ML20010C186
| ML20010C186 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain |
| Issue date: | 08/03/1981 |
| From: | Mcbride L PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20010C185 | List: |
| References | |
| NUDOCS 8108190226 | |
| Download: ML20010C186 (5) | |
Text
.
TNTHTv OPERATING INFORMATION DISTRIBUTION Number of Copies Di re c t o r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -(j ) (Original of P Letter)
Office of Inspection and Enforcement U. S. Nuclear Regulato ry Commission 1ashington, D.C.
20555 Karl V. Seyfrit. Director 1
I l****#'
Region IV Of fice of Inspection and Enforcement Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Director - - - - - - - - - - - - - - - - - - ----------------- -- 2 (P Letter)
Office of Management Information and Program Control U. S. Nuci tar Regulatory Commission Washington, D.C.
20555 Ted Cintula 1
(P Letter)
U. S. Nuclear Regulatory Commission 12105 National Maryland Bank Building Washin gton, D.C.
20555 Mr. Richard Phelps 1
(P Letter)
FSV, GA, Site Rep rese nta tive General Atomic Company P. O. Box 426 Platteville, Colorado 80651 NRC Resident Site Inspector --------------------------- 1 (P Letter)
Senior Vice President, Room 770 1
(P Letter)
Vice President. Electrical Engineering and Planning, 30th Avenue - - - - - - - - - 1 (P Letter)
"ic2 President, P roductien Divis ion, Belleview - -
- - - - - - - - - - - - - 1 (P Letter)
Quality Assurance Manager
1 (P Letter)
S it e En ginee ring Coo roina to r - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)
Nuclear P roj ect Manage r, Mon tbello - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)
Cary Reeves, Public Relations, Room 950 - - --- --------- -------
1 (Griginal of Memo)
Bill Shinkle, Property Accounting. Holly Service Center 1
(Original of Memo)
Supe rvisor, Licenaing and Administrative Services, Nuclear Project Departmett, Monthello -
r-------
1 (P Letter)
Supervisor, Project Engineering Nuclear Project Depar* ment, Montbello - - - - - - 1 (P Letter)
Documents Control Technician, Montbello - - -- - -- - ------------
2 (2 P Letters)
Correspondence Coordinator, Nuclear Project Department, Montbello 1
(P Letter)
Nuclear Production Manag r - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)
Op e ra t ion s Ma n a g e r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)
Administrative Services Manager --------------
c ---------
1 (P Letter)
PORC Committee - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)
FS V N FS C S e c r e t a ry - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)
P Files ------------------------------------- 1 (P Letter)
R'.ord Storage - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2 (P Letter)
Technical Services Review ---------------------------- 1 (P Letter)
Technical Services Supervisor -------------------------- 1 (P Letter)
G re y Boo k Nc t e book - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 Monthly Operacions Folder ---------------------------- 1 Mon thly Operat in g In forma tion Folde r - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letterl Mont hly 03e rating Inf o rma tion File - - - - - - - - - - - - - - - - - - - - - - - - 0 (Original of Report and 1 Copy of P Letter)
Gas cooled Reactor Associates -------------------------- 1 (p Letter)
Attention:
Mr. R. A. Evans 3344 North Torrey Pines Court Suite 300 LaJolla, California 92037 Electric Power Research Institute - - - - -------------------- 1 (p Letter)
Attention:
Mr. Melvin E. lapides 3412 Hillview Avenue P. O. Box 10412 Palo Alto, California 94303 8108190226 810810 DR ADOCK 05000267 PDR r-
~.
OPEFATING DATA REPORT DOCLZT NO.
50-267 DATE 810803 COMPI.ETED ar L. M. McBride TELEPHONE (303) 785-2224 OPERATING STATUS NOTES 1.
cnit Name:
Port St. Prain 2.
Reporting Period 810701 through 810731 3.
Licensed Thernal Power (,Wt):
842 4
Nameplace Rating (Cross We):
342 3.
Design Electrical Rating (Net We):
330 6.
Maximum Dependable Capacity (Cross We):
342 7.
Maximus Dependable Capacity (Net We):
330 8.
If Changes Occur in Capacity Racings (Items Number 3 Through 7) Since Last Report, Give Reasons:
None 9.
Power Level To Which Restricted If Any (Net We):
231 10.
Reasons for Restrictions, If Any:
NRC restriction 70% oendine resolution of temperature fluxuations.
This Month Year to Data Cumulative
- 11. Hours in Reporting Period 744 5.087 18_298 l
- 12. Number of Hours Reactor Was Critical 391.2 3.056.7 12.141.4
- 13. Reactor Reserve Shutdown Hours 0.0 0O n_n 14.
Sours Generator On-Line 130.0 2_261.9 7-Qsa R
- 15. Unic Reserve Shutdovu Hours O_O nn nn 16.
Cross Thernal Energy Generated (WR) 56.99R.1 1 1SQ Al&_4
'l R67_507_7
- 17. Cross Electrical Energy Generated (51) 10.443 410.RR8 1 9R9_6R9
- 18. Net Electrical Energy Generated (51) 4.172 J _477 1.179_77R
- 19. Unit Service Factor 17.5 44.5
&L5 20.
Unit Availabiluy Factor 17.5 44_s 43.5 21.
Unit Capacity Factor (Using MDC Net) 1.7 22.2 19.4
- 22. Unit Capacity Factor (Using DER Net) 1.7 22.2 19.4
- 23. Unit Forced Outage Race 34.3 35.7 3 6. 9,_
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Maintenance /nodification shutdown September 1,1981 lastinct 4 months.
- 23. If Shut Down at End of Report Period, Estimated Date of Startup:
N/A 26.
Units In Test Status (Prior to Commercial Operation):
Forecast Achieved 1NI!!AL CRITICALITT N/A SI/ A INITIAL ELECTRICITT N/A
'U A CcHMERCIM. OPERATION N/A N/A n-
i UNIT SilUTIOWNS AND POWER REDUC 1DNS i)oCKET NO.
50-267 UNIT NAME Fort St. Vrain DATE 810803 COMPLETED BY
- h. M. McBride REPOtT HONTli July, 1981 TELEPuohE (303) 785-2224
~
HEIllOD OF SituTTit.C DOWN SYSTEM COMPONENT NO.
DATE _
TYPE DURATION REASON REACTOR LER #
CODE Q)DE CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRf.NCE 81-17 810520 S
504.1 C
N/A N/A N/A N/A Continued refueling outage begun May 20, 1981.
Turbine generator placed on line for test af ter repairs.
31-18 310722 S
42.0 B
N/A N/A N/A N/A Test of turbine generator repairs over.
31-19 810723 F
67.9 11 N/A N/A N/A N/A Turbine generator taken off line to recover Loop I.
W
-~
AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-267 Unit Fort St. Vrain Date 810803 Completed By L. M. McBride Telephone (303) 785-2224 Month July, 1981 i
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t)
(Mile-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
n.n 21 0.0 6
0n 22 0.0*
7 nn 23 0.0*
8 nn 24 2.88 9
0.0 25 0.0 20 nn 26 0.0 11 nn 27 61.96 1
12 0.0 28 71.99 13 0.0 29 70.33 14 0.0 30 74.71 15 r.o 31 79.54 16 0.0
- Generator on line but no ' net generation, e
.w.
y
,,7_-,
-,-,7y,%.,--_.-.y,,,,,%-
\\
\\
i v
REFUELING INFORMATION 1.
Name of Facility.
Fort St. Vrain Unit No. 1 2.
Scheduled date for next refueling shutdown.
October 1, 1982 3.
Scheduled date for restart following refueling.
December 1. 1982 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
No f
i If answer is yes, what, in
__ general, will these be?
If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Committee to deter-mine whether any unreviewed safety questions are associated The Plant Operations Review Committee will with the core reload (Reference review any questions associated with the 10CFR Section 50.59)?
reload.
i If no such review has taken place, when is it scheduled?
May 1, 1931 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 1482 HTGR fuel elements (a) in the core and (b) in the spent fuel storage pool.
250 spent HTJR fuel elements 8.
The present licensed spent fuel pool storage capacity and the Capacity is limited in size to about one-size of any increase in licensed third of
.re (approximately 500 HTGR storage capacity that has been elements). No change is planned.
requested or is planned, in number of fuel assemblies.
D
J REFul!I.DG DIFORMATION (CONusuru) l 9.
Ihe projected date of the 1986 under the Three Party Agreement (Con-last refueling that can be tract AT (04-3)-633) between DOE, Public discharged to the spent fuel Service Company of Colorado (PSCo), and pool assuming the present General Atomic Company.*
licensed capacity.
- The 1986 date is based on the understanding that spent fuel discharged during the cars of the Three Party Agreement will be shipped to the Idaho Na'tional F.ngineering 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.
D l
.-