ML19351A653
| ML19351A653 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/31/1989 |
| From: | Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-89477, NUDOCS 8912200248 | |
| Download: ML19351A653 (8) | |
Text
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-16805.WCR 19.'1/2, Platteville, Coloradd 80651 !
1 December 6, 1989 Fort St. Vrain Unit No. 1 , P-89477-I 0..S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop P1-37 Washington, D.C. 20555 Docket No. 50-267
SUBJECT:
OCTOBER 1989 MONTHLY OPERATIONS REPORT
Dear Sirs:
Enclosed, please find the Monthly Operations Report for the month of October 1989, submitted per the requirements of Fort St. Vrain Technical Specification AC 7.5.1. Nuclear Operations at Fort St. Vrain were terminated August 29, 1989.
-If' you' have any questions, please' contact Mr. M. H. Holmes at (303) 480-6960.
Sincerely, [k Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF:DLW/bhb Enclosure cc: Regional Administrator, Region IV ATTN: Mr. T. F. Westerman, Chief Projects Section B Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain (
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'This report: contains' the . highlights _-of the Fort St. Vrain,- Unit -
h- No. 1, activities operated under the provisions L of the. Nuclear Regulatory LCommission . Operating License No. DPR-34. This report is
'for the month of October, 1989.
1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE
- , The' reactor remained -sh'utdown-.the entire montn of October,1989,
'following Public Service Company of Colorado's decision to-~end nuclear operation at Fort St. Vrain.
. Preparations' for defueling'and decommissioning are proceeding.
2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS OF-10% OF THE- ALLOWABLE ANNUAL VALUE= None 3.0 INDICATION- 0F FAILED FUEL RESULTING- FRCM IRRADIATED FUEL EXAMINATIONS None
'.l 4.0 MONTHLY OPERATING DATA-REPORT-Attached 5.0 CONTROL ROD'! DRIVE PARTIAL SCRAM TEST RESULTS AND MAXIMUM DAILY
-TEMPERATURE REPORT-Not requirec this month.
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n i i l OP[PATING DATA rep 0RT DOCKET NO. 50-267 DATE November 15. 1989 COMPLETED BY _ M. L. Block TELEPHONE (303) 620-1180 Ort #ATI'd STATUS NOTES i
- 1. Unit Name Fort St. Vrain. '! nit No. 1 '
! 2. Reporting Period Roinni then..~h Ro1 nit
- 3. Licenseo Thennel Power (MWt): Ro? -
4 hameplate Rating (Gross MWe): 342
- 5. Design Electrical Rating (het MWe): 330
- 6. Maximum Depencable Capacity (Gross MWe): 342 '
- 7. Maximum Depensable Capacity (het MWe): 330 E. lf :hanges Occur in capacity Ratings (!!t s humter 3 Through 7) Since Last Report. Site Reasons: !
None 9- Power tevel To Which Restrictec, if Any = *iet Wel: 0.0
- 10. Reasons for Restrictions, If Any: Fort St. " rain ceased nuclear operation on August 29. 1989. ,
this Month Year To Date Cumulative
- 11. Hours Iri Reporting Period _
745.0 7,296.0 90.625.0
- 12. Numoer Of Hours Reactor Was Critical _ N/A N/A N/A
- 13. Reacter Reserve Shutdown Hours N/A N/A N/A
- 14. Mours Generator Ons tne N/A N/A N/A-l$. Unit Reserve Shutdowr. 49urs N/A N/A ,_, N/A
- 16. Gross ibermai Energy Generated (MWH) N/A 1.562.0/.1.1 16.690.691.9
- 17. Gross Electrical Energy Generate 0 (MWH) N/A 576.430.0 4.836.834.0
- 18. - het Electrical Energy Generated (MWH) -2,340.0 527,042.0 4,277,036.0
- 19. Unit Service Factor N/A N/A N/A
- 20. Unit Availability Factor N/A N/A N/A
- 21. Unit Caoacity Factor (Using MDC Net; N/A N/A N/A
- 22. Unit Cacacity Factor (Using DER Net) N/A N/A N/A
- 23. Unit for:ed Outage Rate N/A N /A N/A 24 Shutsowns Scheduled Over Next 6 Months ti :e. Cate, and Duration of Each): Fort St. Vrain ceased nuclear operation on Aucunt 29. 1989.
' 2$. . !f Shut Down At End Of Report Period. Est" atec Cate Of Startup: N/A Forecast Achieved
- 26. Units in Test Status (Prior To Conenercial heration):
1 INITIAL CRITICAL!!v N/A N/A
- INITIAL,ELECTRICITv N/A N/A COMMERCIAL OPERAi::N N/A N/A
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^ \ F* - AVERAGE DAILY' UNIT POWER LEVEL
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, :(MWe-Net)- (MWe-Net) b~
. '1' O.0 17- 0.0
'2 0. 0' :18 0.0 i
- 3 -0.0 :19 0.0
,\p,. - 4L 0.' O 20 0.0 54 ' O.0 ' 21 0.0 6- -0.0 22 0.0 7- 0. d -- 23 0.0
'8- 0.0- 24- 0.0 x-
- 9. 0.0' ~25 0.0-10' 0,0 26 0.0-
'll -0.0 _. 27 0.0
, 12 -0.0 28- 0.0 l 13'- 0.0- 29 0.0 114.' 0 '. 0 '- 30- 0.0'
~ 15- 0.0 31- 0.0-16- 0.0
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Nuclear OperationsTat: Fort St. Vrain were ter.r.inated on August 29, 1989. 1 E 1 t g;_ - i'M O .,,
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p. REFUELING INFORMATION l . l . l l ~ 1. Name of Facility I Fort St. Vrain Unit No. 1 l l -
. l . .
l 1 2. Scheduled date for'next. l None,-no further refueling at l l refueling shuteewn. 1 FSV.is expected. l-
- 1. l . l l 3. . Scheduled date for restart. l N/A l
- l follow' refueling. l l l- -l- I l' 4.- Will retueling or resumption ofl N/A l
.l operation'thereafter require a l l l . technical speification change l l l- or other licente amendment? l l l 1 If answer is yes, what, in 1 ---------------- l l general, will taase be? I l l -
I l l 'If answer is no, has the reload l l 1 fuel design anc_ core configura-l l l tion been reviewed by your l l l- Plant Safety Review Committee l N/A
.l. to determine wnether any unre- l l- . viewed safety ouestions are l l associated with the core reloadj l l (Reference 10 CFR Section -l l-l 50.59)?' 1 l
- l. I l l If no such review has taken l N/A l l place, when is it scheduled? I l 1 - . I l' l 5. Scheduled-date(s)-for submit- l l l -ting proposed l' censing action l ---------------- l l and supporting information. l l l - . . .
l l l 6.- Important licensing considera- l l
- l. tions associatec with refuel- l .l
;l- -ing, e.g. new cr different-
,- l- l
-l fuel design'or supplier, unre- I ---------------- l l- viewed design er performance l l l analysis methocs, significant l l l changes-in fuel cesign, new l l l -- -operating proce:ures. I l 1:- 1 l l-7. -The number of fuel assemblies l l l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l l spent fuel storage pool. I b) O spent fuel elements l y
i .
-,. . . - . ... ~. . . . - . . . . ,
c u. s-REFUELINGINFORMATION(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 ! Capacity is limited in size to l l licensed storage _ capacity that l.about one-third of cere.. l l has been requested or is l (approximately 500 HT3R elements).l l planned, in-number of fuel: l No nhange is planned. l l assemblies. 1 l l . I I l'9. The projected date of thilast-l No further refueling is l
-l refuelir.g 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. 1 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.
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