ML19274D160
| ML19274D160 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/05/1979 |
| From: | Gahm J PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML19274D156 | List: |
| References | |
| NUDOCS 7901150110 | |
| Download: ML19274D160 (7) | |
Text
.
OPERATING DATA REPORT DOCKET NO.
50-267 DATE 790101 c0MPLETED BY J. W. Gahm TELEPHONE (303) 785-2253 OPERATING STATUS NOTES 1.
Unit Name:
Fort S t.
Vrain, Unit No. 1 2.
Reporting Period:
781201 to 791231 3.
Licensed Thermal Power Out):
842 4.
Nameplate Rating (Cross Ne):
342 5.
Design Electrical Rating (Net FWe);
330 6.
Maximum Dependable capacity (Cross la'e):
342 7.
Maximum Dependable Capacity (Net }L'e):
330 8.
If Changes occur in Capacity Ratings (Itecs Number 3 Through 7) Since Last Report, Cive Reasons:
None 9.
Power Level To Which Restricted, If Any (Net PL'e):
231 10.
Reasons for Restrictions, If Any: Nuclear Regulatory Cocunission restriction (70%) pending reso1ution of certain Einal Safety Analysis Report and Technical Specification ges discrepancies. This unit is in the power ascension phase of startup testing program.
\\
This Month Year to Date Cumulative
- 11. Hours in Reporting Period 744 8,760
- 12. Number of Hours Reactor Was Critical 674.1 6.839.2 13.473.7
- 13. Reactor Reserve Shutdown Hours
- 0. 0
- 0. 0 0.0
- 14. Hours Generator On-Line 547.3 4,504.6 7,842.6
- 15. Unit Reserve Shutdova Hours
- 0. 0 0.0
- 0. 0 16.
Cross Thermal Energy Generated (FLH) 273,810 2,044,210 3,202,998
- 17. Cross Electrical Energy Genera'ted (FL'H) 98,583 6C,393 946,270
- 18. Net Electrical Ener4' Cenerated (FL'H) 92,476 609,092 851,451
- 19. Unit Service._ 'or N/A N/A N/A
- 20. Unit l',
- 2 C Factor N/A N/A N/A 21.
Unit L.,4 cit'
-?or (Using MDC Net)
N/A N/A N/A 2L Unit Capacity Factor (tarrg DER Net)
N/A N/A N/A 23.
Unit Forced Outage Rate N/A N/A N/A 24.
Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):
Refueling; March, 1979; 2 Months 25 If Shut Down at End of Report Period, Esti=ated Date of Startup:
N/A 26.
Units In Test Status (Prior to Coc:cercial Operation):
Forecas t Achieved INITIAL CRITICALITY 740201 740131 790115ouo INITIAt tECrRIC m 7612 761211 COMMERCIAL OPERATION
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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-267 Unit _Fo r t S t.
Vrain, Unit No. 1 Date 790101 Completed By J. W. Gahm Telephone (303) 785-2253 tbnth December, 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 194 2
0 18 192 3
0 19 192 4
0 20 167 5
0 21 190 6
0 22 189 0
7 23 189 8
0 24 181 9
59 25 102 10 117 26 132 11 141 27 157 12 188 28 168 13-203 29 189 14 197 30 189 15 196 31 190 16 196
- Generator on line but no net generation,
REFUELING INFORE\\ TION 1.
Name of Facility.
Fort S t.
Vrain, Unit No. 1 2.
Scheduled date for next refueling March 1, 1979 shutdown.
3.
Scheduled date for restart May 1, 1979 following refueling.
4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes*
If answer is yes, what, in To facilitate insertion of eight fuel test general, will these be?
elements.
If answer is no, has the reload
- NOTE:
If Technical Specification change fuel design and core configura-approval is not received from NRC in time tion been reviewed by your Plant for refueling, then the answer to #4 is Safety Review Committee to deter-NO and the reload fuel and graphite design mine whether any unreviewed have been reviewed.
safety questions are associated with the cere reload (Reference 10CFR Section 50.59)?
If no such review has taken place, when is it scheduled?
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
January 9, 1978 6.
Important licensing considera-Eight test fuel elements to allow:
tions associated with refueling, e.g.,
new or different fuel de-
- 1) Different fuel particle design.
sign or supplier, unreviewed design or performance analysis
- 2) To qualify near isotropic graphite.
methods, significant changes in fuel design, new operating pro-cedures.
7.
The number of fuel assemblies a) 1482 HTGR elements.
(a) in the core and (b) ir the spent fuel storage pool.
b) 0 in fuel storage wells.
S.
The present licensed spent fuel Capacity is limited by size only to about pool storage capacity and the one third of core (approximately 500 HTGR size of any increase in licensed elements).
No change is planned.
storage capacity that has been requested or is planned, in number of fuel assemblies.
REFUELING INFOIOfATION (CONTINUED)
/
9.
The projected date of the 1986 under the Three Party Agreement last refueling that can be (Contract AT (04-3)-633) between DOE, discharged to the spent fuel Public Service Company of Colorado (PSCo),
pool assuming the present and General Atomic Company.*
licensed capacity.
- Ihe 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 (I CPP). 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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