ML20090H617
| ML20090H617 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/23/1984 |
| From: | Guttmann J Office of Nuclear Reactor Regulation |
| To: | Sheron B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML082380335 | List:
|
| References | |
| CON-FIN-A-2311, FOIA-91-106 NUDOCS 8403120396 | |
| Download: ML20090H617 (2) | |
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MEMORANCOM FOR: B-ian Sheron, Chief, Reactor Systems Branch, DSI THRU:
tbruan Lauben, Section Leader, Section A RSB i
FRON:
Jack Guttmrn. Section A. Reactor Systems Branch
SUBJECT:
STATUS REPORT REGARDING TilF GINE SGTR AttA. LYSIS BY ANL (FIN to. A-2311)
On February 14,1984, I was contacted by ANL regarding the ebject analysis they are performing for RSB. At program initiation, we be-lieved that given the RETRAN input model of the Girma event (developed by INPO), a reanalysis of the steam generator tube rupture event would be straightforward and uncomplicated. Unfortuaately, we are finding this P : to be the case. The INPO analysis consisted of over 20 re-start which included extensive input model modifications. As it turns out, this is not easily replicate 3.
Also, we do not have the exact version of the code used by INPO and are encour.tering diffi-culties making their input execute on our version of the code.
Due to the extensive computer time required to complete the base case
' analysis and our present understanding of the complexities of the analysis, it is becoaing apparent that the task of analyzing the i
eveht with a PORV stuck open and enother with continued ECC injection avy not bs accomplished under present funding levels. These cases ara not just trip logic modifica' 'or.3 to the input deck as we pre-viously beileved them to be.
Ry instr actions to ANL (Paul Abramson) were to complete the analysis with the INP0 model. Upon completion of this analysis, ANL was -di-rected to report to us the status, conclusions, and the requirements for completing the contracted work.
It should be noted that ANL has developed a RELAP5 input deck and a TRAC-Pfi-M001 input deck for the Ginna plant. These decks are being demloped at AHL by foreign students' at no manpower cost to our pro-graa (IAEA funded). The Ginua deck developed and QA'd by the industry was found to be significantly different from the Generic 2-toop plant developed on TRAC by SNL. Based on previous discussions with RGaE, we-learred that there exist two designs of a Westinghcuse 2-Loop plant.
1he generic (SNL) plant w believe tnay be tore typical of the Knwaunee NSSS design.
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. l Based upon any understanding of the INP0 sodel, it wuld not be sur-prising if neither TRAC not' F.ELAP5 could recreate the Ginna event with reasonable accmey [this is not to imply that the assulyses wuld be non-unservative). This observation is bued on the lack of a mixture level calculation within a node and the potential for repressurization s.s the liquid level increases within a node (piston effects). Should either of thesa codes be able to recreate the even* with reasontble accuracy, then the sensitivity studies out-lined in the pM> gram could be accomplished with little effort (ex-cluding compuur costs).
I will keep you appraised of the progress being made.
original sisqpy Jack Guttmann, Section A Reactor Systems Branch, DSI cc:
R. W. Houston S. Boyd P.Abramson(ANL)
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