ML19320A979

Monthly Operating Rept for June 1980

ML19320A979
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/01/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19320A978	List: ML19320A977 ML19320A979
References
NUDOCS 8007080409
Download: ML19320A979 (5)

Text

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CPEMTING DAM RDORT D0cKET NO. 50-267 DATE 800701 .

ceeLET:D 37 J. W. Gahm TEtnecNE (303) 785-2253 OPERATING STATc5 30Izs

1. cait Name: Fort St. Vrain

2. Reporting Period: 800601 through 800630

3. Licensed Thermal Power Olit): 842

4. Nameplate Ratiss (. Gross We): 342

5. Desigv Electrical Racing Olet We): 330 .

6. %ximus Dependable Capacity (Gross We): 342

7. Maximus Dependable Capacity (Net We): 330

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

None

9. Power Level To Which Restricted, If Any (Net We): 2 31 lo. Reasons for Restrictio n , If Any: Nuclear Regulatory Comission restriction 70% oendino resolution of temoerature fluctuations This Month Year to Date Cumulative

11. Ecurs in Reporting Period 720 4.367 8.784

12. Number of sours Ructor vsa critical 720.0 3.024.9 5.557.7

u. Ructor Reserve Shutdeva sours 0.0 0.0 0.0 la. aours cenerator on-Line 406.6 2.053.5 3.035.7 l 1

13. cnit Reserve Shutdown sours 0.0 0.0 0.0 I f

16. cross Thermal Energy cenerated (Wa) 244.228 969.291 1.447.246 1

17. Cross Electrical Energr Generated (Wa) 75_923 312.946 453.742

, ts. Net Eieecrical Energy cenerated (Wa) 70.314 290.327 413.911

19. cnit Service Factor 56.5% 47.0% 34.6%

to. cnic Availabiner rector 56.5% 47.0% 34.6%

21. enic capacity ractor (esing xDc Nee) 29.6% 20.1% 14.3%

22. cait capacity Factor (esing DER Net) 29.6% 20.1% 14.3%

23. cnic rare.d cutage Race - 43.5% 27.3% 46.2%

24. Shutdowns Scheduled over Next 6 Months (Type, Date, and Duration of Each): August 30 - September 30, complete required surveillance testing.

23. If Shut Down at End of Report Period, Estimated Date of Startup: N/A

26. enits In Test Status (Prior to coassereial Operation): Forecast Achieved InTut camcALITT N/A N/A I:rITut zLEcTRIcm N/A N/A N/A N/A 80070.8090f WERcw. cPEnIIoN

t unit SmrnxuNs ANE riuER RElIUC1DN,$

. ET IRI. 50-267 UNIT NAME Fort St. Vrain DATE 800701 CowirrED eT J. W. Gahm REPORT EMml June, 1980 inEPa>NE (303) 785-2253 ME11100 0F SHUTTING DluN SYSTEM COW ONENT NO. DATE TYPE DelRATION REASON REACTOR I.ER I CODE CDDE CAUSE AND CORRECTIVE ACTION TO PREVENT RFCURRFRCE 80-12 800617 F 313.4 H N/A N/A N/A N/A Turbine taken off line to recover shutdown loop. Reactor not shutdown.

}

SUMMARY

Continue power generation at < 70%.

h.

.- AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267

• Unit Fort St. Vrain Date 800701  !

Completed By J. W. Gahm Telephone (303) 785-2253 Month June. 1980

, DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 146 17 18 2 i63 18 0 3 182 19 0 4 191 20 0 5 191~ 21 0 6 190 22 0 7 192 23 0 8 191 24 0 9 190 25 0 10 188 26 0 11 188 27 0 12 188 28 0 13 186 29 0 14 186 30 62 15 185 31 N/A 16 183

• Generator on line but no net generation.

REFUELING INFORMATION

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

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

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

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

Safety Review Committee to deter-mine whether any unreviewed safety questions are associated with the core reload (Reference i 10CFR Section 50.59)? I If no such review has taken January 1, 1981 place, when is it scheduled?

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.

i

7. The number of fuel assemblies a) 1482 HTGR fuel elements (a) in the core and (b) in the spent fuel storage pool. b) 184 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 ele-size of any increase in licensed ments). No change is planned.

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

-- n.

~'*"

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 D0'E, Public discharged to the spent fuel Service Company of Colorad (PSCo), and pool assuming the present General Atomic Company.*

licensed capacity.

• The 1986 date is based on the understanding that spent fuel discharged during the term of the Three Party Aareement 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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