ML19210C654

Monthly Operating Rept for Oct 1979

ML19210C654
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/01/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19210C651	List: ML19210C650 ML19210C654
References
NUDOCS 7911190324
Download: ML19210C654 (5)

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OPERATIN: DATA RIPORT DOCKET NO. 50-267 DATg 791101 COMPLETED BY J. W. Gahm TE:.EPHONE (303) 785-2253 OPERATING STATUS NOTES

1. rnit Name: Fort St. Vrain, Unit No. 1

2. Reporting Period: 791001 thru 791031

3. Licensed Thermal Power Okt): 842

4. Nameplate Rating (Gross We): 342

5. Design Electrical Rating (Net We): 330

6. Mzimu:n Dependable Capacity (Gross We): 342

7. Maximum Dependable Capacity (Net We): 330

8. If Changes Occur in Capacity Ratings (Iter.s Number 3 Through 7) Since Last Report, Cive Reasons:

None

9. Power Level To Which Restricted If Any (Net We): 2 31

10. Reasons for Restrictions, If Any: Nuclear Regulatory Comission restriction (70%)

pending resolution of temperature fluctuations.

g. ., s, This Month Year to Date

• Cumulative *

11. Hours in Reporting Period 745 2,953 2,953

12. Number of Hours Reactor Was Critical 613.9 2,419.8 2,419.8

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 340.4 982.2 982.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. cross Ther=al Energy cenerated <>5m) 147,847 476,555 476,555

17. cross Electrical Energy cenerated (mm) 46,367 140,796 140,796

18. Net nectrical Energy cen rated (mm) 41,716 123,584 123,584

19. Unit Service ractor 45.7% 33.3% 33.3%

20. Unit Availability Factor 45.7% 33.3% 33.3%

21. unit Capacity ractor (csing MDC Net) 17.0% 12.7% 12.7%

22. Unit Capacity ractor (Using DER Net) 17.0% 12.7% 12.7%

23. Unit Forced Outage Rate 44.1% 65.1% 65.1%

24. Shutdowns Scheduled over Next 6 !bnths (Type. Date, and Duration of Each):

Maintenance Shutdown Becan October 26, 1979. Scheduled to last 45 days.

25. If Shut Down at End of Report Period. Estinated Date of Startup: December 10. 1979 0 284 Achieved

26. Units In Test Status (Prict to Comnercial Operation): rotecast g y7 initAL CRITICALITY 740201 740131 INITIAL ELECTRICITY 7612 761211 COMMERCIAL OPERATION 790701 790701

• Totals corrected to refer to July 1,1979, commercial operation date, as starting point.

.U,N_I_T_S_II_tr_n_WNS_AN D P_(M_ _E.R..R E_IWC. TONS, ' " ~

50-267 DoCxET en.

IINIT NAttE Fort S t. Vrain, Unit No. 1 DnE 791101 COttri.rTrn ny J. W. Cahm REPORT Ikifml October, 1979 TEl.rPiinNE (303) 785-2253

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f1E1110D OF SilVTTING IWN SYSTEM COtlPONErtT NO. DATE TYPE DURATION REASON REACTOR I.ER I CODE WDE calls 1C AND CORRECTIVE ACTION TO PREVENT RECURRENCE 79-12 790901 F 37.1 II 4 79-035/01-T ZZ SUPORT Due to inconsistencies discovered in a random sample of safety related piping, Public Service Company elected to initiate an orderly shutdown of the plant. Reactor restarted September 15, 1979, but generator remained of f line due to low power levels.

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79- 13 791014 F 231.0 11 N/A N/A N/A N/A Turbine tripped on low steam tempera-ture. Reactor not shutdown.

79-14 791026 S 136.5 B 2 N/A N/A N/A Scheduled shutdown for plant mainten-ance and installation of region con-straint devices.

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CD' S UMMARY : Scheduled to remain shutdown throngli November to perform required plant maintenance and to install the region constraint devices.

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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain, Unit No. 1 Date 791101 Completed By J. W. Gahm Telephone (303) 785-2253 Month October, 19 79 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 17 2 15 18 3 63 19 4 76 20 5 85 21 6 92 22 7 108 23 -0

• 8 132 24 106 9 152 25 197 10 154 26 39 11 176 27 12 182 28 13 194 29 14 49 30 15 31 16

• Generator on line but no net generation.

0 286

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REFUELING INFORMATION

1. Name of Facilitv. Fort St. Vrain, Unit No. 1

2. Scheduled date for next refueling shutdown. September 1, 1980

3. Scheduled date for restart following refueling. N vember 1, 1980

4. Will refueling or resumption 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 fuel design and core configura- will review any questions associated tion been reviewed by your Plant with the core reload.

Safety Review Committee to deter-

=ine whether any unreviewed safety questions are associated with the core reload (Reference l 10CFR Section 50.59)? I If no such review has taken place, when is it scheduled? March 1,1980

5. Scheduled date(s) for submitting --

proposed licensing action and suoporting information.

6. Important licensing considera- - -

tions associated with refueling, e.g., 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 number of fuel assemblies a) 1482 HTGR fuel elements.

(a) in the core and (b) in the spent fuel storace pool. b) 244 spent HTGR fuel elements.

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

storaga capacity that has been ,

requested or is planned, in }) )J

. number of fuel assemblies.

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REFUELING INFORMATION (CONTINUED)

9. The 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 the spent fuel Service Company of Colorado (PSCo), and pool assuming the present General Atomic Company.*

licensed cacacity.

• The 1986 date is based 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.

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