ML19326B729

Forwards Pages 4,4a & Exhibit I as Addendum I to Valve Wall Thickness Verification Program Forwarded in Util 731207 Ltr. Provides Addl Info on Core Flood Valves CV-2415 & CV-2419

ML19326B729
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/01/1974
From:	Phillips J ARKANSAS POWER & LIGHT CO.
To:	Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19326B720	List: ML19326B719 ML19326B727 ML19326B729 ML19326B732 ML19326B737
References
NUDOCS 8004170561
Download: ML19326B729 (5)

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A R K A N S A S P O W E R & LI G H T C O f.1 r. A N Y STM AVENUE AF 0 PINE STACET

• PINE BLUFF. AAKANGAS 71601 e (5013 534-1330 February 1,1974 i

Mr. Norman C. Mmeley, Director Directorate of Regulatory Operatione Region II United States Atomic Ene 3y Commission 230 Peachtree Street, N.tl. - Suite 818 -

Atlanta, Georgia 30303 L

Subject:

Arkansar: i over & Light Compan; Arkansas Nuclear One - Unit 1 '

, Docket No. 50-313 Valve Wr.11 Thickness Verification

• Addendun 1

Dear Mr. Moseley:

3 Enclosed c.re two (2) copies each of pages 4, 4a, and Exhibit I which we -

submit as Addendum 1 to our Valve Wall Thickness Verification Program, j forwarded to you by our letter of December 7,1973. It is necessary to

make this addendum to provide additional information on Core F1ced Valves CV-2415 and CV-2419.

Very truly yours, ,

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[( ,.l u t ' y '.T.)

J. D. PHILLI?3 Senior Vice President JDP: NAM:mb l

Enclosures as noted l l

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i C Nc i4 e  :* TAX P AYING. INVESTOR OWNED 3 MEMUS A MICOLE SOUTH UTILITIES SYSTEM

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indicated on the contour dravings. All the valves'were evaluated in accordance with the Codes and the required tm .

listed on the large valves list (Exhibit I). The results l I

of the measurements are shown on the ND Inspt tion Reports (Exhibit IV).

! l valves DH-14 A, B, and CF-1A, B have 12" bodies with reducers j

i welded on eithr* end to suit 14" diameter pipe. The connections for all Nucicar Class I valves and reducers wer. anal.=ed and the analysis shows that there connections rect theErequire-  !

j monts of ANSI B31-7 Code.

J Valve body c n:.sur at weld ends is in accordance with ANSI B 16.5. The only thic, knees restriction relate.. to the 1-1/2 t (t n nominalpipewa'llthicknes7) distance used in describing the weld en'd geometry is that the wall thickncss of the valve should not be'less than 1.15 t at this point. ,

This is per letters from ANSI Standards Committee B16 to Velan Engineering  ;

Ltd. dated June 30, 1971 and February 3, 1972. (See Exhibit VIII). The measured t'm (valve body wall at a distance of.

1-1/2 t from end of the valve) was therefore compared to,a ,

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value equal to 1.15 -(where t = nom. wall of connecting pipe) . , ,

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,h The piping upstream of valves CV-2415 and CV-2419 has been J, designed at 700 psig and-300*F, whereas the downstrear side is' designed'to 2500 psig and 300*F. We have s'hown both I these conditions'and the required t ,on Exhibit I. ~,

ADDENDUM 1

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l l The' pressurizer ' safety. valve, PSV-1000, which is an cicetruantic relief l F  :

valve', manufactured by Dresser, was measured in suspect areas wherever  !

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_ possibic. There was one particular area shown on the Vendor's drawing, j l where it was found that there could be an encroachment on minimum wall, i

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- that was not measured, as it was not possible to get a reading l l

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li ADDENDUM 1  ;!

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. EXilIRIT I ,

ADDENDUM 1 LARGE VALVE LIST Des. Des.

Press Tt .p Reqd 9ty Size Type Valve No. System Psig. *F Code (1) tm 2, 14" Check DilV 14A, B Decay lleat Removal 2500 650 ASME N.P&V 2.10" 2 14" Check CF 1A, B Core Flooding 2500 300 1. 5 0" (2) 12" "

2 Check DilV 13A, B Decay IIeat Removal 2500 300 1. 4 6 " (2) 1 10" Gate CV-1400 Decay IIeat Removal 2500 650 ANSI B31.7 1.719"

& B 16.5 1 10" Gate CV-1401 Decay lleat Removal. 2500 300 1.719" 1 12" Gate CV-1050 Decay IIcat Removal 2500 650 2.000" 12" "

l Cate CV-1410 Decay Heat Removal 2500 300 1.330" (3)

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14" Cate C'l-2415, CV-2419

')* 700 300 0.542" (3) 32 Core Flooding ((I; Outlet)2500 300 "

1.431" (3) 2 3" x 6" Relief PSV1001, PSV-10.02 R. C. System 2500 670 ASME Sec III, '68 0.625 f & ANSI B 16.5 l' 21" s x 3" Belief PSV 1000 R. C. System. 2500 670 0.500" 2 8" s, heck DH-17, Dil-18 Decay 1: cat Removal . 2500 650 ASME Sec ,III, '71 1,41" (1) Codes:

ASME N.P. & V - Draft ASME Code for Pumps and Valves for Nuclear Service ASME Sec. III, '68 - ASME P & V Code,Section III, 1968 Edition ASME Sec. III, '71 - ASME P & V Code,Section III, 1971 Edition

. ANSI P31.7 - Nuclear Power Piping Code ANSI 5.5 , Steel Pipe Flanges and Flanged Fittings (2) iNon-Standard Rating- See para. II 5 of the Program -

I Per MSS-SP-66 Requirements

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! Letter from Arkansas Pow-: and Light company, J. D. Phillips, FEB 3 31974  !

i dated February 1, 1974 -

50-313 t

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