ML20140F559

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Summarizes Discussions Held on Safety/Relief Valve Loading During 770216 & 17 Meetings W/Ge,Mark II Owners Group & BNL in San Jose,Ca.Monticello Test Results & Analytical Model Verification Areas of Concentration
ML20140F559
Person / Time
Site: Monticello, 05000000
Issue date: 03/03/1977
From: Teh-Chiun Su
Office of Nuclear Reactor Regulation
To: Lainas G
Office of Nuclear Reactor Regulation
Shared Package
ML20140F372 List: ... further results
References
FOIA-85-665 NUDOCS 8604010085
Download: ML20140F559 (13)
v • d • e


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  • e HAR 3 1977 MEMORANDUM FOR: Gus C. Lainas, Chief, Containment Systems Branch, DSS FROM: T. M. Su, Containment Systems Branch, DSS THRU: J. Kudrick, Section A Leader, Containment Systems Branch, DSS C.

SUBJECT:

SRV DISCUSSION WITH THE MARK II OWNERS GROUP Meetings were held on February 16 and 17,1977, in San Jose, California with representatives of General Electric, Mark II owner group, NRC staff and our consultants (BNL). The minutes of these meetings will be prepared by Sydney Miner, the project manager for Mark II containment.

This memo, however, is to apprise you about the discussions held on SRV loadings.

The discussion concentrated on two areas, namely, Monticello test results and the analytical model verification. The following sumarizes this discussion:

Monticello Test Results The test results indicate that the air bubble was deflected consistently to one side along the ramshead discharge. Cause of this deflection is not yet determined. Investigation of the tested ramsheads to determine any dislocation or obstructions on the discharge will be conducted in the next scheduled outage.

It is anticipated that this phenomenon of deflected bubble will impose ,

further difficultiei for analytical model verification because of the  :

instrumentation setup. Note that most of the pressure transducers were I concentrated on one side of the discharge. There is only one pressure l transducer in the side, which appears to be where the bubble was located.

Furthennore, the interference of the I-beam, which supports the ramshead discharge, on the bubble pressure field. appears significant. The i applicability of the Monticello test for those plants without the I-beam should be evaluated. .

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Contact:

1 T. M. Su, CSB 492-7711 PDR FOIA l FIREST005-665 PDR 9 5'-

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MAR 3 1977 Gus C. Lainas The applicability of the Monticello test for Mark II containment was also discussed. We indicated that concerns of fluid / structure interaction i and orientation of the ramshead discharge should be considered. The Monticello is a steel containment while most of the Mark II designs are ,

concrete containments. Also, the ramsheads for Monticello are oriented '

parallel with the boundaries while the Mark II containments such as i' Shoreham and Zininer have the ramsheads oriented toward the boundaries.

Final report on Monticello test will be issued in April 1977. i Analytical Model GE indicated that the existing analytical model is being modified. Details of this modification has not been presented. However, GE indicated that one  :

of the key assumptions, i.e., bubble fonnation efficiency, has been deleted in the modified model. A description of this model will be issued in l June 1977.

The comparison of model with test data, however, will be made on the basis of existing model . Report on this comparison will be issued in the second  ;

quarter of 1977. l S S T. M. Su Containment Systems Brarch  !

Division of Systems Safety cc: R. Tedesco -

l C. Anderson J. Kudrick J. Shapaker S. Miner T. Su File: BWR Pool SV/RV Load Problems (Ramshead) e O

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TYPICAL l' ARK II SlEiERGED STRUCTU?ES e S/RV LITES #9 SUPPORTS e f%IN VBIT #9 BPACI!!G SYSTB1 e DIAPHRAGli FLOOR SlPPORT COLuii!S e ECCS SUCTI0il #4D RETUfil LIIES l

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l PEGRNi ORJECTIVE PEVIE APLYTICat IERODS TO EFI E LOADS 0:1 SLETERGED STRUCPJES Ift-f%RK I, II a III SUPPfESSIO:1 POOLS DLE TO e FAlft VEIT AIR QBRIllG BLEBLES (LOCA) ,

. e f%Ill VEff WATER JETS e S/RV AIR CLEARIlG DB9FR (PMSHEAD KD QLS10ER) e S/RV WATER JETS (PMEHEAD KB OLE!GER) e f%IllVEff STEN!C0fES!SATIO:!

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SUBMERGED STRUCTURE LOADS EVALUATION PROGRAM MK II HIGHLIGHTS C

MODELS LOCA/SRV AIR BUBBLE TSC TSC REVIEW REVIEW LOCA/SRV

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APPLICATIONS REVISION .

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QUENCHER WATER JET MAIN VENT CONDENSATIOV LOADS NRC REVIE'.:

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PFDGRN1 SOEDULE l 1976 1977 1978 10 11 12- 1 2 3 4 5 6-7 8 9 10 11 12 l2345678 PARTI

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I, f0IR IEVt10PIETT LOCA&S/RV V W PRELIf NARY REPORT STEN 1C0f0BEATI0il Y '# V

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. SbI'iARY OF PRELIMINARY RESULT [/.

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e SRV PIPE PRESSURE ,

'e AVG. OF 275 PSIA (1 SIGMA =

  • 3%) FOR BASE I CASE (COLD PIPE, COLD POOL) CONDITIONS.

- MODEL~l40-50% CONSERVATIVE. I e HIGHEST MEASURED - 320 PSIA FOR SECOND ACTUATION CASE (1 MIN. BETWEEN ACTUATIONS).

-e TORUS SHELL PRESSURE e AVG. PEAK PRESSURES OF +21 AND -10 PSID FOR BASE CASE.

1 SIGMA =

  • 9% (POS.), 8% (NEG.)

e MODEL OVERPREDICTS~20% ON POSITIVE AND UNDER PREDICTS 20-30% ON NEGATIVE.

e SUBSEQUENT ACTUATION EFFECTS e ~80% INCREASE IN PEAK POSITIVE RELATIVE TO 1sT ACTUATION.

e ~30% INCREASE IN PEAK NEGATIVE RELATIVE TO 1sT ACTUATION.

e HIGHEST MEASURED: +36 AND -16 PSID (SECOND ACTUATION, 30 SECOND BETWEEN ACTUATIONS)

- NEW MODEL WILL INCLUDE 2ND ACTUATION -

e MULTIPLE VALVE ACTUATION EFFECTS he DATA APPEARS TO BE AND WILL PROFABLY REMAIN INCONCLUSIVE. .

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2 1 o EFFECTS OF LEAKING SRV AND POOL TEMPERATURE:

e ALL ELEVATED POOL TEMPERATURE TESTS DONE WITH LEAKING SRV.

e POOL TEMPERATURE EFFECT CONSIDERED INSIGNIFICANT.

e LEAKING SRV RESULTED IN A 33% INCREASE IN PEAK POSITIVE SHELL PRESSURES RELATIVE TO COLD CASE.

e TORUS SHELL PRESSURE OSCILLATION FREQUENCY e RANGED BETWEEN 4 HZ AND 8 HZ (COLD PIPE TESTS) e RANGED BETWEEN 4 HZ AND 12 HZ (HOT PIPE TESTS) l r

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CONTAINMENT SYSTEMS BRANCH 98stel$6Mi

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SHAPAK F. LTAW LA i T. G E t

1 W. M EAD D. ICKE T C. TINKLER Return to G. Lainas s ss te

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