ML19291B907

Monthly Operating Rept for Nov 1979

ML19291B907
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/03/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19291B906	List: ML19291B905 ML19291B907
References
NUDOCS 7912140335
Download: ML19291B907 (5)

Text

4 OPERATING DATA REPORT DOCKET NO. 50-267 DATE 791203 CcMPLETED av J. W. Gahm TE: epa 0xE (303) 785-2253 OPERATING STAT"S notes

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

2. Reporting Period: 791101 through 791130

3. Licensed Ther=al Power (Wt): 842

4. Nameplate Rating (Cross We): 342

5. Design Electrical Rating (Net We): 330

6. Maximum Dependable Capacity (Gross We): 342

7. Maximum Dependable Capacity (Net We): 330

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

None

9. Power Level To Which Restricted, If Any (Net We): 231

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

pending resolution of temperature fluctuations.

Ihis Month Year to Date Cumulative

11. Hours in Reporting Period 720 3,673* 3,673*

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

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 0.0 982.2 982.2

15. Unic Reserve Shutdown Hours 0.0 0.0 0.0

16. Cross Thermal Energy Generated (5"d) 0.0 476,555 476,555

17. Gross Electrical Energy Generated (%"d) 0.0 140,796 140,796 IS. Net Electrical Energy Generated (WR) 0.0 123,584 123,584

19. Unit Service Factor 0.0% 26.7% 26.7%

20. Unit Availability Factor 0.0% 26.7% 26.7%

21. Unit Capacity Factor (Using MDC Net) 0.0% 10.2% 10.2%

22. Unit Capacity ractor (Using DEx Net) 0.0 10.2% 10.2%

23. Unic rorced Outage Rate 0.0 65.1% 65.1%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Maintenance shutdown began on October 26, 1979. It is scheduled to last 45 davs. .rnn

25. If Shut Down at End of Report Period Estimated Date of Startup: December 10, 1979 IJOV 3C0 J

26. Units In Test Status (Prior to Commercial Operation): Forecast *9121:dhd 4

INITIAL CRITICALITY 740201 740131 INITIAL ELECTRICITY 7612 761211 COMMERC OPERATION 790701 790701

• Totals corrected to reier to July 1,1979, commercial operation date, as st;arting point

k s

UNIT SIIUTDOWNS AND POWER REDUCTONS ,

~

DoCxET No. 50-267 UNIT NAME Fort S t. Vrain,. Unit No. 1 DATE 791203 COMPLETE!) BY J. W. Gahm REPORT HONTil Novembe r, 1979 TE:.ErnoNg (303) 785-2253 HE1110D OF SilUTTING DOWN SYSTEM COMI'ONENT NO. DATE TYPE DURATION REASON REACTOR LER I CODE (I)DE CAtlSE AND CORRECTIVE ACTION TO PREVENi RECURRERCE 79-14 791026 S 720.0 B 2 N/A N/A N/A Scheduled shutdown for plant mainte-nance and installation of region con-straint devices.

LT1 CO CD u .

Ln S ummary ; Scheduled shutdown for plant maintenance and installation of region constraint devices is to be completed l

by December 10, 1979, The plant is scheduled to return to 70% power for the remainder of December.

J

' 6 AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unic Fort St. Vrain, Unit No. 1 Date 791203 Completed By J. W. Gahm Telephone (303) 785-2253 Month November, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) .

1 17 2 18 3 19 4 20 5 21 6 22 7

23 ,

8 24 9 25 10 26 11 27 12 28 13 29 14 30 sg 15 31 16 --

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. REFUELING INFORMATION

1. Name of Facility. Fc rt S t . Vrain, Unit No. 1

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

3. Scheduled date for restart following refueling. November 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-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? March 1, 1980

5. Scheduled date(s) for submitting ----

proposed licensing action and supporting 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 storage 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 elemen ts) . No change is planned, storage capacity that has been requested or is planned, in 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 capacity.

• The 1986 date is based on the understanding that spe:'t 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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