ML20065L962

Forwards Summary of 820917 ASME Code Comparison Working Meeting W/Crbr Project Ofc,Lasl,Westinghouse & Wllco in Bethesda,Md to Resolve Concerns Re Utilization of 1974 ASME Code for Design of Containment Vessel

ML20065L962
Person / Time
Site:	Clinch River
Issue date:	10/15/1982
From:	Longenecker J ENERGY, DEPT. OF
To:	Check P Office of Nuclear Reactor Regulation
References
HQ:S:82:106, NUDOCS 8210210022
Download: ML20065L962 (16)

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Department of Energy Washington, D.C. 20545 Ds:ket No. 50-537 HQ:S:82:106 0CT 151982 Mr. Paul S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D.C. 20555

Dear Mr. Check:

ASME CODE COMPARIS0N WORKING MEETING -

SUMMARY

This letter transmits a summary of the ASME Code comparison working meeting held on September 17, 1982. The summary provides an overview of the discussions which were conducted and other relevant information.

Sincerely, Jo n R. Longen er Acting Director, Office of the Clinch River Breeder Reactor Plant Project Office of Nuclear Energy Enclosure

,- cc: , Service List Standard Distribution Licensing Distribution pool 8210210022 821015 PDR ADOCK 05000537 A PDit

ASME CODE COMPARISON WORKING MEETING -

SUMMARY

A working meeting was held on September 17, 1982 to resolve NRC concerns relative to the CRBRP utilization of the 1974 ASME Code for design of the containment vessel. A presentation was given to show the comparative eval uation results (contained in the response to NRC Question 220.25) of the 1974 ASME Code versus the 1980 ASME Code for buckling. The presentation and resultant discussions !ndicated the relative comparability of applying the 1974 ASME Code in lieu of the 1980 ASME Code. The NRC reviewers were generally in agreement w ith the results of the eval uation; however, they requested additional time to consider specific areas. See Attachm6nt il for meeting viewgraphs, Attachment #2 for meeting agenda, and Attachment #3 for meeting attendees.

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CE RP CONTAINflENT DESIGN AND EVALUATION CONIAINMENT BUCKLING EVALUATION - CODE CASE N-28tl PRESEllTED BY RICHARD ORR  :

, CHIEF ENGIllEER, CIVIL AND STRUCTilRAL ENGINEERING ,

WESTINGHOUSE - 0FFSHORE POWER SYSTEMS SEPTEMBER 17, 1982 4

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LOAD COMBINATIONS FOR BUCKLING EVALUATION

'ASME CLASSIFICAT'qN LOAD COMBINATION (SERVICE LEV _t>

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D + L + T' + Pg A D + L + To + OBE B D + L + To + SSE , C D + L + Le + T' + OBE + Pg Cl)

B D + L + L c + T' + SSE + PgCl) C" WHERE D = DEAD LOAD L = LIVE LOADS (EXCLUDING CRANE LIVE LOAD)

Le = CRANE LIVE LOAD

< . To = NORMAL OPERATING THERMAL T' = ACCIDENT THERMAL LOADS Pg = EXTERNAL PRESSURE

! OBE = OPERATING BASIS EARTHQUAKE SSE = SAFE SHUTDOWN EARTHQUAKE (1) THESE LOAD C0KBINAT10NS ARE USED IN THE BDSOR4 EVALUATION.

e--- , - - , . , , , . - - - - - - - , , ,, . . - - -

l DLdIGN BASIS ACCIrs :NT FOR REACTOR .: .

CONTAINMENT BUILDING .

o POSTULATED INISTANTA\lEOUS NON-MECHANISTIC RELEASE OF MAXIMUM AVAILABLE SODIUM VOLUME FROM THE PRIMARY SODIUM STORAGE TANK C35,000

GALLONS;l -

! o POSTULATED DE-INERTED CELL ENVIRONMENT FOR MAINTENANCE WITH PRIMARY SODIUM STORAGE. -

TANK. FILLED WITH 400 F SODIUM; 10 DAYS AFTER SHUTDOWN .,

i o ALL AVAILABLE OXYGEN IN CONTAINMENT IS -

l REACTED WITH SODIUM. THIS RESULTS IN BURNING '

OF APPROXIMATELY 23,000 GALLONS O,.F SODIUM o ACCIDENT OCCURS AT END OF PLANT LIFE ..

1 MAXIMIZING PRIMARY SOD. LUM COOLANT .

I RADIOL 0GICAL ACTIVITY W-7737-43 ,

9 CO NTAI N MENT ATMOSPH ERE PRESSURE-PRIMARY SODIUM IN-CONTAIN MENT STORAGE TANK FAILURE DURING MAINTENANCE (PSIG) 1.0 .

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0 O 10 20 30 40 50 60 70 80 90 100 TIME (HOURS)

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CONTAINMENT ATMOSPHERE

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SODIUM IN-CONTAINMENT  !

STORAGE TANK FAILUR5~ ,

DURING MAINTENANCE =

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CONTAINMENT ATMOSPHERE TEM PERATU R E, (*F) 140 .

m 130 - .

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l 110 - -

100 - -

90 ' -

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70 O 100 200 300 400 500 600 TIME AFTER SPILL (HOURS)

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t CONTAll\ MENT VESSEL

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TEMPERATU RE-PRIM ARY

~ SODIUM IN CONTAINIWENT -

STORAGE TANK FAILURE - -

DURING MAINTENANCE CONTAIN MENT. VESSEL '

TEMPERATURE, ( F) -

130 120 -

110 - .

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90 .

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SHELL ANALYSES J

SHELL MODEL FOURIER HARMONICS LOADS l

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< LUMPED MASS BEAM MODEL 0&I  : OVERALL SE.ISMIC RESPONSE i

AXISYMMETRIC SHELL OF 0 DEAD LOA'D, PRESSURE, REVOLUTION TEMPERATURE, EQUIVALENT STATIC VERTICAL SEISMIC t -

ON SHELL '.

1 i 1 EQUIVALENT STATIC '

! HORIZONTAL SEISMIC '

ON SHELL O TO 14 DEAD, LIVE AND SEISMIC CRANE LOADS I

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[ _wo N SHELL l 9 EL 85G'-O' N STIFFENERS cD

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• 830' $ 85G' Im = es'-o" EL839'-O' in-T D a . _

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_ EL SIGj,,,OPERAT[NG FLOOR h_Jri Lr-_- -

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I MATERIAL: SA SIGG n 70 I i l I .

I i i Ul 1 I'UNER 4 8. 0P

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t- M-TOP EL 750'-O' OF u g fgg'e7-22"pA 5 %

CRBRP CONTAINMENT VESSEL

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SHELL STRESSES IN THE BAY ,. , /E THE OPERATING DECK l ,

(PSI, COMPRESSION POSITIVE) l .

STRESSES AT EL 816' STRESSES AT EL, 827' -

LOADING AXIAL HOOP SHEAR AXIAL HOOP SHEAR SHELL DEAD LOAD 683 205 646 CRANE DEAD + LIVE LOAD 413 123 443 -4 OBE - VERTICAL 575 172 571 -6 l

NORTH-SOUTH 1900 570 65 1553 -241 59

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EAST-WEST 1093 1061 SRSS 1985 595 1095 1655 -241 1063 SSE - VERTICAL .. 907 272 897 -10 NORTH-SOUTH 2710 813 80 2231 -393 75 EAST-WEST 1711 1655 SRSS 2858 857 1713 2405 -393 1657 DL + LL + OBE 3081 923 1095 2744, -245 .. 1063 DL + LL + SSE 3954 1185 1713 3494 -397 1657 i

ELEVATION 816' = OPERATING DECK ELEVATION 827' IS ABOUT THE MIDDLE OF THE BAY .

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EL 875' h

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= 0 CO CL N.

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EL 856' y a

STIFFENER MODELED

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EL 816' y l

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HOOP: a s,= 0.8 EL 816' TO EL 875' 1:

AXIAL: a, = 0.275 EL. 816' TO EL. 839' 0.330 EL. 839' TO EL 856' O.309 EL. 856' TO EL. 875' o APPLIED PRESTRESS (LB/IN) FOR BOSOR4 LINEAR BIFURCATION ANALYSIS HOOP STRESS /a, .

AXIAL STRESS /a, .

o ADJUSTMENT FOR SHEAR STRESS

+ +8 11 FOR CYLINDER BETWEEN RINGS OR SUPPORTS A

\"+e "+eet)

WHERE A = ElGEN VALUE FROM B0SOR4 ANALYSIS

'+e = SHEAR STRESS

= KNOCKDOWN FACTOR FOR SHEAR (= 0.712, EL. 816' TO EL. 839')

"+e o,,,t= CLASSICAL BUCKLING VALUE UNDER SHEAR LOAD BASED ON N-284 FORMULA

-FS = FACTOR OF SAFETY i .

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EL 875' EL 856' a

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l l' EL 816' BOSOR4 BUCKLE MODE' RADIAL DISPLACEMENT (N = 21)

DL + LL + SSE + THERMAL + Pg D

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d ATTACHMENT d2 Meeting Notice ASME Code Comparison Working Meeting Location: WLLCO, Landow Building, Rm. 1111 7910 Woodmont Avenue Bethesda, Maryland Time: 8:30 AM Date: September 17, 1982

Purpose:

To resolve concerns relative to the CRBRP utilization of the 1974 ASME Code Scope: To show the comparative evaluation results of the 1974 ASME Code vs. the 1980 ASME Code. To highlight the relative comparability of the 1974 ASME Code vs. the 1980 ASME Code, except where specifically noted.

ASME CODE COMPARISON WORKING MEETING AGENDA _

l. Introduction V. Fayne l

11. Comparison of PSAR to 1980 ASME Code W-LRM ll1. Comparison of PSAR to N-284 W-LRM IV. NRC Concerns with using 1974 ASME Cd,de PO l -

V. Discussion Open l

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_ ATTACHMENT 63 SEPTEMBER 17, 1982 l

ATTENDANCE NAME -

ORGANT2ATTON PHONE-NUMBER P. R. Washer CRBR-PO 615/576-6179 G. A. Fidler CRBRP/PO 615/5'76-6241 C. P. Tan NRC 301/492-8424 J. G. Bennett Los Alamos 505/667-7888 Tom Butler Los Alamos 505/667-5171 P. T. Kuo NRC -

301/492-8442 G. H. Clare Westinghouse, Oak Ridge R. Orr Westinghouse, Jacksonville R. E. Gale Westinghouse, Oak Ridge f P. Docherty WLLCO Vincent Fayne CRBRP/PO 615/576-6394 4

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