ML20128P282

Forwards Oecd/Committee on Safety of Nuclear Installation Group of Experts on Source Term, Per K Araj Request Rept Sen/Sin (84)50.Viewgraphs Encl.W/O Rept

ML20128P282
Person / Time
Issue date:	11/29/1984
From:	Ryder C NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	Goren S CALIFORNIA, UNIV. OF, BERKELEY, CA
Shared Package
ML20127A894	List: IA-85-110, Forwards Technical Papers from Eg&G,Idaho for ANS Meeting in Snowbird,Ut.W/O Encls ML20127A890 ML20127B539 ML20127B616 ML20127C187 ML20128M621 ML20128M642 ML20128M650 ML20128M656 ML20128M664 ML20128M670 ML20128M675 ML20128M679 ML20128M684 ML20128M693 ML20128M700 ML20128M705 ML20128M712 ML20128M723 ML20128M727 ML20128M731 ML20128M739 ML20128M746 ML20128M753 ML20128M760 ML20128M767 ML20128M774 ML20128M781 ML20128M788 ML20128M795 ML20128M798 ML20128M819 ML20128M839 ML20128M853 ML20128M859 ML20128M865 ML20128M874 ML20128M878 ML20128M883 ML20128M890 ML20128M913 ML20128M918 ML20128M924 ML20128M946 ML20128M953 ML20128M973 ML20128M982 ML20128M990 ML20128N000 ML20128N011 ... further results
References
FOIA-85-110 NUDOCS 8507130241
Download: ML20128P282 (8)

Text

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OFFiO't L RECORD CO:V

/

st PARTICIPANTS l-STEAM EXPLOSION REVIEW MEETItiG NOVEMBER 27-28, 1984 l

G. BANC0FF NORTH WESTERN M. BERMAN SNL W.' B0HL LANL A. BRIGGS WIf1 FRITH T. BUTLER LANL I. CATTON UCLA D. CHO ANL l

M. CORRADINE (1)

WISCONSON P. CYBULSKIS BCL H. FAUSKE FAUSKE ASSOC.

l T. GINSBERG (1)

BNL F. MAYINGER (2)

FRG D. SQUARER W

T. THE0 FAN 00S PURDUE (1)

Co-CHAIR PERSON (2)

WRITTEN RESPONSES ONLY, MUNICH IECHNICAL UNIVERSITY 6

r a /4 j

I DELPHI EXERCISE QUESTION #1 WHAT, IN YOUR JUDGMENT, IS THE BEST ESTIMATE VALUE FOR THE 1

PROBABILITY OF CONTAINMENT FAILURE ARISING FROM A STEAM EXPL0SION, GIVEN A CORE MELT, THAT WE SHOULD BE USING IN THE SEVERE ACCIDENT PROGRAM.

AS PART OF YOUR RESPONSE, PLEASE PROVIDE THE BASES (EXPERIMENTAL AND/0R ANALYTICAL) AND THE APPROACH USED IN REACHING YOUR CONCLUSIONS.

QUESTION #2 PLEASE PROVIDE WRITTEN COMMENTS ON THE SANDIA STUDY DESCRIBED IN NUREG/CR-3369 AND ANY ADDITIONAL INPUTS AND ANALYSES WHICH YOU FEEL ARE RELEVANT TO THIS STUDY.

AS POINTED OUT i:

AB0VE THE SNL REPORT IS BASED ON ASSUMED UNIFORM DISTRIBUTIONS

)

AND SOME ADDITIONAL CALCULATIONS, ASSUMING OTHER DISTRIBUTIONS, MAY BE REQUIRED.

lF

,j QUESTION #3 I'

COMMENTS ON STEAM EXPLOSION RESEARCH PROGRAM...

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j-i I

i'

\\

i PRELIMINARY IfWESTIGATOR FAli_URE PROBAEILITY BEST ESTIf1 ATE UPPER LIMIT B0liL/3 UTTER 3 x 104

,1

~

l BRIGGS

< 10-2 l

CATTON 5 x 10-5

~

~

Cl-l0 VERY UNLIKELY CORRADINI 10-4 10-2 L

~

FAUSKE WILL NOT OCCUR

~

GINSBERG 4 x 10-3 4 x 10-2 MAYINGER INTEGRITY OF GERMAN PWR WOULD NOT BE ENDANGERED SQUARER 10-4 10-6 10-4 Tile 0 FAN 00S L

BERI1AN 1

S l

L

i

~

e ENERGY IMPARTED TO STRUCTURE FOR ALPHA FAILURE

.5GJ MISSILE KIrlETIC ENERGY 120MJ ENERGY TO FRACTURE BOTTS 150MJ ENERGY TO RUSH INTERNALS 250MJ e

EXPLOSIVE ENERGY (T0 SLUG) 1-2GJ e

TOTAL THERMAL ENERGY AVAILABLE

~100GJ l

e CONVERSION RATIO 3-15%

e ALL INVESTIGATORS PRESENT LIMIT TO MIXING OR C0HERENT PARTICIPATION ARGUMENTS e

INVESTIGATORS ANALYZED MELT PARTICIPATION PROCESS AND CONCLUDED THAT SEVERAL 1000KG COULD INTERACT C0HERENTLY WITH EFFICIENCIES UP TO 15% TO PROVIDE l,

ESTIMATES OF EXPLOSIVE YIELDS LESS THAN 500MJ l

y

?

l t

l l

l TASK II INDEPENDENT AUDIT l

l e

BNL, T. PRATT, G. GREEN, ET AL e

SURRYTMLB'-Y j,

~

e INDEPENDENT APPLICATION OF CODE SUITE INPUT / BOUNDARY CONDITIONS OBTAINED FROM BCL i

l MODELLING/N0 DING / DATA TRANSFER INDEPENDENT l

MARCH, MERGE, CORS0R, TRAPMELT, CORCON, VANESSA, flAUA i

j e

OBJECTIVE SHOW LIKE VALUES OF AIRBORNE CONCENTRATION i

WITHIN CONTAINMENT VS, TIME DEMONSTRATE TRANSFERABILITY l

l-1

-,4.

.. - _,. ~. _. -. _.. _ _.. - _ _ - _ - _, _ _,, _ - -... _ - - -. - -.

l 9

i l

L l

GESSAR e

GE STANDARD PLANT-APPLICATION BWR-6, MARK III i

e NEW METHODS EMPLOYED L!

i e

RANGE OF VALUES OF RELEASE FRACTIONS REPORTED

.. !o

~

l REFLECT DECADES UNCERTAINTY FOR SOME NUCLIDES o

CENTRAL ISSUE FOR THIS DESIGN IS P0OL SCRUBBING l

AND P0OL BYPASS e

STAFF ABLE TO MAKE DECISIONS l.

e COST / BENEFIT ANALYSES USED AS A SCREENING TOOL l

FOR POTENTIAL DESIGN ENHANCEMENTS, BECAUSE UNCERTAINTIES LARGE COST / BENEFIT CANNOT BE USED FOR FINE DISCRIMINATION e

HYDR 0 GEN CONTROL SYSTEMS REQUIRED BASED ON DEFENSE IN DEPTH AND UNCERTAINTY OF PHENOMEN0 LOGY i

{

l, t

'4 i

e

L NRR APPLICATION 1

i e

MUST RELY ON INFORMED USERS QUESTIONING UNDERLYING l

PHYSICAL UNDERSTANDING SUPPORTING BOTTOM LINE NUMBERS l

e SPECIFIC APPLICATIONS OF NECESSITY MORE DELIBERATE NATURE THAN DEVELOPMENTAL NATURE OF BMI-2104 e

IN ANY SPECIFIC APPLICATION WE WILL STRESS IMPORTANT ASPECTS OF PROBLEM AT HAND (FCI, CCI, FAILURE MODES AND LOCATION) e WORK TO BE COMMENSURATE WITH IMPORTANCE TO SAFETY (GDC-1)

CODE V8V TRACEABILITY OF CODE AND CODE MOD STANDARDIZED MODELING QC 0F IMPUT e

CHECKS APPLICANT / LICENSEE WORK SUBJECT TO 0/A PROCESS NRR REVIEWS APPLICANTS WORK AND APPLICAtlT REVIEWS NRR SPONSORED INDEPENDENT CALCULATIONS WORK SUBJECT TO SCRUTINY OF HEARING PROCESS AND ACRS t

9