ML20127J161
| ML20127J161 | |
| Person / Time | |
|---|---|
| Site: | 05000268, Fort Saint Vrain  |
| Issue date: | 05/31/1985 |
| From: | Novachek F PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20127J140 | List: |
| References | |
| NUDOCS 8506260476 | |
| Download: ML20127J161 (7) | |
Text
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o PUBLIC SERVICE COMPANY OF COLORADO FORT ST VRAIN NUCLEAR GENERATING STATION MONTHLY OPERATIONS REPORT NO. 136 May, 1985 M
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1 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 May, 1985.
1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RILXTfD MXfRi'EilAs~E C
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Fourteen control rod drive and orifice assemblies were refurbished in May. Three were reworked to install the slack cable bushing retainer. One of these (Control Rod Drive #21 -
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the first unit worked), was completely disassembled to 2
relubricate gears and install new bearings.
If the present rate i
of refurbishment is maintained, thirty-seven operable rods will be available by June 19, 1985.
i Helium Circulator "lA" was returned to operation on April 27, 1985.
The electronic controls and the digital valve on the main drain of this circulator are functioning very well at this time.
The electronic controls have been installed on the four helium circulator main drain systems.
Helium Circulator "1A" was the first circulator operated with the new controls.
The steam outlet block valve on Helium Circulator "1B" was dismantled.
Visual inspection revealed valve internal problems.
The valve is being repaired at the present timo.
Helium Circulator "1D" has been returned to the reactor vessel.
The circulator bolts were changed.
The process of installation requires several checks and many hours of welding.
The circulator is presently scheduled for completion on June 8,
1985.
The Loop !
reheat stop check valve x-ray indicated that a i
por'.lon of the weld buildup was not successful.
A portion of the valve was removed and the area was rewelded. Heat treating j
and x raying are scheduled for the first week in June.
Condenser vacuum and feedwater cleanup will be established after the previous items are complete.
The flywheel for P-450l$ has been changed out, and is ready for the June 24, 1985 American Nuclear Insurers inspection, j
The annual roqualification examinations administered by the Training Department for licensed operators are completed.
All personnel passed the test.
The Nuclear Regulatory Commission j
administered their examination to eight license holders during i
May.
l Training for the anticipated startup is in progress for plant l
operators, i
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.g.
2.0 SINGLE RELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF 10*6_OF THE ALLOWABLE ANNUAL VALUE None 3.0 INDICATION OF FAILED FUEL RESULTING FROM IRRADIATED FUEL LiAMDistTONS None 4.0 MONTHLV OPERATING OATA REPORT Attached 1
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TSP-3 Attcchtent-33 Issue 2 50-267 ortratts: on A trPont pocxzT No.
ont June 10, 1985 Com.ctro T Frank flovachek m.truoNr (303) 785-2224 cPERATING STATt1 NOTIS 1.
Unit Name Fort St. Vrain 2.
Reporting Period 850501 through 850531 3.
Licensed Thermal Fever (*t):
842 4.
Nameplate Rating (Gross We):
342 5.
Design Electrical Rating (Net We);
330 6.
hximum Dependable Capacity (Gross We):
34 7.
hximum Dependable Capacity (Net We):
330 8.
If Changes occur in capacity Ratings (1tema Number 3 Through 7) since Last Report Cive Reasons:
fione 9.
Feuer Level To Whinh Restricted. If Any (Nat.We):
280
- 10. maaeou for Restrictsens. It Any:
Por commitment to the flRC. lono torm oneration above 85% power is pending completion of B-0 startup testing.
Thte Nath fear to Date Cumulative
- 11. Hours in Reporting Period 744 3,623 51,888
- 12. Number of nours paatter Was Critical 0.0 0.0 27,151.4
- 13. Reester ps orve shutdown usure 0.0 0.0 0.0
- 14. naure cenerater on Line 0.0 0.0 18,468.0
- 15. Unit peserve shutdown usure 0.0 0.0 0.0
- 16. Crees Therut tursy cenerated (Wu) 0.0 0.0 9,R61,714.4
- 17. Cree. Eleeirteal enersy cenerated (Wu) 0.0 0.0
_ 3,248,594 1s. het riseirse.1 toergy courated (re,5)
-2,199
-10,247 2.917,711 to, cast s'ervice rester 0.0 0.0 35.6
- 20. Unit Avattabitsty rester 0.0 0.0 36.6
- 21. Unit Capeetty Faster (Using FX ket) 0.0 0.0 17.0
!!. (tnit Careetly Teeter (Voing Dtt Net) 0.0 0,0 17.0
- 21. Unit Peteed Outage pate 100,0 100.0 51.9 He thutdene Scheduled Over kost 6 Nnths (fyre, Date, and (Neatlan of taah): J Q{;01 to 160701.
.E.0hDIrs 0
- 25. If thus tw et tnd of p pert perg,de fetteated bate of Startupe AllIV I n__l9M
- n. enise in t.ei siai..e arrier is C.,,eesiat op.reisenn reveuei A,mieved tt.ittAL catticAun
__fl/A ft/A I//A fl/A txif1At ettenactn II/A fi/A co + 9 etat ort u tion
r TSP-3 Attechment-3A AVERAGE DAILY l' NIT POWER LEVEL Isoue 2 Pcg2 1 of 1 Docket No.
50-267 Unit Fort St. Vrain Date June 10, 1985 Completed By Frank Novachek Telephone (303)785-2224 Honth May, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
(!fa'e-Ne t)
(.%'e-Ne t) 1 0.0 17 0.0 2
- 0. 0' is 0.0 3
0.0 19 0.0 0.0 20 0.0 4
0.0 0.0 5
21 6
0.0 22 0.0 7
0.0 23 0.0 0.0 24 0.0 8
9 25 0.0 0.0 10 0.0 26 0.0 0.0 27 0.0 11 12 0.0 28 0.0 13 0.0 29 0.0 14 0.0 30 0.0 15 0.0 3t 0.0 16 0.0
- Conerator on line but no not generation.
l
__jiO-267 imir une Fort St. Vrain i
mTE June 10. 1985 l
CowtrTro at Frank Novachek amar wwTu May 1935 Ttterwar (303) 785-2224 n u n er smunc mwe sTsim crocomorr
!ID.
EstTE TTFE OEATICS IIASCW REACTUS ttX f CDDE EDGE cat'SE AND GIRRECTIVE ACT1088 TD FRETENT RECT 1RRIEE E-CC6 540501 F
74:
A 3
50-267/84-008 AA JC Control Rod Drive Refurbishment 50-267/85-002 A3 BLO and Circulator Changeout m
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REFUELING INFORMATION I
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l _1.
Name of Facility l Fort St. Vrain Unit No. 1
_l l
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l
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l 2.
Scheduled date for next 1
l l
refueling shutdown.
l January 1, _1987 l
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l l 3.
Scheduled date for restart l February 1, 1987 l
l following refueling.
l l
l l
l 4.
Will refueling or resumption ofl No l
l operation thereafter require a l H
l technical specification change l H
l or other license amendment?
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_H l
l H
l If answer is yes, what, in l ----------------
l general, wl11__these_be?
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If answer is no, has the reload l 1
l fuel design and core configura-H l
tion been reviewed by your H
l L
Plant Safety Review Committee No i
l to determine whether any unre-l viewed safety questions are l
associated with the core reload l
l (Reference 10 CFR Section l
50.59)?
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l If no such review has taken 1985 l
l plac k when is it scheduled?
l l
l S.
Scheduleddate(s)forsubmit-l l
ting proposed licensing action '
l and suppor,tJn,g information,.
l l 6.
Important licensing considera tions associated with refuel-i ing, e.g., new or different fuel design or supplier, unre-i I
viewed design or performance I
analysis methods, significant i
changes in fuel design, new
_ ___opgat[ng_ procedures.
f l7.
The number of fuel assemblies t
l (a) in the core and (b) in the a) 1482 HTGR fuel elements L _.. Spent fuel stnra28 P001. _. _._b) 13L spent, fuel olomonts l
r i
r e.
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