ML19246A991
| ML19246A991 | |
| Person / Time | |
|---|---|
| Site: | Crane, Davis Besse  |
| Issue date: | 05/17/1979 |
| From: | Bryan S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19246A988 | List: |
| References | |
| NUDOCS 7907100322 | |
| Download: ML19246A991 (2) | |
Text
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UNITED Si'ATES NUCLEAR REGULATORY COMMISSION 3m - a WASHINGTON, D C. 20555 s, v /
May 17, 1979 e
MEMORANDUM FOR:
Norman C. Moseley, Director, DROI, IE e,
FROM:
Samuel E. Bryan, Assistant Director for Field Coordination, DROI, IE
SUBJECT:
SAFETY CONCERNS - J. CRESWELL This memorandum records the elements of a discussion I had with Jim Creswell on Miy 1, 1979.
I had the disci'sion with Jim for the purpose of obtaining his :ifety concerns so they could be appropriately resolved.
Those concerns are listed below.
1.
Would the presence of auxiliary feeu.ater in its normal sequence have altered the TMI event; that is would unacceptable results have occurred with nomal auxilir ry feedwater, other parameters and events being as they were experienced? For example, what are the fuel sin compression factors ender such a transient?
2.
In a circumstance such as TMI-2 ir:ident, can the reactor coolant pumps be relied on to continue operation; i.e., can pump operation be counted on to continue forced circulation in the saturated condition?
3.
Natural Circclation - Can B&W plants accommodate natural circulation for situations as described in Mr. Michaelson's report?
4.
Operator action required to be taken within 10 minutes to combat : LOCA, for example.
Is this in adequate time?
5.
Incore monitors should be reviewed in light c,f TMI-2 to determine whether or not they should be safety grade.
6.
DavisBesseplantisa}lowedalargepositivemoderator coefficient +0.9 x 10~
Ak/k per F.
Can we accept this value?
7.
Davis Besse has two steam driven auxiliary feedwater pumps --
no electrical driven, therefore no diversity.
Should this be allowed?
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I Norman C. Moseley I recommend that we forward his concerns to NRR and request that we be kept informed of their status or resolution.
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Samuel E. Bryan, Assistant Director for Field Coordination Division of Reactor Operations Inspection, IE cc:
J. G. Keppler, RIII R. F. Heishman, RIII J. Streeter, RIII E. L. Jordan, IE J. S. Creswell, RIII
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l WASHINGTON D. C. 20555 MAY 3 01979 MEMORANDUM FOR D. Ross, Deputy Director Division of Project Management V. Stello, Director Division of Operating Reactors FROM Roger J. Mattson, Director Division of Systems Safety SUBJECT SAFETY CONCERNS - J. CRESWELL The enclosed May 29, 1979 memo from Moseley requests NRR evaluation of concerns raised by Region III inspector J. S. Creswell.
I believe a proper breakdown of assignments for the seven concerns is as follows:
1.
Lessons Learned Task Force 2.
Lessons Learned Task Force 3.
Bulletins and Orders Task Force 4.
Lessons Learned Task Force 5.
Lessons Learned Task Force 6.
Division of Operating Reactors 7.
Bulletins and Orders Task Force Please provide your input to Warren Minners by June 15, 1979. He will coordinate your input with that of the Lessons Learned Task Force for my reply to Mr. Moseley.
Division o[r Systems Safety Rog MJtson,tDirector cc:
J. G. Davis, IE J. G. Keppler, RIII R. F. Heishman, RIII J. Streeter, RIII J. C. Creswell, RIII S. E. Bryan, ADFC, IE E. L. Jordan, ADTP, IE W. Minners R. Ireland F. Schroeder NRC PDR
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