ML19224C529
| ML19224C529 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/29/1979 |
| From: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Mattson R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19224C528 | List: |
| References | |
| FOIA-79-98 NUDOCS 7907020492 | |
| Download: ML19224C529 (1) | |
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UNITED ST ATES NUCLEAR REGULATORY COMMISSION 2
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MAY 2 91979
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MEMORANDUM FOR:
Roger J. Mattson, Director, Division of Systems Safety, Office of Nuclear Reactor Regulation FROM:
Noman C. 240seley, Director, Division of Reactor Operations Inspection, Office of Inspection and Enforcement
SUBJECT:
QUESTIONS OF P0TENTIAL SAFETY CONCERN Discussions between J. S. Creswell, Region-III inspector, and S. " Bryan have disclosed safety concerns that Mr. Creswell has that resul'.u from the TMI-2 incident.
These concerns are listed in the enclosure as "'
Nos. I through 5.
(The remaining two will be referred to V. Stello).
Since these items relate to matters leading to licensing decisions, we request that DSS evaluate the concerns and provide a response to me.
I will appreciate any early attention you can give these concerns.
- PCmf
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s'rr> 9 -
Norman C. Moseley Director Division of Reactor
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Operations Inspection Office of In:pection and Enforcement
Enclosure:
Memo, S. E. Bryan to N. C. Moceley (items 1-5) dtd 5/17/79 cc:
J. G. Davis, IE J. G. Keppler, RIII R. F. Heishman, RIII J. Streeter, RIII J. C. Creswell, RIII
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L S. E. Bryan, ADFC, IE E. L. Jordan, ADTP, IE CC:lTACT:
S. E. Bryan, IE 7907 02 0D.
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UNITED STATES y
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, Hay 17, 1979 MEMORANDUM FOR: Norman C. Moseley, Director, DROI, IE t (,
FROM:
Samuel E. Bryan, Assistant Director for Ficid Coordination, DROI, IE
SUBJECT:
SAFETY CONCERNS - J. CRESWELL This memorandum records the elements of a discussion I had with Jim Creswell on May 1, 1979.
I had the discussion with Jim for the purpose of obtaining his safety concerns so they could be appropriately resolved. Those concerns are listed below.
1.
Would the presence of auxiliary feedwater in its normal sequence have altered the TVI event; that is, would unacceptable results have occurred with nomal auxiliary feedwater, other parameters and events Seing as they were experienced? For example, what are the fuel pin compression factors under such a transient?
2.
In a circumstance such as TMI-2 incident, can the reactor coolant pumps be relied on to continue operation; i.3., can pump operation be counted on to continue forced circulation in the saturated condition?
3.
Natural Circulation - Can B&W plants acco:podate natural circulation for situations as described in Mr. Michaelson's
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report?
4.
Operator action required to be taken within 10 minutes to combat a LOCA, for example.
Is this in adequate time?
5.
Incore monitors should be~ reviewed in light of TMI-2 to detemine 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?
272'166 7007020Wl b<.
Noman C. Moseley -
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-- - - ' I~recomend that we forward his concerns to NRR and request that we be kept infomed of their status or resolution.
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w SamuelE.Eryan,AssistantDirector 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 m
272 167