ML20086B173

AO 50-267/74-20A:on 741116,during Low Power Physics Testing, Conflict Found Between Tech Specs 4.2.11 & 4.4.1 Re Moisture Limits.Caused by Last Minute Change in Tech Specs 4.2.11. Tech Specs Revised

ML20086B173
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/09/1976
From:	Brey H, Hillyard H, Swart F PUBLIC SERVICE CO. OF COLORADO
To:	NRC
Shared Package
ML20086B175	List: ML20086B173 ML20086B178 ML20086B185
References
50-267-74-20A, AO-50-267-74-20, P-76249, NUDOCS 8311170088
Download: ML20086B173 (6)

Text

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O O assau public service company or cenende P. O. Box 361, Platteville, Colorado 80651 November 9,1976 Fort . g' U , g

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Office of Information and Program Control U. S. Nuclear Regulatory Commission

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1 s 9g78 ' 20/l g g aW Washington, D.C. 20555 -

77 Gentlemen:

(i Enclosed please find a copy of Abrormal Occurrence Report No. 50-267/74/20A, Final Supplement, and the Licensee Event Report for this abnormal occurrence.

l Sincerely, Y.,

• H. W. Hillyarf, Jr.

Technical Services Supervisor Fort St. Vrain Nuclear Generating Station HWH/alk V

cesansa P 8311170089 761109 PDR S ADOCK 05000267 .

PDR U b.OL)

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LMSUAL EVENTS AND A1W0 ictal OCCURRENCE REPORTS DISTPIBUTION Number of Copies San Francisco Operations Of fice ERDA 1333 Broadway Oakland, California 94612 Attn Manager - - - - - - - - - - - - - - - - - - - - - - - - - ,- - - - - - 2*

Califo rnia Pa tent Group - - - - - - - - - - - - - - - - - - - - - - - - 1*

Division of Reactor Development and Demonstration ERDA Washington, D.C. 20545 Attn: Director ------------------------------- 1*

Division of Nuclear Research &

Applications ERDA Washington, D.C. 20545 Attn: Actg. Asst. Dir. for Reacto r Programs - - - - - - - - - - - - - - - - - 2*

ERDA-PMRS-SAN - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - la P. O. Box 81325 San Diego, California 92138

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Add re ss +++ Director ------------------------------------ 1 Letter To EKDA-SCEPO P. O. Box 1446 Canoga Park, California 91304 ,

Technical Informerion Center -------------------------- 3*

, ERDA P. O. Box 62 Cak Ridge, Tennessee 37830 Address +++ Mr. E. Morris Howard, Director ------------------------- 1 (copy of Licensee P Letter Region IV. Event Report)

To Office of Inspection & Enforcement Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Director of Nuclear Reactor Regulation --------------------- 1 (copy of Howard's Atta Mr. Roger S. Boyd Director letter, mailogram, Division of Project Management & Licensee Event U. S. Nuclear Regulatory Commission Report)

Washington, D.C. 20555 Address +++ Of fice of Information & Program Control - - - - - - - - - - - - - - - - - - - -( Criginal of Licensee P Letter U. S. Nuclear Regulerary Commission Event Report) ,

To Washington, D.C. 20555 l Address +++ ' John M. Waage, Project Manager - - - - - - - - - - - - - - - - - - - - - - - - - 10*

FPLC Letter General Atomic Company P. O. Box 81608 To San Diego, California 92183 I

• Indicates a zerox copy of the letter to the Director, ERDA-SCEPO, is sent with the copy of the report.

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. O UCENSEE EVENT REP $

CONTROL OLOCK:l l l l l l l [PLEASE PRINT ALL REGUutEO INFORMATION) 1 6 NAME LCENSE NUMBER E TYPE O Ic lo ir I S I vl 11 I ol 01-101 o l ol ol 01-10 lo I 141111121ol Iof11 7 89 14 15 25 26 30 31 32 CATEGCHY TV AC DOCKET NUMBER EVENT CATE REPORT OATE O 1 CON'T lM lI l 7 8 57 58 59 W60 lo l5 l0 l-l 0 l 2 l 6 l 7 l 61 68 l1 l1 l1 l6 l 7 l 4 l 69 74 l 1l ll 0l ol 7l Al 75 80 I

j EVENT DESCRIPTION EE l During low power physics tests it was found that a conflict existed between two l 7 89 80 EE l Technical Specifications on moisture limits. Moisture monitors bvoassed and moisture!

7 89 80 EE l monitored to assure compliance with one Technical Specification. l 7 89 80 Bl 7 89 80 l

HG l (A0 74/20A) l 7 89 m 80 OCE COMPONENT CODE MANUF VOLATON EE l C l J l W l X l X l X l Xl Xl Xl W l Zl 9 l 9l 9l y 7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION U l One cineri f f enrinn n11 mued 5_000 PPMV mi c:enro nth er n11nued 500 nnmv nn hioh vnnon and l - ~

7 89 80 HE I 100 ppmv on low range. Technical Specifications changed to indicate dewpoint i 7 89 80

& l rennernrure. l s  % POWER OTHER STATUS O VERY DISCOVERY DESCRIPTCN 1

L8J lol ol ol I I Ld lN/A I 7 8 9 10 12 13 44 45 46 80 0 OF E E AMOUNT OF ACTIVITY LOCATCN OF RELEASE E0 7 8 9 d W 10 I N/A 11 l

44 lN/A 45 80 I

PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTON DE b lo lo l LzJ l n/A l 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER CESCAIPTON D E I ol ol ol l N/A I 7 89 11 12 80 OFFSITE CONSEQUENCES l BG l N/A l l 7 89 80 LOSS OR DAMAGE TO FACIUTY TYPE DESCRIPTON D] W 7 89 l N/A 10 80 l

PUBLICITY DE l N/A l 7 89  % 80 ADOITIONAL FACTORS 18 l N/A l 7 89 80 DE l . , 1 NAME: b PHONE: (303) 785-2253 H. W. Hillyftra, Jr. / f ePo een.eer

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RI:Poni Dirr.: __ h o v e c.tv r 9, 1976 AbGGRPal. OCCI:dd.?CE 74/20A Pp.-

1 of 3 OCCt!R!:!'.h'GC DilC: Novt mbe r i 6 I 9 7 's roi;T ST. VR/d M 'n'CLU/.': GENTFAT1:e ; tifA rI0'! -

Pin:LIC SERVICE COMi%Ui 0F COLu uiiM P. O. !:0X 361 PLATfEVILLi:, COLORADO C00.51 REPORT NO. 'i0-267/74/20.\

Fina1 Supph cwnt Iih;;J f r;CR110:: Or.

Os'Cp utr,l'. : ' :

U.t Saturday, Novenher _16,1974, durin:: tou po.mr phy :les teuttng, i t. wa.; fcund t hat a confif tt nisted betecen LC3 4.2.11 and LCO 4.4.1 of the Technical Specificatloas, ihtcau c of reactor conditionr and the need to coat.Ince t entier.,

it n: deci&d to ge eith the rmisture Linitt. m: stated in LC0 4.2. l t and disam the r.:anitors of LCu 4.4.1 cad to not.ify rnd resolve the conflict as soon as possib le wi th the : uclear Regulatory Corrd ssic:1. This would be d t. -

li.ned as an abnormal occurrence, per 2.lb of thu Techn teal'Specificaticas.

CONDLTIO::S'PhTOR TO GCD"MM:i;cr. y g, gaa t, 9 tate Pou.'r Ponei!"- Shetde'.'s llo t Shutdown Routine Load Change Cold Shutdown X Other (specify)

Refueling Shutdown Low Power llot Physics Routine Startup Tests The major plant parameters at the time of the event were as follows:

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Power RTR 10 % - 5 x 10~3% Power ELECT N/A MWe-Secondary Coolant Pressure N/A psig Temperature N/A *F Flow N/A f/hr. .

Primary Coolant Pressure 80 - 270 psig Core Inlet Temperature 110 *F-Core Outlet Tem;>erature 110 *F Flow 100,000 #/ltr.

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O Ai NtW:M. OCCup.E:.:CE 74/20.i l'i . p.e 2 oi 3 DLic Ipr!O:'

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I re , unnind Part 1 o f Start up Tent A- P. t o deternlee the ret rt ur pre unt of re.;ct ivity t;ere in p roc & . 'l h in test required ti e reactor to ; + ltical while pritrary coolant pressure was varied while nain--

talainn the .< actor critic.il by contral red noven.nt.

1.C0 4. 2. i t stared t hat belou 72 V'F core outic t tempt.rature , 5,000 ppmv mot u-t urc was allowed .in the prir.ary coolant. LCO 4./: . J Tabi c 4. 4-1, I reu 4, stater. t he ra::1..'m ne t t ings of tlw high level. imd loop celorurc ':'ni tora, 500 pen and 100 rpsv, respectively, and alao staten that thete nic no par-nis.41?+ 1e bypa:.n conditicus of the hi;)t wn; mcai w n.

The de. paint hel':t ure moni tors had b.: a e J ir. atal apparent ly d.ie to a snall anaunt of icoisture that had accumlat ed in tha mp N lines dur ta;: the long peric d cf ves,..or shutdown, cpurious: trips were 1 c Iv3 received unich ene:ed rauctuc r.crau.

Becaat. the reaeroc ter.p rat. ore was lov, nhout 130*l, cod moisture levn1 ab w r J /:0 ppm, it was perniss!'_1c to operat e f he reactor. To allw operutivn of the renetor, tha .It v point mintuce nealter outputs wn.e bypacaud and set poin':. ralued to approximat ely 5,000 ppa and 1,000 ppm on the hi>;h rt.y nnd loop imaitura, respqctively.

A note to t hin cifect uas put in the tation'J og, . along uith r. ces:nent that we would contact AEC-DOL as soon as per.,sible to cicar up the discrepancy.

This was done on Mandaf norming, November 18, 1974.

Operation of the reactor continued at powers as high as 5 x 10 % 3power.

At no time was the moisture J evel in the primary- coolant above 150 ppmv or-the temperature above 130*F.

APPARENT CAUSE OF OCCURRENCE: Design - Unusual Service Cond.

Including Environment Manufacture Component Fallure Installation /Const. X Ot he r . (speci fy) m- Operator ,

Discrepancy between tuo Tech.

Procedure Spec. LCO's, and the decision .

to continue operation tining the limits of only one.

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/.H T n.91.1 0'.CU::nt;::LE 7.',,/20fs Pa r,e 3 of 1 N,'ALYS lS (W OGCt': F.!::. ..! : .

Th t. . er.fl a t in the fet :! cal Sptcificatin w: b r ou;,h t .d.u a t i:f ,

J . : t n : nn '. c c a:a.g e a b.o '..'.Li J..t p for t.o ir, nance, i o al:e inio aciount cot d i t in:r, ac to..lly c::p :rienced durin,; t he p]:m t ha t. flo.' t es ts and t he evncern for borou carb i de n::i dat ion at' e l eva ted t erper..t u res 'i .. t he p resence o f mo f >.t u r . At

.uteq:ilte cearch of t!te Tecanical Spe ci fica t.lunn for o the r 1.CO's wh ic't r:- )

be . f fee:.ed >s apparently not .ade.

A t. n t ii c : .,, the reactor operated at poue r l eu.. ] - and t c.'pe r; f o re n t h..t couJd b..\; .![cct.d the reatt ar c: re p re.ph it.c , it.),

.r burn dle j ota'J ;; k J ;i.

t h- r.o l . ; ur. p re.* n t . l.: i:o t J:m . , L:e '

al t h r ed a ti.* Ly of t h< linblte cod a ce r. .'

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l'e , i: len ' L 3 t o t he Tort !L . Vrain Tech 71 ca] 1:p t . ' { i c . r '. l o . > revi% d 5:ce Io, 4.2.l! m T;:.h '4 .4.1 The set;.aint of the hi;;h rr. odd EM I H F D *'" D: G I ' ' t was chaut ml t o 6 7* r ar d < 2 7'F f or the J eop coIsti:re r!.uI t ers . Th i s, i h a, r, -

re: v. t!'s d ,crepene, b 2 t u t.ca T:l le 4 . 4 . ] and LCO 4.2.11.

':o Tucthti ro.rectiv; action i s anticipntcJ o r required.

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--PROGRAISLW1C IliN,C1 : -

None COD *' IMPACT:

None

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4 Subattted by:

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11. W. Ililly; rd, Jr.

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Technical Services Supervicor

.J Reviewed by: --d-TM,W b) em H. Larry Byey' Superintendent, Opera {t. ions Approved by: ,[)744- hb - k.

Frederic E. Swart Nuclear Production Ma[ ) nager t

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