ML20008F894
| ML20008F894 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/07/1981 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML20008F895 | List: |
| References | |
| P-81140, NUDOCS 8105120272 | |
| Download: ML20008F894 (1) | |
Text
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public Service Company *2 CoBomale 16805 ROAD 19%
PLATTEVILLE, COLORADO 80651 kN
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F f,gy 1 IbOIb C Fort St. Vrain L
Unit No. 1
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Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Fort St. Vrain Nuclear Generating Station Public Service Company of Colorado Docket No. 50-267 Operating License DPR-34
Dear Sir:
Attached please. find the March,1981, Monthly Operating Information for the Fort St. Vrain Nuclear Generating Station.
Very truly yours,
L 46-Q/am Don Warembourg Manager, Nuclear Production DW/lsb Attachment cc:
Mr. Karl V. Seyfrit Office of MIPC
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orERATDIC DATA REPO M DOCEET NO.
50-267 DATE 810505 i
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J. W. Gahm TELErn0NE (303) 785-2224 OPERATING STATUS NOTES 1.
Unit Name:
Fort St. Vrain 2.
Reporting Period:
810401 through 810430 3.
Licensed Thermal Power Osit):
842 4.
Nimeplate Rating (Gross We):
342 I
5.
'sesign Electrical Rating Clet We): 330 6.
Maximo Dependable Capacity (Gross We): 342 7.
1aximum Dependable Capacity Clet We): _ 330 8.
If Changes occur in capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
None 231 9.
Power Level To Which Restricted, If Any (het We):
Nuclear Regulatorv Commission restriction 70% pending 10.
Reasons for Restrictions. If Any:
resolution of temperature fluctuations.
This Month Year to Date Cumulative
- 11. sours in Reporting Period 719 2,879 16,080
- 12. Number of Hours Reactor Was Critical 668.2 2,363.7 11,498.9 I
- 13. Reactor Reserve shutdown sour.
0.0
- 0. 0 0.0
- 14. sours Generator on-Line 373.2 1,845.6 7,538.9
- 15. Unic Reserve shutdown nours 0.0 0.0 0.0 2
- 16. Gross Thermal Energy Generated (WR) 197,337.4 931,677.5 3,639,7_70.3
- 17. Gross Electrical Energy Generated 01WB) 69.848 335.739 C:
1.207.533
- 18. Net Electrical Energy Generated Osts) 63.549 310:213 1.109.514
- 19. Unit Service Factor 51.9 1 64.15 46.9%
- 20. Unit Availability Factor c;1. 0 %
64.1%
46.92
- 21. Unit Capacity Factor (Using MDC Net) 26.87,,
32.7%
20.9%
- 22. Unit Capacity Factor '.tsing :ER Net) 26.8%
32.7%
20.9%
- 23. Unic Forced Outage Rate 48.1%
35.9%
37.0%
- 24. Shutdowns Scheduled over Next 6 Months (Type Date, and Duration of Each):
Refueline. startine June 1.1981 for approximate 1v 8 weeks.
25.
If Shut Down at End of Report Period. Estiar:.ed Date of Startup:
NA
- 26. Units In Test Status (Prior to Cosmercial Operatien):
Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITT NA NA W oS7 2.o.2.7 9-ccMMERCIAL OPERATION NA NA t
UNIT SHUTDtWNS AND POWER REIRfC1DNS'-
vocRET m).
50-267 IINIT NAHE Fo rt S t. Vrain DATE 810505 cote i.ETui at
.I. W. Cahm REPURT HON 111 April,1981 TEurnoNE (303) 785-2224 HE11tOD OF SHUTTING lxWN 5YSTEN C099'ONENT DATE TYPE DURATION, REASON REACTOR I.ER f c0DE n)DE CAUSE AND QIRREcTIVE ACTION 1U PREVt.NT RECURRENCE 81-11 810401 F
232.5 A
2 80-030/03-X-1 IIB llTEXCil Unit taken off line and reactor shutdown due to excessive loop 2 steam generator penetration interspace pressurization helium leakage.
Continuation of shutdown from March, IS 81 81-12 810413 F
23.8 A
3 NA ED CKTHRK When "A" Reactor Building eyhaust fan was started a bad connection caused the breaker to fail and resulted in a hot reheat scram.
81-13 810419 F
23.2 A
3 NA IB INSTRU A faulty speed cable on ID helium circulator caused the circulator to -
trip and subsequently resulted in a hot reheat scram, i
81-14 810420 F
24.3 A
NA NA In INSTRU A faulty Integaeted circuit and a failed relay catued both loop II circulators to trip. The turbine generator was taken of f line to recover the loop.
81-15 810425 F
42.0 B
3 NA IB INSTRU During calibration of IA helium circ-ulator main drain valve a buffer-mid-buf fer trip occurred vli;ch resulted in a hot reheat scram.
Shunnary: Plan to continue operation at 70% power until refueling shutdown.
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1 AVERAGE DAILY UNIT POWER LEVEL Docket No.
50-267 Unit Fort St. Vrain Date 810505 Completed By J. W. Gahm Telephone (303) 785-2224 Month-April, 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DA1LY POWER LEVEL (MWe-Net)
(MWe-Nec) 1 0.0 17 242.6 2
'0. 0 18 250.2 i
3 0.0 19 7.0 4
0.0 20 78.0 21
- 0. 0
- 5 0.0 6
0.0 22 170.3 7
0.0 23 215.1 8
0.0 24 255.3 9
0.0 25 11.5 10 10.1 26 0.8 11 67.6 27 86.1 12 103.0 28 209.5 13 118.2 29 213.6 14 27.7 30 216.9 15 197.4 31 NA 16 220,8
- Generator on line but no ' net generation.
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L REMELING INFCRMATION 1.
Name of Facility.
Fort St. Vrain. Uni: No. 1 2.
Scheduled date for next refueling shutdown.
June 1, 1981 3.
Scheduled date for restart following refueling.
August 1, 1981 4.
' Jill refueling or resump: ion of operation thereaf:er 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 :he reload Yes fuel design and core configura-tion been reviewed by your Plan:
Safe:y Review Co=mittee to deter-mine whe:her any unreviewed safety questiens are associated with the core reload (Reference
.t 10CTR Section 50.59)?
I If no such review has :aken place when is it scheduled?
k 5.
Scheduled dace (s) for submi::ing proposed licensing accion and supoor ing informacion.
6.
Impor:an: licensing considera-Peripheral fuel elesen:s changed from chin tions associated vi:h refueling, thorius buffer to thick thorium buffer, e.g., new or different fuel de-sign or supplier, unreviewed i
design or performance analysis methods, significan: changes in fuel design, new opera:ing pro-cedures.
7.
The number of fuel asse=blies a) 1481 ETGR fuel elenents.
(a) in the core and (b) in
- he spen: fuel s:orage oool.
b) 10 scen: u*G t fuel elenen ts.
3.
The presen: licensed spen: fuel Capacity is 11=ited in si:e to abou: one-pool storage capaci:y and the third of core (approxina:ely 500 ETGR ele-size of any increase in licensed ments).
No change is planned.
storage capacity tha: has been reques:ed or is planned, in number of fuel assemblies.
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RETUELING INFCPyATION (CONTINUED) 9.
Ihe projected date of the 1986 u= der the Three Party Agreement (Coc-last refueling that can be tract AT (04-3)-633) between DOE, Public discharged to the spent fuel Service Company of Colorado (?Sco), and pool assuming the present General Atomic Company.*
licensed caeacitv.
- The 1985 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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