ML19209B717

Monthly Operating Rept for Sept 1979

ML19209B717
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/01/1979
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19209B715	List: ML19209B714 ML19209B717
References
NUDOCS 7910100352
Download: ML19209B717 (5)

Text

.

OPERATING DATA RIPORT DOCKET NO. 50-267 DATE 791001 COMPLETED BY J. W. Cahm TELEPHONE (303) 785-2?53 OPERATING STATUS NOTES

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

2. Reporting Period: 790901 thru 790930

3. Licensed Thermal Power Out): 842

/. . Nameplate Rating (Gross We): 342

5. Design Electrical Rating (Net We): 330

6. Maximum Dependable Capacity (Gross We): 342

7. Maximu:n Dependable Capacity (Net We): 330 _

8. If Changes occur in Capacity Ratings (Items Nu:nber 3 Through 7) Since Last Report. Give Reasons:

None

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

10. Reasons for Rest *,etions If Any: Nuclear Regulatorv Commission restriction (70%) pending resolution of temperature fluctuations.

This Month Year to Date Cu:nulative

11. 'Iours in Reporting Period 720 ,

6,551 2,208 1.: . Number of Hours Reactor Was Critical 396.3 _2.952.3 16.426.0

13. Recctor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 13.7 1.307.1 9.149.7

15. Unit Reserve Shu:down Hours 0.0 0.0 0.0

16. cross Therr.al Enerr; Generated (&"rl) 16.162 644.453 3.847.451

17. cross Electrical Energy cenerated ($10 1.828 204.281 1.152.551

18. Net Electrical Energy cenerated (W H) 0.0 183.045 1.034.496

19. Unit Service Factor 1.9% 29.1% 29.1%

20. Unit Availability Factor 1.9% 29.1% 29.1%

21. Unit Capacity Factor (Using MDC Net) 0.0% 11.2% 11.2%

22. Unit Capacity Factor (Using DER Net) 0.0% 11.2% 11.2%

23. Unic Forced Outage Rate 98.1% 70.9% 70.9%

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

Maintenance Shutdevn, October 20, 19 79, 30 days

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

26. Units In Test Status (Prior to Cou::nercial Operation): Forecas t Achieved INITIAL CaITICALITY 740201 740131 INITIAL ELECTRICITY 9 7612 761211 CO.uRCIAL OPERATICN .7 91010 0 b90701 790701

tm!T Suum *. iS.

l Asn rtutR _R,r.itic;1?HS-1 KET PRI. _50-267 _

llNTT NAME Fort St. Vrain, Unit No. I nATE 791001 Conr!.ETrn nT J . W. Gahm REPORT HONTil pptember. 1979 1 Et.Ernoi4E _( 303) 785-2253 _

~ ~

HElllOD OF SHUTTING IMNN SYSTEH COMPONENT NO. DATE TYPE DURATION REASON REACTOR I.ER I CODE Q1DE CAlfSE AND CORRECTIVE ACTIO't TO PREVENT RECURP.ENCE 79-12 790901 F 706.3 11 4 79-035/01-T ZZ S UPORT Due to inconsistencies discovered in a random sample of safety related piping, an orderly shutdown of the plent was accomp'ished per agreement between Public Service Company and the Nuclear Regulatory Commission.

Reactor was restarted on September 15, 1979, but generator remained of f line due to low power levels.

M W*

Ln

%~

u N

S UNfARY : Plan to continue operation for electric production and fluctuation testing until release to contint'e power ascension testing above 70% received from Nuclear Regulatory Commission.

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort S t. Vrain, Unit No. 1 Date 791001 Completed By J. W. Gahm Telephone (303) 785-2253 Month Sep tembe r, 19 79 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 _

68 17 2 18 -n-3 19 _n_

4 20 5 21 6 22 7 23 8 24 9 25 10 26 11 27 12 28 13 29 14 30 15 31 N/A 16

• Generator on line but no net generation, Ii35 338

REFUELING INFOPRATION

1. Name of Facility. Fort St. 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 tuel 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 questipns are associated with the core reload (Reference  ! ,

10CFR Section 50.59)? l 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 scent fuel storage pool. b) 244 spent HTCR fuel elements.

8. The present licensed spent fuel Capacity is limited in rize to about one pool storage capacity and the third of core (approxies ;ely 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.

i b bbh

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 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 Plan t (I CPP) . 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.

I13b 340