ML20076L207
| ML20076L207 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 07/08/1983 |
| From: | Fuller C, Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| P-83238, NUDOCS 8307190080 | |
| Download: ML20076L207 (9) | |
Text
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PUBLIC SERVICE COMPANY OF C0LORADO FORT ST. VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 113 June, 1983 1
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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 DPR-34. This report is for the month of June,1983.
1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE The reactor was operated up to a power level of 14% during the month of June. During all operation, the helium circulators were operated in different configurations in an attempt to remove primary coolant moisture.
The most effective configuration was to operate with the "1C" and "1A" circulators ~
at maximum attainable speed.
Although the moisture levels remained high most of the month, they were dropping steadily by the end of the month. Operation above an average core outlet temperature of 725 degrees is anticipated in mid-July.
Early in the month, water makeup to the Loop 2 bearing water surge tank dropped to unacceptably low values. The normal level centrol valves were removed, and a wrist pin from an upstream check valve was found. The check valve was repaired and makeup flow returned to normal.
High pressure feedwater heater #6 developed a severe leakage problem. It was removed from service, and the leaking tubes were repaired by an explosive plug process. Twelve tubes were plugged.
The reactor was, in mid-June, shutdown to repair leaking electromatic isolation valves.
While shutdown, a Loop 2
temperature trim valve flange was also repaired. Prior to i
startup, IB circulating water pump discharge valve would not operate.
The circulating water tower and tunnels were drained, and the valve was repaired.
The Bahnson building return air fan developed an unbalance and severely damaged the fan.
It was replaced and returned to service.
A low pressure helium bottle bank which had been isolated due to j
mercury contamination was repaired and returned to service.
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The new goosequill ditch was flow tested to 3300 gpm. Flow has now been routed normally through the goosequill.
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- 2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10% OF THE ALLOWABLE ANNUAL VALUE None C
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l l 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL EXAMINATIONS None 4.0 MONTHLY OPERATING DATA REPORT Attached 4
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l Att achent-38 Issa 2 opt u m e DATA uroar DocxtT 30.
50-267 Dart July 8.1983 ccMrutto at Chuck Fuller Tztzrnour (303) 785-2224 orERA n No STATT5 soTES 1.
cnit same:
Fort St. Vrain l
2.
neportins Period:
830601 thru 830630 3.
Licanoed Thermal power Dett):
842 4.
Memoplate Ratias (Gross tele):
342 5.
Design nectrical natins Oset leie):
330 6.
Maziansa Dependable capacity (csoes leie):
342 7.
Maximina Dependable capacity Diet leia):
330 8.
If Chaseos occur in capacity Racings (Items Number 3 Through 7) Since Last Report, cive Rassees:
NONE 9.
Power L-1 Te *Aich Beatricted, If Aar (Net We):
231 1o. neae as for aestrictsens. If any:
Restriction to 70% pendina resolution of contractual matters.
This Heath Year to Date Cumalative u. aours in aeportins persed 720 4.343 35,064
- 12. member of nours aeector uns critical.
589.6 1,918.7 21.665.4
- 13. Reactor neeern shecdo== usur.
0.0 0.0 0.0
- 16. news cenerator on-time 0.0 905.0 14.079.5
- 15. Cait Resern shutdova Boure 0.0 0.0 0.0
- 16. cross Thermal tearsy coeerated cent) 45,910.9 512,703.4 7.302.128.8
- 17. crose nectrical zaersy cenerated osm) 0 140,814 2.467.718 is. set nectrical smersy cenerated com)
-5,390 111,460 2.234.570
- 19. cait Service rector 0.0 20.8 40.2
- 20. Unit Availab uity Tactor 0.0 20.8 40.2
- 21. ratt cap. city rector (catas une set) 0.0 7.8 19.3
- 22. Unit capacity rector (usins Den unt) 0.0 7.8 19.3
- 23. cnic Forced outase mate 100.0 79.2 44.2
- 4 shutdowns scheduled over next 6 nonths (Type. Date, and Duration of sach): -
830701 throuah 830705 (120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />) - primary coolant impurity cleanup.
- 25. If Shut Down at End of Report Period. Estimated Date of Startups 830706
- 26. cnics In Test Status (Prior to commercial operation):
Forecast Achieved
/A N/A IsITuL cuncaun IxInA:. n.EcTRIcIn N/A N/A cotatracIA:. orEIATIos N/A N/A
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TSP-3 Att achment-3A Issue 2 AVERAGE DAILY UNIT POWER LEVEL Page 1 of 1 Docket No.
50-267 8
Unit Fort S t. Vrain Date July 8, 1983 i.
Completed By Qiuck Fuller s
Telephone (303) 785-2224
& nth June 1983 4
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL..
()6ie-Net)
(!We-Net) i 1
0 17 0
2 0
18 0
3 0
19 0
4 0
20 0
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5 0
21 0
6 0
22 0
4 j
7 0
23 0
8 0
24 0
9 0
25 o
10 0
26 o
11 0
27 o
i 12 0
28 0
13 0
29 0
l 14 0
30 0
(
l 15 0
31 N/A 16 0
- Generator on line but no net generation.
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T
t REFUELING INFORMATION 1.
Name of Facility.
Fort St. Vrain Unit No. 1 2.
Scheduled date for next refueling shutdown.
April 1,r1984 3.
Scheduled date for restart following refueline.
June 1, 1984 4
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Ye,s If answer is yes, what, in meneral, will these be?
Use of tvoe H-451 oraphite.
If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Cossaittee to deter-mine whether any unreviewed safety questions are associated 1
with the core reload (Reference 10CFR Section 50.59)7 l
If no such review has taken
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place, when is it scheduled?
5.
Scheduled date(s) for submitting proposed licensing action and*
Not scheduled at this time; supporting information.
to be determined.
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
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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.
11 spent HTGR 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 core (approximately 500 HTGR storage capacity that has been elements). No change is planned.
requested or is planned, in number of fuel assemblies.
1 I
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REF0ELING INFORMATIoN (CONTINUED) 9.
Iha projected date of the 1s.192 unde.r Agreements AT(04-3)-633 and last refueling that can be DE-SC07-791D01370 between Public Service discharged to the spent. fuel Company.of Colorado, General Atomic pool assuming the present Company, and DOE.*
licensed capacitv.
The 1992 estimated date is based on the understanding that spent fuel discharged during the tem of the Agreements will be stored by DOE at the Idaho Chemical Processing Plant. The storage has evidently been sized to accomodate eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.
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PLIblie Nt*Viee (On1)) ally T OE00Hld@
16805 Road 19 1/2, Platteville, Colorado 80651-9298 July 13, 1983 Fort St. Vrain Unit No. 1 P-83238 Office of Inspection and Enforcement ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Reference:
Facility Operating License No. DPR-34 Docket No. 50-267
Dear Sir:
Enclosed please find our Monthly Operations Report for the month of June, 1983.
Very truly yours, 04 % em k ny & ?>] N ? % 4 J Don Warembourg Manager, Nuclear Production DW/djm Enclosure cc:
Mr. John T. Collins TE 14 DjI
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