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| number = ML20091J625
| number = ML20091J625
| issue date = 12/31/1991
| issue date = 12/31/1991
| title = Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/ 920115 Ltr
| title = Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/
| author name = Block M, Warembourg D
| author name = Block M, Warembourg D
| author affiliation = PUBLIC SERVICE CO. OF COLORADO
| author affiliation = PUBLIC SERVICE CO. OF COLORADO
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = P-92006, NUDOCS 9201140249
| document report number = P-92006, NUDOCS 9201140249
| title reference date = 01-15-1992
| document type = MONTHLY OPERATING ANALYSIS REPORT, TEXT-SAFETY REPORT
| document type = MONTHLY OPERATING ANALYSIS REPORT, TEXT-SAFETY REPORT
| page count = 8
| page count = 8

Latest revision as of 06:50, 25 September 2022

Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/
ML20091J625
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 12/31/1991
From: Block M, Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-92006, NUDOCS 9201140249
Download: ML20091J625 (8)


Text

- - - .

Putdic Servece Public Service- c- e c-~

16805 WCR 19 1/2, Platteville, Colorado 80651 January 15, 1992 Fort St. Vrain Unit No. 1 P-90006 U. S. Nuclear Regulatory Commission ATTN: Docu.nent Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

DECEMBER, 1991, MONTHLY DEFUELING OPERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34

Dear Sirs:

Enclosed, please find the Monthly Defueling 0;.erations report for the rmth of December,1991, 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) 480-6960.

Sincerely, i

l /h 0' )? ann bwh, D. W. Warembourg Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station l

DWW:MLB/as Enclosure cc: Regional Administrator, Region IV Mr. J. B. Baird Senior Resident Inspector Fort St. Vrain

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PUBLIC SERVICE COMPANY OF COLORADO  ;

e FORT ST. YkAIN NUCLEAR GENERATING STATION i 6

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MONTHLY DEFUELING OPERATIONS REPORT  ?:

NO .215 December, 1991-i.

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1-This report contains the highlights of the Fort St. Vrain, Unit ,

J

No. 1, activities operated under toe provisions of the Nuclear Regulatory Commission Operating License No. DPR-34. This report is for the month of December, 1991.

1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RilYE0 MAINilNANCE The reactor remained shutdown the entire month of Decer r, 1991, following Public Service Company of Colorado's decision- to end nuclear operation at Fort St vrain.

.. 5 On December 27, 1991, the first load of six fuel elements was deposited in the Fort St.~ Vrain Independent Spent Fuel Storage-Installation (ISFSI). During the month of December, a total of -

eighteen fuel elements were deposited in the ISFSI.

2.0 SINGLE RELEASES OF RAJ20 ACTIVITY OR RADIATION EXPOSURE IN EXCESS -

@~I W OTTRE ALLO 9ABLE ANNUAL VALUE None 3.0 INDICATION OF- FAILED FUEL RESULTING FROM IRRADIATED

~~ ~

FUEL ~

fiKMTiTA710NS L None t

4.0 MONTHLY OPERATING DATA REPORT Attached e

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P!t A11;iL(jATA .1POR1 '?DCKET NO , ?0-267 .

DATC hnuatv 14 14 01 -.- ,_ -

COMPLETED BY  % 1,. B 1 o c L , . ,,,,,

trLEet DQ1LE2.0:.J333  ;

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iNUTIS t

.. Unit hame: Fo t,t St. Vrain. l' nit Mo. 1

. Reportirt' 4too: 911?ni t,hrDUQM 911231 i

3. Lice.1ses itennal Power (MWL)! R42 ,

4 Nmeplats Rating (Gross MWe): 342 >

5. Design llectrical Rating (Ne, MWe): H0
5. *ntmum Lepencable Capacity (Gross MWeh _'M :'

' v aninum Cependable Choac't / (h MWe): Ujg. . .

I

6. '.hances 0: cur in Capacity k .ings iltems humoer 3 Througn 7) Since Last Report. Sive Nealota: '

None _ .- , _ , . , . -

l As - +

9. Eceer tevel Io hhtch Festr1CteQ. !I Anf j'tet MWel: 0.0 ,
10. Getsons Ier sestrictions. .f Any: ,_!,grt St. Yrn ig,,ngsp,,d nuc i o nr . opent i nn an,Jimun e '"1 . 10R4.

This Moith Year To Date Cumulative

11. Pours In Geporting Period 744 8.760 109.609
12. fiumoer Of Hours Reactor has Critical N/A N /,g ,, An. ;76_ L
13. Eeseter seserve Shutdown Hours N /4,,, N/A N/A 14 -::urs Generator On Line . N/A *! / A 27.777.fe
15. init Reserve Shutcown Hours N/A N/A ,,,,., N/A_ ij
16. "rcss *remal Energy Generates (MWH) N/A N/A 14.450.6E' L
  • ?. 5 cogs s';ectrical (netgy Generated (MWH)

, N/A N/A '4 . A 3 6 . 8 3 4 . 0

13. het Electrical Energy Generatec (MWH) ,

1,841 19,627 4 J39.169 -

19. Unit tervice Factor g A,, y /A ,,,,,,,,,,_
  • ! / A
20. Lnit Availability f actor N/A ,,,,,,,,,,,,,,,_

N/A .,,,,

N/A_; ,

21. kntt f.acacity f actor (Using MDC Net) v/A y/A *g/L l ,

j' 22. ' rtt Cacacity f actor (Ustng DER het)

. M/A N/A , N/A

23. '?1t Forces Outage Rate u /s z!A v/A
24. Snutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Eachlt Fort St. Vrai t) ceased i .iw1nnr nnornt 6n on Aunust ?9. 1989.

1 C5,  !< Shut uwn At End Of Report Period. Estimateo Date Of Startup: N/A

6. . nits in Test Status (Prior To Cor
rnercial 0:eration): forecast achieved INITIAL CRITICALITY N/A ,

- N/A-IN!T!AL ELECTRICIT Nia _

N/A i COMMERCIAL OPERATI0fi N/A N/A l -i ra'9'L--9'Tw= e y (m-w.,- em. g - e-'A.sge,.9 9.- -f-, -,-g.9--=9 y w,y.-9 yW g - - - y- g wair ema.5e ara,-yy g e- =em

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Y AVERAGE _0AILY UNIT POWER LEVEL [

Docket No. 50-267

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Unit To7t 3t. Vrain Unit No. 1

~~  !

l Date @ nuar'y ll, 1992 i Completed By M. L. Block ~

Telephone (155TTf0-1313 _--

i Month DEEEMBH __

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DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0.0 17 0.0 i 2 0.0 18 0.0  ;

3 0.0 19 0,0 i 4 0.0 20 '

O.0 ,

t 5 0.0 -21 0.0 ,

6 0.0 22 0,0 f

0.0 23 0.0 _

i 4 0.0 _

24 0.0 3 0.0 _

25 0.0 -

10 0.0 26 f} O '

i 11 0.0 -

27 0.0 12 0.0 28 _ _ . 0.0 13 0.0 29 '0.0 .- -

l 14 0.0 30 0.0 15 0.0 31 0.0 _

16 0.0 .

Tuclear Operations at Fort St. Vrain wereLterminated on August &9, 1989..

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, . Docket No. 50-267 i . Unit Fort St. Vrain Unit No. 1 .

t t Date January ~15,lV92 l Completed By fi. L. Block ~

l Telephone [lD3)_62QifT l

l

REFUELING _INFORMATION j 1 - .-

( l l l e I 1. Name of Facility -_j_ Fort St._Vrain Unit No. 1 l  !

! I l - 1 l 2. Scheduled date for next l None, no further refueling at i I re f uel,1,n3 t hutd_own ._ _. _.,1 TSV is expected. _I I I I l l 3. Scheduled date for restart l N/A l l followino refueling. I ,_ l l 1 l l 4. Will refueling or resumption off N/A l l operation:thereafter reovire a j l l technical specification change l l .

I or other licenso amendment? I _

_j 3

I I I I If answer is yes, what, in l ----------------- l l general, will these be? I __ , , _ , _ , .

,1 -

l l l l If answer is no, has the reloadi l I fuel design and core configura-l l .

I tion been reviewed by your l l l Plant Safety Review Committee l N/A l l to determine whether any unre- l l ,

i viewed safety questions are l l 1 associated with the core reloadj l l (Reference 10 CFR Section l I l l 50.59)?

0 I _ _l l l 1 -l .

i 1 If no such review has taken l N/A l d

] place, when is it scheduled? I _l 1 1 1 1 3. Scheduled date(s) for submit- . j- l l ting proposed licensing action ) --"---------~ l 1,,_ .and supporting information. I_ -_,l 1- .

I ,, l' l 6- . Important licensing considera- l l l _tions associated with refuel- l j t i ing, e.g., new or different l l i l' fuel design or supplier, unre- l ---------------- l_ _,

l viewed design or performanco ] _l l- analysis methods, significant i .l l changes in fuel design, new l l l operating procedures. _ ,,_, _ l l l .

I i-l 7. The number of fuel assemblies l- . _

l I' f a) in the core and-(b)-in the l a).1024 HTGR fuel elements l t l spent fuel storage pool. L,,b.) _ 422 HTGR fuel elements _ l {

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, , ,REFUEllNGINFORMATION(CONTINUED}

l l l l l B. The present licensed spent fuel l Onsite capacity is limited in 1 i i pool storage capacity and the. l size to about one-third of core, l

, I size of any increase in i 504 HTGR elements. C.nstruction i i licensed storage capacity that i of an Independent Spent Fuel j ,

I has been requested or is l Storage Installation (ISFSI) l 1 planned, in number of fuel l with a capacity of 1620 FSV HTGR l l 4ssemblies. l elements has been completed and l l J

l l and the facility has been l ,

i licensed by the NkC.* l

l I

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

, I refueling that can be dis- l anticipated at Fort St. Vrain. ** I _

l charged to the spent fuel pool l l l l assuming the present licensed l l l capacity. _ l _ ,_ _ l ,

-3 The Independent Spent Fuel Storage Installation (ISFSI), which is presently undergoing fuel loading, will be capable of storing the l entire FSV core (1482 HTGR fuel elements) with storage space for an '

additional 138 HTGR fuel elements.  ;

Under Agreements AT(04-3)-633 and DE-SC07-791001370 between Public. 1 Service Company of Colorado, General Atomic Comoany, and 00E, spent fuel discharged during the defueling process will be stored by DOE at the Idaho Chemical Processing Plant. The storage capacity is presently limited to eight fuel segments. It is estimated that the eighth feel segment will be discharged in 1992. Discussions ,

concerning the disposition of ninth fuel segment are in progress with '

00E. Nuclear Operations at Fort St. Vrain were tern ,ated August 29, 1939. >

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