ML20197H872

Monthly Operating Rept for Oct 1990 for Fort St Vrain.W/

ML20197H872
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/31/1990
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-90337, NUDOCS 9011200227
Download: ML20197H872 (8)

Text

. .._ .

Public Service' "Ah P.o. Box 840

. Denver, Co 80201 0840 16805 WCR 19 1/2, Platteville, Colorado 80651

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' November 15, 1990-Fort St. Vrain Unit.No- 1 F' ~P-90337 U. S. Nuclear Regulatory Commission '

ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

OCTOBER, 1990, MONTHLY DEFUELING 0PERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34 l'i '

Dear Sirs:

' Enclosed,:please find the Monthly Defueling Operations report for the

• month of October,.1990, submitted.per the requirements of Fort St.

Vrain Technical Specification AC 7.5.1.

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

• o 480-6960.

Sincerely , 3

M [k Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear ~ +

r Generating Station.

s .CHF:DLW/bh-p Enclosure ,

1 cc: Regional Administrator, Region IV ATTN: Mr. G. L. Constable,. Chief Technical. Support Section Division of Reactor Projects Mr. J. B. Baird '

-Site Resident Inspector Fort St. Vrain ool120o22[$$$$b67 pog ADOC PDC R 76g qo

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

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MONTHLY DEFUELING OPERATIONS REPORT NO. 201 October,1990

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i'I - -

e This report contains the1 highlights o f- the Fort St. Vrain, Unit

! No. 1, activities operated under the provisions of the Nuclear

- Regulatory Commission Operating License No. DPR-34. This report is for the month of October, 1990.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND -MAJOR SAFETY RELATED MAINTENANCE The reactor remained shutdown the entire month of October, 1990, following Public Service Company of Colorado's decision to end nuclear operation at Fort St. Vrain.

Preparations for-shipping spent fuel are proceeding.

4 -On _ October 18, 1990, an Erf rcement Conference was held with Region IV in Arlington, -Texas, as a result of an unplanned exposure event _ on September 19, 1990. This event resulted in 6 Notices of_ Violation.

, _ 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None-4,0' MONTHLY OPERATING DATA REPORT Attached

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r t+ J! N DATA rep 0RT DOCKET NO. 50-267 DATE Novomher 18;. 1990 COMPLETED BY M. L. Block _

TELEPHONE (303) 620-1180 OPERA **N3 5* TUS

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NOTE 5

1. Unit Name: Fort St. t* r s in . Unit No. I

2. Reporting Period 401001 thenunh 0010*41 *

3. Licensed Thermal Power (MWt): P,4 2

{ 4 kameplate Rating (Gross MWe): 342

5. ;esign Electrical Rating (Net MWe): 330

, 6. Maximum Dependable Capacity (Gross Mwe): 342 g ]

7. Maximum Dependabic Capacity (Net MWe): 330 l L 6.  :' Changes Occur in Capacity Ratings (Items humoer 3 Througn 7) Since Last Report Give Reasons: f Mnne 1

L-4 9 .' Fower Level To Whith Restricteo. If Any (het MWe): 0.0  !

10. Reasons For Restrictions, If Any: _Eort Et. Vrnin conced nucient enerneinn nn Aucune 90. 14R4.

This Month Year To Date Cumulative

11. ours In Reporting Period 745 7.296 99.385

12. Numoer Of Hours Reactor Was Critical N/A N/A LA M7K.7

13. Reactor Reserve Shutcown Hours N/A N/A N/A 14 ecurs Generator On Line N/A N/A 27.777.4

15. Lnit Reserve Shutdown Hosts .. N /A . . N/A N/A

. 16. Gross Thermal Energy Gener?ted (MWH) N/A N/A 14.450.651.2_

17. . Gross Electrical Energy Generated (MWH) N /A N/A 4.R16.R14.0

18. Net Electrical Energy Generated (MWH) 1.660 -18.075 4.254.929

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

20. Lnit Availability Factor N/A N/A N/A_ ,

21. Unit Cacacity Factor (Using MDC Net) M/A N/L 1 5

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

23. Unit Forced Outage Rate v/A v/A N/A  !

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each): Fort St. Vrain caased nurt nr nnerneinn nn Aucunt 29. 1989.

2$. lf Shut Down At End Of Report Period. Estimated Date Of Startup: N/A

26. Units in fest Status (Prior To Commercial Opere, tion): Forecast Achieved i INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COM ERCIAL OPERATION N/A N/A I t

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AVERACE DAILY _ UNIT POWER LEVEL b:( , . .. ,

Docket No. 50-267 pA' . i- " '

Unit' Fort St. Vrain Unit No. I Date November 15, 1990 Completed B/ M. L. Block Telephone (303) 620-1180 i

w Month OCTOBER

,,s DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL I," (MWe-Net) (MWe-Net) 1 .

0.0 17 0.0 vg i 2 .- 0.0' 18 '

O.0 M 3; 0.0 19 0..

" .l 0.0:

7' ' 4 .- _

20 0.0 Si 0.0 21 ,_

0.0 16 0.0 22 0.0 i 7: 0.0 23 0.0 l

, ;8. 'O.0" '24 0.0

-'  : 9' O.0 '

_ 25 0.0 10: ' O . 0 ~. 26' O.0'

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11- O . 0 -- 27 0.- 0 ,

7, '

, -12  ; 0.0 - :28 0.0 a

9 13- --0. 0 - 29' O.0 m g. , 14 LO.0 30- 0.0-

1. /15i, __& 0.0- 31- 0,0 =. j

'16 l 0.0

,  : Nuclear.. Operations at Fort St. Vrain were. terminated on August 29, 1989.

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-UNIT SitufDOWIIS AND POWER REDUCTIONS

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DOCKET NO.~50-76T *~

1 tMelT MAME Fort St. - Vra in Uni t No. 1

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DATE teovensber IL 1990 COMPLETED BY M. L. Blocis , , , , .

- REPORT MONIH - OCTOIMR. 1990 l i .l .I I iMETH00 0Fl I l l .

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l .lsMurTING 1:. I I I cAUSE Asso coRatcTIVE ACitoM i l 40. I 'DAiE .lTYPEI DURAT1086 l . REAS0st ' IDOWN ~ l. 'LER #. ISYSTEMICOMPOISENTI 10 PREVENT RECURRENCE I I I i 1 l- IREACTOR I ICODE ICODE I I I I I I I I l i i i  !

189-098 901001 l. F l- 78:5.0 ' l F i . 1- l M/A I N/A: I N/A i *0uc l ea r Ope ra t i on s we re te m i na ted on l

'l i I l!  ! I l l .- l ' I August 29, 1969, see LLR 89-018. I I I l I" l .I I I I I I i 1 I I I- 1 -1 i 1 l i i i I l- I l~ l i i l I i I i :I i 1 -. I i 1 1 I I I I .I' 'l i I I I I I I I i -1. I- 1 i i I .I I I l -. 1 1 I 'l i I I I I I I I- l' I -11 I I I l 1 -

l 1 1 I I l- 'l .I -1 I I i i I 'l- 1 1 1: I i i I I i 1 "I l -- I 1: -I 'l I i l i i 1 -I' i 1. I I I I I I I I I I :l~ l i I I I I I .I i l I i l I I i i 1 1 l I 1. .1 -- I I I I I I 1  ! :l l- -l i I I I I I i :I 1 't. I I I I i l I l' i 1 I I I I I I I I I I l' I i 1 i I I I I I I I l' _I I I I I l I 'l l i i 1 i i  !

1 I I i l I I I I I i I I l l I 'l .I- 1 I I I l l l l 1 1 I I l- I l-l  : I 't I I I I l i I i l 1 l= 1 .I I I I -1 1 1 l- I. ~1 I l- l '- I -1 -l' I i i i i 1. 1 l i I i i I I l l 1 -l l' I i 1 I

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V -

4 REFUELING INFORMATION

l. l l -

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

l l l ~ 2. Scheduled date for next l None, no further refueling at l l _, refueling shutdown. l_FSV is expected. l l l l t l 3. Scheduled date for restart l N/A l l following refueling. I I

_ l i 1 I  ;

l 4. Will refueling or resumption ofl N/A l  !

l operation thereafter require a l l

-1 technical specification change l l l l or other license amendment? l l l

.If answer is yes, what, in l l ---------------- l 1 generali will these be?' I -

.l

.If answer - 's- no, 'has the reload l l

, fuel design and core configura-l l tion been, reviewed by your

.I l l le Plant. Safety Review Committee l N/A l g l' to'_ determine whether any unre- l' l viewed safety questions are ~l. l

, associated with the core reload l l ,

I (Reference 10 CFR Section l  !

, 50.59)?~ l <

l t

. I I i' l -If no such review has taken l'N/A l place. when -is it scheduled? '

l_ l l .

l f E -l: 5.- Scheduled date(s) for submit- ~l_ l

-l- ting proposed licensi ng action l ---------------- i

.l and supp_orting information. l l  ;

I .

I. l .

Important licensing considera- l

. l 6. l 9

l .tions associated _with refuel- l l .;

l -.ing, e.g.,,new or different l l l

~l fuel. design or supplier, unre- l ---------------- 1; g l viewed design or: performance l l~

t l analysis methods, significant l l

l. changes.in-fuel design, new

~

l l .

p l operating procedures. l l'  :

l . -

.-. I I l-7.. The number of_ fuel assemblies l l-l -(a) in the core and (b) in the l a) 1024 HTGR fuel elements I r

l spent' fuel storage pool. I b) 458 spent fuel elements l 1

'l 4

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. 6_ . . . :-

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REFUELING INFORMATION (CONTINUED) l l l l 8.; The present licensed spent fuell l pool storage. capacity and the l l l l size of any increase in l Capacity is limited in size to l l licensed storage capacity that l about one-third of core l l- has been requested or is l (approximately 500 HTGR elements).l K

l planned.:in number of fuel l No chsnge is planned. l L assemblies. I l.

I '

,l l l k '

9. The projected date of the last-l No further refueling is [

refueling that can be dis- l anticipated at Fort St. Vrain.

• I charged to the spent fuel pool l l

l ~

assuming the present-licensed l l-l capacity. l l; 7

-* Under Agreements AT(04-3)-633 and DE-SC07-791001370 between Public Service Company of Colorado,. General Atomic Company, and DOE, spent p fuelfdischarged during the defueling process willlbe stored by DOE at-the Idaho Chemical 1 Processing Plant. The storage' capacity is-

. presently sized'to accommodate eight fuel' segments. It is estimated that.thefeighth fuel, segment will be' discharged in 1991. Discussions concerning the disposition of-ninth fuel segment.are in progress with

< DOE. Nuclear 0perations at Fort St. Vrain were terminated August 29,

11989.

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