ML20059J106
| ML20059J106 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/31/1990 |
| From: | Block M, Fuller C PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-90282, NUDOCS 9009190169 | |
| Download: ML20059J106 (8) | |
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'$ Public Service' Eh P.o. Boa 840 Denver. Co 80201 084o 16805 WCR 19 1/2, Platteville, Colorado 80651 September 11, 1990 Fort St. Vrain Unit No. 1
.P-90282 U. S. Nuclear Regulatory Commission ATTN:' Document Control Desk l'
Washington, D.C.
20555 Docket No. 50-267
SUBJECT:
AUGUST, 1990 MONTHLY DEFUELING OPERATIONS REPORT
REFERENCE:
Facility Operating License Number DPR-34
Dear Sirs:
Enclosed, please find the Month 1'y Defueling Operations report for'the month of August, 1990, submitted per the requirements of Fort St.
-Vrain Technical-Specification AC 7.5.1.
If you haveanyquestions,pleasecontactMr.M.H.Holmesat(303) 480-6960.
Sincerely, Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station
[
CHF:DLW/bh Enclosure 1.
cc: Regional Administrator, Region IV-ATTN: Mr. J. B. Baird i
Technical Assistant IL Division of Reactor Projects 1
L Mr. D. Garrison 0 n,,,,t;v s Site Resident Inspector Fort St. Vrain 9009190169 900831 PDR ADOCK 05000267 R
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inis report contains th-highlights of the Fort St. Vrain, Unit No. 1, activities operateu under the provisions of the Nuclear Regulatory Commission-Operating License No. DPR-34. This report is for t.he month of August,1990, 1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor remained shutdown the entire month of August, 1990, following Public Service Company of Colorado's decision to end nuclear operation at Fort St. Vrain.
Preparations for shipping spent fuel are proceeding..
i 2.0 SINGLE RELEASES OF RADI0 ACTIVITY OR RADIATION EXPOSURE IN EXCESS-0F 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 h
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OPr*AT!NG OATA REPORT DOCKET NO.
50-267
-DAir September 14,'1990-COMPLETED BY M. L. Block' OPERAT*NG STATUS t10TES =
- 12 ' Unit Name Fort Er Vrain. Unit No? 1:
- 2.. Reporting Period:-
900801-through 900831
- 3. ~ Li;ensed. Thermal Power (MWt):
842 4. Nameplate Rating (Gross MWe):
342-
-;p
- 5.. DesigW Electrical' Rating (Net MWe):
330i i
- 6. -Maximum Dependable Capacity (Gross MWe):
342=
Max' mum _ Dependable Capacity'(Net MWe):
-330 7.
i
- 8. - - K Changes Occur in Capacity Ratings -(!tes:s'Nunoer,3 Througn 7)-Since Last Report. Give Reasons: -
Nnna 1
9.
Fower Level To Which Restricted, if Any (Net MWe):
0.0
- 10. Reasons For Restrictions, If Any:
Fnre st. Vrnin c an neri nucione nnerneinn nn Anoner 90_ tono.
-This Month Year To Date' Cumulative-
- 11. Hours In Reporting Period 744' 52831 97.920
- 12. Nunoer Of Hours Reactor Was Critical N/Ac N/A An.M7Kf7
-[
- 13. Reactor Reserve Shutdown Hours N/A1
-N/Al
- N/A
- I 14 Hours Generator On Line (1/ A '
N/A' 27.777.'4
- 15. Unit Reserve Shutdown' Hours N/A M/A N/A
- 16. Gross Thermal Energy Generated (MWH)
N/A
'N/A 14.450.651.2
- 17. Gross Electrical Energy Generated (MWH)
' N/A
'N/A 4.Rin.R1A.O
- 18. Net Electrical Energy Generated (MWH)
-1,791.0
-14,795.0-4,258,209.0
- 19. Unit' Service Factor N/A N /A M/A
- 20. Unit Availability Factor N/A N/A N/A_
i
- 21. Unit Capacity Factor (Using MDC, Net)
N/A N/A M/A-
- 22. Unit Capacity Factor (Using DER Net)
N/A N/A N/A
- 23. Unit Forced Outage Rate n/A w/A M/A q
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):
Fort St. Vrain ceased nuclonr nnorneinn nn Anonat 29. 1989.
- 25. If Shut Down At End Of Report Period. Estimated Date of Startuo:
N/A g
- 26. Units in Test Status (Prior To Commercial Doeration):
Forecast Achieved l
INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY
'N/A N/A C069tERCIAL OPERATION N/A N/A v
- a#
AVERAGE DAILY UNIT POWER LEVEL <
- d Docket No. 50-267 Unit! Fort St. Vrain Unit No.1.
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. Date September 14,'1990 l
.. Completed By M. L. Block Telephone (303) 620-1180 q
Month AUGUST i
- i, DAY.: AVERAGE' DAILY POWER LEVEL-DAY -AVERAGE DAILY. POWER LEVEL (MWe-Net)-
-(MWe-Net)-
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0.0 17 '
O.0 2
0.0-IBL OLO-
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-3 0.0 19.
'O.0 i
'4
'0.0 20-0.0 ~
5 0.0
-21 0.01 j
6 0.0 22:
'O.0-7.
0.0 23-
-0.0 8
0.0 24 0.0-
~
9 0.0
'25 0.0: ;
i 5
'10 0 '. 0
.26 0.0; 3
11-0.0 27
'O.0' i
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'O.0 28L 0.0'
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13
-0.0 29-0.0 l
14 0.0
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0.0 l:
15 0.0 31
- 0. 0
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'0.0
.I Nuclear Operations at Fort St. Vrain were termina'ted on Augu>t'29,-1989.-
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'. ' -l UNIT SHUTDOWNS AND POWER-REDUCTfONS DOCKET NO. 50-267 UNIT NAME Fort St. Vra in Uni t C :
DATE September ~ 14.'1990 COMPLETED BY M.
L;'BIock TELEPHONE t3031 620-1180 REPORT MONTH AUGUST. 1990 I
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ISYSTEM COMPONENTI TO PREVENT RECURRENCE-I-
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N/A I N/A 1 N/A-I Nuclear Operations were terminated on
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REFUELING INFORMATION) l
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Name of Facility 1-Fort St. Vrain Unit No. I' j;
i 2.
Scheduled date for-next-I J
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~l'None. no further refueling at l
H l-refueling shutdown.
l'FSV isLexpected.
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Scheduled date for restart-
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following refueling.
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l 4. _Will refueling or--resumption.off N/A;.
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l' operation'thereafter_ require:a l l
l technical specification: change 1
' l or' other license' amendmerit?
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If answer is yes, what nin 1:----------------
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' general ~, will-these be?
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l If answer is no,: has the reloadl; l
fuel design and core configura-l l'
' tion-been-reviewed by your l
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Plant' Safety Review Committee l>N/A
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- l to determine whether any unre-l' l
- l-viewed safety questiont are
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l-associated with'the cc?e reloadj l
(Reference 10 CFR Section:
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50.59)?
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i If no su': review has taken-l N/A l.'
l place, r.en is it scheduled?
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Scheduled date(s) for submit-l l
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ting proposed-licensing action l ----------------
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and supporting information.
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Important licensing considera-l
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.tions associated with refuel-l l
l ings e.g., new or different l
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fuel design or supplier, unre-l ----------------
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viewed design or performance l
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l analys_is methods, significant l
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changes in fuel design, new l
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l operating, procedures.
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1 I 7.
The number of fuel assemblies l l
l (a) in the core and (b) in the l a) 1024'HTGR fuel ele.nents l-I spent fuel storage pool.
I b) 446 spent fuel elements l
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'c.3 REFUELING INFORMATION (CONTIN 0ED):
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The present _ licensed spent;fuell' l-l-
. pool storage capacity,and the l l-i
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size of any increase in.-.. -
l-Capacity isilimited:in size-to l --
l:-
' licensed storage capacity that'l about one-third of core =
l _-
.I has been requested or_is-
-l;(approximately500HTGRelements).l l
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. planned,'in number of. fuel
--l-No change (is planned.
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' assemblies.
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The pro,Jected date of the last l-No further refueling'is l
l refueling.that can be dis -
l: anticipated at' Fort St."Vrein. *- -l-l-
charged to the spent fuel poolLl l-l assuming-the present licensed
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capacity.
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Under Agreements 'AT(04-3)-633 and DE-SC07-791001370 between Public Service' Company 'of Colorado, Genera 1 Atomic Company, and DOE, spent fuel: discharged during the defueling process,will'be stored by DOE at
-(
the Idaho Chemical Processing Plant.
Thef.:,torage capacity is R
presently sized to accommodate eight: fuel segments.
It'is-estimated:
that the eighth fuel segment will be discharged'in 1991. _ Discussions 1,
concerning the disposition ofLninth'. fuel. segment are in progress with DOE. Nuclear.0perations at Fort ~St.sVrain,were terminated August 29, 1989.
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