ML20051P936

Monthly Operating Rept for Apr 1982

ML20051P936
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/07/1982
From:	Mcbride L PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20051P760	List: ML20051P734 ML20051P936
References
NUDOCS 8205170405
Download: ML20051P936 (5)

Text

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e e TSP-3 Attcchama t-35 Issue 2 cPrRATIsc Dm arPoRT DocxtT so. 50-267 DATE 820507 compt.ITED 3Y L. M. McBride Tzt. Paoxe (303) 785-2224 OPERATINc STATUS notes g, gage 3 ,,, Fort St. Vrain

2. Reporting Period: 820401 through 820430

3. Licensed Thermal Power Oeft): 842 4 Nameplate Rating (Gross We): 342

5. Design Electrical Racing (Net We): 330

6. Maximus Dependable Capacity (crose We): 342

7. Maximus Dependable capacity (Net W ): 330

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

None

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

10. Reasons for Restrictions. If Any: NRC restriction of 70% pendine resolution of-tensperature fluctuations.

This Month Year to Data Cumulative

11. Hours in Reporting Period 719.0 2.879.0 2a Ran.n

12. sunoer of nours Raaetor was Critical 535.3 637.2 15.215.6

13. Reactar Reserve Shutdown nours 0.0 0.0 0.0

14. Mours cenerator on-Line 86.2 86.2 9.994.5

13. cnit Reserve shutdown aours 0.0 0.0 0.0

, 16. cross Thermal Energy cenerated (mm) 62,491.6 62,491.6 4.996.436.4

17. cross slectrical Energy cenerated (Wu) 5.691 5.691 1.697.047 1s. Net tiectrical znergy cenerated (mm) 160 -7.205 1.547.054

19. Unit Service Factor 12.0 3.0 40.2

23. Unit Availability Factor 12.0 3.0 40.2

21. Unit Capacity raetor (usins MDc set) 0.1- 0.0 18.9

22. Unit Capacity Paccor (esing DER Net) 0.1 0.0 18.9

13. Unit Forced Outage Rate 38.2 38.2 34.1

24. Shutdowns Scheduled over Next 6 Months (Type, Data, and Duration of Each): None l~

l 25. If Shut Down at End of Report Period. Estimated Date of Startup: 5/3/82

26. Units In Test Status (Prior to Commercial operation): Fo recas t Achieved IsITIAL cRITICALITT N/A N/A INITIAL ELECTRICITT N/A N/A cc:Df!RCIA*, 0PERATIc3 N/A N/A 8.2 0 517 o y d f m - __ _ ___.

TSP-3 Attachnent-3A AVERAGE DAILY CIIT POWER LEVEL Issue 2 Page 1 of 1 Docket :lo. 50-267 Unit Fort St. Vrain Date R9nsn7 Completed By L. M. McBride Telephone (303) 785-2224 Month Anril 1982 DAY AVERAGE DAILY POWER LEVEL

• DAY AVERAGE DAILY POWER LEVEL.

(MWe-Net) (MWe-Net) 1 0.0 17 50.5 2 0.0 18 23.3 3 0.0 19 41.1 4 0.0 20 23.4 5 0.0 21 0.0 .

6 0.0 22 0.0 7 0.0 23 0.0 8 0.0 24 0.0 9 0.0 25 0.0 10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 30 0.0 15 18.2 31 N/A 16 0.0

• Generator on line but no net generation.

TSP-3 At t as ta w sn t - 3C

!smise 2 ,

Page I of &

UNIT SituTDsMNS AND hWtR RFJ1UC1UNS 50-267 im*ET mi.

j UNIT NAHE Fort St. Vrain nAiE 820507 CoMrLETan af L. M2 McBride f nErouf Hoenn April, 1982 _ TELErmmE _{10 j ) 785-2224 HEUiOD OF SiluTTING 1RMN SYSTEH COPS'ONENT

IN). DATE TYPE IMIRATION REASON REACTOR LER # OUDE Q1DE CAUSE AND CnRRECTIVE ACTION TO PREVt'NT RfrURRENt

E 81-026 820401 S 331.3 B 2 N/A CBI XXXXXX Loop-split modification, i

l 82-001 820415 F 35.3 F 3 N/A IBH INSTRU liigh pressure scram - PPS.82-002 820418 F 10.0 H 4 N/A HBD INSTRU Turbine manually tripped due to electro-hydraulic control system up-

.f set during maintenance. Reactor remained critical.82-003 820418 F 5.0 A 4 N/A IIBD VALVEX Turbine manually tripped for maint-enance. Reactor remained critical.

82-004 820419 F 2.9 A 4 N/A IlBD INSTRU Turbine trip due to low hydraulic control pressure. Reactor remained critical.82-005 820420 S 251.7 B 2 N/A CJB XXXXXX Manual shutdown to change-out control j

rod drive (CRD) in region 19 as per request of NRC.

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6 m OIG CTFCRMA**CN

1. Name of ?actlit r. ?cr- Sc. Vexin Uni: ?fo . l . _ _ _

2. Scheduled data far sex: :sfueling shutdown. Oc:ober 1. 1983

3. Scheduled date for :sstarn folleving esfueli=r.  %-he 1. to83

/* . ' Jill :sfueling or :ssumption of ,,

~

operacion chereafter : squire &

t e 5 =d M. specificacion change or other license amendment? Yes ._.

If answer is yes, whac, in

_. teneral, will .hese be? Use of type H-451 graphite. __

If answer is so, has the reload fuel design and core configura-clon been reviewed by your Plan:

Safsey Raviaw Comai::se co decar- _ _ _ _

mise whether any unreviewed safecy questions are associated vi:h the core reload (2eference 10C7R See:1ou 50.39)? _ __

If =c such review haa :2 ken -- - -----

elacs. when is 1: schedulad? _ _ _ _

3. Scheduled dace (s) for submi::1sg proposed licensing action a=d succorting i= formation. Not scheduled at this time: to be determined.

6. I=poranc Licensing considers-tions associaced si-J: refueling, e.3. , new or Ad ##erant fuel de=

sign or supplier, unreviewed design or performe=ce analysis methods, significanc changes is fuel design, new operacing pro-endures. -

7. The number of fuel assemblies 1482 3 GR fuel elements (a) in :he core and (b) 1:

250 spent HTGR fuel ele =en:s the scan: ,,,el storage ecol.

3. "ha presen . licensed spene_ fuel pool storage capac1:7 and :he l Capacity is id=1:ad in si:e :o abc .: one-sias of any increase in licensed ' ch1rd of core (approximacaly 500 E GR storage' capaci.7 :ha: has been ele =eces). No change is planned.

i recuestad or is planned, is ,

number of fuel assemblies. -

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'9

w REFUELING INFORMATION (CONTINUED) i

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' Company of Colorado, General Atomic pool assuming the present Company, and DOE.*

licensed capacitv.

.

• 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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