ML20042E642

Monthly Defueling Operations Rept for Mar 1990 for Fort St Vrain.W/900413 Ltr

ML20042E642
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/31/1990
From:	Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-90132, NUDOCS 9004260306
Download: ML20042E642 (8)

Text

-

O Publ c Service'  ::*J"L.-

16805 WCR 19 1/2, Platteville, Colorado 80651 April 13, 1990 Fort St. Vrain Unit No. 1 P-90132 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267

SUBJECT:

MARCH, 1990 MONTHLY DEFUELING OPERATIONS REPORT

REFERENCE:

Facility Operating License Number DPR-34

Dear Sirs:

Enclosed, please find the Monthly Defueling Operations Report for the month of March, 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) 480-6960.

Sincerely,

& ;alh Charles H. Fuller t 3 Manager, Nuclear Production Fort St. Vrain Nuclear s Generating Station 40 hs c6 CHF:DLW/bhb gg Enclosure g cc: Regional Administrator, Region IV #

c>o ATTN: Mr. J. B. Baird s

$@ Technical Assistant y Division of Reactor Projects fh

.cc Lr g/@g c Mr. Robert Farrell LL Senior Resident Inspector, FSV (g Fort St. Vrain

.,s.

. ,a

s;,- y >;e,9n u- ,< _ _ , s 4

ot -

~

, f '

4- (

..E,'

1 -

-. 1 m.

s

.. w.

r

.J

+ '

IJ- , T . -L , ,

.,. ,j

.[ _ ,

> i i q

t

.'+h 1 g 4 -,

5 t -h

3. ,

.p i, -;

3; i

4 sl n

e

• if .

x-:r. ,

,o ,; g c 3

PUBLIC SERVICE COMPANY OF. COLORADO' . .

4  ?.

. :i FORT:ST. VRAIN NUCLEAR GENERATING. STATION- A L

q"

]

~

J r -

s:+

o $

x .

s

-a

.. s

n.. 8

• 6 r < a p,  ;,

4,. 4

[ 5

'f, e

i ;-

a 9

_ n'_-

.- .. 1 MONTHLY +DEFUELING 0PERATIONS: REPORT l _

w ,s j!

.,o a NO. 194i <;

i

'y.

- Marchi1990~- ,

, , Li a.

-3 te c?

M

'g-p

_w- l- J u

-- [

a, < .-

Tr.

T v. ,=-s .

u

~,, -

, 7"

.L:

(f i -b,

~ -

, i ne . l d,

- ' . bf,'

, t

?I

> ' '4:

m u. ,

[?- ~5 ,

.y'w This report contains the highlights of the Fort St. Vrain, Unit j No. 1, activities operated under' the provisions of the Nuclear Regulatory Commission _ Operating License No. DPR-34. This report is for the month of March, 1990.

1.0 NARRATIVE

SUMMARY

OF -OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE-l; The reactor remained shutdown the entire month of March, 1990,  :

following Public Service Company of Colorado's decision to end  ;

nuclear operation at Fort St. Vrain.  !

Preparations for shipping spent fuel are proceeding. .

2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS ,

OF 10% OF THE ALLOWABLE ANNUAL VALUE None f 3.0 INDICATION OF FAILED- FUEL RESULTING FROM IRRADIATED' FUEL- '

EXAMINATIONS None _

4.0 MONTHLY OPERATING DATA REPORT Attached f

b f

t 9

5 h

k

.I

4; '

.N *

- l t

1 i

gDERATINGDATAREPORT DOCKET NO. 50-267  !

DATE Anrf1 12. 1990 l t

COMPLETED BY M. L. Block TELEPHONE (303) 620-1180 ,

OPERat*'G STATUS NOTE $

l. Unit Name: Fort St. Vrafn. t' nit No. 1

2. Reporting Period 900401 throuch 900331 .

3. Licensen Therinal Power (Mut): 842 4  ;

hameplate Rating (Gross MWe): 342

5. Cesign Electrical Rating (Net MWe): 330

6. Martmum Dependable Capacity (Gross MWe): 342

7. Maximum Depensable Capacity (Net MWe): 330 f B.  :

1. Changes Occur in Capacity Ratings lltems Numoer 3 Througn 7) Since Last Report, Give Reasons:

wns

9. Fower Level To Which Restricteo, !f Any (het MWe): ' O.0

10. Reasons For Restrictions, If Any: rner Mr. Vrai n casamA nuelane onsvar4nn nn Annume 70. 10AQ. i' i

This Month Year To Date Cumulative

11. Nours in Reporting Period {

7AA ?_160 94.249 (

13. Nummer Of Hours Reactor Was Critical N/A N/A An %7K 7 -

I

13. Reactor Reserve Shut 00wn Hours N /A - N/A N/A [

14. nours Generator On-Line w/A Mll 27.777.4  :

15. Unit Reserve Shutdown Hours N /A N/A N/A  !

16. Gross Thermal Energy Generated (MWH) N/A N/A 14.450.651.2

17. Gross Electrical Energy Generated (MWH) }

N/A N/A ' 4 . A M . R *ta . 0

18. het Electrical Energy Generated (MWH) f

-1.918.0 -5.857.0 4.267.147.0 l

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

30. Lntt Availability Factor N/A N/A_ N/A j

21. Unit Capacity Factor (Using MDC Net) w/A w/A w / A __ (

28. Unit Capacity Factor (Using DER Net) N /A N/A N/A I

33. Unit Forced Outage Rate w /A w/A w/A 24 Shutoowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each): Fort St. Vrain cansad -

nur1 mar nnovar4nn nn An eme 29. 1989.

35. If Shut Down At End Of Report Perico. Estimated Date Of Startup: N /A ,

36. Units In Test Status (Prior To Cosmercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A IN!T!AL ELECTRICITY N/A N/A COPMERCIAL OPERATION N/A N/A

-(

k I

['

l Q , .[ .

%,g:. - AVERAGE DAILY UNIT POWER' LEVEL-f Docket No. 50-267 Unit Fort St. Vrain Unit No. 1-Date April 12,-3990 Completed By M. L. Block-Telephone (303) 620-1180 Month MARCH' DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY' POWER LEVEL-(MWe-Net) (MWe-Net) 1 0.0 17- 0.0 2 0.0 18 0.0-a 3 0.0 19 0.0 _

4 0.0 20. _ 0.0 5- 0.0 21' O.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 2 6 -- 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 0.0 31. 0.0 16 0.0 Nuclear Operations at Fort St. Vrain were terminated on-August 29, 1989..

e: .

~

UNIT SHUTDOWsts AleD POWER REDUCTIONS . *,

DOCMET No. 50-267 UNIT NAME rort St. Vra i n Un i t 900. 1 DATE April 12. 1990

~

COMPLETED BY Pt. L. Block TELEPHONE f3031 620-1180 REPOR,T MONTH . PIARCH. 1990 I l l 1 1 IMETHOD OFI l I I I I I I I I ISHUTTING I I $ I CAUSE A800 CORRECTIVE ACTIOes l I NO. 1 -DATE ITYPEI DURAT1081 i REASON IDOWN I LER f ISYSTEMICOMPOIIENTI TO PREVE81T RECURRENCE I I' I i i i IREACTOR I ICODE ICODE I I

't I- 1 I I .I I I I I I

189-091.900301 I rI 744.0 I r 1 1 1 N/A l N/A I N/A I Ituclear Operations were terminated on .I l i I I I I I I l' l August 29,.1989, see LER 89-018. I i l' I I I I I .I i i I I I I I I I l l I l- 1 I I i 1. I I I I -l I i

1. 1 I I I I i I I i I-

1. I I .I l- 1 I I I l- I I ~I i 1. 1 I I I I I. I I I I -1 I I I I I I.'~ l l- 1 I l' I I I I I I i i I I I I I I I- 1 I 1 l- l- I .l- "I l- 1 I I I I 1 .I I I I I I I .I I I i I l- 1 I- 1 I I l- I' l- 1 I I l- 1 I I I I I I I I I I I I I I I i 1 :I I I I I I I l- 1, I.

i I i i i :8. .I I I I I

_l I l- I I- I- 1 I I I I l Li l .I 1. 't I- l I- 1 I El l I I I l- 1 I l' I I 1 i # 'l' I i .I' I I I I I

.I l- 1- I l- l' i 1. I. I- I

.' t . 'I -1 I I l- I- .I -l. 1 1 I- .I 'l I 'I .I I I I I I I I ~l l I I I i i I I 1 .I l .I I I I -11 l- I l-E t -- 1 I l- 'l l' I' l- 1 I I ~

l- 1- I. l- l 'l 'I l- I' l- I l l l 8 I I I I- I -l I

~1 3- 1 I I I il I. I I l I .l 1 1 I 'l 1 1 .I I I I l -- .I 'I. I 1. I 3: l -l l' g- g '. g I .. .g '

1 1. I -- l- I_ l

'l I fl -1 I I i l' l. I I

~

- - - - _ - - . , + c,,. . . . _ , - .- - ..--._L-----,- . - - -

p 1 A ,cy ..

REFUELING INFOR!% TION 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 .I l 3. Scheduled date for restart l N/A -l l following refuelino. l.

l- l l 4. Will refueling or' resumption ofl N/A l l operation thereafter require a-l l l technical specification change-l l l or other license amendment?- I l l l I l If answer is yes, what, in l ----------------

l general, will these be? I ( ,

l l l If answer is no, has the reload l l ll l fuel design and core configura-l l l tion been reviewed by your l l-l Plant Safety Review Committee l N/A ll l to determine whether any unre- l l l viewed safety questions are l l l associated with the core reload l l-l (Reference 10 CFR Section l l l 50.59)? l l' l l I I If no such review has taken l N/A l l place, when is it scheduled? {-

1 I; l 5. Scheduled date(s) for submit- l l l ting proposed licensing action 1 ----------------

l l and supporting information.

l 1 ,

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 1; I analysis methods, significant l l-l changes in fuel design, new l l l operating procedures. I l-l l l l 7. The number of fuel assemblies l l l (a) in the core and (b) in the l a) 1024 HTGR fuel elements l l spent fuel storage pool. I b) 446 spent fuel elements l-

( . ..

.* .+

s ~

REFUELING INFORMATION (CONTINUED) l I I l 8. The present licensed spent fuell l 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 l about one-third of core l l has been requested or is l (approximately 500 HTGR elements).1 l planned, in number of fuel l No change is planned. l l assemblies. l l l l 1 l 9. The projected date of the last l No further refueling is l l refueling that can be dis- l anticipated at Fort St. Vrain.

• l l charged to the spent fuel pool l l l assuming the present licensed l l l capacity. l l Under Agreements AT(04-3)-633 and DE-SC07-791001370 between Public Service Company of Colorado, General Atomic Company, and DOE, spent fuel discharged during the defueling process will be stored by DOE at the Idaho Chemical Processing Plant. The storage capacity is presently sized to accommodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1991. Discussions-concerning the disposition of ninth fuel segment are in progress with DOE. Nuclear Operations at Fort St. Vrain were terminated August 29, 1989.

I