ML20070A584

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Monthly Operating Rept for Dec 1990 for Fort St Vrain Unit 1
ML20070A584
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 12/31/1990
From: Block M, Fuller C
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
P-91023, NUDOCS 9101230243
Download: ML20070A584 (8)


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cenw.Co K1201 DM0 16605 WCR 19 1/2, Platteville, Colorado 80651 January 14, 1991 Fort St. Vrain Unit No. 1 P-91023 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267 ,

SUBJECT:

DECEMBER, 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 December, 1990, submitted per the requirement 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, hCharles.$H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF:DLW/bh Enclosure 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 l

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PUBLIC SERVICE COMPANY OF COLORADO 1

.. FORT $T. VRAIN NUCLEAR GENERATING STATION l MONTHLY DEFUELING OPERATIONS REPORT . ,

1 NO, 203 December, 1990 u

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This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated under the provisions of the Nuclear i Regulatory Commission Operating License No. OPR-34. This report is for the month of December, 1990, 1.0 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAISTERXNft ,

The reactor remained shutdown the entire month of December, 1990, following Public Service Company of Colorado's decision to end nuclear operation ct Fort St. Vrain.

Preparatio 3 for shipping spent fuel are proceeding.

On December 31, 1990, Public Service Company of Colorado was informed by the Nuclear Regulatory Commission that the Defueling Emergency Response Plan (DERP) was approved as submitted. The existing Radiological Emergency Response Plan (RERP) will remain in effect until DERP procedures and training are fully implemented.

2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS 6F 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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OPERATING DA1A REPORT DOCKET NO. 50-267 OATE _ January 15. J991 COMPLETED BY M. l.. Illock TELEPHONE /303) 690-1313 OPERATM3 STUS NOTE 5

1. Unit hame: Fort St. t'rnin . l' nit No. I
2. Reporting Fericci 901201 through 901231
3. Licensed Thermal Power (MWt): 842 4 Nameplate Rating (Gross MWe): 342
5. ;esign Electrical Rating (Net MWe): 330
6. Maximum Depencable Capacity (Gross MWe): 342
7. Mutmum Cepenoable Capacity (Net MWe): 330 i
6.  :' Changes Occur in Capacity Ratings (!tems humoer 3 Through 7) Since Last Report. Give Reasons:

Mnnn

9. Fe er tevel To Which Restrictec, if Any (het MWe): 0.0
10. Reasons for Restrictions. If Any: rnre St. t'r n i n conced nuc_ lent nenrntinn nn Aucune 99. 10A0.

This Mon'.h Year To Date Cumulative

11. Hours in Reporting Period 7dd -

R_76n 100.849

12. Numove Of Hours Reactor Was Critical N/A N/A A n . 9 7 K _ 7_ _
13. Peactor 8eserve Shutcown Hours N/A N/A N/A
14. mourg Generator On.Line M/A 9/A 27.777.4 j
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) M/A ,,,

M/A 4.R16_R14.0

18. Net Electrical Energy Generated (MWH) - 1. 7 L -21.325 4.251.679 '
19. Unit Service Factor N/A N/A N/A
00. Lnit Availability Factor N/A N/A . N/A
21. Lnit Cacacity Factor (Using MDC Net)- M/A M/A M/A
22. Unit Capacity Factor (Using DER Net) N/A N/A ,,

N/A

23. Unit Forced Outage Rate yfi y fi yfa
24. Shutoowns Scheouled Over hext 6 Months (Type. Date, and Duration of Each): Fort St. Vrnin ceased nurinnr nnnenrinn nn August 29. 1089 j
25. :' Shut Down At End Of Report Perloc. Estimateo Date Of Startuo: N /A f Forecast Ach1H ed
26. . nits in test Status (Prior To Comercial Doeratier):

1 NIT!AL CRITICALITV N/A N/A _

INITIAL ELECTRICITY N/A N/A ,

COMMERCIAL OPERATION N/A N/A

- -- -AVERAGE DAILY-' UNIT--POWER LEVEL-Docket-No. 50-267 Unit' Fort St. Vrain Unit No. 1 Date January 15, 1991 Completed By M. t.. Block Telephone (303) 620-1313 Month DECEMBER-DAY -AVERAGE DAILY-POWER' LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Not) (MWe-Net)

,- .1 .0.0 17 0.0 2 -- 0.0 18 0.0 3 0.0 19 0.0 4 0.0 20 0.0 5 0.0 21 0.0 $

6 00u 22 0.0

/ 0.0 23 0.0 ,

8 0.0 24. 0.0 9 0.0' 25 0.0 10- 0.0 26- 0.0 11~ 0.0- 27- 0.0-12 ' 0.0 28 0.0 13' O.0 -

29 0.0 14- _

0.0 30- 0.0 g -- 15 0.0 31 0.0 16 0 '. 0 Nuclear Operations-at Fort St. Vrain were-terminated on August 29, 1989.

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UNIT a m .N i AND t'OWLR RED 8JC T I ONS - ,

DOCKET RO.'50-267 UNIT N AME f o rt. St. Vra in Uni t No. 1 DAT E January 1b '991 t/.! iPLE T ED BY M. L. Block TELEP110NE'13Q3) 620-1313-RE POR1 ' MONTit - DECEMBER; 1990 .

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l- I i  ! l i 1 .I I I e Nuc l ea r Ope ra t i ons we re te rm i na ted on I 91 901201 1 . 724 rs ,0 i f i 1 1 N/A I .f A. I f:/A I F'l I l l t i Aug ts s t 29, 1989, see t.ER 89-018.

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Docket No. 50-267

.,' Unit Fort St. Vrain Unit No. 1 Date January 15,T991 Completed By M. L. Block Telephone (303) 620-1313 REFUELING INFORMATION r

l l i 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.

I FSV is expected. I l .

I 1 l 3. Scheduled date for restart i N/A l l following refueling. l l l l l l 4, Will refueling or resumption ofl N/A l l operation thereafter reyuire a l l l technical sp6:cification change l l l or other license amendment? I l l l l

.l If answer is yes, what, in 1 ---------------- l l general, will these be? l l

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l l l If answer is no, has the reload l l l fuel design and core configura-l l l tion been reviewed by your l l l Plant Safety Review Committee l N/A l l 'to determine whether any unre- l l l viewed safety questions are  ! l l associated with the core reloadj l

-l - (Reference 10 CFR Section l l

.! 50.59)? I l l l- 1

(~ If no such review has taken l N/A l l place, when-is it scheduled? l l l . 'l l l 5. Scheduled date(s) for submit- l l

-l ' ting proposed licensing action l ---------------- l l and supporting information. I _l

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- l 6 ,' Important licensing considera- l l

l. tions associated with refuel- I . l -.

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

i fuel design or supplier, unre- l ---------------- l l viewed design or performance l l l analysis methods, significant 1 i

-l --changes in fuel design, new I -l-l operating procedures.' l l L l l l l: 7. The rumber of fuel assemblies l l 1 -(a) in the core and (b) in the l a) 1024 HTGR fuel elements l l spent fuel storage pool. I b) 458 HTGR fuel elements l

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REFUELING INFORMATION (CONTINUED) l 1

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-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- 4 l has been requested or is 1 (approxi.tately 500 ETGR elements),1- ,

l -planned, in number of fuel l No change is planned. -l 4

l assemblies. I l l .

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-l l 9 - The projected date of-tht last l No further refueling is l l- refueling that can be. dis- l anticipated at Fort St. Vrain,

  • l l chr ged to the spent fuel 43o1 l l l assuming the present licenseo j l l capacity. I l Under Agreements AT(04-3)-633 and DE-SC07-791DG1370 between Public Service Companysof 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 acconnodate eight fuel segments, It is estimated.

that-the'_ eighth fuel segment will be discharg'ad in 1991. Discussions 4 concerning the disposition of ninth fuel.-segment are in. progress with DOE, Nuclear Operations _at Fort St, Vrain were terminated August 29, '

-1989.

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