ML20140G241

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Recommends That Interim Inservice Insp Requirements for Containment Structures Be Developed for Use Until ASME Section XI Code Addresses Integrity of Containment Liners, Coatings & Matls
ML20140G241
Person / Time
Issue date: 04/02/1976
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Stello V
Office of Nuclear Reactor Regulation
Shared Package
ML20140F372 List: ... further results
References
FOIA-85-665 NUDOCS 8604020033
Download: ML20140G241 (8)


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'. . Otello, Director, Division of Oparating Ecactors, C;tR , .,- ,

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I.;'I't.IV.CE 12:322CTION 07 C0: TAII?.":::: STRUCTUTIC

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'..acant events which have directed our attention to inspections of ; 2 L.or:.

h.we brcught to 11;ht the fact that ther.: are prescatly no icv.rvie3 lu; ec .ior A

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requira=ents for I'JR containments other than tha requiru co* -"- j aa.bse rate testing, and a general " visual inspection" raquirectat. Ihc s L c 3 '. 1.nic.1

t. pears to be true for n'?.'s , except that there cre requiratants for ri. . 2=

s rveillsaca in the c:se of 1restressed str"ctures.

I'^ re cuare that ef forts Itave been initiated by ErI to develo: Ia mvice. 3 in;pec:: ion recuircre .ts Mr sceel contaia=ents, as wcll es reacrate .c.:c:-

raats , but it is not anticipated that approved c:d.fc will be ev:d t014 fe ne for pe chan 2-3 years, t a believe that interin inservice inspectica requirements for c:arat.=2 :.

structures should be developed for use until the .'.3:*2 Caction ::I Cr.ca 1. irs i.firessed thzse areas to assure that the integrity of contain rnt h .e.r, e.ri,

.: stings, and materials is being caintained. Verification of pl st.= thic'e raar;

.. d coating adherence should be addressed specifically in such reauirement.s.

$* --ert =echars should also receive specific attontion; thest .uould in .Ich te r.:s cupports, relief valve discharge piping supports in both the dry.te 1 r.-3 r.c eus and other supports for piping inside or attached to the contain ent structures. We reco:cend that DOR develop appropriate requirements to be ir.:crporated in technical specifications. If you have qusstiens regarding this

=atter . please contact I;. V. Seyfrit, Chief, Reactor Technical Assistance Braoch.

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  • Ecyce*H. Grier, Director Divition of Reactor Inspection Progrc=s Office of Inspection and Enforcecant ,

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cc: J. G. Davis, IE )

3. Tho=pson, IE  ;

J. P. O'?cIlly, Director, IE:I .

N. C. 1Ioseley, Director, IE:II -

IJ. C.1:appler, Director, IE:III E. II. Howsrd, Direc:cr, IE:IV R. F. ';nselken, Dire ctor, IE:V R. 3. 3: yd, NhR R. E. Hs?.naman, NRR

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.i The attached Table indicates the design pressure of the plants utilizing the Mark I type containment. The maximum calculated pressures and torus j shell thickness for each plant are also indicated.

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! The tori of the Oyster Creek and Nine Mile Point Unit 1 plants are designed

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! to a lower pressure than the remaining Mark I type plants. The reason for i

this difference in design pressure is not based on safety considerations, because the calculated pressure in all cases are below design, but on practical consideration for conducting the structural proof test. Oyster ,

f Creek and Nine Mile Point Un,i t 1 were the first plants utilizing the Mark I concept. Because of the difference in design pressure between the -

torus and drywell, the. structural proof test of each structure (air

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pressure test at.1.15 of design) was different. This required that the .

torus and drywell be temporarily " blocked off" which required time and expense. The torus design pressure for the later plants was increased to the same as the drywell, so that both structures could be tested at the same time and at the same pressure.

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,/ Peak Calculated Maximum ***

/ Pressure Allowable Pressure Wall Thickness Psig Psig Plant Inches Drywell Wetwell Drywell Wetwell 1

, Oyster Creek .385 33 20 62 35 Nine Mile Point 1 .460 50 25 62 35 1

, Monticello .533/.584* 42 25 --62 both--

Vermont Yankee .583' 43.5 27 --62 both--

1 Fermi 2 .587/.658* 56.5 25.2 --62 both--

, Hatch 2 .540/.607* 57.5 27 --62 both--

Brunswick . .375 liner ** 49 28 --62 both--

! Dresden .585/.653* 47 27 --62 both--

i Quad Cities .582/.649* 47 25 --62 both--

Millstone .596 /.625* 43 25 --62 both--

1 J Pilgrim T568/.629* 45 27 --62 both--

Peach Bottom .604/.675* 41.5 27 --62 both--

Fitzpatrick .568/.632* 45 26 --62 both--

Cooper .616 -

46.2 29 --62 both-- .

Duane Arnold .500/.534* 54 25 --62 both--

Browns Ferry .750 49.6 27 --62 both--

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  • Top Thickness / Bottom Thickness ,

, ** Concrete Structure

      • Based on Section III revision, this is indicated to be 56 psig (however, the capability of the containment remains at 62 psig).'

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cc: EPEales [_)

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  • F- BABush 1 SCChang GEGruen / l JHRamsthaler T0 Knight-ID

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  • IDAHO NATIONAL ENGINEERING LABORATORY JAKudrick-DSS MEMO OF CONVERSATION PHVanderHyde ECLemmon LPleach File C1.0 Date Time 1: pm Commitment Made Yes No Person Calhng L. Wheat et al Person Called J. A. Kudrick. ft.Su G. Lainas(Part time)

Representing INF1- Representing NRC-USS Purpose of Conversation * * " O Models(LLW-18-76)

O Text of Conversation 9.8 Bush, S.C. Chang, L.L. uheat c# "'EL aad 7.0. Vai;ht c# In discussed +he G.E. S/D Ualue analytical "Odel with DSS. V"dr4ck #al* *ba "annr+e nf Mille and chann woro nnt in anropront, hot TMFI etated they aro in conoral agroo-on+ with d4fferent donroce nf dotnil IMrt etated that a neoliminary accocc ont of Onad cities reliof valvo data did n6t <hnw enneittent radpl enneer-vatie- en-o ite-c nf nr chann'c rennet RRn 70 76 woro dicencend- n<t was ennearned that the TPIFf dnenronte wnnld ha enneidorod_ hy nther PIRC norennt. tn be final cositions on the GE models. As stated in LLW-18-76, additional model 0

_. review ~is~in n"Ograss along with data review Tho individual rannrte aro #inal

._Dut$thA "ndAl a<<pstnAnt it not final.

Vnd ri e fe connected Tflel tn enntact the i OFT ctaff and nhtain their encront nnininne nn the CF 9/P valvo mndole. and tn rennet hack tn him in one wook on this iten.

GC Amand-ont f!n.1 was briefly discussed. flRC(Suiwil.l_trytnarrpngea GF/f1Rc/INEI technical review reatinn in tha naar fotorn tn resnivo nur concerns.

/

Signed  ! ' -- Date /

cob u <l) gM

- . - ~ - - - - -

l MEM0 0F CONVERSATION L.L. Wheat May 11 1976  !

Page 2 Mr. Lainas feels the LLW-18-76 cover letter was too public (NRC ERDA, INEL only, not in public document room), and wants us to provide information to him(CSB) even more informally. Mr. Lainas wanted to know what our mile-stones were for this level of effort task, and we discussed what our plans were, as previously negotiated with Jack Kudrick. No specific milestones -

were agreed to, other than to provide level of effort to work on the BWR problems.

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v~. r~.s Dero et nucleor Compontj Interoffice Correspondence

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May 28,1976 J. H. Ramsthaler #

TSB 59 -

PEriETRATI0ti AliD SCALIliG STUDY - LLW-25-76

Reference:

(1) JIMills, "BWR Pool Penetration and Scaling Study,"

SRD-77-76, June, 1976 This '

This letter transmits Reference (1) to NRC and ERDA-ID for information.

work was completed in support of the BWR Analysis task of the I-214 program, and is a follow-up effort to a similar task documented at the end of FY-1975.

Copies cf this letter and Reference (1) are being informally sent to the following flRC and ERDA personnel:

TDKnight ZRRosztoczy PELitteneker PEllorian WLJensen tJAKudr.ick Glainas LSlegers L. L. Wheat Analytical Model Development Branch cb .

Attachments as stated cc: BABush (2)

SCChang EPEalesafuL.

WHLee LJMetcalfe JIMills (2)

WJMings RPMoore CLilalezny PHVander Hyde -

. File C2.0 9 AS