ML20235C479

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Forwards Request for Addl Info Re Proposed Reduction in Design Pressure of Containment Drywell & Torus for Plant,Per 700522 Meeting
ML20235C479
Person / Time
Site: Brunswick, 05000000
Issue date: 05/28/1970
From: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
To: Colby P
CAROLINA POWER & LIGHT CO.
Shared Package
ML20235B311 List: ... further results
References
FOIA-87-111 NUDOCS 8709240466
Download: ML20235C479 (4)
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Text

Distribution:

% :ket (2) #

AEC PDR (2)

DR Reading DRL Reading NAY 2 81970 BWR-1 File CKBeck, DR Docket Nos. 50 324 / M ann, DR and 50-325 FSchroeder. DRL Aust.

EGCase, Directors,DRL(4:l1 DRS '

RRMaccary, DRS Hwe, DRL Mr. P. S. Colby BG & es, DRL Senior Vice President DRL/DRS Br. Chiefs Operating & Engineering Group Carolina Power & Light Company *[' 'DR 336 Fayetteville Street Raleigh, North Carolina 27602 A S (18) 7"# (2)

Dear Hr. Colby:

In the course of our review of your proposed reduction in the design pressure of the contairement drywell and torus for the Brunswick units, we have found a need for additional information. The specific informa-tion required is described in the enclosed " Request for Additional Information," which was discussed with your representatives during a meeting held at our Bethesda office on May 22, 1970.

A timely conclusion of our review of this matter requires that you submit the requested information as soon as possible. Please call me if further discussions will help in clarifying any of the requested information.

Sincerely, ertsinal siesed by pseer A. Norris Peter A. Morris, Director Division of Reactor Licensing

Enclosure:

Request for Additional Information cc: George F. Trowbridge, Esq.

Shear, Pittman, Potts Trowbridge, & Madden 916 17th Street, N.W.

Washington, D. C. 20006 (Rewritten per PAMorris, 5/28/70.

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REQUEST FOR ADDITIONAL INFORMATION

1. Provide a comparison of the calculation (with the present G. E. pressure suppression codes) of Bodega tests 29 through 54 with the actual test data.

Include comparisons of code calculations of the drywell, suppression chamber, and reactor vessel pressure transients with all the corresponding test data.

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2. C&1esiste mass and energy blowdown rates that match the measured blowdown rates in these tests. Compare these test-determined blowdown rates with the calculated (Moody model) blowdown rates by plotting (1bs/ hour) and (energy / pound) versus time. Using the test-determined bloudown rates, recalculate the pressure transients for the drywell and suppression chamber. q j

For all containment pressure transient calculations, use the same code as l was used for the data in Section 14.5.1 of the Brunswick FSAR as revised in Supplement 2, dated March 11, 1969 (Docket No. 50-324 and 50-325).

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3. specify the monstants for the vent flow model (e.g., k, R, I) used in your prior analyses for the Brunswick plant. (Section 14.5.1 of the PSAR, supplement 2.). Justify the adequacy of this model, including constants, or justify %t adequacy of an improved model which you may wish to present at this time.
4. With the same code and conditions used in the prior Brunswick analyses except for the vent flow model, recalculate the Brunswick containment conditions following the design basis loss-of-coolant aceCdent using that vent flow Perform model which conservatively bounds all the Emmboldt and Bodega tests. i sensitivity analyseton the Brunswick containment conditions by varying '

parameters such as d .1, at* &., in the vent flow model ranging between those assumptions for homogeneous flow and for slip flow.

5. Justify the use of the Bodega and Bumbolt test data for developing a cal-culational model which can be applied to im'redhe BWR plants. Include the analyses by which you determined the error that may exist (1) in the test data and (2) in applying the test data to full-sise plants. f
6. Recalculate the Brunswick containment accident pressures by assuming initial reactor vessel pressures of 1150 and 1250 pai with sero steam and feedwater flow.

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Dear Mr. Colby:

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/ ACRS (18) WNyer (2)

In the course of our review your proposed reduction in the design pressure of the contain= ant, 11 and torus for the Brunswick units, wefindaneedforsomeadpitiy1information. The specific informa-tion required is described la enclosed " Request for Additional Information," which was iscussed th your representatives during a meeting held at our Be eda office May 22, 1970.

'We recognine that a lyconclusionkourreviewonthismatter requires that you dayrelop the requested hpormatica on an decelerated schedule. Please call me if further discu Mions will help in clarifying any of the requested information.\

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sincerely, '\ s PeterA. Morris,Dirhtor

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Division of Reactor Ideensing Enclosur :

Request or Additional Info tion ec: rge F. Trowbridge, Esq.

aw, Pittman, Potts, Trowbridge, & Madden l 16 17th Street, N. W.

i Washington, D. C. 20006 (Rewritten per EGCase/GArlotto, 5/27/70. See attached.)

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REOUEST FOR ADDITIONAL INFORMATI0tt

1. Prov a comparison of the calculation trich the present G.E. pre re suppre ion codes)'ef Bodega tests 19 through 54 with the actua test

' data. lude comparisons of code calculations of the drywe ,

suppress chamber, and reactor vessel pressure transients th all .,

the corres ing test data.

2. Calculate maa and energy blowdoun rates that astch t measured blow-down rates in se tests. Compare these test-dete ed blowdown rates with the e culated (Moody Model) blowdown r s by plotting (1bs/ hour) and ( sy/ pound) versus time. Usin the test-determined

. blowdown rates, ree culate the pressure trans ts for the drywell and suppression ch r. For all containment res'sure transient cal-culations, use the code as was used for he data in Section 14.5.1 of the Brunswick PSAR a revised in Suppleednt 2, dated March 11, 1969 (Docket No. 50-324 and 25).

3. Justify the went flow model ed in present E.E. pressure suppression code. Imelude (1) justificat for steam and water flow rates through the vent pipes that are used thi code and (2) present a sensitivity analysis to show the effect of ing these flow rates on drywell pressures.

g4. Justify the use of the Bodega oldt test data for developing a

) calculational model which can app ed to full-size EUR plaats. Include the analyses by which you de ruined error that may exist (1) in the test data and (2) in applyi the test ta to full-size plants.

1. Recalculate the Brunswie containment ace t pressures by assuming initial V reactor vessel pressure of 1150 and 1250 p with sero steam and feedwater flow.

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Form AEC-818 (R.v. 9-63) uA sowanuam munNo orr% tsee- o-ss4-see

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