ML20154C920
| ML20154C920 | |
| Person / Time | |
|---|---|
| Site: | 07106639 |
| Issue date: | 02/21/1986 |
| From: | Odegaarden R NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 8603050345 | |
| Download: ML20154C920 (23) | |
Text
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I
'7 l-- & &y1 l Distribution:
l Mtg Attendees w/o encl i l FCTC Mtg Book i
CEMacDonald w/o ecl l FEB 21695 GBeveridge
! Docket File FCTC:P.!!0 l
71-6639 NRC PDR C'.~5!
l NMSS R/F g, Mtif.in l FCTC R/F M6-SS t'Ef t0RAtlPtP1 FOR: The Files i FR0": Richard H. Odegaarden, FCTC, f0SS !
SUU,1ECT: SUf'tiARY OF MEETING C0flCERflING t*0 DEL fl0. t'H-1 A PACKAGE Attendees l Westinghouse Hanfor_d DOE ANL fnC U. J. Gruber D. E. Venyon G. F. Popper R.11. Odegaarden J. D. Berger G. Chalfant !!. W. Lee ',
R. 1. Jackson Roy Carrison ll. H. Lake P. C. Ferrell C. E. Ifilliams introduction A reeting was held at the rennest of the Departnent of Energy (DOE) at !
Silver Spring, Maryland, on February 10, 1986, with regard to proposed responses to the 'IRC letter concerning the l'odel No. f'5f-1 A package !
(cask).
Discussion 1 1
On February 19, 1905, COE requested approval of the t'odel Ho, MH-1 A cask design and on May 31,1935, the f1RC staff requested additional information reaardinq the application. Vestinghouse Ifanford Company rnade a presentation to the f'9C staff concerning their preliminary assessment and plans for t continuation of the fMC certification of the package. An outline of the presentation is attached to this nemorandun.
Mestinghouse Hanford Company expects to ricet with the fmc staff sometime in the Spring of 1990 to discuss in more detail their proposed approaches to responding to FRC letter dated ay 31, 1985.
Mfel$fPed by b n v. 4 Richard II. Odegaarden, Pro.fect !!anager 8603050345 860221 Transportation Certification Branch PDR ADOCK 07106639 Division of Fuel Cycle and C PDR ffaterial Safety,IP'SS n bec1nsw a- M< ted kITC FCTC " " " ' " " " ' " " ' '""'""'"' '"""'""""
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me roau ne no-somacu ono OFFICIAL RECORD COPY
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ESTINGHOUSE HANFORD C0ffANY PFESENTATICN TO l
NRC l
l l . MH-1A PRELIMINARY- ASSESSENT l
l
. PLANS FOR CONTINUATION 1
l l
FEBRUARY 10, 1986
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l MH-1A RECERTIFICATION i
0 DT/WDL TEAM i !
.i DT/HQ - ROY GARRISON '
DT /RL - DEBBIE KENYON/ BOB HIEGEL. ,
i i
EDL .
JIM BERER - RESPONSIBLE MANAER B0B JACKSON - TEAM LEADER BILL GRUBER - CONTAINENT AM) CRITICALITY j PAT FERRELL - STRUCTURAL ANALYSIS OVERV!EN STAN FIELDS - TERMAL ANALYSIS LARRY HANSEN - STRUCTURAL AND SAR OVERVIEW i PRIVATE SECTOR - STRUCTURAL ANALYSES <
l f
HEDL INVOLVEMENT s
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, PROVIDED INDEPENDENT OVERVIEW OF POTENTIAL FOR hE-1A REGULATORY COMPLIANCE REA SAFETY ANALYSIS REPORT l
NRC QUESTIONS ON SAR l
l ADDIT 10NAL WORK BY SNL 0 REQUESTED TO ATTEMPT RECERTIFICATION OF hN-1A l
i l
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W DL ACTIVITIES TO DATE i
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0 REVIEW EXISTING SAR O REVIEW AND CONCtRRENCE WITH NRC COMENTS i
, O ASSESSED ALTERNATIVE APPROACES FUEL APO CLADDING FOR CONTAINENT CASK FOR SHIELDING APO PAYLOAD RETENTION t
0 REC 014 ENDED APPROACH TO RECERTIFICATION i l
i i
MH-1A PRELIMINARY ASSESSW NT I
0 C0fflLE DATA AND DEVELOP ASSUfeTIONS 0 PERFORM SCOPING ANALYSES THERFAL STRUCTURAL FISSION PRODUCT RELEASE SHIELDING CRITICALITY 0 EVALUATE RESULTS AND DEVELOP CONCLUSIONS l
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% w . q MH.1A CASK THERMAL AND STRUCTURAL ANALYSES. (PHASE I) LOGIC DIAGRAM A A e.u .... n . .. .a .. w. p - A
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I MH-1A PAYLOAD DESCRIPTION
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8 !
O MH-1A PAYLOADS ARE LIMITED TO TRIGA AND MTR TYPE (W BR, MURR, NBSR) 1 FUEL ELEENTS 0 TRIGA ELEENTS ARE STABLE TO HIGER TEWERATURES APO CONTAIN LOER ,
i FISSION PRODUCT INVENTORIES THAN MTR ELEENTS i
t l
l 0 MTR FEL ELEENTS, PARALLEL PLATES WITH ALUMINUM CLADDING AL-U ETAL UO2 - AL CERET U3Si - AL CERET t
6 i
I i
5H-1A THERT%L ANALYSIS 0 ASSUSPTIONS HFBR II PAYLOAD CONFIGURATION (WORST THERh'AL CASE) 1.73 KW DECAY HEAT PARTIAL HEAT TRANSFER BY CONVECTION (AIR) FOR STEADY-STATE (NORhML) CONDITION N0 HEAT TRANSFER BY CONVECT 10N DURING TRANSlENT (HYP0TETl CAL FIRE) l .
b Mi-1A TWRMAL ANALYSIS t
RESULTS: !
NORMAL TRANSPORT COPOITIONS HYPOTWTICAL ACCIDENT COM)ITIONS -
CONSERVATIVE CONSERVATIVE !
ESTIMATE ALLOWABLE ESTIMATE ALL0E D i MAXIMUM FUEL i
l CENTERLIE i
TEWERATURE, F 460R401 950 825 950 l l
MAXIMUM LEAD l TEMPERATURE, F 309 620 580 622 .
i IWITH CONVECT 10N/WITHOUT CONVECT 10N CONCLUSIONS 0 CEL ELEENTS RETAIN ERETIC INTEGRITY O CASK DAMAGE CAUSES ONLY LOCAL TEWERATURE PERTUBATIONS ;
~
O LEAD SHIELDING REMAINS BELOW ELTING (WITH POSSIBLE EXCEPTION OF SMALL VOLtK ADJACENT TO OUTER SWLL) ;
i r
I i
f/H-1A STRUCTURAL EVALUATION SCOPE OF STRUCTURAL ANALYSES WAS LIMITED TO DETERMINING CERTIFICATION FEASIBIL:TY ,
0 30 FT DROP TESTS REDh000 IMPACT LIMITER CHARACTERISTICS UNDER DYNAMIC STRESS (STIFFER THAN OPTit/m )
dab %GE TO LID (N0 BREACH, BOLTS INTACT)
LEAD SLUMP / DISPLACEMENT (2-3 IN. h%X. LEAD SLUMP) dab %GE T0 INNER SELL (PLASTIC HINGE INWARD DEFORMATION) dab %GE TO OUTER SHELL (PLASTIC DEFORMATION FROM LEAD SLLNP)
SEAL INTEGRITY (CANNOT BE ASSURED)
FUEL ELEMENTS (UNDAMAGED) 0 40 IN. PUNCTURE TESTS DAf/ AGE TO CLOSURE (LID) AND SEAL INTEGRITY (RETAINS FUEL IN CASK)
DAMAGE TO OUTER SHELL (PLASTIC DEFORMAT10N, RETAINS INTEGRITY) l l
ASSlW TIONS FOR MH-1A FISSION PRODUCT RFIFASE CONSIDERATIONS O FUEL ELEENTS WERE UNDAMAGED 0 SOURCE TERMS BASED ON WBR IRRADIATION CYCLE ,
FISSION PRODUCT INVENTORIES DECAY EAT GAlHA RAY SPECTRA -!
O USED HIGEST FiSS10N PRODUCT INVENTORY O 1.73 KW TOTAL DECAY EAT (16 MONTH DECAY)
O FEL TEWERATURES FROM TERMAL CALCULATIONS !
i i 0 FISSION PRODUCT RELEASE CHARACTERISTICS FROM REFERENCED STUDIES i
1 0F MTR TYPE FUELS ;
t
, 0 OPERATIONAL CONTROLS (CHAP. 7) WILL CONTROL INTERNAL CONTAMINATION ,
i TO ACCEPTABLE LEVELS i
I
l 5H-1A FISSION PRODUCT REtEASE EVALUATION l
RESULTS l FISSION PRODUCT RELEASE FROM fM-1A HFBR (h0RST CASE) PAYLOADS l n O NORMAL TRANSPORTATION C0tOITIONS: NO W ASURABLE RELEASE IN REFERENCED DATA 0 HYPOTETICAL ACCIDENT CONDITIONS: EXEECTED RELEASE ALLG4ABLE 1700 10,000 l 1.4 X 10-3 10 l
0 CONCLUSION:
fN-1A PAYLOADS PROVIDE ADEQUATE CONTAIfFENT OF FISS10N PRODUCTS:
. FORMAL TRANSPORTATION CONDITIONS
. HYPOTETICAL ACCIDENT C0folT10NS l
l 1
MH-1A SHIELDING EVALUATION 0 BASED ON TE GAhWA RAY SPECTRUM FOR A 1.73 KW PAYLOAD, IT WAS DETEfNIED THAT ABOUT 5 IN. OF LEAD SHIELDING ARE REQUIRED 0 5'H-1A CASK PROVIDES 7.62 IN. OF LEAD SHIELDING 0 LEAD SLL7P h%Y DISPLACE SHIELDING, LEAVING A VOID AT TOP OR BOTTOM 2-3 IN. WAXIfGD O
PUNCTURE DAMAGE hMY RESULT IN LOCALIZED LEAD ELTING NEAR TE OUTER SELL IN TE IMPACT AREA DURING TE HYPOTETICAL FIRE. SINCE TE OUTER WALL IS PROBABLY INTACT, MOVEENT OF LEAD UPON ELTING WOULD BE INSIGNIFICANT CONCLUSION:
0 SHIELD IS EXPECTED TO EET 10 CFR 71 CRITERIA DURING NORMAL A?O HYP0TETICAL ACCIDENT C0folTl0N
O
- hH-1A CRITICALITY EVALUATION s
RESULTS:
l l 0 NO RECONFIGURAT10N TO FUEL GEOMETRY 0 REVIBED CHAPTER 6 0F REA SAR 1
l CONCLUSIONS:
l O KEFF <<1 l
l CONCLUSIONS 1
THERFAL 0 ALL TEffERATURES ARE ACCEPTABLE WITH POSSIBLE EXCEPTION OF LOCAL PERTUBATIONS IN DAMAED AREA STRUCTURAL 0
UNDER f0RFAL AND HYPOTETICAL ACCIDENT C0f0lT10NS CASK IS EXPECTED T0:
REPAIN INTACT CONTAIN PAYLOAD PROVIDE ADEQUATE SHIELDING l
FISSION PRODUCT RFIFASE O FEL ELEfENTS REPAIN UNDAVAED BY If@ACT 0 FUEL ELEfENTS REMAIN INTACT DURING FIRE 0
FUEL ELEENTS PROVIDE CONTAINTENT DURING IMPACTS AND FIRE EVEN IF CASK SEAL FAILS, IN ACCORDANCE 10 CFR 71 SHIELDING 0
SHIELDING IS EXPECTED T0 FEET 10 CFR 71 CRITERIA UNDER HYPOTETICAL ACCIDENT C0fDITIONS CRITICALITY 0 SIGNIFICANT MARGIN EXISTS
f/H-1A SAR PROCEDURE 0 CASK FUNCTION SHIELDING CONFitSENT OF PAYLOAD TERMAL BARRIER O FTL FUNCTION l
CONTAi!4ENT I
1 i
l l
l l
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NRC CO M NTS (MAY 31, 1985)
STRUCTURAL CO M NT 1r 0 CALCULATED STRESSES IN CASK EXCEED CRITERIA ,
O SOE STESSES SHOULD BE RECATEGORIZED AS PRIMARY ESPONSE-0 STRESS CRITERIA CHANES WEN CASK IS NOT CONTAINENT 0 CASK WILL BE ASSESSED FOR DEFORMATION AfD INTEGRITY STRUCTURAL CO M NT 2 0 INADEQUATE DISCUSS 10N OF DROP 0 MUST CONSIDER MOST DAMAGING ORIENTATION
RESPONSE
0 FORMAT FROM EGULATORY GUIDE 7.9 WILL BE USED AS A BASIS FOR SAR STRUCTURAL CO M NT 3:
O C0lelED EFFECTS OF ECHANICAL APO TERMAL LOAD NOT CONSIDERED .
IN CONTAIER ESPONSE:
O COPEIED EFFECTS OF ECHANICAL APO TERMAL LOAD (REG. GUIDE 7.8) -
~
WILL BE CONSIDERED IN FUEL
NRC CON 7ENTS (h%Y 31, 1985)
STRLCTURAL CCt."ENT 4:
0 lNTERACTION LOADS FROM DEFORED COMPONENTS NOT CONSIDERED LEAD LATERAL PRESSURE DIFFERENTIAL TERh%L EXPANS10N AND CONTRACTIONS
RESPONSE
0 INTERACTION OF DEFORED COPPONENTS WILL BE CONSIDERED TO SHOW THAT:
FEL ELEENTS ARE UNDA.VAED SHIELDING IS RETAINED TERFAL BARRIER IS 5%INTAINED STRLCTURAL C0f?ENT 5:
0 BUCKLING OF INNER SELL WAS NOT PRECLUDED
RESPONSE
O INNER SWLL DEFORh% TION WILL BE LIMITED TO PRECLUDE FUEL DAh%E AND ASSURE ADEQUATE SHIELDING
, NRC COMENTS (MAY 31, 1985)
STRUCTURAL COMMENT 6:
- O VALIDITY OF FINITE ELEMENT ANALYSIS NOT ESTABLISED CH0 ICE OF MODEL BOUNDARY CONDITIONS MATERIAL PROPERTIES IDENTIFICATION LOAD DISTRIBUTION LOAD COMBINATION PROCEDURE INTERPRETATION OF N0DAL STRESSES
RESPONSE
O REG. GUIDE 7.8 AND 7.9 WILL BE USED AS BASIS FOR SAR i
STRUCTURAL COMENT 7: ,
O ANALYSIS OF IMPACT LIMITER APPEARS NONCONSERVATIVE
RESPONSE
0 AGREE 0 WILL BE REASSESSED DURING SAR REhRITE i
NRC COMMENTS (MAY 31, 1985)
STRUCTURAL COMMENT 8:
0 ANALYSIS DOES NOT CONSIDER NORMAL TRANSPORT CONbITIONS
RESPONSE
0 COND1TIONS FROM 10 CFR,71, PARA. 71 WILL BE CONSIDERED STRUCTURAL COMMENT 9:
0 STRESSES ARE NOT REPORTED IN:
CLOSURE BOLTS DRAIN VENT LINES
RESPONSE
0 ASSESSMENT WILL BE MADE AND DEFORMATIONS OR STRESSES WILL BE REPORTED STRUCTURAL COMMENT 10:
. 0 EFFECT OF LEAD SLUMP ON SHIELDING NOT REPORTED
^
RESPONSE
O EFFECT OF LEAD SLUMP ON SHIELDING WILL BE REPORTED
4 NRC COME NTS (MAY 31, 1985)
STRUCTURAL COMMENT 11:
0 PUNCTURE EVALUATION DOES NOT CONSIDER I
TOP CLOSURE PLATE ,
BOTTOM PLATE
RESPONSE
0 ASSESSENT WILL BE MADE OF DEFORMATIONS OR BREACH i
STRUCTURAL C0f*ENT 12:
0 STRESSES NOT PREDICTED L
CASK BOTTOM END PLATE j ,
CONTAINER BOTTOM END PLATE
! RESPONSE:
0 ASSESSENT WILL BE MADE OF DEFORMAT10N OR BREACH i ; THERMAL COMMENT:
I- -
0 EMISSIVITY VALUES APPEAR LOW
RESPONSE
!. 0 AGREE THAT SOE EMISSIVITY VALUES WERE LOW b
NRC COMMENTS (MAY 31, 1985)
OPERATING PROCEDURES COMMENTS 1 AND 2:
0 APPARENT INCONSISTENCIES i '
RESPONSE-4 0 OPERATING PROCEDURES SECTION WlLL BE REWRITTEN ACCEPTANCE TEST AND MAINTENANCE PROGRAM COMMENTS 1 AND 2:
0 M0ISTURE CONTENT OF WOOD SHOULD BE KNOWN TO BE BELOW A SPECIFIED VALUE f
RESPONSE
l 0 THAT REQUIREENT WILL BE INCLUDED URANIUM ALUMINUM AND SILICIDE FUELS:
0 PHYSICAL DESCRIPTION AND REACTIVITY ANALYSIS SHOULD BE INCLUDED FOR EACH FUEL TO BE INCORPORATED 1 RESPONSE:
, O ALL FUELS WILL BE DESCRIBED 0 REACTIVITY ANALYSIS WILL DEFINE AND JUSTIFY WORST CASE ANALYSIS l _ _ _ _ -_