ML20214G819

Summary of 731017-18 Meetings W/Util,B&R & GE in Bethesda,Md Re Outstanding post-CP Items

ML20214G819
Person / Time
Site:	Columbia
Issue date:	11/21/1973
From:	Elliott D US ATOMIC ENERGY COMMISSION (AEC)
To:	US ATOMIC ENERGY COMMISSION (AEC)
References
CON-WNP-0091, CON-WNP-91 NUDOCS 8605220536
Download: ML20214G819 (6)

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j NEITING St30tAtr CCToan 17-18,44993 WEM abSEIN EDE FIE.3c fou n W sTstuu, mIscussion or oursrauexmG sesT-constascTicu Insanrr ITimes, ,

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SWel&RY A meeting was held at Bethesda on October 17-1s 1973 to discuss the sestus of the outstanding post construction permit items incinding the schedule forji their resolution. In attendance were representatives of the AEC seector  !

projects and technical review sectices, Usshington Fabiic Fouer, Barns and Roe and General Electric. A meeting ste==d ar= list is attached. '!'

MIETING AGEND& ITINS

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Bacirculation Pump Control Valve Desian The development program for the recirculatica pump castrol valve as out-Lined in the su contemplated testing a Elemer valve and, applytag the results of that test to a Benford-2 valve. The Zissner volve is smaller (20 inches vs. 24 inches) them the Eenford valve but isI 'of identical desism. It is now pE;- :f to su a complete test om e Benford sised volve. The test program includes cold and hot floe tests, electrieel controller tests, system responses and common failure mode tests. ,

A report describing the test program and the results of 'the test will

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- he s=hmitted by June 30,1974. 1he , testa are beias parfa==ad by GEg \

p f, the testw.report moy.be a GE I; -DL ,

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pressure plus 101 that the component could ever experienee is either the

,,g. .w eemsel, upset, emergency or feutted somditions.. .no campement sill he.3 r hydrotested at 1.5 times the design stasse.

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i h-; ;he-opplisant and the sepseeestdtives 'frem tages and Reardhesed ehet'they W o = + ' esse committed to enemine bseeker Leestimma -ta' all high emergy lines within the reactor contaimment vessel in accordance with Regulatory Guide 1.46.

Se applicant expects to submit their report em Pipe lenip Inside Contaissent I

during March, 1974. Any differences between the applicant's approach and Regulatory Guide 1.46 will be discussed la detail in the embaitted asterial.

_H_izb Easjay Five Break Outside Contalsment The applicant and the representatives from Busas and Ese stated that their analysis would follow the guidelines presented in the ABC letters of ~.h December 22, ~.972 and January 12, 1973. staff comments included the f suggestion '.nat an effort be made to minimise encapsulation of pipes and h components and that the section of the main steam line between the contaia=

ment vessel sad the outer: isolation valve anat be included in the analyste4 k The applicant should demonstrate sufficient conservatism to sender a break- \

in the main steam line between the coatsimment vessel and the outer isolationi valve incredible. This could be done by a substantial reduction of the ,

material alloweble stress values and/or augmented inservice inspection \

technigues. :s ne applicant expects to submit his fosmal response to the ABC December 22,

1972 letter by April 1,1974.

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i,s . % t sis.,'es,a~mitted as a assi ks n mystem for thei'.

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tfthat no desiston~ had ' ands ea'the eeeeeptust-desty of thei 4 1 seal systps. ^to; applicant l P -cM,, ~. b1' system'for e v. s asC review ~hy ',Juns ?UQte ~ submit H C44fL a aceseytest' M desig i .s_ '

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l form AEC-Ste tRev. 9-53) AICM 0240 see .es- to-stese- eesrs l

NOV 211973 margin of the ultimate heat sink in the event of spray header failure due

_to tornado caused missile danese sad on the q& coussitment for the

• water system during January 1974. - -

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4 tih Tesi appaneet.and the sepseessentisee'erassus:and nos pensamend a dagensston

, of possmetattleek soareas heeseen es.drysett and seeme11. 'the system.se be W +maad teemseest these leeks and ebe,seasessee se he used se operate chi leak deseettenteystem. - < = ; 15 2, ,, - o ~ fj g i C7A . .i 3 9 @ r3 D O ty e te . @-

Fotential, leak sources which eeze discussed in aswatest detail and uklah received the most discussion included 'the vacutua breaker valve design,' the concrete floor sealant and the metal peripheral seal of the drywell floor.

With regard to the vacuum breaker valves, it was pointed est by the sta'ff. I that the reliability of these valves is low est that the escuracy sad

• reliability of the valve position indicating switches should be carefully considered. ,s The applicant stated that he was examining suitable floor sealers even though he did not expect drywell to wetwell leakage throudt the concrete floor to be a problem.

The details of the floor to containment seal were presented. The seal is essentially a sectioned stainless pipe attached to carbon steel support \

plates which are then attached to the floor med the containment vessel. 3 ., \

The seal alloes differential horisontal and verticle movement, water

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drainage and inspection of seal welds. A report dealing with drywell to \

wetwell leakage is scheduled for sehmittal by the applicant daring 1 April 1974.  ;

Drywell to Wetwell Leak Detectice Breg otential for a The leakor periodic detection system continuous leakproposed rate messarement.by, the appliesst has theisp'desigad%o "

The system ,

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• M Teseestated with difSering envisonnenes1Jese644tsee tegneesWeithia  !'

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SUM 4AMEpm DATE > . , . .

Fons AEC-588 (Rev. 9-53) AECM C240 **e esa-no-eness-s eaa-ors t

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1.ded the following:

1. Additional loads to the seestor pedestal soeulting from the ersetion of the scarificial shield should be seasidered.

2. We sacrificial shield erection procedure abould be tactuded in the submitted material.

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3. ne esiculations of the pressure differential sesses the seerificist shield resulting from a pipe break should be shoum.

4.

He temperature increase in the amoulus should be considered following

, a pipe break as should the problems resulting from temperature differences between the steel and caecrete compements of the sacrificial shield. '

5. he difference in radial growth between the sacrifisial shield and

• pedestal should be considered.

6. Increased pressure resulting from blockage of the sacriftetal shield annulus by insulation or other meterial following a pipe supture should be considered. C f

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D. E Elliott, Project Manager Beiltas unter anectors Branch 1 Directosets of Licensing macmsure:

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sesmaansen, DME11iott:ks WRButIe

,,,,,,, 11/9/73 11/10/73 , _;,,

Posun AsGHSlase. 9 SM ABC3d OHO ero saa se eseee.e one. eve

MEETING ATTENDANCE Washington Public Power Supply System WPPSS Nuclear Project-2 (formerly Hanford-2)

October 17, 1973 AEC Burns & Roe D. Elliott J. Forman S. Salah*

D. Tondi*

R. Baldwin F. Patti S. Miner

• K. Ronis J. Richardson

• R. Jensen C. Long*

J. Verderber WPPSS GE R. Chitwood P. McCabe J. Woolsey H. Summers J. Mowery J. Major C. Fies J. Power October 18. 1973 AEC

! Burns & Roe l

D. Elliott R. Baldwin C. Anderson

• K. Ronis G. Lainas* F. Patti R. Cudlin*

J. Forman S. Miner

• J. Verderber A. Gluckman* R. Jensen WPPSS GE C. Fies P. McCabe J. Woolsey H. Summers J. Howery R. Chitwood

• Part time attendance 4

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