ML18220A508

Attached Slides Entitled, Steam Generator Enclosure Pressure Analysis, Present Summary of Preliminary Results Which Westinghouse Has Obtained with Multi-Node Model

ML18220A508
Person / Time
Site:	Cook
Issue date:	11/18/1977
From:	Judkis M American Electric Power, Westinghouse Electric Corp
To:	Case E Office of Nuclear Reactor Regulation
References
NS-PLC-4549, S. O. AMP-460
Download: ML18220A508 (21)

Text

NRC FORM 195 U.S. NUCLEAR REGULATORY CO>'4IISSION DOCKET NUMBER (2-761 .

FILE NUMBER NRC DISTRIBUTION FoR'ART 50 DOCKET MATERIAL TO: ~ .Ã FROM: DATE OF DOCUMENT Westinghouse E3.ectric Corp>> 11/18/77 Pittsburgh, Pa,

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Edson G>> Case DATE RECEIVED M>> H>> Judkis 11/21/77 BETTE R QNOTOR IZED PROP INPUT FORM NUMBER OF COPIES RECEIVED HCJ N C LASS I F I E D SCOPY (en .

DESCRIPTION ENCLOSURE Documentation of the presentation made to the NRC on ll/ll/77 re>> the D>> C>> Cook steam generator enclosure pressure analysis>> ~~~~ ~~~

PLANT'NAIK - Cook Unit No>> 2 (2-P) (10-P)

RJL 11/21/77 FOR ACTION/INFORMATION ENVIRONMENTAL ASSIGNED AD: OR (LTR I CH CHIEF: BRANCH CHIEF'-

PROJECT i~IANAGER:

LIC ~ ASST: 77K B. HARLESS INTERNAL DISTRIBUTION SYSTEMS SITE SALTY G ENVIRON ANALYSIS DENTON G MULLER OSSICK Q STAFF ENGINEERING TO RON TECH ERNST CTORS BALLARD AGEMENT ACTOR SAFETY TECH ROSS AltIMILL 2 NOVAK L R ROSZTOCZY ANALYSIS CHECK VOLLNER JAI P. T. S LTZMAN EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: 1 TIC N IC

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I REG V J. HANCHETT) 16 CYS SENT CATEGOR

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Yi(estinghouse Electric Corporation Power Systems PWtt SyStemSDllNSttm Sax 355 Pit tstturghPtlttsylvm15230 November 18, 1977 NS-PLC-4549 S. 0. AMP-460 Mr. Edson G. Case, Acting Director 0)

~D Office of Nuclear Reactor Regulation CP U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014

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Dear Mr. Case:

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etr,claH g 5, AMERICAN ELECTRIC POWER Conald C. Cook Nuclear Plant Steam Generator Enclosure Pressure Anal sis '4 This letter serves to document the presentation made to the NRC on November 11, 1977 regarding the D. C. Cook Nuclear Plant steam generator enclosure pressure analysis. The attached copies of the slides present a summary of preliminary results which Westinghouse has obtained with a multi-node model of the enclosure (Slide 1). The analysis was per-formed with the Westinghouse TMD code using unaugmented critical flow and the compressibility factor. A multi-node representation of the enclosure geometry was established and is shown in slide >2. Vent flow-paths exist out the bottom of each enclosure to the lower compartments.

Also, vent flowpaths exist between adjacent enclosures; specifically between nodes 46 and 55, between nodes 47 and 56 and between nodes 48 and 57. The two break locations considered were:

1) Break at the top - TMD node 46-

2) Break at the side - TMD node 51.

In order, to keep the cases clearly referenced either the words "BREAK IN 46" or "BREAK IN 51" appear in the upper right hand corner of each slide depicting results.

For the 'case of the break in the top region (46), slides 0'3 and tIt4 show the pressure and temperature transients in the break node 46), respec-tively. Slide tnt5 shows the differential pressure which would be present from the break node to the upper compartment (across the roof and the

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Page top portion of the enclosure wall). Slide 86 illustrates the differential pressure which would be'resent in the high pressure region across the internal wall between the adjacent enclosures. In both cases of slides 85 and h'6 the maximum pressure differential which would exist across the structure is presented. In the case of the pressure differential across the enclosure wall, the maximum pressure differential at a mid-elevation would be approximately 26 psi and ll psi at a lower elevation.

The pressure differentials would vary similarly along the internal wall.

For the case of the break along the side of the vessel (51), slide 87 shoWs the pressure transient in the break node (51). Slide 88 presents the bounding pressure differential which would be present across the crane wall. In reality the ice condenser region exists on the other side of the crane wall from the steam generator enclosure, however the upper compartment pressure was used as the backpressure for the pressure differential calculation and represents an upper bound of the differential pressure. The short duration inertial peak is approximately 38.8 psi and the steady state peak later in time is approximately 22 psi for the pressure differential across the crane wall. Slide 89 illustrates the maximum pressure differential across the internal wall from the break node (51) to the adjacent enclosure. The short duration peak differen-tial pressure is approximately 38.8 psi and the steady state peak later in time is approximately 22 psi. Slide 810 illustrates the maximum pressure differential across the steam generator vessel from the break node to the opposite side of the vessel (DP 51-53). The short duration inertial peak is approximately 38 psi and the steady state peak later in time is approximately 13 psi. These results represent maximum pres-sure differentials; other locations yielded lower pressure differentials across structures and the vessel.

Very truly yours, N. H. Ju is, Man ger American Electric Power Project

. C. Ratsep/re Attachment Forty (40)

CC: R. W. Jurgensen, 1L (AEP), 5A

'R. S. Hunter, 1L AEP)

R. F. Hering, 1L AEP)

S. H. Horowitz, 1L (AEP)

P. W. Daley, 1L (AEP)

S. J. Milioti, 1L (AEP)

J. G. Feinstein, 1L (AEP), lA

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