ML20071B991

Monthly Operating Rept for Jan 1983

ML20071B991
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/08/1983
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
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ML20071B895	List: ML20071B894 ML20071B991
References
NUDOCS 8303010389
Download: ML20071B991 (8)

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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION m

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MONTHLY OPERATIONS REPORT NO. 108 January, 1983 3

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This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated under the provisions of the Muclear Regulatory Commission Operating License DPR-34. This report is for the month of January,1983.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE

• Following the completion of repair to a leaking steam generttor tube in Loop 2 on December 22, 1982, the reactor was brought critical. .

On January 1, 1983, 30% power was attained, and the turbine-generator synchronized to the electrical distribution system.

Seventy percent power was reached on January 4.

A helium circulator trip occurred on January 4 while a plant protective system surveillance was being performed. Power was reduced to 30% for several hours while the circulator was being recovered. Power was again increased to 70%.

A venting system which prevents "B" purification train cooler from becoming gas-bound was installed, tested, and placed in operation.

During the rise-to power operation, primary coolant moisture

'] monitor problems were encountered. A variance from LC0 4.4.1 was granted for a short peric.i of time. Sample lines were purged extensively during thi', period, which resolved the problem. Methods to prevent recurrence are being evaluated.

Extensive cleaning to remove oil from the liquid waste system was completed. One source of oil is suspected to be the rupture of a gas waste compressor cooling system.

Modification of the helium circulator steam water drain control system was completed and put in automatic control.

, A purification system cooling water pump mechanical magnetic coupling repair was done which brought the system to rated efficiency.

Irradiated reflector block shipment began.

A new burner assembly was installed in the "outside" auxiliary boiler, and the boiler control system was recalibrated.

Reactor power remained at 70% until January 28 when a he'lium recirculator trip caused a helium circulator trip, loop r shutdown, and a scram. The helium recirculator wetr level alarm s

3 and trip setpoints were changed as a preventative measure.

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2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILFn FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT .

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. Tse-3 Attccheent-35 8sous 2 ortRATr c oATA u rc e noCxrr s 50-267 oATE Fa'ruary b 8. 1983 m LntosY L. M. McBride nLrruoNE (303) 785-2224 -

CPERATINC $7ATUS

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1. Unit Name: Fort St. Vrain

. Reporting Period: 830101 through 830131

3. Licensed Thermal Power (Wt): 842

1. Nameplace Racing (Gross We): 342 .

3. Desism Electrical 3ating (Net se): 330 .

6. Fad == Dependable Capacity (Cross We): 34 ~

7. Ma*== Dependable capacity (Net we): 330

8. If Changes occur in capacity, Ratings (Items Number 3 Through 7) Since Last Report Give Reasons:

None

3. Fover Level To Which Restricted. If any (Net We): 231

10. Seasons for Bescrictions If Any neerricvinn to 70! nandino resolurion of enn erm e e na l mmermen This Month Year to Date Cumelative

11. Sours in Reporting Period 7AA 7&& 11_465

12. Number of Hours Reactor Was Critical Ann A AAn A 20_407.5

13. Reactor 2aserve shutdown Hours 0.0 0.0 0.0

14. acurs ceneracor On-Line 646.7 646.7 13.821.2

15. Cnic amerve shutdown sours 0.0 0.0 0.0

16. Cross Thermi "mergy Generated (WH) 357.895.2 '357.895.2 7.147.500.6

17. cron nectrical tnerar cenerseed (wa) 122.062 122.062 2.448.966

13. Y e nectrical Energy cenerated (wa) 114.025 114.025 2.237.135

19. Unit Service Factor 86.9 86.9 43.9

20. rnit Availability ractar 86.9 86.9 43.9

21. Unit Capacity Factor (Using E C Net) 46.4 46.4 21.5 1

22. Unit capacity ractor (Using :ta Net) 46.4 46.4 21.5 l 23. Cnic Forced cutage Race 11.1 13.1 36.1

24. Shutdevns Scheduled Over Next 6 Months (Type, Data, and Duracion of Zach): 830201 *hreneh 830216 (384 hrs) for planc recovery; 830323 through 830412'(504 hrs) for surveillance testing.

3. If Shuc Oown at End of 3 aport Period, Iscimaced Dace of Startup: 830216 08J Units In Test Status (Prior s Camercial Operatica): Forecast Actieved 3:nAL CnnCic:n N/A N/A

T:;c EL:C nC:n N/A N/A Cotetz tC:AL ?taAn 3 N/A __

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. ISP-3 Attachment-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2

. Page 1 of 1 Dockat No. sn..?r,7 -

Unit Fort St. Vrain #1 Data Februarv G, 1983 Complaced By L. M. McBride Telephone (303) 785-2224 Month January, 1983 ,

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.,.

(MWe-Net) (MWe-Net) 1 25.1 17 191.6 2 65.5 18 191.7 -

3 87.7 19 192.8 4 g6.1 20 194.1 5 199.7 21 794.s .

6 to9.o 22 iga 1 7 194 4 23 193 3 8 192.7 24 193.2 1

9 193.2 25 193.0 10 193.4 26 193.1 11 192.7 27 19 3.0 12 198.2 28 75.2 13 196.4 29 0 14 192.6 30 0 15 192.1 31 0 16 192.3

• Generator on line but no net generation.

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At t as tin a t-3c Isme= 2

• ras. I of a UNIT SMirrtMEMS ant 1 PWER REIRICTtmS

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DATE _Ichruary_8. 1983 avamp Rv

_L. M._licBride .

RErtmT mainJanuary,_1983- """ -

mtNoD or SNUTTING runs sysTEn neuwnr Iml, DA1E TYPE DURATION REAS441 REACTOR I.ER f OlDE otDE CAlfSE AND 0*RECTIVE ACTIUM 10 PREVENT N!TURRENCE tl2-014830101 F 11.4 11 3 N/A IBil INSTRU Loop 1 shutdown followed by reactor scram and turbine-generator trip on 820930. Outage continued while per-foralng a normal plant start-up.83-001 830128 F 85.9 11 3 N/A 1 811 INSTRU Reactor scram and subsequent turbine generator trip due to a moisture

, ingress to the reactor vessel -

resulting from a helium circulator upset.

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REFUELING INFORMATION -

1. Name of Facility. Fort St. Vrain Unit No. I 1

2. Scheduled date for next refueling ~

shutdown. September 1, 1983

3. Scheduled date for restart following refueling. November 1, 1983

4. Will refueling or resumption of operation thereafter require a .'

technical specification change or other license ame,d==  ! Yes If answer is yes, what, in general, will these be? Use.of type H-431 graphitt.

If answer is no, h'as the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Comunittee to deter-mine whether any unreviewed safety questions are asscciated with the core reload (Reference 10CFR Section 50.59)?

If no such review has taken .

place, when is it scheduled?

5. Scheduled date(s) for submitting I proposed licensing action and Not scheduled at this time;  !

supporting information. to be determined.  !

. 6. Important licensing considera-l tions associated with refueling.

l e.g., new or different fuel de-i sign or supplier, unreviewed -- --

design or performance analysis methods, significant changes in fuel design, new operating pro-cedures.

7. The number of fuel assemblies 1482 HTGR fuel elements.

(a) in the core and (b) in the spent fuel storage pool. 11 spent HTCR fuel elements

8. The present licensed spent fuel i pool stcrage capacity and the Capacity is limited in size to about one-size of any increase tu licensed third of core (approximar =1y 500 HTCR '

storage capacity that has been elements). No change is planned.

requested or is planned, in number of fuel assenblies.

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RETUEI.ING INFORMATION (CONuauw)

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9. The projected date of the 1992 under Agreements AT(04-3)-633 and last refueling that can be DE-SC07-791D01370 between Public Service discharged to the spent fuel i Company of Colorado, General Atomic pool assuming the present l Company,andDOE.*

licensed capacitv. I O

• The 1992 estimated date is based on the understanding that spent fuel -

discharged during the term of the Agreements will be stored by DOE.'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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