ML20065A774

Monthly Operating Rept for Jan 1983

ML20065A774
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/08/1983
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20065A773	List: ML20065A770 ML20065A774
References
NUDOCS 8302220159
Download: ML20065A774 (5)

Text

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TSP-3 Att achment-33 Issue 2

' '" 1 '1 OPERATING DATA REPORT DOCKET NO. 50-267 DATE Februarv 8. 1983 COMPLEIED ST L. M. McBride TEI.EPuosE (303) 785-2224 CPERATING STATt'S sorts '

1. Unit Nae.e: Fort St. Vrain

2. Reporting Period 830101 through 830131

3. Licensed Thermal Power (Wt): 842

4. Nameplate Rating (Gross We): 342

5. DasLgn Electrical Racing (Net We): 330

6. Maximum Dependable Capacity (Cross W ehr 342 -

7. Mexista Denndable Capacity (Net Wa): ___ 330

8. If Chages occur in capacity, Ratings ' Items Number 3 Through 7) Since Last Report, Give Reasors:

None ,

9. Power Level To Wich Restricted. If Lny (yet Wek 23]

10. Reasons for Restrictions, If Any: ,h e rri c ti on to 70Z pendfDg resolution of _

m rnerun1 nnerare This Month Year to :: ate Cumalative

11. Hours in Reporting Period 7&A 744 11.465

12. Number of Hours Reactor Was Critical AAn R 660.A 20.407.5

13. Reactor :eserve Shutdown sours 0.0 0.0 0.0 la. aours cenerator on-Line 646.7 646.7 13.821.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Cross Thermal Energy Generated (WH) 357.895.2 '357.895.2 7.147,500.6

17. cross Electrical Energy cen rated (W a) 122.062 122.062 2.448,966

13. Net Electrical Energy cenerated ( Wa) 114.025 114.025 2.237.135

19. Unit Service Factor 86.9 86.9 43.9

20. Unit Availability Factor 86.9 86.9 43.9

21. taic Capseity ractor (Using MDC Net) 46.4 46.4 21.5_

22. Unit Capacity Factor (Using DER Net) 46.4 46.4 21.5

23. Unic Forced Outage Rate 13.1 13.1 36.1

24. Shutdowns Scheduled 0ver Next 6 Months (Type. Date, and Duration of Zach): 830201 throuch 830216 (384 hrs) for plant recovery; 830323 through 830412'(504 hrs) for surveillance testing.

25. If Shut Down at End of Report Period. Estinated Data of Startup: 830216

26. Units In Test Status (Prior to Coccercial Operation): Fo recas t Achieved INInAL CRITICALIn N/A N/A INInAL E:.EC RICIN N/A N/A 2 ",ca,gnc3 N/A N/A 8302220159 830208 PDR ADOCK 05000267 R PDR . . -. . _ .

ISP-3 Attachment-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2 Page 1 of 1 Docket No. sn_9n7 Unit Fort St. Vrain #1 Date February 8, 1983 Completed By L. M. McBride Telephone ( 303) 785-2224 Month January, 1983 ,

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL ,

(MWe-Net) (MWe-Ne t) 1 25.1 17 191.6 2 -

65.5' 18 _

191.7 3 87.7 19 192.8 4 96.1 20 194.1 5 102.7 21 704.s .

6 101.o 22 194.1 7 194.4 23 193.3 8 192.7 24 193.2 9 193.2 25 193.0 10 193.4 26 193.1

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11 192.7 27 193.0 t 12 198.2 28 75.2 i 13 196.4 29 0 l 14 192.6 30 0 -

15 192.1 31 0 16 192.3

• Generator on line but no net generation.

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I'S P- 3 Altmal w nt-3C Isuem 2 e Page 1 of I .

UNIT SHimMWNS AND P(MER REMICTUNS

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ranET tai, _M-M7 UNIT NAllE Fort St Vrain #1 DATE  : February Buj983 Q1MPl.ETES) KY _L J J g$ridg REroRT nowni January, _1983_ _ TE'ErmtNE J301185-2224

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HE11h)D OF ~

SilUTTING IMEN SYSTEN O W ONENT NO. DATE TYPE DURAT[ON REASON REACTOR LER # Qi'!C 01DE _ CAllSE AND 0)RRECTIVE ACTION TO PREVENT RECtIRRENCE _

B2-014830101 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-forming a normal plant start-up.83-001 830128 F 85.9 11 3 N/A IBil 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. 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 sFecification change or other license amendment? Yes If answer is yes, what, in ]

general, will these be? Use of type H-451 graph 1te. I If answer is no, has the reload 1 fuel design and core configura- l tion been reviewed by your Plsnt Safety Review Committee to deter- - ~ ~ ~ - ' - ~ ~ ~ ~ - ~ ~ ~

mine whether any unreviewed safety questions are associated with the core reload (Reference i 10CFR Section 50.59)? l If no such review has taken _____

place, when is it scheduled?

5. Scheduled date(s) for submit ting proposed licensing action and Not scheduled at this time; suoporting information. to be determined.

l 6. Important licensing considera-l tions associated with refueling, j e.g., new or different fuel de-sign or supplier, unreviewed - -- ==

design or performance analysis l

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

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

(a) in the core and (b) in the spent fuel storage pool. 11 spent HTGR fuel elements S. The present licensed spent fuel pool storage capacity and the Capacity is limited in size to about one-size of any increase in licensed third of core (approximately 500 HTGR storage capacity that has been elements). No change is planned.

requested or is planned, in number of fuel assemblies.

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T 7-REFUELING INFORMATION (CONTINUED) i

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 Company of Colorado, General Atomic pool assuming the present Company, and DOE.*

licensed capacity. l

• 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 acconodata eight fuci segments. It is estimated that the eighth fuel segment will be discharged in 1992.

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