ML19262C706

Monthly Operating Rept for Jan 1980

ML19262C706
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/01/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19262C704	List: ML19262C703 ML19262C706
References
NUDOCS 8002150451
Download: ML19262C706 (5)

Text

" ~

3 CPERATING DATA RIPORT DOCKZT NO. cin.-? A 7 dan 800201 CcteLznD si J. W. Cahm nI.zPacNE __

(303) 785-2253 cPERAnNe STATES m TEs

1. Unic Name: Fort S t. Vrain #1

2. Reporting Period: 800101 through 800131

3. Licensed Thermal Power Ostt): 842

4. Nameplate Rating (Cross We): 342

3. Design Electrical Rating Olet We): 330

6. Maximum Dependable Capacity (Gross W e): 342

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

8. If Changes Octur in Capacity Ratings (Items Number 3 Through 7) Since ust Report. Give Reasons:

None

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

10. Raasons for Restrictions, If Any: Nuclear Regulatory Commission restriction 70% pending resolution of temperature fit.m aations.

This Manch Year to Date Cumulative

11. sours in Reporting Period 744 744 5,161

12. Number of sours Ra4ctor was Critical 36.0 36.0 2,569.1

u. Rasetor Reserve Shutdown sours 0.0 0.0 0.0

14. sours cenerator On-Line 0.0 0.0 982.2

13. Unic Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (WR) 406.8 406.8 478,361.6

17. Gross nectrical Energy Generated (WH) 0.0 0.0 140,796

13. Net nectrical Energy cenarated (Wa) 0.0 0.0 123.584

19. Unit Service Factor 0.0% 0.0% 19.0%

20. Unit Availability Factor 0.0% 0.0% 19.0%

21. Unit Capacity Factor (Using MDC Net) 0.0% 0.0% 7.3%

22. Unit Capacity Factor (Using OZ1 Net) 0.0% 0.0% 7.3%

23. Unir iorced Outage Rate 0.0% 0.0% 65.1%

2 '. . Shutdowns Scheduled over Next 6 Months (Type. Date, and Duration of Each): Plant shutdown to replace helium circulator.

23. If Shut Down at End of Report Period. Estimated Data of Startup: 4-1-80

26. {( A[

Units In Test Status (Prior to Consnercial Operation): Forecast Achieved 1 INI nAL CRI!!CALITT N/A N/A y e INITIAL ELECTRICITT N/A N/A 8002150 c:MMERCIAL OPERATICN N/A N/A g

.r . . . ._. . . . _ _ _ . . . _ _ _ _ . .. . _ _ _ . . . _ _ . . . . _ - .

D-UNIT StilrMuntNS~ ~AND

~~

PtWPR SEl'tPCR)NS

~ ~

tocurr NO. 50-267 g UNIT NAME Fort St. Vrain #1 .t DATE 800201 coHrLETem ny J. W. Cahm urrouT Houns Jan ua ry, 1980 TEt.ErthlNE (303) 785-2253 HEniOD or -

suuTTINc IxWN SYSTEM cotTONLVT NO. DATE TYPE EAlMATION REASON REACT 0k Lkk # CODE CDDE CAtFSE AND COkkECTIVE ACTION Tu PREVENT RECtraRFNCE 79-14 791026 S 744.0 B 2 N/A N/A N/A Scheduled shutdown for plant mainte-nance and installation of region con- ,

straint devices was coupleted De-cember 24, 1979. Although the reactoi was critical at less than 2% for a brief period in January, discovery of a ruptured helium circulator statf(

seal necessitated plant shutdown to replace the circulator with a spare, report submitted on LER #80-01/01-T-u.

I e

i i

I SUtetARY : Plant shutdown January 8, 1980, to replace "B" helium circulator. Shutdown to continue through March, 1980.1 I

I$

AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort S t. Vrain #1 Date 800201 Completed By J. W. Gaho Telephone (303) 785-2253 Month January, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net) (We-Ne t) 1 0 17 0 2 18 3 19 4 20 5 21 6 22 7 -- 23 -

8 24 9 25 10 26 11 27 12 28 13 29 1 .

14 30 l 15 31 J/

16 ,

L

REFUELING INFORMATION

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. Novembe r 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 relsad 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 10CFR Section 50.59)?

If no such review has taken olace., when is it scheduled? March 1,1980 5 '. Scheduled date(s) for submitting - - - - - - - - - - - - -

proposed licensing action and supcorting 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 nu=ber of fuel assemblies a) 1482 HTGR fuel elements.

(a) in the core and (b) in the spent fuel storage cool. 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, storage capacity that has been requested or is planned, in number of fuel assemblies.

REFUELING UTFORMATION (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 Atoric Company.*

licensed capacitv.

• The 1986 date is based on the understanding that er,nt fuel discharged during the term of the Three Party Agreement will be shipped t. the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chemical 'rocessing 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.

.