ML20086B185
| ML20086B185 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 11/20/1974 |
| From: | Brey H, Swart F PUBLIC SERVICE CO. OF COLORADO |
| To: | Howard E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20086B175 | List: |
| References | |
| AO-50-267-74-20, NUDOCS 8311170093 | |
| Download: ML20086B185 (4) | |
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Mr. E. ?! orris Howard, Director Directorate of ite,ulatory Operations
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P. O. Sc:: 5039
'hite Settlement, Texas 761')8
Dear I'r.1:
ovard :
Ref: Facility Operating License No. 33";-34 Docket ;o 50-267 l
"a:loced please find a copy of Abnormal Occurrence
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j 50-267/74/20, cubcitted per tin requircaents of tha Technical Specifications.
3-i Very truly yours,
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'arry 3 rey Superintendent-3perations I' ort St. Vrain :iuclear Concrating Station 1.13:11 cc: !!r. An;;clo Gia.abusso 8311170093 761109 PDR ADOCK 05000267 i
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Noveaber 19. 1974 ADNORTiL OCCURRENCE OCCURRE':CE DATE: _?aven er 1.f,1974 b
FORT ST. VRAIN NUCLEAR CE;ERATING STAT 10:;
PUBLIC SERVICE COXPA'iY Of COLORADO P. O. BOX 361 PLATTLV1LLE, COLORADO 80651 REPORT NO. 50-267/74/20 Preliminary Final IDENTIFICATION OF OCCURRE::CE:
On Saturday, Novenber 16, 1974, durin:; lou power physics testing, it was found that a conflict existed between LCO 4.2.11 and LCO 4.4.1 of the Technical Specificatiens.
Because of reactor conditions and the need to continue testing, it was d 2cided to go with the noisture linits as stated in LCO 4.2.11 and disarm the conitors of LCO 4.4.1 and to notify and resolve the conflict nu soon as possible with the AEC. This would be defined as an Abnorr.a1 occurrence, per 2.lb of the Technical Specifications.
CONDITIO:iS PRIOR TO OCCURRENCE:
X Steady State Povar Routine Shutdown llot Shutdown
__ Routine Load Change Cold Shutdown X
Other (specify)
Refueling Shutdown Low Pcwcr Hot Physics Routine Startup
__ Tests.
The major plant paraneters at the time of the event were as fo11cus:
Power
- RTR, 0.84 - 42 KUth (10-'i% - 5 x 10-3% Power)
- ELECT, N/A Inic Secondary Coolant Pressure N/A,psig Temperature "/A "F Flow N/A
- /hr.
PrJaary Coolant Pressure 80-270psig l
l Tenp.
110
- F Core Julet l
l Temp.
110
'r Core Outlet 1
Flo'. 100,000 _ f/hr.
1 O
o Pap,e 2 DESCRIPTION OF OCCU_nnFTE-Preparations for running Part 1 of Start Up Test A-8 to deternine the reactor precsure coefficient of reactivJty ucrn in process. This test required the reactor to be critical while primary coolant pressure was varied vhile naintaining the reactor critical by control rod movement, LCO 4.2.11 stated that belou 725*r core outlet temperature, 5000 pp::v moisture uas allowed in the priucry coolant.
LCO 4.4.1, Table 4.4-1, itea 4, states the maxhaun settings of the 111gh Level and Loop Meisture Monitors, 500 ppm and 100 ppnv respectively, and also states that there are no permissibic by pass conditions of the high range monitors.
The deu point rcoisture conitors had been cut in and apparently due to a staall amount of coisture that had accumulated in the sar.ple lines during the long period of reactor shutdorn, spurious trips were being received which caused reactor scram.
T,ecause the reactor te.perature vas lov, about 110'F, nnd moisture level about 140 ppa, it u w pernisrible to operate the reactor. To al. lou operation of the reactor, tha deu point noitture nonitor outputs ucre by-pasced and set pointa rclunt to apprunior.tcl:, 5000 ppa and 1000 ppa on the Ili;;h llange cnd laop.:onitors respectivel'j.
A note to this effect wr, put. in the station 2eg, along with a compent that, uc uculd contact AEC-DOL na co-n as postible to clear up the discrepancy.
This was dono en ';nnday rwning, ;;ovcuber 18,194.
Operntjen of tha reactor centhucd at pewco on high ac 5 ': 10-3% power.
At no time was the noisture level in the prinary coolant above 150 ppw or the t enperature above 130'r.
APPARE:sT CAUSr or CCCU:mD:Cri Design
__ Unusual Service Cond.
Including Enviton.
Manufacture
_ Component Failure Installation /Const.
X Other (specify)
Operator D1ncrepnncy betreen tuo Tech.
3 Trocedure S gc. LCO'n, vnd the decision to continue onoration usins: the l
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v Pagc 3 A!;ALYSIS OF OCCUi'ni:':t'E :
The conflict in the Technical Specifications was brour,ht about by a last rtinute change in LCO 4.2.13 just prior to issuance, to take into condition:; ac.. ally experienced durin:; the plant Ifot F. low Tests and account in the the concern for borca carbide exidation at c3 evat ed ter.peratures presence of ruoisture. An adequate scarch of the Technical Specifications for other LCO's which nay be aCfected van apparently net made.
At no tine uas the reactor operated at power levels and tct.:peratures that could have af fected the reactor core graphite, fuel, or burnable 1cading with the nuisture present. At no tine was the health and saf ety of the public cndany,ered.
CORRECTIVE ACTIO:::__
A temporary change to the set t ings of the Moirture Monitors of 5000 pp.i belc.' 725*l Las beca iscrd 1.i AEC-DOL.
A fornal rcquest for a Teebnical Specification cha:.ce vill be subaitted 5.hortly.
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Submitted by:
H. Larry Drey\\
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Superintendent-operations Fort St. Vrain 1;uclear Generating Stetion
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f Approved by:
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Fri'deric E. huart l
SGperdutcadent i;uclear Production Fort St. Vrain 1:uclear CentratJng Station H?..P. :1 L S/il