ML20214X380

Forwards Part 21 Repts,Including VEPCO ,Foxboro Co ,Smud 870210 ltr,Morrison-Knudsen Co,Inc & Isomedix .Recipient Response Not Required

ML20214X380
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/10/1987
From:	Gagliardo J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
References
REF-PT21-87-144-000 PT21-87-144, PT21-87-144-000, NUDOCS 8706160446
Download: ML20214X380 (2)

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1In ReplyjRefer To:- ~ _

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' Docket: .50-267

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ATTN: Robert 0. Williams, Jr. .

Vice President, Nuclear Operations. ..,

'P. 0. Box 840.

Denver-ColoradoL 80201-0840 e Gentlemen: -

This forwards, for ~your information, reports recently received by the Comission

, under-the reporting requirements of 10.CFR Part 21..

Although no response is required 1to this letter, we shall be pleased to answer I

m any questions which_you may have regarding this matter.

Sincerely, i

Ognd signed Dy

3. E. Gagliardo J. E. Gagliardo, Chief.

Reactor _ Projects Branch Attachments: .

1. Virginia Electric and : Power Company' letter -

. dated January 28, 1987- ,

l

'2. . The Foxboro _ Company letter dated February 17, 1987- ~

3.s SMUD letter dated February 10, 1987 .

L 14. Morrison-Knudsen Company, Inc. letter dated I

~ January 13,;1987 .

5.. ISOMEDIX letter dated March 30, 1987 cc w/ attachments:-

Manager, Nuclear Production Division

~~

Fort St.'Vrain Nuclear. Station 16805.WCR 191'

'Platteville,-Colorado 80651 1 P. Tomlinson, Manager, Quality. '

l Assurance Division (sameaddress)J Colorado Radiation Control Program Director LColorado Public Utilities Comission PI'4M .C:RPy C:RP8 JEGacjl prdo g

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bcctoDMB(IE01) bec distrib. by RIV: ^

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R. D. Martin,'RA SectionChief(RPB/A). RSB SectionChief(RSB/ES) Project Inspector, RPB' RPSB- - D. Weiss, RM/ALF

-MIS System R. Hall-RSTS Operator NRR Project Manager

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... Attachment'1 VIROINIA ELECTRIC AND POWEN COMPANY HICHMOND,YlitGINIA 23261

.W.L.SrsWART *' ., 2 P3:ii vn. v.......,

wscm...o.. no.. January 28, 1987 Dr. J. Nelson Grace Serial No. 86-753A

- Regional Administrator N0/RCB:dak Region II Docket Nos. 50-338 U. S. Nuclear Regulatory Commission 50-339 Suite 2900. License Nos. NPF-4 101 Marietta Street, N.W. NPF-7 Atlanta, GA 30323

Dear Dr. Grace:

VIRCINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 NEW SERVICE WATER SPRAY SUPPORT SYSTEM POLLOW UP REPORT On November 12, 1986 Virginia Electric and Power Company reported a potential defect involving a substantial safety hazard at North Anna Power Station Units 1 and 2 in accordance with 10 CFR 21 (Serial No.86-753). In that report, we committed to ultrasonic testing of suspect materials and development of a repair / replacement plan.

Ultrasonic testing of the suspect materials has been completed, and the results have been documented in a Non-Conformance Report. Twenty-one steel columns supplied by Rockwell Engineering Company were found to have laminations in the web. Eight of the defective columns were never installed and will not be used in the spray' array support structure. An action plan for replacing the remaining thirteen defective columns has been developed -and is summarized below:

Defective columns will be replaced one at a time by removing the column and the attached footing, temporarily supporting connecting members and piping, installing replacement column and footing, and reattaching connecting members and piping.

The replacement plan for each defective column will be reviewed to ensure that injurious stresses are not imparted to adjacent components during the repair process.

Current plans are to replace defective columns prior to placing the new spray array system into operation.

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• Should you require further information, please contact me.

Very truly yours, I'

, c~ .

W. L. Stewart p

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• Attachment 2 4

Foxboro. MA, U.SA 02035 The Foxboro Comnanv s- - a ' * * " *

• Telex 927-6o2 17 February 1987 United States Nuclear Regulatory Commission Office of Inspection and Enforcement ,

Washington, DC 20555 Attention: Director, Office cf Inspection and Enforcement

Subject:

Potential Defect SPEC 200 Current-to-Voltage Cards 2AI-12V and 2AI-I3V

~

~

Please refer to the attached letter sent to nuclear users.

We do not believe printed wiring as'semblies are stored in, unusual,above specification, high humidity conditions in.the nuclear plant. If the off-normal storage condition exists, corrective action has been identified in 'the attached notification. .

Very truly yours, THE FOXBORO COMPANY M l. F h m Michael J. Berberian, D100/N04-2B Hanager, Corporate Quality Assurance Pjb B M O450 EF70217 PDR 87 PT21 ENVFOXB h' d j PDR h*

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7

~O High Moisture Effects on Spec 200 Current-to-Voltage Cards 17 February 1987 Page 2 If these conditions exist, it is recommended that these capacitors be replaced with Part Number H0110BN.

If additional assistance is required, please contact either of the following individuals:

James T. Kaiper, D872/B52-2K, at (617) 549-6332 or Dana A. Hambleton, D137/N04-25, at (617) 549-3889 at The Foxboro Company -

Foxboro, MA 02035 Very truly yours, THE FOKBORO COMPANY

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Michael J. Berberian, D100/N04-25 Manager, Cotsorate Quality Assurance ~

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17 February 1987 Attention:

Dear Esferences

Subject:

High Moisture Effects on Spec 200 Current-to-Voltage Cards, 2AI-I2V and 2AI-I3V, During Long-Tern Storage This letter is to provide advisory notification of an off-normal condition of Spec 200 cards stored in an environment of high moisture without power applied. We believe this kind of environment for storage (in excess of 400C and 95% EE or condensing moisture) yould be very unusual in your nuclear plant._

h above current-to-voltage cards as unpowered shelf spares can exhibit erratic output operation and insufficient span adjustment when put into

• service.

N high moisture allows excessive leakage in a monolithic cerante capacitor manufactured by AVE and these were used in the Spec 200 current-to-voltage cards up to August 1983.

h capacitors are easily identified. Their location is shown in Spec 200 MT 2AI-140 Page 10 and 11, and are identified as C1, C3, C6, and C7. The suspect capacitor manufactured by AVI has a bright blue case and the letter A or AYZ aarked in black.

N conditions for this erratic operation are:

1. Unusual high humidity in storage area 2.- Data code prior to August 1983 *

3. Bright blue capacitors marked with AVI identifier 4

Attachment 3 4

Qsuun  %"

SACRAMENTO MUNICIPAL. UT1uTV DISTRICT C PQ'It Box 16830. Sacramento CA 95852-1830,(916) 452 3211 AWEftdrfl,C SgSTEM SERVING THE HEART OF CALIFORNIA February 10, 1987 dl0:jS JEW 87-119 "//4 :

J. 8. Martin, Regional Administrator Region V Office of Inspection and Enforcement Attn: Document Control Desk U. S. Nuclear Regulatory Comission -

1450 Maria Lane, Suite 210 Walnut Creek, CA 94596 DOCKET NO. 50-312 Rancho Seco Nuclear Generating Station Unit #1 License No. DPR-54 10 CFR 21 REPORT, LIMITORQUE GEARED LIMIT SWITCH ROTORS WARPED

Dear Mr. Martin:

In accordance with 10 CFR 21.21(b)(2), the Sacramento Municipal Utility District hereby submits a written report documenting the notification made by *

• Mr. C. Stephenson of the District to Mr. L. Miller of Region V Nuclear Regulatory Comission (NRC) on February 5,1987 concerning warped geared limit switch rotors supplied by Limitorque Corp., Lynchburg, Virginia.

During the motor operated valve (MOV) refurbishment program initiated by IE Bulletin 85-03, seven (7) out of a group of fifty (50) F1brite (brown color) geared limit switch rotors were discovered to be warped sufficiently to prevent limit switch adjustments. The warped F1brite geared limit switch rotor was detected on January 16, 1987 during the replacement of a rotor on the limit switch gear box. Electrical maintenance personnel installed a new Fibrite rotor onto a limit switch gear box and proceeded to rotate the limit switch rotor with a drill motor during bench testing to ensure engagement of the gears. They observed that the rotor was not making contact with the

" fingers" due to an axial bend in the rotor.

The entire shipment of fifty (50) Fibrite limit switch rotors was checked for warpage. Seven (7) of the fifty (50) were warped severely enough to prevent limit switch adjustments. The shipment was purchased under Purchase Order No. RS 90625.

An internal Occurrence Description Report was initiated on January 16, 1987 requesting the Plant Review Comittee (PRC) to review the warped rotors for possible 10 CFR 21 reportability. On February 3,1987 the PRC recomended that a 10 CFR 21 Report be submitted to the NRC pursuant to 10 CFR 21.4(d)(1).

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RANCHO SECO NUCLEAR GENERATING STATION C 14440 Twm Cities Road, Herald, CA 95638 9799;(209) 333 2935

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Mr. Martin February 10, 1987 District maintenance procedures were in place, prior to the discovery of the -

warped rotors, that prevented the installation of a defective component into i an operating system.

The District considers Limitorque Corporation to be better qualified to provide the NRC an itemization of those facilities which may be affacted by this defect.

If there are any questions concerning this report, please contact Mr. Ron W. Colombo at Rancho Seco Nuclear Generating Station.

Sincerely, ,

l

( k Jo n E. Ward Deputy General Manager, Nuclear cc: Director I&E

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. CONTRACTORS ENGINEERS DEVELOPERS MORRISON-KNUDSEN COMPANY, INC.

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January 13, 1987 Mr. James Taylor USNRC 1717 H Street Washington, D.C. 20555

Dear Mr. Taylor:

Enclosed is supporting documentation concerning a reportable 10CFR, Part 21, condition from our subsidiary, Power Systems Division in Rocky Mount, North -

Carolina.

We will forward further information as it becomes available. You may call meat (208)386-5365 if you desire any further information concerning this subject.

Very truly yours,

.b. b R. D. Kulchak Manager-Quality Assurance RDK/gs Encl.

cc: H. Falter (w/attachs.)

F. Jones K. Sowder ll1 834?s 87

-il#dinx PDR M' f

i CZEATORS OF ELECTRICAL

) POWER SUPPLY SYSTEMS URGENT yECOW SENT:

'PDWER SYST,EM.S a- - r - wesene eo P];.EAS5 ;)ERRTIh IMMEDIA'.'ELY REC *D.:

5 lL '

i DATE: -

n'o'ei'IEE@U.ESE*.f"ng,*

@ / @ , N M lo" " " * *

• TIME-

% DATE:

January 12, 1987 TELECOPY Morrison-Knudsen Company, Inc.- l COMPANY:

ADDRESS:

CITY & STATE:

Ron Kulchak (Quality)

ATTENTION:

REFERENCE:

Reportable Defect Report 10CFR21-0033 TELECOPY NO.:

MESSAGE Please refer to attached memo and report concernine Square D Relays.

FROM:

Marry W. Falter, Principal Engineer _

povven sysitMs A wonnisoN44UD84N DM81oM f81 PAGES, INCLUDING THE COVER SHEET.

, TRANSMITTED HEREWITH ARE_

IF YOU DO NOT RECEIVE ALL PAGES LISTED, PLEASE CALL (919) 977 2720, * '

t EXTENSION

- NOS,210 CR 212 FOR VERIFlQATION,KCB

.J'N $ m3GmH45!aa0W 6C.9126, 21 F#f A.

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• S/N M-E-0-0004 MORRISON-KNUDSEN COMPANY, INC. -

IN?rm.orrice cometemoNogNet e4n. January 12,'1987 Ron Kulchak "'"' Harry W. Falter

• '""' Boise *NI> Rocky Mount, NC

" * C-2726 MK/PSD Memo 5/N M-E-0001 (1/5/87)

Reportable Defect Report 10CFR21-0033 I have reviewed the Square D Company report attached to MK/PSD Report 10CFR21-0033, and I conclude that the defect is reportable.

Review my report and if you agree, notify the NRC within the required time period in accordance with the QAM. -

Please acknowledge' receipt of this transmittal and advise your action. ,

HWF/voa

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Ae 2*d *D'N DJ A>CM H33DDHCSIsrg GE:9143, 2T Wf

1 02ftftl SON-KNUDSEN C$MPANY,INC.

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REPORT 10CFR21-0033 January 12, 1987 Reportable 10CFR-21

_ COMPONENT: Square D Company General Purpose Relay Class 8501 Type KPD-13 130 VDC Service APPLICATION: Control circuits for diesel generators used as emergency power supplies for Nuclear Power

• Plants furnished by Bruce GM Diesel, Inc. or Power Systems Division of Morrison-Knudsen company, Inc.

DEFECT: In an application, the 130 VDC relay was This energized for a long period of time.

~ - period is estimated to be approximately 10 years. When the relay was de-energized, it failed to drop out and remained in its energized state.

CAUSE: Square D Company conducted tests which iden-tified residual magnetism to be the cause.

The probable cause of the residual magnetism was probably due to the DC device being constantly energized for such a long period.

DISCUSSION

Bruce GM Diesel and Power Systems Division ,

used normally energised relays to monitor individual fuses in the control system.

Should a fuse fail, its relay would drop l

out and activate an alarm.

There were a few instances where the emer-l gency start relay was contractually speci-fled to be in its normally energised state j

where the relay would complete the emergency start signal when it dropped out.

l If a fuse blew in a critical circuit, a relay held in by residual magnetism would fail to send the signal to the alarm which was meant to alert an operator of the fuse failure with l

the result that the circuit would not func-tion when called upon. Likewise, if the

relay in the start circuit were to hang up due to residual magnetism, the start signal would not be. transmitted to the circuitry.

Ed *3 N m AG N3SQfM-NOSIdb.N OP t9148. 2I Wf I

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=usemse COMPANY,INCo e

REPORT 10CFR21-0033 January 12, 1987 Page Two u.

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CORRECTIVE ACTION: J >

6 There is no specific test documentation to '

1 provide the exact length of time beforeIt is residual magnetism becomes a factor. j4 recommended that the normally energized f relays be inspected or replaced during every 1 fuel outage. Inspection should be documented 3 and maintained to determine the length of time . residual magnetism becomes a factor. ,

Replacement with the Square D Class 8501, {

type XUD does not appear feasible because of physical differences that require consider-able redesign.

~

CONCLUSION:

The defect is determined to be reportable on the basis that if a blown fuse is not alarmed, the operator would not be alerted and criticalAlso, control in the circuit couldwhere few cases be the isolsted.

relay is normally energized for the emergency start signal, it would not transmit ~the start signal if residual magnetism kept the relay energized. The diesel generator, therefore, would fail to perform its safety function.

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l ' N3 Harry W. Falter, P.E.

N.C. License No. - 7022 gj'g

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!' ATTACMMENTS:

I Square D Letter January 7, 1987 Square D Letter September 19, 1986 l December 31, 1986 TVA Letter Relay Comparison i

'3*H 1W A>OM N35".THM-NOSIE80W IN9T 40, 2T N0f P*d

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suunneD CORAPRNY 28C1mp*m ansaggezeg Tgs m.-, gm ytesse esten am de remommmed tant my seasy that has hmme to een for Sten years or

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3 anger he tempmated er soplaced. En de amt haue aguestfie test Sudemumalan te preytan aten amert length of time batese meelemal magmattam emy numeme a fester.

Etimeofeme. un slee sememumund a pausly temportten en any of 40 mum relays must that e ete-ess sees P.e. een een aseseausse,esecomese esteso euroses he maletalemst te datamedum tem lengtje of stas res&dman imagnustnen "

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nurseme pe.mamme cum Fre& art Symetallet j ' r - Faer Systems Dieteten l P.O. Amu 1928 g,y,

< mecky nomma sc 27eet 0" '

Atta Mr. at. Stas - menhentag Bayetemmt ,

eci s. ement - stemmehame anw ar. sims: s. A. senrhan - sette..ss d am Jammary 5. yee ===*=rt.d am seemadame ese casse aset Type sys.t3 seneret pure Baseys. Year Segmary one to emoords to a sement mette estled to pose ettemeten by j earteus costamere regardlag a prow estAf tentles relemme em the part of the F- Smelser Smgetatory commteams.

E The amatiteetten metWly ledgestas a puentSal restemmt mayestiam probium witte

l ese relays.

O' l As you % sy in ear giumme . -- m* Mme Antial Sagnery sus enda se them

{ yest of the Tse)ma emclear rimmt user amater, erogen. The - v eletame tInst 4

(n the relay taajed to .tae cham emmtuel puume som sammeed f reus the cott.

1 ca l M After tematas testa, en 444 emmelade that the faiteme aus prutably the sesnit of I D resthI augmotsam af etw seley meter ammmatty. The wasSemet angeotim roamitad J tres the fact thsc the ac tomtr.: ret.y .se omrismu.tr muusism sus duusr 1m G YtaEB.

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y h allee yes to sempened to your customer tagssefoe. I am preradias esples of a l a gf euwer latter and team test reselts feromedad AA resysema to the Tregan enclear Plant j { ' %'entr7' w It should he ested that these relays are *Did ter *mummertal umme end ese est ,

} eportitcally domigand for amelmar plant agpIfaatte%.

W d of ter resteeW the etterhed 3etters, **-+d4 yte hues any addlegemet asumettama.

• planen tauntmet me and I et11 preende tan emmeseery lateruuttee.

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Dejan aselaar Plant sme September 19. 1986 thus (1) Game 85et Type RFD.33; 13e 15C; relay edten este ende '8B" (W

, PCElfrolamIhmalaer Flamt 1Tf2) une retarumd Itur ewelustama. Due retare darles time me earles i 78700 Columbia Blver M . $dreutif1catten stangdag.

Bets 6er. M 17868 , pg es== date receload edtle tieto tlhmemer cumplateL is as foDenses mem M tse amandes A. System voltage ens 15 vuc.

! S MIStys CIASS SSSI TTFE E73-83 1 5. Beglee umm lestaned la 19P6.

! Samr Italta

. C. Opit tas enervland ammtimelly. Dettee tem used as name type of e I

thse letter amm,tems any emmouremelan of Septemhee 18 emeerness the abuse amfoty devlee.

] y smt) met. Earlier this ymer. you ammt a Class B191 Type t99-83 relay to my j . estanties for tempmetten and tastems. Seu endtemted that a pewblaim had D. Sevice tem hollowes to home ftsted is the e3mmad peseticus. Failure

. Z es.mtered with am+ erat samatar dewseum at ymer plant. deartstim "tievise fatless to esp sma*.

E. Smytee tue used la e aseleur puser plant.

.It mune d ,e must a to e.,, ear S,agh.mmering . t t.et ,e W

, -Am rorAmtmet.tle.e.

e - cc. . IE:

ts.forihm, men,tym.im.

.m. m. m i 1 mmenettua se the relay mater ammmmhty aktet ens prehmbly one am the BC derten 1he emelse uma flrat esmesented as that it emm1d he reput_Itseely emergiset and

esmetmetty emeestemd. , eWand ammumily. De dueSce ihmerttemed preparty adthed fallere.

I Z The Class SSDS Type E73-l3 relays sure ymrediamme as mammmette&ly smettable Rest, the duties imho ammt$Emdly emer$ISud $$ t03 Sm$ tutti)e Ehg$sgegr$sg && jhr tsJ prederts. Ihmic pmefammmmmme le r=t=*=a to tem asylicasiem to obsede tasy ame a parand of 72 kamrs tdth a 3end er IN VDC. (gers attertumf le repart) at

$, samtalled. the end of the 72 tummre, the relar pmuur amaree emu 9 dt=% ems the destee j'

failed to alrep nat. of the mareally eta ==a ymmittaut. 1 hts emmfaround the It le seemummmend that any otsalar velope he seplaced as emme as ymmettete. ensmesmer sumqstatst, of "tereise ralled to drop sun". (aef: D st setoisr  % 1)

. Same canelderettam =h==td mise ha 34ses to sogending the 5este!!atten. if I passible. untag sur Clasm $305 TWm 3RD ettlity moeillery relay assiedi is ames I molted to mattity plemt applientlemum.

. e-. theatenten 2 bootse M .

h Due th41ere deserthed la this Omstamar theytetut is preteely taur remmAt of

- p 3 opesar r-maa n -mymmata= ef the relay amter enemmhly. Sm. restesal massettam p, prehmanly ressaltad one to the BC relay hetas W=*17 emerglame la the y . seruelty elosed posities.

ummmeme, arter a Tamar smetta=

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1he eurtener atuunste he lefhruund tinat. K destems are eum pnute tie teams W 31. 19e6 / j j

sagsmettred due to their isesresa essee fers. It is suggestad teint the ensstamur p ar*M*9 Wg enestese mal. meca yem

.eten.1 1. .a an ac rela.y se tants asplasmassn.eeim. w t.eset.better

., -u.-.-l a susnette 4. .er systems d e . sie.

eense the returand deelre ene mandactasred it is probable that resiakset w e i. i m .rrisee.

poet efflea ses 3928 p

magertise sepaa esat be as mess of a prutale se la older deshces. gecty asent. Berth Carolles 2 Feet-19Fs (A

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etteet teet Mr. Sorry Falter Goetjemen:

k m fggy 'sers maa ytag j Smytamher 25, 1906 sagestass ammenmaa psame iam saa munrsass etasr StanEBr SIEEEt'SESSS1W 6

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FSS ftsu: Me. 379. gem. 396 1AffSt 30. 429-6F7 l gmasse e

! Frelen Busloor Plant too diseseerad a sguere 9. elene 8541. type syD-13 relay h#-

le their elemet generater esseret pene3e nelch failed to drep est es lees of j restrol peuer. aselpole by Steere 3 Identified the root cease es realesel

! y amenetime et the relay ester essendaar des to the relay telet constantly

! ,X . esersleed le e serumsty c3eese yeeltles. The r_- ^ ^ cerewettse settes j

d lectoded reptocemmet et steller duty rotere es a gerledit boele er a redesige

- of the etremite lose 3ead.

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A meerren of the teettettles anommae for the 14E diesel sammretare reeseled l that ttle type af relay le Sammted le the diesel generster eemtret pomana et j tRatte Der eme Segmogeh. Semese 9 seleys are slee stilland to tan promes yerry j diesen me.or.ter emet,.l., tot te. eso.t ty,. e.mu n.t h. estaui.ned.

I At Frejas. theos meseally emersleet retage are emme to proelde Rose af esseret U1

• paume e3eres.

j E q Fleese toelar ethee mattar oms datasedes its espaleeMilty to our dSemet p

g generatere and meet eervestjes artiene, it emy. utente he taken. thle lies steeld slee he eestestae e4th respect to IGWR , Port 21.

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! 'I . Sep gmoottees se able muttar shoeld be direeted to 51. 5. Eletter et

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INDUSTRIAL CONTROL RELAYS .600 VolJ ,

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' J. 4. I and 12 pole,vermone, with up to 12 poles sonnally opeo er n.o. n c. w rem einsed.

2. Nominal 12SV de cot, capable of handitag 140V de coednuously ,

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3. Enclosed device capable of operating in 145'F ambent ,I t! H

. The Type X Utility Ausillary Raley is ides! for nuclear and Ibstil. .

fueled utility plant applicadons where ferable perfonnance, a pure l .

?,e xupo.tsee de power plant, and up to 12 usable poles are required. ,

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Attachment 5

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March 30, 1987 Mr. Gary G. Zech, Chief Vendor Program Branch Office of Inspection and Enforcement '

U.S. Nuclear Regulatory Comission Washington, D.C. 20555

Dear Mr. Zech:

As you may know, Isomedix provides gamma radiation services related to the qualification of nuclear reactor safety-related equipment. During the past few months, the nuclear equipment qualification program af Isomedix has been under close review by both our customers (equipment manufacturers and test labs) and utility end users. The scope of this review has included our past and present operating procedures and controls as well as current and historical test records. Based upon our review and the recommendations of our customers, we have instituted some changes to operating procedures and documentation methods.

One item which was noted concerns the measurement tolerance associated with t'.c r dose and dose rate values certified by Isomedix on our test reports. Dur-ing a period of the late 1970's, a value of 3% was stated as the accuracy of the dose measurement. This value was based upon literature published regard-ing the Harwell Red 4034 Perspex dosimeter, the system primarily used to moni-tor these irradiations. However, the reporting of this tolerance value ceased by the early 1980's, and from that time until recently our test reports have not stated a value for the measurement tolerance associated with reported dose or dose rate values.

More recently, our Technical Department studied the Harwell Red 4034 dosimetry system and estimated the tolerance associated with this system to be 8% (4%

precision, 4% bias) at the 95% confidence level. This value has been stated in our Standard Dosimetry Procedures since 1984, and is currently being quoted to customers when we are requested to bid on a job as well as listed on cur-rent test reports. However, the magnitude of this value has become a cause of concern to one of our customers and is the reason that this report is written.

Our survey of previous test records included the test files of the Automatic Switch Company of Florham Park, NJ. This customer has used our radiation ser-vices for three equipment qualification testing programs involving solenoid valves and three involving pressure / temperature switches. Our evaluation of test data for these programs was reported to ASCO, and they have requested that we report our findings to your agency under 10CFR21. Their concerns are as follows:

r 870330

• PT21 EMVI R ISOMEDIX INC. }O CORPORA TE OFF/CES 11 APOLLO DRIVE. WH!PPANY. NEW JERSEY 07931 = (201) 887-4700 FAX 887-1476 . TELEX 317361

. . i Mr. Gary G. Zech March 30, 1987 l 2

1) ThattheminimumdosesstatedinthetestreportsforASCOtistscannotbe assured due to the negative measurement tolerance associated wit 5 each dose measurement.- ~

~ 2) That the maximum dose rates stated in the test reports cannot be assured due to the positive measurement tolerance associated with each measurement.

' Note: ASCO also voiced concerns regarding dose rate uniformity, test sample temperature, and test records. These subjects were listed by Mr. Steve Alexander of your staff during his April,1985 inspection, and were addressed in our response dated June 26, 1985. The tests in question were performed ~

between 1978 and 1984, and as such do not reflect the program revisions which were instituted in response to the 1985 E.Q. inspection.

With respect to the question of tolerance for dose and dose rate measurements, our report to ASCO listed a value of i 2% for the associated time measure-

. ments, based strictly upon the test tolerance for calibration of timers. Fol-lowing the issuance of this report, a review of calibration records for the past 5 years was perfomed for the timers in question. These records show-that, in fact, the % error associated with these timer measurements has aver-aged less than 0.7L Based upon this result, the total tolerance associated with Isomedix dose rate measurements (dose / time) is estimated to be i 8.6%,

while the tolerance associated with total dose measurements (dose rate x time) is estimated to be i 9.6%.

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During the time of the April 1985 E.Q. inspection, the" subfect of test tolerance was discussed with Mr. Alexander. Based upon our conversations at that time, it was our understanding that the 10% margins applied to test doses, as prescribed by IEEE 323, were designed to compensate for errors asso-ciated with the measurement process. As the inspection report shows, this subject was not listed as a deficiency or even a comment by the inspector.

For this reasen we had not taken action with regard to specifying measurement tolerances.in our reports. Since our estimate of total dose tolerance is within i 10%, it is our belief that the test requirements for minimum dose have been met.

In the case of the dose rate measurements, the tolerance must be considered in regard to dose. rate limitations imposed by the purchase order. The ASCO tests l were typically performed at dose rates well below the purchase order limita-l- tions, so that a potential increase of s 10% will not cause a deviation. .In one case, however, test records show a dose rate of 3.97 Mrads/ hour, whereas the P.O. states the rate.to be below 4 Mrads/ hour. There most certainly have been other instances where the test dose rate was within 10% of the specified 7 maximum value, and in these cases the potential exists for deviations from specifications. The degree of deviation would not exceed 10%, however, so the effect of this upon a qualification test is likely not significant. As stated above, this report is sent at the request of our customer, due to their con-cerns over the qualification status of their products. While we do not feel that the situation is critical, we wish to bring these facts to the attention of NRC in order to receive a determination from you regarding them.

IscweaDIX INC.

C0D04ATTOFFICEs e 11 APOLLO DNVE. WHtPPANY NEW JERSEY 07M1 e G01) m7400

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Mr. Gary G. Zech March 30, 1987 l

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Obviously, any effects upon the ASCO tests will also affect test ( performed for other customers, since the same systems were used to performithe work. We would therefore appreciate hearing from you regarding this matter in order to 1 guide our planning in this area and to assist our customers whose projects may be affected.

Sincerely yours,.

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ISOMEDIX INC.

WM./

Steven R. Thompson W^- _

Quality Assurance Manager SRT:js cc: G. Dietz ,

W. Owens J. Young L. Olsen, ASCO m

l l soumDIX INC.

CORPORAFE#FCEs e 11 APOLLO DANE. WHiPPANY. NEW JERSEY 07N1 * (201) M74700

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