ML20086B178
| ML20086B178 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| 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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h&EUau>u public service company oe conorado P. O. Box 361, Platteville, Colorado 80651
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November 9, 1976
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Fort St. Vrain
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Unit No.1 P-76248
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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,
'4Y y
Frederic E. Swart Nuclear Production Manager FES/alk cc:
Mr. Roger S. Boyd G
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8311170090 761109 l
PDR ADOCK 05000267 l
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ho.v mber 4, 1976 An! 01;'. i!. OCCUlu:Cr:ct 7'i/20 s.
p:rge 1 of 3 a
OLCUwe.t.'CE IW1 E.
Eommber 16 197'-
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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
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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; i
'10 OCCU;mF.XCC-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. Power 7
ELECT' N/A
' MWc '
l Secondary Coolant '
- Pressure N/A psig N/A
- F-
. Ternperature Flow N/A
- /hr.
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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
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DESCla i'TICM OF UCCim.:t! :
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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 to continue operat ion using the -
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limits of only. ons.
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..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. er r. i l e t. o r s. An
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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.
the rea t or operr.t t.
n pir.ce r l eve la and t c: ;'arat e. e: t h-c 1
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t e:n t a r c.. e. rn;ih t i., f o :!, or bn: nab'e ] c.:i ; ng, vir :.
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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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,.: : 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:
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- 11. W. Ilillydrd, Jr.
p Technical Services Supervisor
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7 I;cviewed by:
Qih). b...wT.
- 11. Larry Egey
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Superintendent, Operations Approved by:
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l Nuclear Product.fon MJ[ nager Frederic E. Swart j -
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O LICENSEE EVENT REP CONTROL,BLOCC l l
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[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 W W l0 l5 l0 l-l 0 l 2 l 6 l 7l l1l1l1l6l7l4l l 1l 1l O! 9l 7l 6l 7 8 57 58 59 60 61 68 69 74 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 80 m,
E COE COMPONENT CODE MANUFAC AER VCLATON 3[ lClJl lDj lXlXl Xl Xl Xl Xl W
lzl9l9l9]
lN l 7 89 10 11 12 17 43 44
' 47 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
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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 d
1010101 l l h iN/A l
1 7 8 9
10 12 13 44 45 46 80 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 Q W l N/A l
7 89 10 80 PUBLICITY
@ l N/A l
7 89 80 ADDITIONAL FACTORS DE l N/A l
7 89 80
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I Affl (303) 785-2253 PAME:
PHONE:
H. W. Hillyard, Jr.
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