ML20059P066: Difference between revisions
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| number = ML20059P066 | | number = ML20059P066 | ||
| issue date = 09/30/1990 | | issue date = 09/30/1990 | ||
| title = Monthly Operating Rept for Sept 1990 for Fort St Vrain Nuclear Generating Station | | title = Monthly Operating Rept for Sept 1990 for Fort St Vrain Nuclear Generating Station | ||
| author name = Block M, Fuller C | | author name = Block M, Fuller C | ||
| author affiliation = PUBLIC SERVICE CO. OF COLORADO | | author affiliation = PUBLIC SERVICE CO. OF COLORADO | ||
Latest revision as of 20:56, 6 January 2021
| ML20059P066 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/30/1990 |
| From: | Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-90312, NUDOCS 9010250094 | |
| Download: ML20059P066 (8) | |
Text
{{#Wiki_filter:.. _ .. . _ _ _ O Publ e Service' :%"L P.o. Box B40 Denver,Co 80201-OR40 16805 WCR 19 1/2, Platteville, Colorado 80651 October 10, 1990 Fort St. Vrain Unit No. 1 P-90312 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington. D.C. 20555' Docket No. 50-267
SUBJECT:
SEPTEMBER, 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 September, 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, 8k Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF:DLW/bh Enclosure cc:. Regional Administrator, Region IV ATTN: Mr. J. B. Baird Technical Assistant. Division of Reactor Projects Mr. D. Garrison Site Resident Inspector Fort St. Vrain
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This report contains the.! highlights _~ of .the Fort:St. Vrain, Uniti. , ,
. No. 1, activities operated under the' provisions:--^ofi the; Nuclear Regulatory Commission Operating License: No.- _DPR-34. This . report isl for the month of September, 1990. -t m 1,.
1.0 NARRATIVE'
SUMMARY
OF ' OPERATING EXPERIENCE <AND TMAJORESAFETYt
- ItEATED MAINTENANCE q The . reactor remained- shutdown the Jentire_ mon'th;of Sept' ember,- , !
1990, following Public Service' Company /of Colorado's"decisionJ.tol ' 1 end nuclear operation at Fort,St.'Vrain. . . i Preparations for, shipping spent: fuel are; proceeding. 7 ; ! 2.0 SINGLE RELEASES OF RADI0ACTIVITYiOR. RADIATION: EXPOSURE'I'N'EXCESSi. OF 10% OF THE-ALLOWABLE ANNUAL VALUE. -
- o. :!
None u, 3.0 INDICATION OF FAILED' FUEL RESULTING ! = FROM IRRAi)IATED i FUEL J- 3, IXAMINATIONS :: q None ' I y w 4 s.g 4~0 MONTHLY OPERATING DATA; REPORT-Attached , s j f
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6 l I OPERATING DATA REPORT DOCKET NO.' 50-267 OATE october 15. 1990 COMPLETED BY M. L. Block TELEPHONE (303) 620-1180 OPERATMiG STATUS NOTES
- 1. Unit Name: Fort St. Vrain. Unit No. 1
- 2. Reporting Period: 900901 throuch 400930
- 3. Licensed Thermal Power (MWt): 842 4 Nameplate Rating (Gross MWe): 342
- 5. Design Electrical Rating (Net MWe): 330
- 6. MaximumDependableCapacity(GrossMWe): 342
- 7. Maximum Dependable Capacity (Net MWe): 330 1
- 8. I' Changes Occur in Capacity Ratings (!tems Numoer 3 Through 7) Since Last Report, Give Reasons:
None '
- 9. Power Level To Which Restricted, If Any (Net MWe): 0.0
- 10. Reasons Fcr Restrictions, if Any: Fort St. Vrnin ennned nuclnne nnerntinn nn Atmitne 94. 14R4.
This Month Year To Date Cumulative-
- 11. Mours in Reporting Period. 720 6,551 98,640
- 12. Numoer Of Hours Reactor Was Critical -N/A N/A An:57K.7-l 13. Reactor Reserve Shutdown Hours N/A N/A N/A
- 14. Hours Generator On-Line N/A' 'N/A 27.777.4
- 15. Unit Reserve Shutdown Hours N/A N/A N/A
- 16. Gross Thennal Energy Generated (MWH) 'N/A- N/A 14.450.651.2 *
- 17. Gross Electrical Energy Generated (MWH) N /A N/A 4 '. R '16 . R 34 . 0 -
L 18. Net Electrical Energy Generated (MWH) -1,620 -16',415 4,256,589
- 19. Unit Service Factor N/A N/A N/A '
- 20. Unit Availability Factor ~ N/A N/A N/A l
- 21. Unit Caoacity Factor (Using MDC Net) N/A N/A l
N/A',
- 22. Unit Capacity Factor (Using DER Net) N /A N/A N/A ,
- 23. UnitForcedOtitageRate n/a n /f. 9/A -
- 24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each): Fort St. Vrain ceased niir i nne nnorneinn nn Aimus t 29. 1989.
l 25. If Shut Down At End Of Report Per so. Estimated Date Of Startup: N/A
- 26. Units in Test Status.'(Prior To Connere.31 Operation): Forecast Achieved Il INITIAL CRITICALITY N/A N/A INITIAL-ELECTRICITY N/A N/A COMMERCIAL OPERATION. N/A N/A
I. ; : AVERAGE DAILY UNIT POWER-LEVEL "
.a .
-Occket No..50-267 Unit Fort St.:Vrain Unit No.-1
- Date October 15, 1990 Completed-Telephone By [M.-L. Block-M3) 620-1180-L Month SEPTEMBER-
~
DAY AVERAGE DAILY POWER LEVEL- DAY: AVERAGE DAILY-POWER-LEVEL-(MWe-Net)- .(MWe-Net) 1 0.0l -17:.- '0.0-2 0.0= 18 0.01 p . 3 0.0 19= < 0.0 : . 4 0.0= ,
'20 > 0. 0 --
f 5 '0.0 21 ,.:0,0: ' 6 '0.0 J22 :0,0 7 0.0 '23 0.0' 8- 0.0 L24 0.0 i 9- 0.0 E25, 0.- 0 ': - 7 10 0.0 . 26 L- 'O.0" ' 11 0.0: *
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27 0. 0 ' ' R 12 0.0 28 ( :0.0:t
, m 13 0.0 29 -. '0.0~ ,
o 14 -0.0- ,30i - 0.0 15- 0.0: L 3I- N/A" >
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'16 0.0 , ,
If ' _
,5-NuclearOperations=atFortSt.Vrainwere'terminatedonAugustl29,:f!1989. :
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UNIT SHUTDOWNS AND POWER REDUCTIONS , 6 DOCKET NO. 50-267 . ~ UNIT MAME rort St. Vra i n Un i t No. 1 DATE October 19. 1990 COMPLETED BY M. L. Block
' ~ ~
. .. TELEPHONE 13031 620-1180 REPORI MONTH _ SEPT EMBER. 1990
~~
El 1 -I_ i i s IME.THoo or 1 -- .I I i l
'l -l CAUSE AND CORRECTIVE ACTION ci I. .. : l I .. . -11 JSHUTTING l .
1 l
~
l'NO.-1 DATE il TYPEl' DURATION 1 REASON ~1DOWN . I t ER g .. ISYSTEMICOMPONENT! TO PREVENT RECURRENCE, 'l
.1 - I_ l' l_ i lttEACTOR /l l CODE ICODE I I al I .I i 1 1 . I I 1 1 IQ9-09 ~900901 1: F l' ;720?t- " F l 1 1 'N/A :1-N/A .l- N/A I Nuclear Operations Were terminated on -l 1
l 1 l I l l August 29, 1969, see LER 69-018. I
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REFUELING INFORMATION-1 I I. Name of Facility l 1. 'l Fort St; Vrain Unit No. 1 l_ l - I . l l 2.. Scheduled date for next -l Nonet.no,further refueling at l- w l refueling shutdown, l'FSV is e'xpected. l l l' 1 1. l 3. Scheduled date for restart. -l N/A l [ following, refueling. l' l: I l 1: , l 4. Will refueling or resumption ofl N/A_ ~l-l operation thereafter require a l; - l-~ l technical specification change'.1-
'l l or other license amendment? - ' l- __l:
I l - l-
-If answer is yes, what, in-l l'---------------- 'l l genert1, will these be? I' l1 l .
If answer is no, has the reloadj
- l. l' 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 .j l Viewed safety questions are :: -l . l: 1 ' l associated with the core ~ reload ( - l, l (Reference 10 CFR Section' l l. l 50.59)? ll 1 : l-l If no such review has taken I N/A 'l : o l Place, when is it scheduled? l-j l . l. :\- a l 5. Scheduled date(s) for submit- l 1l: o l ting proposed licensing! action l --------------- i
.is I and supporting:information. l-
- l.
l - l:- I- d l 6. Important licensing considera- l- ,
- l .
I tions associt.ted with refuel- l -l .- l ing, e.g.,;new or differenti l , l l fuel design or supplier, unre- l ---------------- .l-l viewed design or performance. l-analysis methods, significant l Jll-
. changes in, fuel dasign, new .l' q operating procedures.
l l~ 9 l1 --
- 1. .
. l- l' l 7. The number of fuel assemblies
_l- l l (a) in the core and~(b)~". the l'a)=10241HTGR fuel elements' j
-l J l, spent fuel storage pool. I b) 446 spent-fuel elements o.
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-s REFUELING INFORMATION-(CONTINUED)- ;
a l l ll :- l 8. The present licensed spent.fuell '
, l, g ,
i l pool storage capacity and the .l ..
;- c l: '
l size of any increase:in l Capacity is limited;in size.toi 1.1 l licensed storage capacity 'that l abouti one-third of. core - . .. . : l; i has been requested or is, , -l(approximately'500HTGRelements).lE l l planned, in number of fuel l No change is'plannedi
-l-4 l assemblies. I ll - . .
l . l .l . l 9. The projected date of the,last-l No further refueling is' .
~
- t , 1 l refueling that can be dis- 1l anticipated.at Fort:Sti Vraing* :l .,
charged to the spent . fuel pool l 1
~
I l assuming the present licensed.:l- , l l capacity. :l = ' l? 9 I. Under Agreements .AT(04-3)-633.. andDE-SC07-791001370?between.Public$ Service Company of . Colorado, General Atomici Company,?andt. '00E, Espenti-fuel discharged during the.defueling process will-beistored.by. DOE at- .: the Idaho Chemical. processing : Plant.7 JThe~ istoragei capacity 11s: "
. presently. sized to accommodate'eight'fuelfsegments. JIt91s, estimated?
' that the eighth fuel segmentt will: be discharged int:1991~ ; Discussions..: gf concerni_ng the ' disposition Lof . ninth 1 fuel- segmentiare':ini progress with i 00E. Nuclear Operations at! Fort St.:Vrain weresterminatediAugust 29b i
1989. w , t q tr
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