ML20091A130
| ML20091A130 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain |
| Issue date: | 05/07/1991 |
| From: | Fuller C PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-91134, NUDOCS 9105140331 | |
| Download: ML20091A130 (1) | |
Text
- _ - _ _ _ _ _ _ _ _ _. -
Public Service Public Service-ce,.,. c -..a.
s P o tbt (W) f.
cenvet Co fC201050 16805 WCR 19 1/2, Platteville, Colorado 80651 May 7, 1991 Fort St. Vrain Unit No. 1 P-91134 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Docket No. 50-267 SUBJECT-MARCH, 1991, MONTHLY DEFUELING OPEP.ATIONS REPORT
REFERENCE:
Facility Operating License Number DPR-34
Dear Sirs:
Enclosed, please find the Monthly Defueling Operations report for the month of March, 1991, submitted per the requirements of Fort St.
Vrain Techrical Specification AC 7.5.1.
Please note that this letter and report was originally prepared on April 11, 1991, and was inadvertently misplaced prior to mailing.
This is a reproduction of the March, 1991, report.
If you have any questions, please contact Mr. M. H. Holmes at (303) 480-6960.
Sincerely, i$EYh it Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF:DLW/bh Enclosure cc: Regional Administrator, Region IV Mr. J. B. Baird Senior Resident Inspector Fort St. Vrain 9105140031 910507
/ y} f,
//
PDR ADOCK 05000267 R
V PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY DEFUELING OPERATIONS REPORT NO. 206 March, 1991 9ttry2S+9+2-
.].
This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated under the provisions of the Nuclear Regulatory Commission Operating License No. DPR-34 This report is for the month of March, 1991.
1.0 NARRATIVE SlJMMARY OF~~ OPERATING EXPERIENCE AND MAJOR ~ SAFETY
~tTKTED MAINTENANCE
~
R The reactor remained shutdown the entire month of March, 1991, following Public Service Cortpany of Colorado's cecision to end nuclear operation at Fort St. Vrain.
Preparations for shipping spent fuel are proceeding.
Construction of the Independent s ent Fuel Storage '.astallation e
(ISFSI) is proceeding.
On March 29,
- 1991, the Fort St.
Vrain Defueling Emergency Response Plan (DERP) became effective, replacing the Radiological Emergency Response Plan (RERP).
2.0 SINGLE RELEASES OF RADICACTIVITY CR RADIATION EXPOSURE IN EXCESS OF 10*. Of THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM 1RRADIATED FUEL
.G._XRiiik'T idif
~
~
None 4.0 MONTHLY OPERATING DATA REPORT Attached
l
'JE& AT I'd l AT A RE PORT
- .0CKET V.30-267 DATE April 15. 1991
- 0MPLITED By M.
I Block TELEFHONE (303) 6?O-1313 OPEPt t!'n 5'17US INOTES 1.
Unit Name:
fart St. "rnin.
'_'n i t
'S, 1
- . ecoorting Feriod:
910301 throuch 910331 3.
Licenseo therval Fower (Mdt):
442 4
Nameplate Rattrg (Gross MWe):
342
- esign Electrical Rating (het Pae)
130 6.
"animum Eecencable Capacity (Gress pa'el:
142 Vanimum Cecencable Capacity (Net Pae):
330 Mve s asons:
thances Otcur in Capacity Rattras
.'.tts Nacer 3 Througn 7) Since Last becort.
e leno 9.
inwer Level To which Restrictec. lf Any (Net vae):
0.0 10.
Reasons icr Gettr1ctions. li Any:
Fort h 'frnin cone.ed nuclenr <m e rn r i nn nn Aummr ?9_ 10R9.
This Month Year To Date Cumulative
- 11. Fours In Reporting Pertoo 744
?.160 101.000
- 12. Numoer Of Hours Eeactor Was Critical N/A N/A
'n 976.7 i
- 13. ;eacter Leserve Shutdown Hour 5 N/A_
N/A
'J / A 14.
curs Generator On-Line M/A
"/A 27.777.4 15,
.ntt Reserve Shutdown Nours N/A N/A N/A
- 6.
iross **erral Ercrgy Generatea iudH)
'; / A N/A _
14.450.651.2 2ress Electrical Energy Generatea (%w) 9/A 9/A 4.836.914.0 13.
'et Electrical Energy Generated (PWH)
-1.740
-5,106 4.2 E E73 19.
,.ntt Service esctor 9/A N/A N/A
- 00. Lnit Availat:111ty factor N/A N/A N/A 1.
LMt C30acity f actor (Using MDC Net)
M/A
"/A M/A
- 02. unit Cocacity factor (Using LER het)
N/A N/A N/A 23.
.-1t forcea Outa;e Rate
.. f 3
,, f 3 yf3 24.
inutdowns Ecneculed O C Next e Months (Type, ; ate, and Duration of Eacn):
Fort St. 'Jrain ceased nuc 1 m r nnnrntion nn Aucunt 29. 1999.
- E, :' 5%t :an At ind Of Feport Ferioc, t'.timatec Cate Of Startuo:
"!A lorecast Achieved
~ st Status (Pricr Ic Comercial C;eration):
.:. atts.*
e INITIAL CR17: CAL:Tv s/A N/A INIIIAL E ECTRI;lTV
,,A N/A CCMMERCIAL CTERAi!0',
N/A N/A
4 AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 l
Unit Fort St. Vrain Unit No. 1 Date April 15_t 1991 Completed By M. L. Block Telephone _(303) 620-1313 Month MARCH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(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
0.0 E2 0.0 7
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 I?
0.0 28 0.0 13 0.0 29 0.0 14 0.0 30 0.0 15 0.0 31 0.0 16 0.0 Nuclear Operations at Fort S+.. Vrain were terminated on August 29, 1989.
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Docket No. 50-267 Unit Fort St. Vrain Unit Wo.~T
{
Date April 15, 1991 Completed By M. L. Block Telephone (303) 620-1313 REFUELING INFORMATION l
I l
l 1.
Name d Facility l Fort St. Vrain Unit No. 1 1
I I
I l 2.
Scheduled date f6r next i None, no further refueling at l
l refueling shutdown.
I FSV is expected.
l I
I l
l 3.
Scheduled date for restart l N/A l
l following refueling.
l l
l I
l 1 - 4.
Will-refueling-or resumption ofl N/A l
l operation.thereafter require a j i
1.
technical specification change i I
I or other license amendment?
I l
I l
1
-If answer is yes, what, in
( ----------------
I l
l general, will these be?
I l
l 1
I I
If answer is no,-has.the reloadj l
l fuel design and-core configura-j l
1
-tion'been reviewed by your l
l l
Plant Safety Review Committee l N/A j
l to determine whether any unre-l l
l
-l viewed safety questions are l
l l
associated with the core reload l l
l
-(Reference 10 CFR Section l
l L
l
-50.59)?
l l
l-1 I
l If no such review has taken
-l N/A l
_l Place, when is it scheduled?
I l
l I
l l 5.. Scheduled date(s) for submit-l l
l ting proposed licensing action l I
-j and supporting-information.
I l
1 l
l 1.- 6.
.Important licensing considera-l l
l tions associated with refuel-
[
l I
ing, e.g., new or different-l l-l fuel design or supplier, unre-1 ----------------
I l.
viewed design or performance l
~l l'
analysis methods, significant l
l
[
changes in fuel design, new l
l l
operating procedures.
I l
l l
1 l 7.
The n aber of fuel assemblies l
1 l-l (a) in the core and (b)-in the l a) 1024 HTGR fuel elements l
~l spent fuel storage pool.
I b) 452 HTGR fuel elements l
REFUELING INFORMATION (CONTINUED)
I l
l l 8, The present licensed spent fuell L.crent capacity is limited in 1
j pool storage capacity and the j size to about one-third of core, l
.l
-size of any increase in l S04 HIGR elements.
Construction I
l
. licensed storage capacity that l of an Independent Spent Fuel l
l has been requested or is l Storage Installation (ISFSI) l l
planned, in number of fuel I with a capacity of 1620 FSV HTGR I
- l assemblies.
l elements is procteding.*
_.____l 1
l 1
l 9.
The projected date of-the last i No further refueling is l
l refueling 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-
[
I capacity.
l l
The Independent Spent Fuel Storage Installation (ISFSI) will be capable of storing the entire FSV core (1482 HTGR elements) with storage space for an additional 138 HTGR elements.
Under. Agreements AT(04-3)-633 and DE-SC07-791001370 between Public Service Company of Colorado, General Atomic Company, and 00E, 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 1992.
Discussions concerning the disposition of ninth fuel segment are in progress with
- 00E, Nuclear Operations at Fort St. Vrain were terminated August 29, 1989.
I
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