ML20069G067

Monthly Operating Rept for Feb 1983

ML20069G067
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/08/1983
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20069G056	List: ML20069G053 ML20069G067
References
NUDOCS 8303250009
Download: ML20069G067 (5)

Text

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.. e TSP-3 Att achcen t-33 Issue 2 Page 1 of 1 OPERATING DATA REPORT DOCKET NO. 50-267 DATE Mnrc_h 8. 1981 C0!!PLETED BY T. . M_ McRv4do TELEPHONE (101) 7A9_???4 OPERATING STATUS NOTES

1. Unit Name: Fort St. Vrain

2. Repordag Period: 830201 throuch 830228

3. Licensed Thermal Power (Wt): 842

4. Nameplate Rating (Gross >5ie): 142

5. Design Electrical Racing (Nec 15ia): 110

6. Maximum Dependable Capacity (Cross >$ie): 1&?

7. Maxiwa Oependable Capacity (Net 15ie): 110

8. If Changes occur in Capacity Ratings (Ita=s Number 3 ""hrough 7) Since Last Report, Give Reasons:

NONE

9. Power Level To Vhich Restricted. If Any (Net !5ie): 211

10. Reasons for Restriccians. If Any: Romerferinn en 70T nondine vennlurinn nf enne,neenn1 merava.

This Mcnth Year to Data Cumulative

11. Hours in Reporting Period 672 1.416 32.137

12. Number of Hours Reactor Was Critical 240.2 901.0 20.647.7

u. Reactor Reserve Shutdown nours 0.0 0.0 0.0

14. nours cenerator On-Line 132.0 778.7 13.953.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Cross Thermal Energy Generated (!i'd) 45.880.5 403.775.7 7.193.201.1

17. cross Elaetrical Energy Generated (>SiH) 7.728- 129.790 2.456.694

13. Net Electrical Energy Generated (111H) ?_970 116_9Q9 9.219.705

19. Unit Service Factor 19.6 55.0 43.4

20. Unit Availability Factor 19.6 55.0 43.4

21. Unit Capacity Tactor (Using 3cc Net) 1_2 25.0 21.1 l 22. Unit Capacity Factor (Using DER Net' 1.2 25.0 21.1 l

23. Unit Forced Outage Rate RO_4 49_O 17.4

... Shutdowns Scheduled over Next 6 Months (Type. Date, and Duration of Each): 830301 throuch 830312 (288 hrsi for niant recoverv: 830323 through 830412 (504 hrs) for surveillance testing.

r

25. If Shut Devn at End of Report Periad. Estimated Oate of Startup: 830312 l

26. Units In Test 5tatus (Prior to Ceac:ercial Operation): Torecast Achieved INITIAL C11TICALITY N/A N/A INITIAL 7.LECTEICITT N/A M/A i "/^

CONCH 03Ed'dO9830308 PDRADOCK05000g R

VEl55

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TSP-3 Attachmnt-3A AVERAGE DAILY UNIT POWER LEVEL Issue 2 Page 1 of 1 Docket No. 50-267 l

Unit Fort St. Vrain #1 Date March 8, 1983 Completed By L. M. McBride Telephone (303) 785-2224 Month February, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL. .

(MWe-Net) (MWe-Ne t) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 n 21 0 6 0 22 0 7 0 23 0 1

8  ?? o 24 0 j 9 0 25 0 10 15.8 26 o 11 46.1 27 o 12 4R_n 28 n 13 qt 29 wi 14 An.9 30 N/A 15 9a i 31 N/A 16 0

• Generator on line but no net generation.

1SP-1 Attm harsit-IC lasue 2 ',*

Par.e 1 of I

.U,NI T SilUTDiM_NS A.N_D_P_lWE.R-~R~ EDUC11sNS - -~

InCR T fu, 50-267 UNIT NAME Fort St. Vrain #1 DATE March 8, 1983 _

COMPLETID BY L. M. McBride ,

l REPt*T ik)Nnt February, 1983_ TELErnoNE (303) 785-2224 l

HE11tOD OF SliUTTING DIMN SYSTDI COMPONENT No. DATE TYPE DURATION REASON REACTOR I.ER # 01DK O t0E CAllSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE 83-001 830201 F 173.7 H 3 N/A IBil INSTRU Reactor scram and turbine trip on 830128 due to nristure ingress.

Purification system operation and plant start-up.

83-00; 830208 F 38.7 D 4 83-003 - L - 0 CBI ZZZZZZ The turbine-generator was manually taken off-line to allow decreasing primary coolant temperature / pressure to prevent exceeding moisture limits of the Technical Specifications.

Reactor remained critical.83-001 830210 F 2.1 11 4 N/A IBil INSTRU Turbine-generator protective trip due to low main steam temperature.

Reactor remained critical.

83-00! 830215 F 325.5 A 2 83-007 - L - O EDD GENERA Manual reactor scram and turbine generator trip upon loss of "B" instrument bus. Instrument bus loss

- due to blown inverter fuse. Remained shutdown due to primary coolant impurities.

0

'o REFUELING INFORMATION

, 1. Name of Facility. Fort St. Vrain Unit No. 1

2. Scheduled date for next refueling shutdown. September 1, 1983

3. Scheduled date for restart following refueling. November 1, 1983

4. Will refueling or resumption of operation thereafter require a ,

technical specification change or other license amendment? Yes If answer is yes, what, in general, will these be? Use of type H-451 graphite.

If answer is no, has the reload fuel design and ' core configura-tion been reviewed by your Plant Safety Review Committee to deter-mine whether any unreviewed safety questions are associated with the core reload (Reference i 10CFR Section 50.59)? l If no such review has taken . -

place, when is it scheduled?

5. Scheduled date(s) for submitting proposed licensing action and Not scheduled at this time; supporting information. to be determined.

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 1482 HTGR fuel elements.

(a) in the core and (b) in .

the spent fuel storage pool. 11 spent HTGR fuel elements

8. The present licensed spent fuel pool storage capacity and the Capacity is limited in size to about one-size of any increase in licensed storage capacity that has been third of core (approximately 500 HTGR '

elements). No change is planned.

requested or is planned, in

number of fuel assemblies.

.. .T REFUELING INFORMATION (CONTINUED)

9. The projected date of the 1992 under Agreements AT(04-3)-633 and last refueling that can be DE-SC07-791D01370 between Public Service discharged to the spent fuel i Company of Colorado, General Atomic pool assuming the present l Company,andDOE.*

licensed capacitv. I

• The 1992 estimated date is based on the understanding that spent fuel discharged during the term of the Agreements will be stored by DOE.at the Idaho Chemical Processing Plant. The storage capacity has evidently been sized to accomodate eight fuel segments. It is estimated that the eighth fuel-segment will be discharged in 1992.

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