable (fine mesh) versions.
Howard Richings Reactor Physics Section Core Performance Branch Division of Systems Safety cc: D. Ross P. Check-D. Fieno 90017019 1
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