ML20236C373

Monthly Operating Rept for Feb 1989 for Fort St Vrain Nuclear Generating Station

ML20236C373
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/28/1989
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-89090, NUDOCS 8903220109
Download: ML20236C373 (9)

Text

- .

4

.i

~

,WE PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION l l

t h I 4 1

MONTHLY OPERATIONS REPORT l NO. 181 I l

February, 1989 ' l l

l l

j l

-- l

'A 2 4  ;

\

/

( .!

l i

8903220109 G90228 )

PDR ADOCK 05000267 PDC  !;.,

H 1

l l

. g - - - - ,

.* 3

-- .)-

R R

_1.- ,

This : report contains the~ highlights of the Fcrt St.1Vrain, Unit l j

No.1, activities operated- under the provisions of the Nuclear ',~

Regulatory Commission! Operating. License No. DPR-34. 'The report.for' j the monthly partial scram / maximum temperature reports for control . rod 1 drive and orificing assemblies is.not included this month because the-reactor was critical for a. short duration for ' operator ' training 1 startups only. This ' report' is for the month of February,: 1989, 1.0 NARRATIVE -

SUMMARY

- 0F OPERATING EXPERIENCE' AND J OR SAFETY MA' RELATED MAINTENANCE The reactor remained shutdown the entire month of _ February,1989, i for the continuation of removal of in-core reserve shutdown j material.and primary. coolant cleanup. , 1 1

Recovery .of the reserve shutdown material is expected to be 1 completed in early March of 1989. J

.1 Moisture is currently is excess of levels permitted for; reactor. - 1 startup. "An evacuation of the vessel for' . moisture removal -

-i purposes will begin~ approximately March lith. and should:be ,

completed by the end of March.1 At current moisture levels, 1 reactor startup is anticipated by April 1, 1989.' i The proposed cylinder' head refurbishment, repairs and inspections program for the Emergency; Diesel' Generators are . currently ' in- .

progress. A completion date of. March, 1989, is anticipated. l 1

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS-0F_J0% OF-THE ALLOWABLE ANNUAL VALUE None ,

1

?

o W _ _ _ - _ _ _ - - _ - - . - - _ . - _ _ - - - - - - - - _ - _ _ _ _ _ _ _ _ - -

.) -

c; .

3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None q 4.0 MONTHLY OPER TING DATA REPORT Attached 1

5.0 CONTROL R00 DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY TEMPERATURE REPORT l

Not required this month.

1 i

I l

l 1 f

1 i

l .

l l

.y

, s 6

• )

. OPERATING DATA REPORT DOCKET NO. 50-267 DATE March 15, 1989 -

C.0MPLETED BY M.L. Block  ;

TELEPHONE (303) 620-1180 ..

OPERATING STATUS NOTES l 1. Unit Name: Fort St. Vrain, Unit No. 1

2. Reporting Period: 890201 t.h rou ch 890228 l

3. Licensed Thermal Power (MWt): 842

4. Nameplate Rating (Gross MWe): 342 l S. Design Electrical Rating (Net MWe): 330 l

6. Maximum Dependable Capacity (Gross MWe): 342

7. Maximum Dependable Capacity (Net MWe): _

330

8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None

9. Power Level To Which Restricted, If Any (Net MWe): 270.6 f 10. Reasons For Restrictions, If Any: Reanalysis of safe shutdown cooling following' a 90 minute interruption of forced cooling.

' l This Month Year To Date Cumulative l

11. Hours In Reporting Period 672.0 1,416.0 84,745.0

12. Number Of Hours Reactor Was Critical 0.0 57.6- 37,302.4

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 0.0 0.0 25,072.8

15. Unit Reserve Shutdown Hours 0.0 0.0 '

O.0

16. Gross Thermal Energy Generated (MWH) 0.0 187.2 -12,887,897.3

17. Gross Electrical Energy Generated (MWH) 0.0 0.0 4,260,404.0

18. Nst Electrical Energy Generated (MWH) ;2.448.0 -6,277.0 3,743,717.0

19. Unit Service Factor 0.0 0.0 29.5

20. Unit Availability Factor 0.0 0.0 29.5

21. Unit Capacity Factp (Using MDC Net) 0.0 0.0 13.4

22. Unit Caoacity Factor (Using DER Net) 0.0 0.0 13.4

23. Unit Forced Outage Rate 100.0 100.0 64.8

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

• Nonc

25. If Shut Down At End Of Report Period, Estimated Date Of Startup: April 1, 1989 I

26. Units In Test Status (Frior To Comercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A .

COMMERCIAL OPERATION N/A N/A l

i

~>

i

a

.,- AVERAGE DA8LY UNIT POWER' LEVEL 3 E l

Docket' No.'5'0-267 -

< Unit Fort:St.- Vrain< Unit No.<1-a Date March 15,1989

' Completed By M. L. Block Telephone (303) 620-1180 Month FEBRUARY-DAY -AVERAGE DAILY POWER LEVEL 2DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 2 l ,,

.u 1 0.0 17- 0.0 _

2 0.0 18 0.0-2 3 0.0 19 0.0 4 . 0.0 .20. 0.0

.5 0.0 21 -0.0 6 0.0 22 0.0-l 7 0 . 0, 23. 0.0' 8 0.0 24 0.0 9 - i 0.0 25 0.0 t

10 0.0 ~ 26 '0.0 11 0.0 27 0.0 12 0.0 28 0.0 .

13 0.0 29 N/A 14 0.0 30- N/A 15 0.0 31 'N/A 0.0 16

• Generator on line but no net generation. -

j I

l I

_.____.._________m__._. __ _

W.' O;

~

..y Q" .

REFUELING' INFORMATION l- 1. . . l l 1. Name' of Facility 'l Fort St. ' Vrain Unit' No.1 l 4 l l. .1 l 2. Scheduled date for next l June.7, 1989 l' l refueling shutdown. I 'l l L l- . .

l l 3. Scheduled date'for restart. j' July 30, 1989- l l following refueling. l l l l 1 I 4. Will refueling or resumption ofl No .1 l . operation thereafter require a l -l l technical specification change.I l' "

l-l or other license amendment?- 1 l l } l l If answer is yes, what, in 1 ---------------- 1 J l general, will these be? l- 'l' l .

I I:

l If answer is no, has the reload l l' I fuel design and core configura-l 'l' l tion been reviewed by your l 'l-l Plant Safety Review Committee .1 No l .

l to determine whether any unre--l 1

.l . viewed safety questions are. I 1 l . associated with the core reloadj l l (Reference 10 CFR Section l .i l 50.59)?,_ l l-1 I l 1 l If no such review has taken i 1989 l l place, when is it scheduled?

l l l.

l 5. Scheduled date(s) for submit- 1.  : l.

I ting proposed licensing action l ---------------- l l and supporting information. I [

l l l l

l 6. Important licensing considera- l .l l tions associated with refuel- l l l ing,.e.g., new or different -l l l fuel design or supplier, unre- l ---------------- l l viewed design or performance l l l analysis methods,.significant' l l l changes in fuel design, new l l -

l operating procedures. l l l 1 l l 7. The number of fuel assemblies l .

l l (a) in the core and (b) in the l a) 148?. HTGR fuel elements l l spent fuel storage pool. I b) 0 spent fuel elements l l

L

.v . '

p REFUELING INFORMATION (CONTINUED)'

l ,l' l .

l' 8. The present. licensed spent fuell. I l ' pool storage capacity and the l .

. l.

l ' size of any increase in l Capacity is-limited'in size to- l l licensed storage capacity that I about one-third of core .. l- j l has been requested or i's' l.(approximately 500 HTGR elements).l. j j' planned, in number of fuel l No. change is planned. l.  !

l_ assemblies. l l. ,

l

~

l I l.

I . 9.-. The projected date of the last l 1996 under Agreements'AT(04-3)-6331 l refueling that can be dis- l and DE-SC07-79ID01370 between l I charged to the spent fuel pool l Public Service Company of l l assuming the present licensed -l Colorado, and General Atomic l. a l capacity. l Company, and DOE.* l' ') 1 The 1996 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 accommodate ~ eightL fuel segments. . It' is l i estimated that the eighth fuel segment will be discharged in 1996. l l

9 l

l

e _

6

~ _

C 1II ilIIIIiliI11IlllI 1I1 3 1 _

P .

S o _

T N y _

r y .

t t a r-n i m a e n i m m2 U r i h P r 3ce n 9 0 P au i 8 8 d $

Pts a 9 1 n d Sts r 1 k 1 a n -

TAI V c - a .

o 0 N t

. 5 l 2 O n s 1 1 B 6 I e p 7 S_ T m u 6 h . ) C e t _

2 t c l 3 A c r

- r r 0 E a a -_

0 o a 2 EC l t 5 F M M. 1 VN p S IE e _

. E E Y E TR R g OM T B N CR . n.

N A A O EU tp ip N D D H RC l u nu T E P RE on in E T T E OR Ba aa K I E L C rl e re C N L E T Tl O U P T DN oC C D M NE t r O AV at ot C E l n tn ER ua aarl SP cl U roo po eo AO i S CT CC OC N

O il l l

il1IIII lIl l

ll1 l

I T

T N C 9 E - Z U 8 N P Z D 9 O M Z E 1 PE C Z .

R MD Z Y OO Z R R CC E A 1IllI hlIIlI

l .II l W

l U M O R E P B TE B B E SD A A D F YO N SC A ilII l1 IIII! l' : lIiIII l1!l S

N W H #

O T A A D N R / /

T O E N N U M L H

S T R

T O I

P llIIii l l

.1IiIiIIIIIlII1 I!lI1 N E F U R OG N R _

DI O OT T 1 1 =

HTNC -

TUWA _

ElOE i MSDR IllIiIllIlIiIII1iIlIIIII1 1II1lllIIIlI1 - _

N -

O S

A H H -_

E R -

iiillilIIIIl _

1 I1 llllI!: l1ll N

t O 2 8 _

I T 2 3 A 1 0 _

R 1 3 _

U 1 _

D .

flllll ,1II' :I -

1I llH1II '

E P S F _

Y T _

iliililliiIII1Iii lI IIl1l:l 1

1!iI 1 5 E 0 0 T 1 1 A 0 0 _

D 9 9 8 8 1

il!

l 1 I!.I ,1Ilf ,'

2 1

. 1 0 O - -

N 8 9 8 8 _

11lIl1ll1ilIiIlI )lll Li

.li l -

.c Public Service' March 15, 1989 Ch Fort St. Vrain I Unit No. 1 P-89090 1

U. S. Nuclear Regulatory Commission i ATTH: Document Control Desk Washington, D.C. 20555 j Docket No. 50-267

SUBJECT:

FEBRUARY 1989 MONTHLY OPERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34

Dear Sir:

f Enclosed, please find the Monthly Operations Report for the mor.ch of February 1989, submitted per the requirements of Fort St. Vrain ,

Technical Specification AC 7.5.1.  !

i If you have any questions, please contact Mr. M. H. Holmes at (303) I I

480-6960. {

Sincerely,  !

l b C. H. Fuller Manager, Nuclear Production CHF/cas l

Enclosure 1

cc: Regional Administrator, Region IV '

ATTN: Mr. T. F. Westerman, Chief Projects Section B l Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain fff I \

l