ML20069H641

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Monthly Operating Rept for Sept 1982.Narrative Summary Encl
ML20069H641
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 10/06/1982
From: Mcbride L
PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20069H601 List:
References
NUDOCS 8210190667
Download: ML20069H641 (9)


Text

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i PUBLIC SERVICE CCMPANY OF COLORADO FORT ST. VRAIN-NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 104 September, 1982 e

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This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated under the provisions of the Nuclear Regulatory Commission Operating License DPR-34. This report is for the month of September,1982.

l 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATj0 MAINTENANCE l 1.1 Summary Except for some minor short-term load reductions, the plant operated at 70% power until the end of the month.

I' On September 30, while performing a surveillance on the plant protection system, a spurious trip caused a loop f shutdown followed by a turbine trip and reactor scram, l inis terminated about 31/2 montns of continuous operation.

Plans are underway to complete required surveillances and maka the necessary repairs to return to power operation.

1.2 Operations f

Reactor power was generally maintained at about 70%

throughout the month with the following exceptions.

Reactor power was decreased to about 67% to remove 1A boiler feedpump from service to repair its discharge check valve. The 1A boiler feedpump was repaired, and power was increased to 70% on September 3.

At 1304 hours0.0151 days <br />0.362 hours <br />0.00216 weeks <br />4.96172e-4 months <br /> on September 8, a system fr.equency upset s occurred causing a turbine and reactor power runback of about 30 megawatts. Plant power was returned to 70% by 1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br />.

On September 27, between 0100 and 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />, plant load was decreased to 180 MWe at the request of the system dispatcher. At 0835 hours0.00966 days <br />0.232 hours <br />0.00138 weeks <br />3.177175e-4 months <br />, there was a turbine runback to abou~t 66% when a backup bearing water safety valve opened spuriously.

On Saptember 30 at 0548 hours0.00634 days <br />0.152 hours <br />9.060847e-4 weeks <br />2.08514e-4 months <br /> while performing a Surveillance Test on the ultrasonicz pipe rupture detection

, system, a spurious trip caused a Loop 1 shutdown. Rapidly decreasing main steam temperature in the remaining ' loop subsequently caused a turbine trip and a two-loop trouble scram.

3 At the end of the ' month, the reactor was shutdown.

A 3 ' Surveillances, which require the plant to be shutdown to

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perform are being done, and work is in progress to prepare the plant for operation.

We are_ experiencing some difficulty with our 1 condensate /feedwater systems. High and variable '

concentrations of chlorine in the domestic water supply appears to be causing rapid exhaustion of the makeup and condensate polisher resin. This results in decreased capability--to make up to the condensate system, as well as-increased consumption for regeneration.

On . September 14, a mobile makeup demineralizer was brought on site. By September 18, this unit processed -

300,000 gallons'of water to regenerate all exhausted resins and fill the storage tanks. Although the domestic water supplier has indicated they are taking corrective measures, chlorine, as well as insufficient supply capability, remain to be problems.

A fire . drill was conducted on September 13 in which the Platteville Fire Department participated. In addition, fire drills were conducted on September 20 and on-September 27.

Contract personnel began arriving on September 15 to begin work on the refurbishment of the outside auxiliary boiler.

Among other things,.new internals are being installed in the upper' drum, a heating coil is being installed in the lower drum, and brick work is being. repaired.

Helium purification train IB broke through on September 22.

When the operators tried to isolate the train for regeneration, it was found that HV-2302, the train inlet

- valve, was bound up and would not close using the motor.

Attempts to close the valve using:the the handjack were not successful. This valve is in a well in the top of the prestressed concrete reactor vessel and cannot be repaired until the reactor is shut down and depressurized to less than 100 psia.

- - A new ' replacement tube bundle for heater #5 arrived on site. The old heater #5 was moved down to the railroad bay on September 15. The shell was removed from it and the bundle was removed from the site. ,

- Backup bearing water pressure control valves and safety valves continue to_cause problems. The system was out of service twice during the month 'to rebuild the safety Evalves.

e 1 The. raain steam desuperheater drain lines between the level

  1. : ' control valves and the condenser has developed many leaks

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which resulted in emergency repairs during the month. A temporary repair was finally made by jacketing the line with furmanite.

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS

' 0F 10*.' OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM- IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING OATA REPORT Attached 2

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Attact at-3B l Issu. 2 Pap 1 or 1 )

onunse un arren cocxrt so. 50-267  :

dan October 6.1947 ,

ccxrunD sr L. M. McBride  !

r n:.zracxt _Q03)785-2224 [

estunse sans  !

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1. :ni: s: Fort St. Vrain *
2. a.;ortins ?.rio4: 820901 through 820930 ,
3. uc.nua a.es.1 ro , est): 842 i 4 Nam. plat. Rattag (cross W.): 342  !
3.  :=1, u.etricat antins case We): 330 l i
6. *M- Depen 4abl. capacity (cros. We): 342 -
7. %M- D pen 4able capacity clet We): 330 I

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-S. It Change. Occur *.s Cap. city Eating. (It.a. saber 3 Through I) sine. Last Report, civ. Reasons: ,

None  :

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9. Power Lev.1 To '.'hich Re.trict.4. If Any (set We): 231
10. annens for anscrictions, It any: NRC restriction of 70% oendina resolution of tamnerature fluctuations.

This Month Year to 04t. C asulative f

11. Hours is Raporting Perio4 720 6.551 28.512
. :unner of sours saaccer w critical 701.9 4.169.4 18.747.8
3. zuccor neurre shuceown sours 0.0 0.0 0.0 i
14. aours ceneracar on-u=e 701.9 3.266.2 13.174.5 1s. enic x=.r,. shuc4eva soun 0.0 0.0 0.0 f
15. cr= u n rnal =er:7 cenerse.4 csn> 407,778.9 1,842,485.5 6.776.430.3 i
17. cron n .etrical :nerar c e== raced (Mi1t) 149,021 -635.548 2.326.904
s. rec n.ccrical sn.rsy c. cat.4 csa) 140.362 581.845 2.136.104 i

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19.' Unit ser ric. Factor 97.5 49.9 46.2

0. Chit Availability TactJr 97.b 49.9 46.2
21. ' Unit capacity Factor (Using MDc Nec) 59.1 76.9  ??.7
. cast capacicy ractor (rstes :ta s.e> 59.1 26.9 22.7
. cnic rare.4 oveage anc. 2.5 10.7 29.5  ;

24 shuezovn.' ses.4ul.4 over sext 6 scachs (:yp., nac., an4 ,oracion or each): Maintenance outace -

821101 throuch 821215 - 1.080 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Plant recoverv - 821001 th rouch 821007 - 168

23. If shue cova at t=4 or 7 port seri=4. rsein.c.4 a.c. or startup: 821008** hours .
26. *: nits is Test Seata (Prior to cc:m:.r:ial operation): Forecast Achi.v.4 ,

t:::n:. cuncA:.:n N/A N/A

rtnAI. n nn::n N/A N/A f c:urac.A:. cr xAnes N/A N/A
    • 821008 date reflects information as of September 30, 1962. Anticipated Startup date is not determined as of this transmittal dated October 12, 1982.

s2-3 Ac:achment-3A AVERAGE DAILY UNIT POWER LEVEL Iss 2 Dockee No. 50-267 Unie Fort St. Vrain Date October 6. 1992 Completed By f_ . M McBrida Telephone (303) 785-2224 Month Sectember. 1982

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DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVE'. '

(We-Ne t) (We-Net) 1 192.1- 17 201.0 2 195.2 18 202.5 3 1po_R 19 202.5 4 198.7 20 202.8 .

5 197.7 21 202.0 -

6 107.5 22 202.7 7 198.4 23 203.2 8 198.2 24 202.1 9 1RA.0 25 201.7 10 201.c 26 201.1 11 202.6 27 195.0 12 202.1 28 203.1 13 202.4 29 203.4 14 202.0 30 42.4 15 203.5 31 N/A 16 201.9 l

  • Generscar on line but no net generation.

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omrinFa av _L. 1 _HcBride .

smar e==ni _Sep.tembe.r,_1982 ,

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snirmac tunals 5YSTFM aet1100F.M F leil. IMTE TYrg 14*Afton RFAS4101 REACTOR IJ.R I OllIE Oll* CA485R ANil UlftttFCTIVE ACilsel iti rpEVENT REI3HipH10E 32-014 B20930 F 18.1 H 3 N/A IBH INSTRU Loop 1 shutdown followed by reactor scram and turbine-generator trip.

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1. 2Ia=3 cf ISci'.i:"F. 70-* St. 7 tin Uni: No. 1 l t
1. Scheduled da a *:: =ez: :sfueli=g j shutdown. Oc::bar 1. 1983 l I
3. Scheduled data fer restar l fellesrt:r -steal 1=2. 7 c. - - i . tas3  ;

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4. Will :sd ali=g :: :ssu=p:ics of , i operacies -dersaftar :squirs a  !
., w.s . t 39.,<se-, 1=n cha=ge l

? ether licause ~%:? Yes If answer is yes, what, is ,

tener21 v111 dese be? Use of evee H-451 trachite. i if answer is :c, has he 31:ad fuel desig: and care cenfign n-1:n been : viared by yc.c- Plan:

Saf a 7 3aviar C.:=mit:se :: dess:- -

'.=a whether a=7 ===sstaved safecy questi =s ars asacciatad j vi:h the c rs :aland (Infa:snes  ;

ICC7?. Sec_'_:s 50.591? , I i

if :n such :srisw haa .aka= - )

elzen vhe= is it sched.. lad? l 1

3. Scheduled da:a(s) for sulzi:.1=g  :

pr:pesed lies =s1=g actics a=d '

succe;-d ? i=f: =m .i==. Not scheduled at this :i=e: to be deternined.  !

{. s. *.=perta==

d lics=s1=g c=cside x-ans associa:sd wi h :sf ali g, i

e.g. , saw cr d' '"s:s=c fuel de-- l sign er suppliar, u==sviewed l desigs er pe=f:r. a==a analysis ,

i methods, sig -== cha=gss 1:

  1. e1 desig=, :sw cpers:i=g pr:- ,

, endurss. '

7. Se su=ber of fusi asse=blies  :.a32 E' 2 fuel ele =en=3 (a) is :he :::s a=4 (b) 1: 77 spen: _2.2 .,nsA ele ===:s .

.,.a see=. ,ne_, s

. 2:s teo,.

I t 8 3. S e prssen: 11:sused span: *:s1

col s
:: age capaci:7 a=d de {

Capacity is li=1:ad in si:e e ahcu: ne- .

size of a -y i=c= ease i= lics: sed -di d of :::s (app :ci=a:aly 5C0 E 2 I starsge capaci:7 :ha: has been ele =ac:s) . Itc changs is ;'*- ed.

l :scuestad :: is pt ~ ed, i

[ .=mer of fuel asse=clias.

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  • e RETT IT. I!iFORMATION (CO:iTINUED)
9. The projected date of _ the 1(32 under Agreements AT(04-3)-633 and last refueling that can be
  • DS-SC07-791D01370 between Public Service discharged to the spent fuel i Company of Colorado General Atomic pool assuming the present l Company,andDOE.*

licensed capaci:v. i

  • The 1992 estimated date is based on the understanding that spent fuel discharged during the term of the Agreements will be stored by D01: 'at the Idaho Chemical Processing Plant. The storage capacity has evidently been sized to accomodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.

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