ML20062C230

Monthly Operating Rept for Oct 1978

ML20062C230
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/02/1978
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20062C221	List: ML20062C216 ML20062C230
References
NUDOCS 7811070238
Download: ML20062C230 (5)

Text

-

~

• ormAftNC Dan preonT

!)nCKET, NO. 50-267 DATE 781101 CoretETED nT J. W. Gahmi TELEPuoNE (303) 785-2253 OPEPATINC STATUS

~

NOTES

1. Unit Name: Fort S t. Vrain, Unit No. 'l

2. Reporting Period: 781001 to 781031

3. Licensed Thermal Power OSit): 842 .

4. Nameplate Rating (Cross We): 342

5. Design Electrical Rating (Net We): 330

6. Maximum Dependable capacity (Cross Mle): 342

7. Maximum Dependable capacity (Net Wa): 330

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

None

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

10. Reasons for RestEctions, If Any: NRC restriction (70%) pending resolution of certain 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. nours in neporting Period 745 - _

7,296 -

12. Number of Hmrs Reactor Was Critical 720.2 _

5,477.0 12,111.5

13. Reactor Reserve Shutdown Hours 0 - 0 0

14. sours Generator on-Line 265.3 3.289.5 6,627.5

15. Unit Reserve Shutoovn Hours 0 0 0

16. Cross thermal EnerCy Generated (mm) 121.956 _l.467.219 2.626.007

17. Cross Electri:a1 Energy Generated (WH) 24,880 454,216 739,093

18. Net Electrical Energy Cencrated (51) 19,669 411,796 654,155

19. Unit Service Factor N/A N/A N/A

20. L%it Availability Factor N/A N/A N/A

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

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

23. Unit Forced Outage Race N/A N/A- N/A

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

Refueling, January, 1979; 2 months

25. If Shut Down et End of Report Period. Estimated Date of Startup: - - - - - -

26. Units In Test Status (Prior to Co:ntnercial Operation): Forecast ' Achieved INITIAL CRITICALIT*f 740201 740131 76QQy Oc2.% INITIAL ELECTRICITY 7612 .

761211 C0tNERCIAL OPERATION --- - - - -

UNIr SutmwS AND POWER REDUCTONS ,

D0cxET No. 50-267 UNIT NAME Fort S t. Vrain, Unit No. 1

, DATE 781101 t

COMPLETED BY J. W. Cahm REPORT MONTH _ October.1978 TELEPHONE (303) 785-2253 METl!OD OF Sl!UTTING DOWN SYSTEM NO. DATE TYPE DURATION COMPONENT REASON REACTOR LER # CODE CODE CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE 78-30 780908 S 98.6 B 1 N/A N/A N/A Routine plant shutdown for maintenance and testing.

78-31 781012 F 29.3 4 N/A N/A 11 N/A Surveillance testing caused unexpected turbine-generator load transient.

Transient caused automatic trip of turbine-generator and Loop 1 shutdown.

Reactor was not shutdown.

78-32 781017 F 351.8 A 2 N/A N/A 'A' 480 volt essential transformer N/A tripped due to internal fault. Turbine-generator automatically tripped.

Reactor was manually scrammed.

SUMMARY

Plan to continue operation for electric production and fluctuation testing until release to continue power ascension testing above 70% received from Nuclear Regulatory Conurission.

. 1

AVERACE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit Fort St. Vrain, Unit No.1 -

'Date 781101 Completed By J. E Cahm Telephone (303) 785-2253 Month Oc tober, 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Net) (MRe-Net) 1 0 17 17 2 'O 18 0 3 0 19 0 4 0 20 0

• 5 28 21 0 6 41 22 0 7 81 23 0 8 99 24 0

, 9 104 25 0 30 103 26 0 l 11 102 27 0 12 56 28 0 '

! 13' 0* 29 0 l

l 14 100 30 0 15 99 31 2 16 -

107 i

• Cenerator on line but no net generation.

l l

4*

. l*

REFUELING 1NPORft\ TION

1. Name of Facility. Fort 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?

If answer is yes, what, in To facilit. ate insertion of eight fuel test general, will these be? elements If answer is no, has the reload

• NOTE: If Technical Specification change fuel design and core configura- approval is not received from NRC in time tion been reviewed by your Plant for refueling, then the answer to.#4 is NO Safety Review Committee,to deter. and the reload fuel and graphite design

• mine whether any unreviewed have been reviewed.

safety questions are associated

' 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- Eight test fuel elements to allow:

tions associated with refueling, e.g., new or different fuel de- 1) Different fuel particle design.

sign or supplier, unreviewed '

design or performance analysis 2) To qualify near isotropic graphite.

methods, significant changes in

' 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 elements) . No change is planned.

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

. s REFUELING INFOR1!ATION (CONTINUEL)

/

9. The projected date of the 1986 under the Three Party Agreement last refueling that can be (Contract AT (04-3)-633) between DOE, discharged to the spent fuel Public Service Company of Colorado (PSCo),

pool assuming the present and 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 fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.

9 4

O e

5

. . .