ML20086B178

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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 to Tech Specs 4.2.11. Tech Specs Revised
ML20086B178
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 11/09/1976
From: Swart F
PUBLIC SERVICE CO. OF COLORADO
To: Howard E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20086B175 List:
References
50-267-74-20A, AO-50-267-74-20, P-76248, NUDOCS 8311170090
Download: ML20086B178 (5)


Text

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Q O h&EUau>u public service company oe conorado P. O. Box 361, Platteville, Colorado 80651

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l November 9, 1976 Q.W,sggo,,_, Fort St. Vrain

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Mr. E. Morris Howard, Director Nuclear Regulatory Commission Region IV Office of Inspection and Enforcement Suite 1000 Arlington, Texas 76012 REF: Facility Operating License No. DPR-34 Docket No. 50-267

Dear Mr. Howard:

Enclosed plear,e find a copy of Abnormal Occurrence Report No. 50-267/

74/20A, Final Supplement, submitted per the requirements of the Tech-nical Specifications.

Also, please find enclosed one copy of the Licensee Event Report for Abnormal Occurrence Report No. 50-267/74/20A.

A Very truly yours, y - '4Y Frederic E. Swart Nuclear Production Manager FES/alk cc: Mr. Roger S. Boyd  % <-- %

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! 8311170090 761109 l PDR ADOCK 05000267 l S PDR l',1,bbO l

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i:t: ot T DAtr: ho .v mber 4, 1976 An! 01;'. i!. OCCUlu:Cr:ct 7'i/20 s.

p:rge 1 of 3 l a

OLCUwe.t.'CE IW1 E. Eommber 16 197'-

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i rui:T ST. VRAl'! !!UCD:/ " Gi !r.HATI::G STATIO :

PUliiJC SI:!fi ICS CO;D i:;Y OF col.OHalM

P. O. h05 3;>l Pl.AfTEVILLE, COLot3DO 80651 i

i REPO;.f ;;0 50-267/74/20.i i

1 Final Supple.,ent j

1Dr.NIlriCAT10;I UF CCannI;ct :

On Svturday, ro"e.mber 16, 1974, during leu power phyn i c.s testin;, i t v:ri found th::t a emiflict enis ted 1 e taean LCO 4. 2. 31 and *.C0 4. 4.1 of I he Techn i c.>l

] Specifications. IWeeuse of r.:act:>r conr:Itions niid the und to continu" t esting,

! it una decided to ;;o with the coisture limits os u hi t e d .i n 1.00 4. 2.11 and d is:tre the n mi t ms of LCO 's.4.1 cnd to notify and resolve t he confilet .nc soon as por:ible with the !:uelcar R :;ulatory Cemd:,:i.on. This vonld be dr-fined as au chnarical occurrence, per 2.lb of the Te chr.ical 1 pacificat iva...

i f.0"D*T10::S PRIOt;

'10 OCCU;mF.XCC-i X St e:rd.v Stalw P oer. --._Rwtina S!.etde ' '

llot Shutdrwn _ _ Routine Load Change

, Cold Shutdown X Other (specify) i i

1:cCueling Shutdown Low Power llot Physics

! Routine Startup Tests The major plant parametern at the' tirac of the event were as follows:

Power RTR 10'7. - 5 x 10~3.7 Power ELECT' N/A ' MWc '

Secondary Coolant ' - Pressure N/A psig l

, . Ternperature .

N/A *F-Flow N/A #/hr.

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i. Primary Coolant Pressure 80 - 270 poig l

, Core Inlet Temperature 110' '*F:

l Core Outlet Temperature- l'10 *F l

-Flow 100,000 #/hr.

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AP.iNP?iAf, OCCt1FCIM '/ 4/?!)A 1 pa y,e 2 of 3 i DESCla i'TICM OF UCCim.:t! :

i j l're p._ rat i or.a for ri:nn to;; pa. t 1 of Startup Te st A- L to del et n.:nc t he :. ermhir F p re:. sitie coef ficie::t of renetivi ty vert in proces:.. Th ia t ent re<!uired th.

reactor t o be crit ical while prinary coolan t p essure va varied while naic-j L ai n ia-; the recet or c ritic.il bj cont rol rod mova:Nnt.

j LCO 4.2.11 stated that belou 725* P care outlet te:mer.st ure, 5,000 p;mv moin-4 t ure was alloued in the prie:try coolant. LCO 4.'i.1, Tabic 4.4-1, i ten 4, j a ta t t. t he ruxinam .settin:;a of the high .lcul and icop noistura conttors, 500 pra and 100 pp z, re spcet tvely, and aMo uteten that tharr a r n ., pi: r-j uiss ib h bypae + c"nditions of t he h!nh runt.c r on it m s ,

', The d t.u pr.l e t na is t u re mon i tors had beca ci.t; in an ' apparently du to a c. c. i t ar.cuut of r.ois ture t hat had acct./.ulated in the sa..:pic lines during the Ic ,

perioJ of re.;ctor sl.utdown. cpuricu; t rips vere being rect ived which enn <A reactor neran.

Itcrase t he reactor tenpaature van 1< , abeur 110* l , and r.oisturt J eeel ehet t 140 pt.1, it uas perr.insible to operate t he re e.c t .o . To allow opern: ion of LLe t eatt er, the dew point noi ct ure riunitor outputs vere ' bypam::1 and 1.e t point: raised t o approximately 3.000 pra and 1,000 pp.n on t he h Igh rnnge and loop nanitora, respectively.

i A note to this et t eet was put in tbc stat ion lug,-- along uith a comment LI:at we vould contact AEG-DOL as soon as possible tc clear up the d increpancy. -

3 This vas done on Monday norning, November 13, 1974.

Operation of the reactor continued at pours as high as 5 x 10 D power.

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

1 APPARENT CAUSE j -OF OCCURPINCE: - Design Unusual Service Cond.

4 including Environment l

, Manufacture Component Failure Installation /Const.- X- Other. (specify)-

Operator- Discrepancy between two Tech.

Procedure Spec.'LCO's, and the decision i

to continue operat ion using the -

4 limits of only. ons.

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.. j te; t prior to L cuance , to t.. i n b' meannt conj! t i< .

ac t .i..l ly e: pe rie .> ..I durits; tlw plai r 1:ot I' lou icsts aasi t: *aunecru for heron c a r', i .L e ,i .t..! ;ie ., t e ; . c..i.ed t er: ;i. + o r;:. In the presenc. e r r . i l e t. o r s . An

.;de rpu. t . ar: h of the Techul eal .;,ic ci f i c a tine fo r o t h" r i.(..i's wh i ch rr b .' ..f f e et d ca apparen tly 1.a t r:ade.

.. . ' 1 the rea t or operr.t t. n pir.ce r l eve la and t c: ;'arat e. e: t h-c ro act< d : b. t e:n t a r c. . e . rn;ih t i . , f o :! , or bn: nab'e ] c.:it ; ng, vir :.

t; r."am t . At no L i:a :is t .e  ! lih i.d ..a f. . ' o f t h.: pr' l i -.

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i on J:!.3 t o t h e Fo r t Ft. i' rain Techn ced b; s -i fi ca:. tc. .  : evi:.< d Sc . i<c.

4 . .1 ! an ' T.:ble 4 . 4.1. Yi. > ne t;n,1:.t o f t he hi: r:re. r: , ; n t u re i .n n i t o

. c.h a .' g_ t' to ' 6 /"l' ::nd < 2 7'? fo r I he lo p , - . : ure t.;cn i t o r: .

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4 , .: : a t.he dinecer:.ncy be ttecen Ta'31s  !. 4.1 a w' LW 4. 2,11.

I:o it. ': U o ' c acrec tive .u tic. . i s cu t it ip:'u d or rergel red.

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1Nof1O PROGR.i?"LiTiC IMPACT:

None CODE IMPACT:

None Subr:1Ltted by: '!1 J _,( A ' ,.sVkf] , j-7 l l- d$ f4

11. W. Ilillydrd, Jr. p Technical Services Supervisor

_/ 7 I;cviewed by: Qih). b. ..wT.

11. Larry Egey {

Superintendent, Operations Approved by: 3 74 > .51.

, Frederic E. Swart j-l Nuclear Product.fon MJ[ nager l

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O LICENSEE EVENT REP CONTROL ,BLOCC l l l l l l l [PLEASE PRINT ALL REQUIRED INFORMATION) 1 6 NAME LCENSE NUMBER E T E O1 Ic 10 I e I S I vl il I 0101-10101010101-10101 I 411111210 l l 01 il 7 89 14 15 25 26 30 31 32 CATEGORY T SU OOCKET NUMBER EVENT DATE REPORT OATE hCON'T lM lI l 7 8 57 58 W 59 W60 l0 l5 l0 l-l 0 l 2 l 6 l 7l 61 68 l1l1l1l6l7l4l 69 74 l 1l 1l O! 9l 7l 6l 75 80 EVENT DESCRIPTION 35 l During low power physics tests it was found that a conflict existed between two l 7 89 80 3E l Technical Specifications on moisture limits. Moisture monitors bvoassed and noisture !

7 89 80 3E l monitored to assure compliance with one Technical Specification. }

7 89 80 38 l l 7 89 80 HG l (AO 74/20A) l 7 89 m, 80 E COE COMPONENT CODE MANUFAC AER VCLATON 3[ lClJl lDj 7 89 10 11 lXlXl Xl Xl Xl Xl 12 17 W43 lzl9l9l9]

44 ' 47 lN l 48 CAUSE DESCRIPTION UE l One moeci fi cn r inn allnued 9. 000 PPMV ani seitra nther n11nued 500 nnmv nn hioh rmnen nnd! - ~

7 89 80 3E l 100 ppciv on low range. Technical Specifications changed to indicate dewpoint I 7 89 80 DE le-ngrne,,rg. I STA  % POWER OTHER STATUS OS VERY DISCOVERY OESCRsPTON 1

7 8 9 d 1010101 l 10 12 13 l 45h 44 46 iN/A 80 l

R LEA EO OF EL ASE AMOUNT OF ACTIVITY LOCATON OF RELEASE 3E Iz l 1_z_J l N/A l lN/A I 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUVSER TYPE DESCR!PTON DE b 10 lO 1 LzJ l m I 7 89 11 12 13 00 PERSONNEL INJURIES NUMBER DESCRIPTON 3[ l 0l 0l 0l l N/A I 7 89 11 12 80 OFFSITE CONSEQUENCES

]E l N/A l 7 89 80 LOSS OR OAMAGE TO FACIUTY TYPE DESCRIPTON QW 7 89 l N/A 10 80 l

PUBLICITY

@ l N/A l 7 89 80 ADDITIONAL FACTORS DE l N/A l 7 89 80

$l . # l PAME: I Affl -

  1. PHONE: (303) 785-2253 H. W. Hillyard, Jr. / / cro ess.esT