ML19290E891

Monthly Operating Rept for Feb 1980

ML19290E891
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/01/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19290E889	List: ML19290E888 ML19290E891
References
NUDOCS 8003170274
Download: ML19290E891 (5)

Text

{{#Wiki_filter:'

 .               crenTrNC DATA RIPCRT                                   DOCKzT NO.       50-267 DAT:      800301                     i COntt.zTzD sr      J. W. Gahm TzI.zrmNr        (303) 785-2253 OPERATING STATt3 NOT s

1. cnit Name: Fo rt S t. Vrain #1

2. saporting Period: 800201 through 800229

3. ueensed Thermal Power () sit): 842

4. Nameplate Ratics (Cross We): 342

3. Design Electrical Rating ()tet W e): 330

6. Mariann Dependable Capacity (Grose We): 342

7. Maximum Dependable Capacity (;let We): 330

8. If Changes occur in Capacity Ratings (Iteme Number 3 Through 7) Since Last Report, Give Raascas: I None  !

9. Power Level To Vhich Restricted, If Any (Net lia): 231

10. amasons for ametrie: ions, If Any: Nuclear Regulatory Cornission restriction 70% pending i resolution of te::perature fluctuations. l This Month Year to Date Cumulative

u. sours in taportins Period -

696 1,440 5,857

12. Number of sours anactor was Critical 151.5 187.5 2,720.6

13. Rasetor asserve Shutdown sours 0.0 0.0 0.0

14. Boars ceneratar on-une 0.0 0.0 982.2

15. Unie Reserve Shutdown sours 0.0 0.0 0.0

16. cross Thermal snargy camerated (Ws) 2,886.2 3,293.0 481,247.8

17. cross Electrical Energy cenerated 0511) 0.0 0.0 140,796

18. Net nectrical Energy cenerated esta) 0.0 0.0 123,584

19. Unit Service Factor 0.0% 0.0% 16.8%

20. Unit Armitahility ractor 0.0% 0.0% 16.8%

21. Unit Capacity ractor (csins MDC Net) 0.0% 0.0% 6.4%

22. Unit Capacity ractor (teing Drx Nat) 0.0% 0.0% 6.4%

23. Unic rarced outage nat. 0.0% 0.0% 65.1%

24. Shutdowns Scheduled over Nort 6 )tanths (Type. Date, and Duration of Each): N/A

25. If Shut Down at End of Raport Period Estimated Date of Startup: N/A

26. Units In Test Status (Prior to Comercial Operation): Forecast Achieved INITIAL CRITICAuTT N/A N/A INITIAI. ELzcIIICTTY N/A N/A mMMIRCIAL OPERATICN N/A N/A RGG FQ WO ARBO Q D t

h[jYlj(@j[j([[h ts 0 0317 0 A7/[-

UNIT SHUTlWNS AND IWER REDUCRWS IlOCKET No. JM67 - UNIT NAME Fort St. Vrain #1 gate 800301 COMPLETED BY J. W. Cahm REroRT Howru February, 1980 TEurnoNe (303) 785-2253 HEP.10D OF . SifuTTING DOWN , SYSTEM COHl'ONENT Hn. DATE TYPE DURATION REASON REACTOR I.ER f

• CODE ODDE CAllSE. AND COkRECTIVE ACTION TO PREVENT BECURRENCE 79-14 79102t S 696.0 B 2 N/A N/A N/A Scheduled Ehutdown for plant mainte- ,

nance and installation of region con-straint devices was conpleted De-  ! cenber 24, 1979. Plant remained shut- l down for replacement of one circulator due to a ruptured static seal (refer-  ; ence LER 80-001/01-T-0). Replacement completed and reactor operated at low power levels during the period from i Februa ry 16, 1980, through the end of . the month. Generator remained off-line. . s i

SUMMARY

Plant is scheduled to return to 70% power in early March,1980.

i I

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain #1 Date 800301 Completed By J. W. Gahm Telephone (303) 785-2253 Month February, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Ne t) 1 0.0 17 0.0 2 0.0 18 0.0 3 0.0 19 0.0 4 0.0 20 0.0 5 0.0 21 0.0 6 0.0 22 0.0 7 0.0 23 0.0 8 0.0 24 0.0 9 0.0 25 0.0 10 0.0 26 0.0 11 0. 0 ' 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 30 N/A 15 0.0 31 N/A 16 0.0

• Generator on line but no ' net generation,

REFUELING INFORMATION

1. Name of Facility. Fort S t. Vrain , Unit No . 1

2. Scheduled date for next refueling shutdown. January 1, 1981

3. Scheduled date for restart following refueling. March 1, 1981

4. Will refueling or resu=ption of operation thereafter require a technical specification change or other license amendment? No If answer is yes, what, in general, will these be?

If answer is no, has the reload The Plant Operations Review Committee will fuel design and core configura- review any questions associated with the tion been reviewed by your Plant core reload. Safety Review Comittee to deter-mine whether any unreviewed safety questions are associated with the core reload (Reference 10CFR Section 50.59)? If no such review has taken place. when is it scheduled? July 1, 1980

5. Scheduled date(s) for submitting -

proposed licensing action and supporting information.

6. Important licensing considera- - - - - - - - -

tions associated with refueling, e.8., new or different fuel de-sign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating pro-cedures.

7. The nu=ber of fuel assemblies a) 1482 HTGR fuel elements.

(a) in the core and (b) in the spent fuel storage pool, b) 244 spent RTGR fuel elements.

8. The present licensed spent fuel Capacity is limited in size to a'cout one-pool storage capacity and the third of core (approximately 500 HTGR size of any increase in licensed elements). No change is planned.

storage capacity that has been requested or is planned, in number of fuel assemblies.

REFUILING UEORMATION (CONTINUED)

9. Ihe projected date of the 1986 under the Three Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Public discharged to tt.e spent fuel Service Company of Colorado (PSCo), and pool assuming the present General Atomic Company.*

licensed capacity.

     *The 1986 date is bas ad on the understanding that spent fuel discharged during the term of the Three Party Agreement will be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chemical Processing Plant (ICPP). The storage capacity has evidently been sized to accomodate fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.

om e}}