ML19323C358

Monthly Operating Rept for Apr 1980

ML19323C358
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/09/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19323C356	List: ML19323C355 ML19323C358
References
NUDOCS 8005150390
Download: ML19323C358 (5)

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8005150390

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OPERATING DATA REPORT DOCKII NO. 50-267 dan 800502 CoMPLEno sY J. W. Gahm TELEPEONE (303) 785-2253 OPERATING STA ES sous j 1. Unic Names Fort St. Vrain j 2. Reporting Period 800401 through 800430 T 3. ticensed Thermal Power OSit): 842

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4 Nameplate Rating (Gross We): 342

5. Design Electrical Racing Cret We): 330

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j 6. hximum Dependable Capacity (Gross We): 342

7. Maximum Dependable Capacity Ciet We): 330

3. If Changes occur in capacity Ratings (Items Numoer 3 Through 7) Since Last Report, Give Reasons:

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

10. *iteasons for Restrictions, If Any: Nuclear Regulatory Coc: mission restriction 70% pending resolution of temoerature fluctuations.

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This Month Year to Data Cumulative

11. Hours in Reporting Period 719 2,903 7,320

12. Nur. der of sours i.eacewe Was critical 697.0 1,560.9 4,093.7

! 13. Reactor Reserve shutdown sours 0.0 0. 0 _ 0.0

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14. nours cenerator On-Line 551.3 909.3 1,891.5

13. Unic Reserve shutdown sours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (WR) 245,462 406,611 884,566

17. Cross Electrical Energy cenerated Osta) 80,351 128,778 _ 269,574

! 13. Net nectrical Energy cenerated OsiH) 74,589 117,636 241.220

! 19. Unic service Factor 76.7 31.3 25.8

20. Unit Availability Factor

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76.7 31.3 25.8 31.4 12.3

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21. Unit capacity Factor (Using MDc Net) 10.0

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22. Unit capacity Factor (Using DER Net) 31.4 12.3 10.0

23. Unic Forced outage Race 23.3 .,

33.1* 54.7*

24. Shutdowns Scheduled Over Next 6 Months - (Type, Date, and Duration of Each): N/A I 23. If Shut Down'at End of Report Period. Istimated Date of Startup: N/A I

• These ' numbers reflect the correction of an error in the March,1980, report.

26. " nits in Test Status (P for.co commercial Operation): Forecast Achieved l

INInAL CaInCA:.In N/A N/A INITIAL ELECnICIn N/A N/A ColetERCIAL OPER, n0N N/A N/A L 1 - ......e._-..._.. . ._ ,

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UNIT SutnWWNS gD PQ kp41CluNS iocsET ras. 50-267 O g

UNIT NAME Fort St. Vrain #1 DATE 800502

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Courtriu eT J. W. Cahm kEPONT HONTil April y 1980 TEl.EPHONE (303) 785-2253  ?

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HETil0D OF l ,

SituTTING IM1WN SYSTEM COMPONENT NO. DATE TYPE Id*ATION MEASON REACTOR t.ER f 0)DE 01DE CAllSE AND COkRECTIVE ACTION 10 PREVFNT RECUdHENCE =

80-06 800408 F 30.0 A N/A N/A N/A N/A Turbine generator tritiped during a j Loop 1 shutdown due to instrument p roblems .

80-07 800417 F 0.0 F N/A N/A N/A N/A Reduced power due to primary coolant moisture and administrative controls.

80-08 800418 F 0.6 A N/A N/A N/A N/A Spurious trip while changing instru-ment modules, j l

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80-09 800418 F 118.7 .. N/A N/A N/A N/A Turbine tripped during a Loop 1 shut-down due to buf fer-mid-buf fer problem .

on "A" primary coolant. circulator.

l 80-10 800425 F 5.9 A N/A N/A N/A N/A Turbine taken off line to recover from a loop shutdown.

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80-11 800430 F 12.4 A N/A N/A N/A N/A Turbine taken off line to recover from a loop shutdown. '

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SUMMARY

Plan to continue operations at 70% power, t

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AVERAGE DAILY UNIT POWER LEVEL

. Docket No. 50-267 Unit Fort S t. Vrain Date 800502 Completed By J. W. Cahm Telephone (303) 785-2253 Month Ap ril, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY F0WER LEVEL (MWe-Net) (MWe-Net) 1 166 17 80 2 202 18 48 3 215 19 0 4 190 20 0 5 172 21 0 6 172 22 0 7 154 23 15 ._ ___

8 92 24 77 9 0 25 85 10 101 26 105 11 124 27 120 12 125 28 124 13 124 29 123 14 149 30 55 15 172 31 N/A 16 149

• Generator on line but no ' net generation,

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REFUELING INFORMATION

1. Name of Facility. Fort S t. Vrain, Unit No. 1

2. Scheduled date for next refueling shutdown. January 1, l'81

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

4. Will refueling or resu=ption of operation thereafter require a technical specification change or other license amend =ent? 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 t 10CFR Section 30.59)? I

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If no such review has taken place, when is it scheduled? July 1, 1980

5. Scheduled date(s) for submitting -

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proposed licensing action and supporting information.

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6. Important licensing considera- -----

tions associated with refueling, e.g., new or different fuel de-sign or supplier, unreviewed design or perfor=ance analysis methods, significant changes in

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fuel design, new operating pro-

! cedures.

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7. The number of fuel asse=blies a) 1482 HTGR fuel elements.

(a) in the core and (b) in the spent fuel storage pool. b) 244 spent HTGR fuel elements.

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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.

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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, Publ2e discharged to the spent fuel Ser dce Company of Colorado (PSCn), anc pool assuming the present General Atomic Ccepany.*

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 rear period covered by the Three Party Agreement.

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