ML19351E524
| ML19351E524 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/01/1980 |
| From: | Gahm J PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML19351E523 | List: |
| References | |
| NUDOCS 8012100337 | |
| Download: ML19351E524 (5) | |
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cvEsAT!nc 3ATA REPORT DCCKIT No.
50-267 2Arg 801201 cetetz:ro 3Y J. W. Gahm Tr:.zynast (303) 785-2224 OPERATING STATtS 8 sorts 1.
cnit Nane:
Fort St. Vrain 2.
Reporting Period:
801101 through 801130 3.
.icensed Thermal Power (,4it):
842 4.
'faneplace Rasing (Gross We):
342 3.
Design Electrical Rating (Net We):
330 6.
Maximum Oependable Capacity (Cross We):
342
~
330 7.
Maximus Dependable Capacity Ciet We):
3.
If Changes occur in capacity Ratings (Itema Number 3 Through 7) Since Last Report Give Reasons:
None c:o ch
'9.
?ower Level To Which Restricted If Any Olet }$ie): 231 w
10.
Reasons for Restrictions If aan Nuclear Retulatorv Cor.2 mission restriccion 70% cending <c.
resolution of temperature fluctuations.
c h
b This Month Year to :: ate C a lative 6
0 11.
neurs in neporting Period 720 8,040 12.457
=2 1.
Number of aours aaactor was critical 720.0 5.877.0 8.409.8
[
- u. Reactor Reserve shutdown sours 0.0 0.0 0.0 b
le. sours senerator on-t.ine 4.052.9 S.035.1 683.3 4
12.
"nic Resern Shutdown kurs 0.0 0.0 0.0 e
16.
cross :hernal Inergy cenerated osa) 352,068 1,371,344
- 2,349,299
- u=
~3
-17.
Cross Electrical Energy Generated 05iH) 123,965 603,429 744,225
.m ts. Net tieecrical energy camerated Osia)-
117,119 555,744 679,328 5.
- u. enic serrice ractor 94.9%
50.4%
40.4%
$30
- o.
nic Availability ractor 94.9%
50.4%
40.4' "5 "
a >
- 1. Unit capaciry ractor (Using Mcc Net) 49.3%
20.9%
16.5%
8" wa
- . ; nit canacity ractor (tsing :n Net) 49.3" 20.9%
16.5%
'5 5a
- 23. tatt Tor:no cutage rate 5.1" 26.8%
39.7%
24.
shuteowns seceduled over Next 6 Months (Trpe, cate, and Ouration of taca): 'faintenance and surveil-lance testing - March,1981 for aoproximately 3 weeks.
25.
If Shut Down at End of Report Period, Estimated Oate of Startup: '!/ A 26.
Units In *est Stac2s (Prior to Ccumarcial Operati:n):
rarecast Achieved N/A N/A IsinA:. cat :::Atm N/A N/A
- 3I :A:. :.Ic II:=
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AVERAGE DAILY-UNIT POWER LEVEL -
Docket No.
50-267 Unit Fort St. Vrain Date-801201 Completed By J. W. Gahm Telephone (303) 785-2224 Month November,1980
~
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 133 17 196 2
l'33 18 202 3
134 19 204 4
133 20 205 203 5
150 21 203 6-
'162 22 7
162 204 33 179 181 g
24 9
183 25 158 l
201 10 183 26 177 11 183 27 119 12 28 176 32-13 29 146 166 14 30
' 18' 15 31 N/A 16
- Generator on' line but no 'nat generation.
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~i REFUELING INFORMATION 1.
Name of Facility.
Fort St. Vrain. Unit No. 1 2.
Scheduled date for next refueling shutdown.
September 1, 1981 3.
Scheduled date for restart following refueling.
December 1, 1981 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
No If answer is yes, what, in' general, will these be?
?
If answer is no, has the reload The plant Operations Review Committee will i
fuel design and core configura-review any questions associated with the I
tion been reviewed by your Plant core reload.
l Safety Review Committee to deter-mine whether any unreviewed safety questions are associated I
with the core reload (Reference 10CFR' Section 50.59)?
I If no such review has taken place, when is it scheduled?
March 1, 1981 5.
Scheduled date(s) for submitting proposed licensing action'and supporting information.
6.
Important licensing considera-tions associated with refueling, e.g.,
new or different' fuel de-sign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating pro-cedures.
7.
The number of fuel assemblies a) 1482 HIGR fuel elements.
(a) in the core and (b) in the spent fuel storage pool.
b) 10 scent HTCR fuel elements.
4 8.
The present licensed spent fuel Capacity is limited in size to about one-pool storage capacity and the third of core (approximately 500 HTGR ele-1
- size of any increase ti licensed
=ents).
No change is planned.
storage capacity-that has been requested or.is planned,'in
-number of fuel' assemblies.
?
, ~. -. -.
5 ww
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REFUELING INFORMATION (CONTINUED) 9.
The projected date of the 1986 under the Three Party' Agreement (Contract last refueling that can be AT (04-3)-633) between DOE, Public Service discharged to the spent fuel Company of Colorado (PSCo), and General Atomic pool assuming the present Company.*
licensed capacity.
- The 1986 date is based on the understanding that spent fuel discharged during the term of the Three Party. Agreement will be shipped to the Idaho National Engineering Laboratory for storage by DOE at the Idaho Chemical Processing Plant (ICPP). The storage capacity has evidently been sized to accomodate fuel which is expected to be discharged during the eight year period covered by the Three Party Agreement.
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