ML20086B173
| 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: |
| References | |
| 50-267-74-20A, AO-50-267-74-20, P-76249, NUDOCS 8311170088 | |
| Download: ML20086B173 (6) | |
Text
,
~
O O
assau public service company or cenende P. O. Box 361, Platteville, Colorado 80651 November 9,1976 Fort g'
U g
9
/
Q(DY.f>J
~
.?
'a Lhu.
/+.A 1 s 9 78 ' 20/l Office of Information and Program Control g
'~
g U. S. Nuclear Regulatory Commission g
g a
Washington, D.C.
20555 W
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 ADOCK 05000267 S
I s
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 1*
Attn: Director 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
)
1 Add re ss +++ Director 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 1 (copy of Licensee Address +++ Mr. E. Morris Howard, Director P Letter Region IV.
Event Report)
To Office of Inspection & Enforcement Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 1 (copy of Howard's Director of Nuclear Reactor Regulation Atta Mr. Roger S. Boyd Director letter, mailogram, Division of Project Management
& Licensee Event U. S. Nuclear Regulatory Commission Report)
Washington, D.C.
20555 Of fice of Information & Program Control - - - - - - - - - - - - - - - - - - - -(
Criginal of Licensee Address +++
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.
L :.
r
~
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 W
lo l5 l0 l-l 0 l 2 l 6 l 7 l l1 l1 l1 l6 l 7 l 4 l l 1l ll 0l ol 7l Al 7 8 57 58 59 60 61 68 69 74 75 80 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 l
7 89 80 HG l (A0 74/20A) l 7 89 80 m
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 L8J lol ol ol I I
Ld lN/A I
1 7 8 9
10 12 13 44 45 46 80 0 OF E E
AMOUNT OF ACTIVITY LOCATCN OF RELEASE E0 d
W I N/A l
lN/A I
7 8 9
10 11 44 45 80 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 l N/A l
7 89 10 80 PUBLICITY DE l N/A l
7 89 80 ADOITIONAL FACTORS 18 l N/A l
7 89 80 DE l 1
NAME:
b (303) 785-2253 PHONE:
H. W. Hillyftra, Jr.
/
f ePo een.eer
e O
~
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:
~
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.
f.
7_
O Ai NtW:M. OCCup.E:.:CE 74/20.i l'i. p.e 2 oi 3 DLic Ipr!O:'
UCrt@
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.
3 Operation of the reactor continued at powers as high as 5 x 10 % power.
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.
.s
]-
f-
r b)
U
'v
~
/.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..'
L*tu. e t
,y, a y n, P*
o m.
i.. =
ACTitr :
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.
.....,._-....w r.t teot hr.ru t.t i.9 us a.et.nO L83 :
i.s u e.m
".u Nolte
--PROGRAISLW1C IliN,C1 :
None COD *' IMPACT:
None
'If Jij$ffl 'h ('/ffgy).fr
<l
')'
.fi 1}.
f-t v
4 i./* /.6 G1 Subattted by:
- 11. W. Ililly; rd, Jr.
l/
Technical Services Supervicor Reviewed by:
--d-TM,W b) em
.J H. Larry Byey' Superintendent, Opera {t. ions Approved by:
,[)744-hb
- k.
Nuclear Production Ma[ nager Frederic E. Swart
)
t t
l l
t
.