ML20062F595

From kanterella
Jump to navigation Jump to search
Forwards Info Re Natural Circulation Capabilities of PWRs Following Loss of Flow Transient.Info Supports NRC Position That Natural Circulation in a PWR Is Well Behaved & Likelihood of Fuel Rod Overheating Is Very Remote
ML20062F595
Person / Time
Site: Calvert Cliffs Constellation icon.png
Issue date: 12/12/1978
From: Novak T
Office of Nuclear Reactor Regulation
To: Crocker L
Office of Nuclear Reactor Regulation
Shared Package
ML20062F594 List:
References
NUDOCS 7812200084
Download: ML20062F595 (1)


Text

.

  • ~,

.' jf

.p;,7ce37;7:s

['r fJUCLEAR REGULATORY CO:4f.'IsSiON 4

[$

{, 4;llsf f WAsa:NCTCN, D. C. 20355 o, 9

%, u.- p DEC 121978 MEMORANDUM FOR:

L. P. Crocker, Technical Assistant to the Director, DPM FROM:

T. M. Novak, Chief, Reactor Systems Branch, DSS

SUBJECT:

INFORMATION REQUEST FROM DR CARBON, ACRS Following my discussion with Dr. Carbon during the November ACRS meeting, I agreed to provide him with some additional information regarding natural circulation capabilities of PWRs following a loss of flow traasient. The enclosed information represents only a partial survey of PWR performance during natural circulation tests.

It supports the staff position that natural circulation in a PWR is

~

(.

well behaved and the likelihood of fuel rod overheating resulting from a critical heat flux condition is very unlikely.

Please transmit the enclosure to Dr. Carbon for his information.

D % :: w

. Thomas M. Novak, Chief.

Reactor Systems Branch Division of Systems Safety

Enclosure:

Memo, J. Olshinski to S. Israel, dated Dec. 7,1978

('

cc:

R. Mattson R. Tedesco l

Contact:

Tom Novak, NRR r

49-27460 i

a 78122000(4

,-