ML19323H671

Monthly Operating Rept for May 1980

ML19323H671
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/02/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19323H653	List: ML19323H652 ML19323H671
References
NUDOCS 8006160036
Download: ML19323H671 (5)

Text

-

L. . . .

O DOCKET NO. 50-267 CPERAT!NC DATA RIPCRT 3A;g 800602 c0xPL =t3 af J. W. Cahm TELEPHONr (303) 785-2253 OP!7ATINC STAn1 liGTES

1. Unit Name Fort St. Vrain

2. Reporting Period: 800501 through 800531

3. I.icensed Thermal Power ($t): 84 2

4. Nameplate Rating (cross We): 34 2

3. Design Electrital Racing Clet We): 330 .

6. hximum Oependable capacity (cross We): 342

7. Nxinus Dependable Capacity (Net We): 330

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

None

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

10. Reasons for Restrictions. If Any: Nuclear Regulatorv Commission restriction 70t nondino resolution of temperature fluctuations.

This Month Tear to 3 ate cumulative Hours in Reporting Period 744 3,647 8,064 11.

744.0 2,304.9 4,837.7

12. Number of sours Reactor was critical 0.0 0.0 0.0

13. Reactor Raserve shuedovu aours 737.6 1,646.9 2,629.1 1a. aours cenerator On-t.ine 0.0 0.0 0.0

15. cnit Reserve Shutdown nours

16. cross Thers.1 nergy cenerated os.'u) 318.452 725.063 1,203,018

7. cross nectrical Energy ces rated (Wa) 108,245 237.023 377.819 102,377 220.013 343,597 is. Net nectrical Inergy cen rated osm) 99.1% 45.2% 32.6%

19. nit service raetor

20. Unic Avatiartitty ractor 99.1% 45.2% 32.6%

n. Unit capacity Factor (retag xoc Net) 41.7% 18.3% 12.9%

41.7% 18.3% 12.9%

. Unit capsetey ractor (Using :tR Net) 0.9% 21.7% 46.5%

23. Unic rorced outage Rate

24. Shutdowns Scheduled over Next 6 Months (Type. Date, and Ouration of taca): N/A _

25. If Shut Down at End of Report Period Estimated Oate of Startup: N/A

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRIT *CALITT N/A N/A INInAL EL cTRIc::T N/A N/A 80061600 N J ccamac A CP dan cN N/A N/A

ll w

_ E

_ C N

_ F k

R 1

1 r

e C v t

k o T

c n 3 N e I 5 E r a 2 V r 2 E R o V m - P t h 5

. a 8 0 e 1

t C 7 n .

8 2 N i n 0 . ) t O l w t 6 W ] T o r 0 0 C f d A

o 0 . 3 f t f 8 J ( E ou V h

_ t 1 ns E E E C

E e

Y k p t

T B N k t

A M i k

N

)

ao N I u i O

t o E r l T T

E t.

D e N t ir N na i

i n T A i r

o E b m C S r r o iA ur C Tf T

N E

N A O /

• E G N t >

Ont CO M

E TE A St

/

Y)

SO N i

tu.

l, C ,.

f t_

i F _

N __ 0 R. 8 E_ 9 d_ 1 A_

t P.

D y N_

A_ l a .

F I S

N __ R A

t n /

m E N  %

M_

i I'.

N U

B 0

U. H 7 F

oG l

S T N N R <

A T_ U uI 0 I_ P suT 8

/ t N, E i TNC U_ N ruMA N a eix nSI k E t

_ n o

l i

t 0 t 5 A a A

E r

R e n

e G

N O

I 4 r T e A 6 w ik t

o l

a P

e u

E P

F n i

T 1 t n

0 o t 3 C E 4 T

A 0 D 0  :

8 Y 1 R 1 A I

- R

). 0 F i

A 8 U S

AVERAGE DAILY UNIT POWER f.EVEL Docket No. 50-267 Unic Fort S t'. Vrain Date 800602 -

Completed 3y J. W. Gahm Telephone (303) 785-2253 -

?!onth May, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (.%'e-Ne c)

1 95 17 125 2 123 18 125 3 121 19 124 1

4 131 20 124 l 3 123 21 134 ,

l l 6 137 22 136 l

7 131 23 138 8 129 24 146 9 133 25 161 i 10 135 26 174 11 _

133 27 183 12 133 28 134

[

13 125 29 186 14 124 30 158 15 124 31 145 16 125 5

• Generator on line but no net generation.

REFUELING INFORMATION i

1. Name of Facility. Fort St. Vrain, Unit No. 1 l 2. Scheduled date for next refueling shutdown. June, 1, 1981 i

3. Scheduled date for restart -

following refueling. September 1,1981 l

l

. *. Will refueling or resumption of  ;

i operation thereafter require a technical specification change -

or other license amendment? No P

, If answer is yes, what, in general, will these be?

i

) If answer is no, has the reload The Plant Operations Review Committee will I i fuel design and core configura- review any questions associated with the

tion been reviewed by your Plant core reload. (

Safety Review Committee to deter-

.  ; mine whether any unreviewed

I safety questions are associated j l with the core reload (Reference j

l 10CFR Section 30.59)?

l 8 If no such review has taken

! place, when is it scheduled? January 1, 1981 2

5. Scheduled date(s) for submitting ---------------

proposed licensing action and supporting information.

6. Important licensing considera- -----------

tions associated with refueling,

) e.g., new or different fuel de- '

sign or supplier, unreviewed design or performance analysis ,

methods, significant changes in i fuel design, new operating pro-

! cedures.

7. The number of fuel assemblies a) 1482 HTGR fuel elements (a) in the core and (b) in the spent fuel storage pool, b) 238 spent RTGR fuel elements

8. The present licensed. spent fuel Capacity is limited in size to about one-pool storage capacity and the third of. core (approximately 500 HTGR ele-size of any increase in licensed men ts) . No change is planned.

storage capacity that has been requested or is: planned, in number of fuel assemblies.

1

, m---r A w , - - , , , - -

.a- r - + , . . , - w-. v v -,a,- .- - -zw w - n -,- ~

. . -.. . ._. _ - . . _ ~ - .. -

=

j REMELING INFORMATION (CONTINU?.D) 1

9. The projected date of the 1986 under the Three ' Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Public discharged to the spent fuel Service Company of Colorado (PSCo), and pool assusing the present General Atomic Company,*

licensed capacitv.

• The 1986 date is based on the understanding that spent fuci discharged during the term of the Three Party Agreement will be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chemical Processing Plant (ICPP) . The

, storage capacity has evidently been sized to accomodate fuel which is expected to i be discharged during the eight year period covered by the Three Party Agreement.

J e

--.. - - - , - . - . . . - , . , , -, , . . , - , , - . . .,-