ML20064C088

Monthly Operating Rept for Sept 1978

ML20064C088
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/01/1978
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20064C083	List: ML20064C077 ML20064C088
References
NUDOCS 7810160103
Download: ML20064C088 (5)

Text

- .- - .- -. _ . - - _ . .

1 .

Orr.RATinc DATA atfo!E .DoCxET so. 50-267-DATE 781001 Cac 1.ETED cT J . TJ. Cahm TELEPuoxE (30 3) 785-2253

_0PERATING STATUS NOTES

1. Unit N.ne: Fort St. Vrain, Unit No.1

2. Reporting Period: 780901 to 780930

3. Licensed Thervi Power (Wt): 842

, 4. Nameplate Rating (Cross We): 34 2

5. Desisa Electrical Rating (Net We): 330

6. Maximum Dependable capacity (Cross 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:

Non.

l.

i

9. Power Level To Which Restricted If Any (Not We): 231

10. Reasons for Restrictions, If Anyt hinc v .erf eef nn ( 7f1T) n nAfnc, v..ni nef an of ceremin final safety analysis report and Technical Specification bases discrepancies.

This unit is in the power ascension phase of startup testing program.

• This Month- Year to Date Cumulative

11. Sours in Reporting Period 720 6.551 -

l 12. Number of sours Reactor was Critical 252.2 4, 756. 8 11,391.3

13. Reactor Reserve Shutdown Hours 0 0 0 i

14. nours cenerator on-Line 183.1 3,024.2 6,362.2

15. " nit Reserve Shutdown Hours 0 0 0

16. Cross Thermal Energy Generated (WH) 75.706 1,345,263

• 2,504,051

17. cross Electrical Ener Genera'ted (WH) 25.147 429.336 714,213 1s. Net Electrical Energy Generated (Wu) 21.165 392,127 634,486 l 19. Unit Service Factor N/A N/A N/A

20. Unit Availability Factor N/A N/A N/A

21. Unit Capacity Factor (Using MDC Net) N/A N/A N/A

22. Uhit Capacity Factor (Using DER Net) N/A N/A N/A

23. Unit Forced Outage Rate N/A 4

N/A N/A 1

24.

Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each): - ~~~

, Refueling. ' January. 1979: 2 months l 25.

If Shut Down at End of Report Period. Estimated Date of Startup:

J

26. Units In Test Status (Prior to Cournercisi operation): Forecast Achieved INITIAL CRITICALITY 740201 e

740131 INITIAL ELECTRICITY 7612 NNd1 CDMtERCIAL OPERATION -

761211 i

_ . . _ , , . _ , . , . . ..-__ __, _.m _ . . . , , _ , , - _ . . , . _ _ , _ . , - _ . , _ _ , , _ _ _ . , , - _ _ _ _ . , _ _ . . . -_,_m_,_ ._ ,,,_._ ___ , __,m. , _

i

UNIT SilVTDOWNS AND POWER REDUCTUNS DOCKET NO. 50-267 UNIT NAME Fo r t S t . Vrain , Uni t No . 1 DATE 781001 COMPLETED BY J. W. Gahm REP N T HONTH Sep tembe r , 1978

• TEI.EPHONE (303) 785-2253 IETHOD OF SIIUTTING DOWN SYSTEM COMPONENT NO. DATE ITPE DURATION REASON REACTOR LER # CODE CODE CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE -

78- 30 780908 S 536.9 B 1 N/A N/A N/A Routine plant shutdown for maintenance and testing.

s l

l SUmfARY : Plan to continue operation for electric production and fluctuation testing until release to continue 1

l power ascension testing above 70% received from Nuclear Regulatory Commiission.

l w

.1

= .

y AVERACE DAILY UNIT P0h'ER LEVEL 9

Docket No. 50-267 Unit Fort S t. Vrain, Uni! No. *.

Date 781001 Completed By J. W. Cahm Telephone (303) 785-2253 Month Sep tember, 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 103 17 0 2 132 18 0 3 131 19 '

0 4 132 20- 0 5 i 132 21 0

1 6 132 22 0 7 144 '23 0 8 84 24 '

0 9 0 25 O 10 0 26

! 0 11 0 27 0 12 0 28 0 '

13- .

0 29 0 14 0 30 0 15 0 31 N/A 16 0

• Generator on line but no net generation, D

4

s -

. e s

• RETUCLIIIC INFOR1ATION

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

2. Scheduled date for next refueling shutdown. January 1,1979

3. Scheduled date for restart following refueling. March 1, 1979

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes*

, If answer is yes, what, in To facilitate insertion of eight fuel test general, will these be? elemen ts If answer is no, has the reload fuel design and core configura-

• NOTE: If Technical Specification change tion been reviewed by your Plant approval is not received from NRC in time Safety Review Committee to deter- for refueling, then the answer to #4 is NO mine whether any unreviewed and the reload fuel and graphite design have safety questions are associated been reviewed.

with the core reload (Reference 10CFR Section 50.59)? _

If no such review has taken place, when is it scheduled?

5. Scheduled date(s) for submitting proposed licensing action and supporting information. January 9,1978

6. Important licensing considera-tions associated with refueling, Eight test fuel elements to allow:

e.g., new or different fuel de-sign or supplier, unreviewed 1) Different fuel particle design. .

design or performance analysis methods, significant changes in 2) To qualify near isotrophic graphite.

fuel design, new operating pro-cedures.

7. The number of fuel assemblies a) 1482 HTGR elements.

(a) in the core and (b) in the spent fuel storage pool. b) 0 in fuel storage wells.

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

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

PIFUELING INFOIDIATION (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 Plant (ICPP). The storage capacity has evidently been sized to accomodate fuwl which is expected to be discharged during the eight year period covered g by the Three Party Agreement.

b e

/

e 0*

_ _ _ _ _