ML19343A143

Monthly Operating Rept for Aug 1980

ML19343A143
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/02/1980
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19343A141	List: ML19343A140 ML19343A143
References
NUDOCS 8009160288
Download: ML19343A143 (5)

Text

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CP! RATING DATA RI? ORT DocKIT No. 50-267 DATg 800902 CcxPLETE3 s! J. W. Gahm TE:.EPHCNE (303) 785-2253 OPERA!!NO STATUS No!ES

1. cnic Name: Fort St. Vrain

. Raporting Period: 800801 through 800831

3. Licensed nersal Power (Wt): 842 4 Naseplate Rating (Gross We): 342

5. Design Electrical Rating (Net .We): 330

6. P.axi:us Dependable Cavacity (Gross We): 342

7. Maximus Dependable Capacity (Net We): 330

8. If Changes Occur in Capacity Ratir.gs (Items Nu=ber 3 Through 7) Since Last Report, cive Reasccs:

None

1. ?over Level To Vhich Restricted, If Any (Net We): 231

10. Reaso ns for Restrictions, If Any: Nuclear Retulatorv Comission restriction 70i nendi- 2 resolution of temperature fluctuations.

This Month Year to Oate Cusulative

11. Mours in Raporti=g Period 744 5.855 10.272

11. Number of Hours Reactor Vas Critical 619.4 4,343.1 6,875.9

13. Reactor Faserve shutdeva Hours 0.0 0.0 0.0

14. aours cenerator on-Line 517.7 2,974.9 3.957.1

15. Unit Reserve shutdevu Sours 0.0 0.0 0.0

16. cross normai Energy Generated (Wa) 217,522 1,350.116 1.828.071

17. cross nettrical Energ7 Generated (wa) 66,793 429,129 569.925

13. Net tect-ical Inergy cenerated (Wa) 60,272 393,379 516.963

19. Unic service ractor 69.6% 50.8% 38.5%

o. Unit Availability factor 69.6% 50.8% 38.5%

1. : nit Capatiey raetor (;st=g MDC Net) 24.5% 20.4% 15.3%

2. Unit Capacity Factor (Using OE1 Net) 24.5% 20.4% 15.3%

23. Unit 7 arced outage Rate 24.5% 30.1% 44.0%

4. shutdowns Scheduled Over Next 6 Ponths ("ype, Date, and Duration of Iach): Throu2h Sectember 30.

1980, to ceciplete required surveillance te tting.

25. If Shut Devn at End of Report Peri:d. Estinated Oate of Startup: October 1. 1980

6. Units In Test status (Prior to Cc==ercial Operation): Forecast Achieved INIT:AL C2:TICAL f N/A N/A

1. 1. 1. "'^

l00

NITIALELECT1:@

WCIAI ^PERATION N/A N/A

F,NJJ SlHnWS ANJ[gy[R,3lBij(1pNy H F ET m). 50-267 UNIT NAnE Fort St. Vrain _

,,4T E 800902 __

cairinni af ,J. W. Gahm uu ouT norm August, 1980 n.u.rm NE (303) 785-2253 HE111013 OF EllUTTING MWN SYSTEH Coltr0NENT Mt. DATE 11frE l>URATION REASON HEACTOR 1.ER # u)DE O)DE CAUSE AND O)RRECTIVE ACTION TO PRFVENT RECUNRENCE 80-15 800804 F 65.2 11 3 N/A N/A N/A Reactor scram and turbine trip occurred due to loss of all four circulators.

80-16 800816 F 102.7 A 2 50-267/80-45 /03-L AD PIPEXX rurbiue tripped and reactor manually scrammed as a conservative measure due to rupture of a hydraulic .,11 supply 11ne.

80-17 800829 S 58.4 11 1 N/A N/A N/A Following a turbine runback as a result of personnel working on the EllC system, the turbine was manually tripped and the reactor shut down. This began the scheduled shutdown for surveillance testing.

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SUNIIARY: Scheduled shutdown for surveillance testing throughout the month of September. g

.. , ~ , . . . -. = . -. . . . . .

.,. AVERAGE DAILY UNIT POWER LEVEL

+

Docket No. 50-267 Unit Fort St. Vrain Date 800902 Completed By J. W. Gahm

$ Telephone (303) 785-2253 Month August, 1980

?

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t) (Mye_ Net)

I 1 128 17 _o_

2 133 13 _o_

l- 3 132 19 4 57 - 20 25 5 65 4

21 6

106 22 37 147 i 7 23 1

8 24 146 -

9 107 25 146 i 10 105 26 148 11 103 27 146 12 123 28 137 13 129 29 66 4

14 137 30  ;. 13 152 31 t 2

~ 16

- 9

,

• Generator on line but no net generation.

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. REFUELING INFORMATION-

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

2. . Scheduled date for. next refueling shutdown. June 1,1981

3. Scheduled date for restart following refueling. September 1,1981 2

'4 . Will refueling or resumption of

. operation thereafter require a technical' specification change

or other license amendment? No

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

l . If answer. is no, has the reload The Plant Operations Review Committee will fuel design and core configura- review any questions associated with the 4

tion been reviewed by your Plant core reload.

Safety Review Committee to deter-

, mine whether any unreviewed j safety questions are associated i

with.the core reload (Reference 10CFR Section 50.59)?

i

t. If no such review has taken

place, when is it scheduled? January 1, 1981

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

proposed licensing action and suonortine information.

1

6. Important licensing considera- -

tions associated with refueling, i e.g., new or.different fuel de-sign or supplier,'unreviewed j design or performance analysis l methods, significant changes in fuel design, new operating pro-

, cedures.

i J

7.- The' number of fuel assemblies a) 1482 HTGR fuel elements

'(a) in the core and. (b) in i the spent fuel storage pool. b) 82 spent HIGR fuel elements 1

8. 12un 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 h2 licensed ments). No change is planned.

s storage capacity.- that has been

- requested or is planned, in number of fuel assemblies.

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.- 1 REFUELING INFORMATION (CONTINUED) )

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. 9. Th> projected date of the 1986 under the Three Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Pub 11c l discharged to the spent fuel Service Company of Colorado (PSCo), and pool assuming the present General Atomic Company.* l licensed capacity. l

• The 1986 date is based on the understanding that spent fuel 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 be discharged during the eight year period covered by the Three Party Agreecent.

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