ML20085D335

Comments on Verification of Valve Wall Thickness.Qa Records Do Not Include Documented Valve Wall Thickness Measurements Necessary to Obtain Measurements to Comply w/720630 Request

ML20085D335
Person / Time
Site:	Robinson
Issue date:	09/05/1972
From:	Utley E CAROLINA POWER & LIGHT CO.
To:	Jennifer Davis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20085D331	List: ML20085D335
References
NUDOCS 8307210163
Download: ML20085D335 (3)

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. , o o Carolina Power & Linhe o Company Ra!ciph. Rnh C:uelina 27t02 Septeaer 5, 1972 br. John G. Davis , Direct or Directoret' of lleruletter, Operatienc United Stutt > Atoric Enar3y Cer:is.. ion Rc",ien 11 - Suite S13 230 reacntree Stre( c, ::ar t !r. e a t Atlant a, Gecreia 30303

11. B . R o m ::30:: U::iT :;0. 2 LIC G D ri'- ? 3 .

VALV" U.il L FID CiJ:!:f ;

Daar lir. Davis:

Your letter of June 30, 1972, requerted Carolina Pe. r f Light Company verify by apprcpriate recorda th at certain valvet in..Lalled in our facilities and importt.nt to nuclear safety t eet r.luinue wall thich-ness requirer eut e of specified cd a. ny sepa: ate correspondence, the Ccepaay hcu iniicat ed beu compliance with this requent vill be carried out in new construction plc.ute. Verification of valve wall thickness prior to reactor operation is primari]; an econonic ccnnideration and re3atively straightforward to accomplish. 11c.:ever , cenplying with your request for a plant that has been in operation is a more complex undertaking.

It has been verificd that the qua'ity assurance records at II. B.

Pobinaen Unit No. 2 do not include docu=nted velve vall thichness tasasure-cents and it vill thertfere he necessary to obtain these treasurements to cc. ply with your request. There ar e 122 valvcs over 1" in the reactor cct ? ant boundary . Fifty-two of these are cast valven and ma'; be difficult to ultrasonically r.r2cqure to an accuracy 1cvel of 2%. For valves 4 inches or ens, it is estimated that an accuracy of 107, may be realistic. Of con ern to the Cmpany is the deliberate radiation exposure required to obtain valve thichness ceasurec.ents in a plant with a radiation history.

We have estimated that it may require at least 180 rea to acccrplish the inspections en all valves and assuming the plant continues to hrve faverable fuel pcriorraance. With a. failed fuel history, the total eyposure would be several orders of magnitude greater. A Technical Specifications chang,e vill be required to aceccplish valve measurements on the Rer.idual Ileat Ker. oval system. Since the Ria system must reraove decay heat in the shutdewn rmde, the valves in this cysten cannot he drained or disassembled uhen the plant is chut down under current directives.

9307210163 730410 PDR ADOCK 05000261 G PDR

- Mr . J eh u G . Davis Saptm.ber 5, 1972 Thouah recorded values of valve va ll thi chaco a in msure ; s.i' :

vere not obtained durinr, cenal ruct ion, it s%ubi im rico;>nined that thero .

i rR'aSure2?DLS vere not requirrd Lo b" decl-J ' l od kil0n the 'N IVe:. [ D i'

! H. B. Robinacn Plant ucre purchartd. The J: s' of doctmcntatioa de. not ,

confirm t hat the;e tac;urencnt, vere not L .&e n . Vendor qualit y cont rel  !

l procedure. have required that c rit wall thichen r easure:wnt F be tPhen

to ensu.e that no core shift has taken place and that the ccating confore to drauings.

I The structural integrity ef the reactor ecolant boundary ef the ,

II. B. Robinnn Plc.nt vac coafire d by a hydrectatic t ect. at 3110 pai prior

) to fueling anl operatien of the p la n t. AddJtinnally nonerou' operational  ;

t hydrontatic testr at 2350 poi hmvc becn acce.:plichcd. None of these teste  !

have indicatcd leukape in valve bo.11u, or in velds.  !

Caroline l'on or N I.Qht Comp t. , , to co ply uith your request, . i vill accemplish a valve val] thichn -

veri fi cation pregran by said-1975.

1 Recognizing that radiation expoatwes should be kept to a niuit u.i, 252, of

! the valves ot' each si ze, mwnf actu:s d by a ver lor, and of the san e rcattt ini vill be inspnted to verify vall thichness adequacy. If significant vall r

. thictucts discrepancios are found in any particular type of valve, a (

l complete inspection will be r .le, if pe'alble, o t' all valves of t hat type.

]

The ahility of the Corpany to .etemplish this i:mi:ection depends, in part, i on Technical Specification chanaen. During the first refocling, t.puilence  ;

l uill he c;ained on decc+y heat Lereration ;.nd appropriate requests n ulo to j the Ato;.

• c F.ac rt;i Cu:aircion as to an acceptable Imthod of verif yin;; th" valver in tin. LiiR .systen, t

i

'rhe Corrany intends to comply with the intent of your request but regnest: that tL Arc reassess the requirement for this inspection on operating pla.ts. Carolina Power & Light Compan-f believes that the requested innpecticn ir noc nccer. cry or varranted in that there has been no recorded

{ history of valve body failure in the nuclearITdustry, in that the plant was subjected to an initial hydreatatic test of 125% of dasign pressure, and i because the exposure level to irspection personnel vill be sizeable.

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Yours very truly, 1

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E. E. Utley Manager Eulk Power Supply NBn/za ec: Mr. C. D. Earham Mr. N. D. Bessac Mr. B. J. Furr

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