ML20140G303

From kanterella
Jump to navigation Jump to search
Requests Listed Repts as Pertinent Info for NRC Evaluation of Pressure Suppression Containments
ML20140G303
Person / Time
Issue date: 10/14/1975
From: Heineman R
Office of Nuclear Reactor Regulation
To: Stuart I
GENERAL ELECTRIC CO.
Shared Package
ML20140F372 List: ... further results
References
FOIA-85-665 NUDOCS 8604020103
Download: ML20140G303 (2)


Text

-_

o tf.1Ti!!a '~.*'.M l q [ 'Mg {

suco.t.a r.ccui.Aiu e u.. m u

< u as m u c w n. v. .:. m t.c. ...'L: ./

pi=

i OCT A 41975 Mr. Ivan Stuart, Manager l Safety and Licensing Nuclear Energy Division

General Electric Company 175 Curtner Avenue San Jose, California 95114 _

Dear Mr. Stuart:

On September 15 and 17, 1975, members of the iluclear Regulatory Staff met with your representatives in San Jose, California, to revie: and audit certain information which General Electric has used for the design of re'ief valve quencher devices and the deter:aination of downcomer lateral loads and suppression pool temparatura limits in -

pressure suppression contair. tents. Since these data were originally generated by a third party with contractual agreements with Generel l Electric Company that prevents public release of actual data, this audit was undertaken to determine what kind of intencation was necessary to be docu~:ented to' assure the availability of a technical basis for proceeding with licensing action. Based on this audit, ut have determined that the data and test descriptions given in the fellcwing reports are pertinent to our evaluation of pressure suppression contain-mr.nts and therefore should be submitted to us for cur deiciled revie..*.

! 1. Exocrimental Determination of Horizontal Shearing Forces on tne Vent Pipes.

i

2. Air Clearing with Perforated Pipe.
3. Excected Results of the Blowdown Tests with the Relief System at tne i.on-nuc~iear Hot Tests.
4. Results of the Non-Nuclear Hot Tests with the Relief Sys te.n.
5. Specification for Slow Of-f Tests in "on-Nuclear Heat Tes ti ng .
6. Condensation and Air Clearing Tests witi Several Typeq of Parforated Pipes. -
7. Test's for Steam-Air Condensation with the f% del ilozzic. *
8. Non-Nuclear Steam Test.

8604020103 860114 PDR FOIA FIRESTOB5-665 PDR pd

-r- - - , ,..r-- -- , , - . , .m- , , - . . . ~ - - - - - - - . - - - - - - - - - - - -. - . . - -

. - , . . - + . - , . . . , -

1 O

e 4

  • Ivan Stuart .

I understand that any submittal of this information may involve GE modifications to the original data report format and arrarcea0nt, and that conclusions or assertions regarding the use of these data in the design of pressure suppression containicents are those of the seneral Electric Ccrpany. The information raay be submitted as a G2 topical report and my also be provided as proprictcry uith suitable justifi-cation.

~

~ th / (WzN .

[],rg.;;a J .

. r .wi . . ~. e , -

Robert E. Heinenan, Director Division of Technicci Revie.i Of fice of I!uclear Recc tor Regulation 9

O m

  • O O