ML20237G196

Summary of 870224 Sixth Coordination Meeting on Research Re Containment Performance Under Severe Accidents in Bethesda, MD Concerning Containment Model Experiments.Attendee List & Presentation Matl Encl

ML20237G196
Person / Time
Issue date:	03/13/1987
From:	Graves H NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:	Joel Jenkins, Larkins J, Weidenhamer G NRC COMMISSION (OCM), NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
Shared Package
ML20237G159	List: IA-87-367, Notification of 870224 Sixth Coordination Meeting on Containment Performance Under Severe Accident Conditions in Bethesda,Md.Agenda Encl ML20237G156 ML20237G196 ML20237G210
References
FOIA-87-367 NUDOCS 8708130350
Download: ML20237G196 (157)

Text

-

n a tag'o UNITED STATES g

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g NUCLEAR REGULATORY COMMISSION l;

• p WASHINGTON, D. C,20565 MAR 131987 MEMORANDUM FOR: Distribution FROM:

H. Graves, DES:RES

SUBJECT:

MEETING NOTES:

THE 6TH COORDINATION MEETING ON RESEARCH RELATED TO CONTAINMENT PERFORMANCE UNDER SEVERE ACCIDENTS i

j The meeting was held on February 24, 1987, Bethesda, MD.

A list of attendees is attached as Enclosure 1, and the agenda as Enclosure 2.

Copies of all papers presented are included as Enclosure 3.

A brief sumary of questions and coments raised at the meeting are listed below:

1..

Containment Model Experiment - W. von Riesemann, gave an update of the 3

program status and talked in detail about various failure modes being I

predicted for the 1/6 scale concrete model.

The model experiments are

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scheduled to begin in early April FY 1987.

The predominant failure modes discussed were yielding of liner at cylinder midsection and yielding of-inside reinforcing bars at cylinder to basemat junction.

i 2.

Containment Event Tree - D. Pyatt, described the essential features of containment event tree analyses.

He presented the probability of early.

containment failure for several plants ; Zion, Surry, and Peach Bottom.

Insights gained were that direct heating was very important for Zion and Surry, while drywell liner meltthrough is important for Peach Bottom.

l 3.

Containment Piping (Penetration - G Weidenhamer, presented a test plan on upcoming research mid FY 1987) on a containment isolation system valve.

Questions where raised on the thenna1 and pressure loading histories -

was it representative of what the isolation valve would experience in operation.

The choice of an 8-inch piping system as a " typical' piping" system was also questioned as being representative of: a system in a nuclear plant. Weidenhamer stated that because of cost and the need to do equipment qualification.were reasons why an 8-inch piping system was choosen for testing.

4.

Containment Electrical Penetrations - W. von Riesemann, indicated that there was no leakage measured during test of penetrations but loss 'of power because of damage electrical assemblies could be of concern. _That is if electrical continuity is a functional requirement then the potential for loss of power needs to be evaluated.

Other areas thgt were i

not evaluated were the perfonnance of penetrations beyond 1400 F and field designed penetrations.

These areas may ' be evaluated. in future programs.

8708130350 870812 PDR FOIA SHOLLYB7-367 PDR

5.

Containment Penetration Research - W. von Riesemann, presented the results of tests performed on seals gnd ggskets.

Results given showed that seal material degrades between 500 -650 F but leakaoe will occur only when seal-ing surfaces deform relative to one another (i.e., sliding, separation).

The test plan for a fullscale personnel airlock that will be tested in May FY 1987 was also presented.

One concern is the effects of stiffner detail on airlock door strength-this could be of significance when one looks at the deformation of the sealing surfaces.

6.

Effect of Containment Venting on Risk - J. Jenkint, questions were raised on the definition of successful venting and if venting was beneficial.

Successful venting was defined as the ability to open vent valves which reduce p)ressure inside containments. reduce risk for certain severe accident sequence The benefits of containment ventin are:

1 and 2) the potential' to reduce radiological release.

7.

Direct Containment Heating - T.

Lee, gave a definition, outlined con-cerns, and highlighted the latest research efforts on the probability of core melt in relation to containment heating.

Appendix J.5 of NDREG-1150 contains a staff position on direct containment heating, and Appendix J.?

of NUREG-1150 present a discussion on core melt progression and bydrogen generation.

8.

NUREG 1150 (draft) " Reactor Risk Reference Document" - R. Denning, gave l

background information on the development of the NUREG 1150 and pre-sented bottom line values on risk estimates.

A major issue disucssed was the uncertainty range in relation to the safety goal.

The meeting was adjourr 6 et 3:40 p.m.

Co ts on the meeting and feedback on presentations or new information on topi dis ssed are welcomed.

7 H. Graves, EB: DES:RES

Enclosures:

As stated Distribution List: See attached page

4 Distribution J. Larkins OCM J. Jenkins RES G. Weidenhamer RES J. F. Costello RES D. W. Pyatt RES P. K. Niyogi RES t

M. Dean Houston ACRS N. D. Romney NRR:PWR-A:EB J. C. Lane DSRO: RIB C. G. Tinkler NRR:PWR-A:PSB-P. M. Wood RES:AEB Lyman Heller NRR:DSRO:EIB L

Lowell Greiman Ames Lab Warren Lyon NRR:PWRA: FOB l

Rich Denning Battelle l

Walter A.' von Riesemann Sandia National Laboratories l

N. Chokshi NRR Chen P. Tan NRR:DBR:EB Jerry Hulman NRR: DBL:PSB l

Jack Kudrick NRR: DBL:PSB l

Brad Hardin NRR:DSRO:RRAB T. J. Walker RES i

l Tim H. Lee RES l

i

L

(

LIST OF ATTEhDEES AT l

COORDINATION MEETING ON CONTAINMENT PERFORMANCE ON FEB. 24, 1987 Name Affiliation Phone H. Graves RES 443-7862 G. Weidenhamer RES 443-7870 J. F. Costello RES

'443-7709 D. W. Pyatt RES 443-7617 P. K. Niyogi RES 443-7611 M. Dean Houston ACRS (202)634-3267 N. D. Romney NRR:PWR-A:E8 497-4709 J. C. Lane DSRO: RIB 492-4446 C. G. Tinkler NRR:PWR-A:PSB 492-8218 P. M. Wood RES:AEB 443-7613 Lyman Heller NRR:DSRO:EIB 492-7646 Lowell Greiman Ames Lab

.(515)?94-5586 Warren Lyon NRR:PWRA:F0B t

Rich Denning Battelle FTS 976-7810 Walter A. von Riesemann Sandia National Laboratories 844-2430 J. Burns RES 443-7860 Chen P. Tan NRR:DBR:EB 492-7287 Jerry Hulman NRR: DBL:PSB

-492-7941 Jack Kudrick NRR: DBL:PSB 492-7626 Brad Hardin NRR:DSR0:RRAB 492-8986 i

T. J. Walker RES 443-7614 Tim M. Lee RES 443-7616 i

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w_____-------

Enclosure.2 I

6th C0 ORDINATION MEETING ON CONTAINMENT PERFORMANCE RESEARCH UNDER SEVERE ACCIDENTS Date:

February 24, 1987 Place: P-110 P-114 l

AGENDA Meet ting Coordinator:

H. Graves Introductory Remarks J. Burns-RES 9:00am Containment Model Experiment W. von Riesemann-SNL

& Analysis Containment Event Tree D. Pyatt-RES Containment Piping Penetration System G. Weidenhamer-RES Containment Electrical Penetrations W. von Riesemann-SNL LUNCH BREAK Containment Penetration Research W. von Riesemann-SNL 1:00pm Effect of Containment Venting on Risk J. Jenkins-RES' Direct Containment Heating T. Lee-RES 1

I l

Containment Integrity Under High Seismic Load J. Costello-RES l

l NUREG 1037 " Containment Perfonnance Working G. Bagchi-NRR l

Group Report NUREG1150(Draft)"ReactorRiskReference R. Denning-Battelle Document" Closing Remarks J. Burns-RES l

1 Adjournment H. Graves-RES 3:40-l 1

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COPIES OF PAPERS PRESENTED i

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CONTAINMENT INTEGRITY 1

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CONTAINMENT MODEL EXPERIMENTS AND ANALYSES i

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PRESENTATION TO THE STH COORDINATION MEETING ON CONTAINMENT PERFORMANCE l

RESEARCH UNDER SEVERE ACCIDENTS i

FEBRUARY 24, 1987 j

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WALTER A. VON RIESEMANN SANDIA NATIONAL LABORATORIES ALBUQUERQUE, NEW MEXICO

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SAFETY ISSUE j

HOW WILL THE CONTAINMENT SYSTEM PERFORM WHEN IT.IS SUBJECTED TO AN ENVIRONMENT J

MORE SEVERE THAN ITS DESIGN CONDITION?

(BOTH SEVERE ACCIDENTS AND EARTHQUAKES 1

ARE CONSIDERED)

NOTE -- CURRENTLY, LARGE UNCERTAINTIES IN i

PREDICTING PERFORMANCE DOES NOT PERMIT l

EXTRAPOLATION FROM THE DESIGN STATE l

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TASKS CONDUCT EXPERIMENTS ON SCALE CONTAINMENT i

MODELS TO VALIDATE METHODS FOR

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EVALUATING PERFORMANCE

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j PERFORM PREDICTIVE ANALYSES AND COMPARE WITH EXPERIMENTAL RESULTS CONDUCT ANALYSES AND CONDUCT EXPERIMENTS OF SCALE AND FULL-SIZE PENETRATIONS CONDUCT EXPERIMENTS ON SEALS AND GASKETS PROVIDE NRC WITH A SUITE OF VALIDATED I

METHODS TO PREDICT CONTAINMENT PERFORMANCE (PRESUPPOSES THAT ENVIRONMENT IS KNOWN) b e

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KNOWLEDGE OF CONTAINMENT PERFORMANCE NEEDED FOR--

J "RULEMAKING" ACTIVITIES l

EMERGENCY PLANNING SITING SAFETY GOALS DESIGN AND EVALUATION OF ACCIDENT MITIGATION EQUIPMENT RISK (SAFETY) ACTIVITIES RISK STUDIES (PRAS)

ACCIDENT MANAGEMENT o

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SNAPSHOT VIEW OF THE TASKS CONTAINMENT MODFIS

~l STATIC INTERNAL OVERPRESSURIZATION STEEL TESTED FOUR 1:32-SCALE AND ONE 1:8-SCALE REINFORCED

.1:6-SCALE MODEL CONSTRUCTED CONCRETE l

TESTING TO BEGIN IN APRIL 1987

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PRESTRESSED WORK PLAN UNDER. DEVELOPMENT CONCRETE l

DYNAMIC INTERNAL OVERPRESSURIZATION POSSIBLY LIMITED ANALYSES l

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IN SCALE MODELS l

EQUIPMENT HATCHES 4

PERSONNEL AIRLOCK IN SCALE MODELS (N0 SEALS) l FULL-SIZE MODEL - FY86-87 1

1 BWR DRYWELL HEAD ANALYSES SHOW THAT SEPARATE (MK-I, MK-II)

EXPERIMENT IS NOT REQUIRED

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BELLOWS FULL-SIZE TESTS - FY87

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SEALS AND GASKETS 44 EXPERIMENTS CONDUCTED ON FOUR q

DIFFERENT SEAL GE0METRIES 6

EXPERIMENTS ON INFLATABLE SEALS (TO BE DONE), PLUS COMPRESSION SET EXPERIMENTS l

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FLECTRICAL PENETRATION ASSEMBLIES EXPERIMENTS CONDUCTED ON 3 FULL-SIZE EPAS I

D. G. O'BRIEN, WESTINGHOUSE AND CONAX r

ANALYSES PRE-TEST FOR PLANNING OF INSTRUMENTATION TYPE AND LOCATION, AND CONDUCT OF EXPERIMENT CREDIBILITY OF CALCULATIONS l

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REFINED COMPUTATIONS I

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PLANNING PRESTRESSED CONCRETE EARTHQUAKE LOADING l

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C RESHLTS FROM THE PROGR MS WHEN COMPLETED MODEL TESTS EXPERIMENTAL DATA USED TO BENCHMARK l

STRUCTURAL CODES STEEL - VALIDATED COMPUTER CODES REINFORCED CONCRETE - LIMITATIONS OF THE CODES AREAS FOR IMPROVEMENT IDENTIFIED PRESTRESSED CONCRETE - SAME AS REINFORCED CONCRETE MECHANICAL PENETRATION TESTS STRUCTURAL DEFORMATION - FOR BENCHMARKING LEAKAGE CHARACTERISTICS - INPUT-TO PERFORMANCE MODEL j

ELECTRICAL PENETRATION ASSEMBLIES l

l LEAKAGE DATA - INPUT TO PERFORMANCE MODEL ELECTRICAL CONTINUITY I

THERMAL RESPONSE - BENCHMARK THERMAL CODES SEAL & GASKET TESTS PERFORMANCE BEHAVIOR FOR A VARIETY OF MATERIALS, GEOMETRIES AND THERMAL CONDITIONS.

INPUT TO' PERFORMANCE MODEL I

PERFORMANCE MODEL L

SUITE OF METHODS TO PREDICT PERFORMANCE

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COORDINATION, PFFR REVIEW STATUS REPORT GIVEN PERIODICALLY TO

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RES, NRR AND ISE COORDINATION GROUP PEER REVIEW GROUP W6RKSHOP (MAY 1986)

INFORMATION EXCHANGE AND COOPERATION WITH EPRI FOREIGN GROUPS FEDERAL REPUBLIC OF GERMANY FORMAL FRANCE UNITED KINGDOM ITALY INFORMAL --

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PEER REVIEW GROUP 1

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- CB&I BILL BAKER

- SOUTHWEST RESEARCH BILL BLACK

- CONSULTANT TED BROWN

- WISS,<!ANNEY, ELSTNER j

RICH DENNING

- BATTELLE COLUMBUS l

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- BECHTEL TED JOHNSON

- BECHTEL l

METE S0 ZEN

- UNIV. OF ILLINOIS JOHN STEVENSON

- CONSULTANT J

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- EPRI JOE UCCIFERRO

- UNITED ENGINEERS DICK WHITE

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CONVENTIONAL MATERIAL PRIMARY REBAR, #4 (1/2" DIAM.)

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TEST IN U.S. (NRC)

AT THE MINIMUM SEPARATE EFFECTS TESTS WILL BE CONDUCTED (NRC) e

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t MODEL ANALYSES STEEL NUREG/CR-4209 COMPARISON OF ANALYTICAL PREDICTIONS AND EXPERIMENTAL RESULTS FOR A 1:8-SCALE STEEL CONTAINMENT MODEL PRESSURIZED TO FAILURE DAVE CLAUSS REINFORCED CONCRETE

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R/C MODEL ANALYSIS (SANDIA)

ABAQUS CODE AXISYMMETRIC THICK SHELL ELEMENTS 92 NODES BASEMAT ON A RIGID SURFACE BUT ALLOWED TO LIFT-OFF LAYERED SHELL'AND REBAR OPTIONS.

LINER VON MISES YIELD

- ISOTROPIC HARDENING REBAR

- UNIAXIAL,'PIECEWISE. LINEAR STRESS-STRAIN CURVE CONCRETE - ELASTIC-PERFECTLY PLASTIC MATERIAL WITH DIFFERENT' YIELD STRENGTHS IN TENSION AND COMPRESSION FAILURE CRITERIA REBAR

- 99 KSI (TENSILE TESTS)

LINER

- EQUIVALENT PLASTIC STRAIN OF 15%

CONCRETE - EMPIRICAL CRITERION FOR SHEAR STRENGTH SHEAR RIGIDITY REDUCED.

TO ACCOUNT FOR' CRACKING

m e

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, pg,,,,,,,

s NONLINEAR MEMBRANE ANALYSIS OF CYLINDER WALL e Neglects the tension in the concrete and the curvature due to bending

• Approximately represents conditions at the cylinder midheight away from penetrations e Gives an upper bound for the strength of the containment e Provides a

reference to compare with finite element results 0

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AXISYMMETRIC FINITE ELEMENT ANALYSES

. Thick. shell theory is used in the dome, cylinder, and basemat regions.

1 e All reinforcement layers are represented as lamina i

with load carrying capacity in one direction.

l

. The concrete is modeled as an elastic-plastic materialin tension and compression.

. The shear rigidity of the shell is reduced to account for the lower shear stiffness of concrete after cracking.

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FINITE ELEMENT i

ANALYSIS

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1 STRESSES IN INNER HOOP REINFORCEMENT 90

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PRESSURE (PSIG)

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HISTORY OF EVENTS 4

-9 Pressure Event 30-35 psi.

Cylinder cracks in the hoop direction.

l 35-40 psi.

Cylinder cracks in the 1

meridional direction.

40-45 psi.

Dome cracks in the 1

1 hoop and meridional direction.

110-115 psi.

Liner yields in cylinder midsection.

125-130 psi.

Inside meridional bars yield at cylinder to basemat junction.

1 e

_m---

_..m

._m

HISTORY OF EVENTS t' cont.)

Pressure Event-130 psi.

Hoop bars yield in cylin-der midsection.

135-140 psi.-

Seismic and meridional l

bars yield in cylinder midsection.

145 psi.

Concrete above the cylin-der to basemat junction begins to crush.

170 psi.

Bending failure above the cylinder to basemat junction.

190 psi.

. Hoop bars reach ulti-mate stress at the mid-height of the cylinder.

j 1

1 I

1 l

l FUTURE PROJECTS l

. Three. dimensional finite element shell models of equipment hatch "A" i

• Study of liner strains in the vicinity of concrete cracks (cylinder midheight and

)

basemat/ cylinder junction) i l

)

e Post-test analyses l

l l

I e

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

1 NFAR-TFRM ACTIVITIF_S SEPARATE EFFECTS TESTS R/C -- AFTER MODEL TEST

\\

=

PRESTRESSED k

THERMAL LOADINGS PRESTRESSED CONTAINMENTS WORK SCOPE DYNAMIC LOADINGS HYDROGEN DETONATION

- LITERATURE SURVEY A ND ANALYSIS OF A 'REAL' CONTAINMENTLIM i

l 1

4 i

l l

1 l

i OBSERVATIONS l

CANNOT EXTRAPOLATE RESULTS TO Rh.L SCALE CANNOT GENERALIZE PERFORMANCE i

CASE-BY-CASE BASIS LARGE UNCERTAINTIES IN LOADINGS (BOTH PRESSURE AND TEMPERATURE)

NEED SKIN TEMPERATURE AND GRADIENT THROUGH THICKNESS UNCERTAINTIES IN PREDICTING

\\

CONTAINMENT PERFORMANCE LEAKAGE -- DIFFICULT TO QUANTIFY l

" BURST" -

t WHAT IS END USE OF THE " NUMBERS" IN SOME CASES DESIRE HIGH CONFIDENCE, LOW PROBABILITY (HCLP) VALVE, I

i IN OTHER CASES -

'BEST' ESTIMATE 0F FAILURE PRESSURE l

i l

I a

DETERMINISTIC VS. PROBABILISITC ANALYSES VENTING NEEDED?

FILTERING-NEEDED?

STEEL ANALYSES WITHIN STATE-0F-THE-ART CONCRETE -- TBD AS BUILT MATERIAL PROPERTIES AND DETAILS.CAN AFFECT.RESULTS IMPROVE DIALOGUE BETWEEN SYSTEMS -- LOADING -- PERFORMANCE -- PRA j

EMERGENCY l

PLANNING, l

ETC.'

AS-BUILT MATERIAL PROPERTIES AND DETAILS CAN AFFECT RESULTS 4

(

1iI

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p. G. O'BRIEN EPA TEST COMPLETED I

• RADIATION:

200 MRAD (AIR), 0.8 MRAD /HR

• THERMAL:

275'F, 165 HOURS

• SAC:

361*F, (155 PSIA), 10 DAYS i

RESULTS:

l 1.

NO DETECTABLE LEAKS DUEING THE STEAM PRESSURIZED PORTIONS.

9 2.

POSTTEST AIR LEAK-RATE MEASUREMENT (AMBIENT AT 155

]

PSIA) MAS 0.13 CC/SEC.

i i

3.

ELECTRICAL RESULTS l

A.

ALL MODULES DEGRADED TO < 10 OHMS (TO GROUND AT 50 VOLTS) AFTER 2 DAYS.

l B.

5 Or 8 CIRCUITS SHONED 1/2 AMP LEAKAGE (CIRCUIT l

sGLIIMUM ALLOWED) AFTER 10 DAYS.

C.

POSTTEST INSPECTION SHONED ALL BUT ONE CIRCUIT F&ULTT (NOISTURE IN C9NNECTORS).

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r WESTINGHOUSE EPA TEST COMPLETED

~

e RADIATICIf:

200 MRAD (AIR), 0.8 MRAD /HR

• THERMAL:

300'F. 100 HOURS

• SAC:

400*F (75 PSIA), 10 DAYS RESULTS:

1.

32 DETECTABLE LEAES DURING THE STEAM PRESSURIZED PORTIONS.

i 2.

ALL AIR LEAK-RATE MEASUREMENTS WERE LESS THAN ABOUT 10~4 CC/SEC.

3.

ELECTRICAL RESULTS:

A.

FUNCTION OF CABLE HQI EPA.

R.

VARIOUS CABLES SHOWED SPORADIC AND LOW IR READINGS, MOISTURE LEAKAGE. AND OTHER DEGRADATION AS EARLY AS 1P HOURS INTO TEST.

C.

POSTTEST (DRY) RESULTS SHOWED SIGetIFICANT ELECTRICAL PROPERTY RECOVERY.

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r 90NAX EPA TEST COMPLETED I

I i

e RADIATICOI:

200 MRAD (AIR), 0.8 MRAD /HR e Mr.:

300*F, 100 HOURS

• SAC:

700*F (135 PSIA), 9 DAYS I

l RESULTS:

1.

182 DETECTABLE LEAKS DURING THE STEAN PRESSURIZED PORTIONS OR AFTER C00LDOWN.

1 I

2.

ELECTRICAL RESULTS:

l A.

AT 5 HOURS INTO THE TEST, COPPER CARLES (KAPTON INSULATION) DEGRADED FROM 2 KOHMS to 1 880638.

3.

AT 11 HOURS INTO THE TEST, THE COPPER'CARLES Mme TO 1 OHN TO 10 K0EWIS.

C.

NfPLE CABLES (KAPT005 INSULATIcel) PERFORMED SATISFACTORILY DURING SAC TEST.

D.

COPPER CABLES DID NOT RECOVES AFTER C00LDOWN.

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EEA1 OBSERVATIONS DESIGNS TESTED FOR GIVEN-PRESSURE AND TEMPERATURE DID NOT LEAK, HOWEVER F'ORCONDITIdNSBEYONDTHOSETESTED (E.G. 1400'F BWR) NEED MEANS.T0 l

EVALUATE PERFORMANCE, ALSO FOR EPAS NOT TESTED, ESPECIALLY FIELD

+

DESIGNED, NEED METHOD FOR EVALUATION ELECTRICAL CONTINUITY (A FUNCTIONAL REQUIREMENT)

SHOULD BE EVALUATED i

FAULT CURRENTS NOT EVALUATED l

l

EEAS HAVE ON HAND i

i D. G.-0'BRIEN (SAME AS ONE TESTED)

WESTINGHOUSE AND CONAX--MEDIUM VOLTAGE COULD BE USED FOR FAULT CURRENT TEST UNDER SEVERE ACCIDENT CONDITION OR FUNCTIONAL TEST l

l

/

I l

i

4 CONTAINMENT INTEGRITY MECHANICAL PENETRATIONS PRESENTATION TO THE STH COORDINATION MEETING ON CONTAINMENT PERFORMANCE RESEARCH UNDER SEVERE ACCIDENTS FEBRUARY 24, 1987 l

WALTER A. VON RIESEMAN':,

SANDIA NATIONAL LABORATORIES ALBUQUERQUE, NEW MEXICO 4

G

.d

l MECHANICAt_ PENETRATIONS

]

' OPERABLE' EQUIPMENT HATCH PERSONNEL AIRLOCK ESCAPE HATCH DRYWELL HEAD -- BWR MK-I & II

' FIXED' PIPING BELLOWS CHARACTERIZATION STUDY (ARGONNE PLUS SANDIA)

INVESTIGATE EQUIPMENT HATCH PERSONNEL AIRLOCK l

SEALS AND GASKETS j

BELLOWS I

RESEARCH PROGRAM NOT NEEDED FOR DRYWELL HEAD (THERMO-STRUCTURAL ANALYSIS PLUS SUPPLEMENTARY EXPERIMENT) l ESCAPE HATCH l

PIPING i

SIGHT GLASSES I

l i

=

9 w__

1 i

IASKS EXPERIMENTAL AND ANALYTICAL METHODS WILL BE USED l

IN SOME CASES, RESULTS WILL BE USED TO VERIFY COMPUTATIONAL METHODS IN OTHER CASES, RESULTS WILL BE EMPIRICAL EXTRAPOLATION WILL BE DIFFICULT I

1.

EQUIPMENT HATCHES BECAUSE OF SHELL INTERACTION, TESTS CONDUCTED AS PART OF SCALE MODELS 2.

PERSONNEL AIRLOCK FULL-SIZE TEST WITH PRESSURE AND TEMPERATURE i

3.

SEALS AND GASKETS TESTS CONDUCTED ON FULL CROSS-SECTION BUT REDUCFB DIAMETER l

INFLATABLE SEALS -- TO BE CONDUCTED l

OVEN TESTS TO MEASURE COMPRESSION SET --

TO BE CONDUCTED 4.

BELLOWS WORK SCOPE TO BE DEVELOPED l

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i D. G. O'BRIEN EPA TEST COMPLETED

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1 e RADIATION:

200 MRAD (AIR), 0.4 MRAD /HR e THERMAL:

275'F, 168 HOURS

• SAC:

361*F, (155 PSIA), 10 DAYS

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BESULTS:

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NO DETECTABLE LEAKS DURING THE STEAM PRESSURIZED

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POSTTEST AIR LEAK-RATE MEASUREMENT (AMBIENT AT 155 I

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3.

ELECTRICAL RESULTS l

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ALL MODULES DEGRADED TO < 10 OHMS (TO GROUND AT 50 VOLTS) AFTER 2 DAYS.

5.

5 Or 8 CIRCUITS SHONED 1/2 AMP LEAKAGE (CIRCUIT SUGIMUN ALLONED) AFTER 10 DAYS.

C.

POSTTEST INSPECTION SHONED ALL BUT ONE CIRCUIT FAULTY (NOISTURE IN CONNECTORS).

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r tfESTINGHOUSE EPA TEST COMPLETED e RADIATICIf:

200 MRAD (AIR), 0.8 MRAD /HR e THERMAL:

300*F, 100 HOURS

• SAC:

400*F (75 PSIA), 10 DAYS RESULTE:

1.

E DETECTABLE LEAKS Dt1RIlfG THE STEAM PRESSURIZED FORTICIfS.

2.

ALL AIR LEAK-RATE MEASURENEIITS WERE LESS THAN ABOUT 10 CC/SEC.

3.

ELECTRICAL RESULTS:

A.

FUNCTICIf CF CABLE l$21 EPA.

B.

VARIOUS CABLES SHotfED SPORADIC AND Lott IR READIlfGS, NOISTURE LEAKAGE, AND OTHER DEGRADATION AS EARLY AS 18 HOURS INTO TEST.

C.

POSTTEST (DRY) RESULTS SHotfED SIGIt!FICANT l

ELECTRICAL PROPERTY RECOVERY.

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DRYWELL PRESS, pain i

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CONAX EPA TEST COMPLETED e RADIATION:

200 MRAD (AIR), 0.8 MRAD /HR e THERNAL:

300*F. 100 HOURS e SAC:

700'F (135 PSIA), 9 DAYS RESULTS:

1.

382 DETECTABLE LEAKS DURING THE STEAN PRESSURIZED PORTIONS OR AFTER COOLDokN.

2.

ELECTRICAL RESULTS:

A.

AT S HOURS INTO THE TEST, COPPER CABLES (KAPTON INSULATION) DEGRADED FRON 2 KOHMS to 1 NotM.

B.

AT 11 HOURS INTO THE TEST THE COPPER' CABLES metD TO 1 OHN TO 10 KOHMS.

C.

THEaN0 COUPLE CABLES (KAPTON INSULATION) PERPORNED SATISFACTORILY DURING SAC TEST.

D.

COPPER CABLES DID NOT RECOVER AFTER C00LDONN.

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OBSERVATIONS DESIGNS TESTED FOR GIVEN PRESSURE AND TEMPERATURE DID NOT LEAK, HOWEVER F'ORCONDITIdNSBEYONDTHOSETESTED J

(E.6. 1400*F BWR) NEED MEANS TO

)

EVALUATE PERFORMANCE, ALSO l

FOR EPAS NOT TESTED, ESPECIALLY FIELD DESIGNED, NEED METHOD FOR EVALUATION ELECTRICAL CONTINUITY (A FUNCTIONAL REQUIREMENT) l SHOULD BE EVALUATED FAULT CURRENTS NOT EVALUATED I

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EPEi

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l HAVE ON HAND q

J D. G. O'BRIEN (SAME AS ONE TESTED)

WESTINGHOUSE AND CONAX--MEDIUM VOLTAGE COULD BE USED FOR FAULT CURRENT TEST UNDER SEVERE ACCIDENT CONDITION OR FUNCTIONAL TEST I

i i

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MECHANICAL PENETRATIONS k

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PRESENTATION TO THE STH COORDINATION MEETING ON CONTAINMENT PERFORMANCE RESEARCH UNDER SEVERE ACCIDENTS i

~

FEBRUARY 24, 1987 WALTER A. VON RIESEMANN SANDIA NATIONAL LABORATORIES ALBUQUERQUE, NEW MEXICO 1

t e

MECHANICAL PENETRATIONS

'0PERABLE' EQUIPMENT HATCH PERSONNEL AIRLOCK ESCAPE HATCH DRYWELL HEAD -- BWR MK-I & II

' FIXED' i

PIPING BELLOWS CHARACTERIZATION STUDY (ARGONNE PLUS SANDIA)

INVESTIGATE EQUIPMENT HATCH PERSONNEL AIRLOCK SEALS AND GASKETS BELLOWS RESEARCH PROGRAM NOT NEEDED FOR DRYWELL HEAD (THERMO-STRUCTURAL ANALYSIS PLUS SUPPLEMENTARY EXPERIMENT)

ESCAPE HATCH PIPING SIGHT GLASSES

i i

TASKS EXPERIMENTAL AND ANALYTICAL METHODS WILL BE USED IN SOME CASES, RESULTS WILL BE USED TO

+

VERIFY COMPUTATIONAL METHODS IN OTHER CASES, RESULTS WILL.BE EMPIRICAL EXTRAPOLATION WILL BE DIFFICULT 1.

EQUIPMENT HATCHES BECAUSE OF SHELL INTERACTION, TESTS CONDUCTED j

{

AS PART OF SCALE MODELS 2.

PERSONNEL AIRLOCK i

FULL-SIZE TEST WITH PRESSURE AND TEMPERATURE

)

3.

SEALS AND GASKETS TESTS CONDUCTED ON FULL CROSS-SECTION BUT j

REDUCED DIAMETER INFLATABLE SEALS -- TO BE CONDUCTED OVEN TESTS TO MEASURE COMPRESSION SET --

+

TO BE CONDUCTED 4.

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• J o

FIGURE 8.5 1 t COMPARISON OF SURRY RISK TO SAFETY GOAL porvtyJAL R!SK CF EARLY FATAUTY PER W 1M j <:: GOAL 15-7 l-:: ( tM. i s i j '1H :- E ? 58-10 aM wrm DCH a M.NO DCH 1 SOCETAL R9< PER YEAR ,g j = 5 <; GOAL se-e r:i se-7 I 1H r e iM r ( 6. 5-10 mm, wrm ocx aM. NO DO1 I am pueK MCM NTWTW. EVENTS 04.Y l i I I a. crecT cowr/M. L - _ _ - - - - - - eir HEATNG------- t FIGURE 8.6 i ~ P'ROBASILITY OF LARGE RELEASE SURRY I PRC8ABUTY PER YEAR i 1:H5 6 1E-6 r* Ovm4CN ~. l 4 15-7 r: = 2 I 1E-4 :- i b 4 l 1E-9 EJPtY W/ DCH EffW NO DCH 4

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